ML18153D034

Monthly Operating Repts for May 1992 for Surry Power Station Units 1 & 2.W/920610 Ltr

ML18153D034
Person / Time
Site:	Surry
Issue date:	05/31/1992
From:	Mason D, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-395, NUDOCS 9206160024
Download: ML18153D034 (19)

Text

e -VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 10, 1992 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 MONTHL V OPERATING REPORT Serial No. NO/RPC:vlh Docket Nos. License Nos.92-395 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 May 1992. Very truly yours, LJ~ W. L. Stewart Senior Vice President

-Nuclear 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 ,,------L_

... _r I ~} 9206160024 920531 PDR ADOCK 05000280 R .. PDR VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-05 Approved:

e TABLE OF CONTENTS Section e Surry Monthly Operating Report No. 92-05 Page 2of 18 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.

..............................................................................

1 O Procedure or Method of Operation Changes That Did Not Require NRC Approval ...........................................

14 Tests and Experiments That Did Not Require NRC Approval ......................................................................

15 Chemistry Report .............................................................................................................................

16 Fuel Handling -Unit No. 1 .............................................

.....................................................................

17 Fuel Handling -Unit No. 2 ...................................................................................................................

17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications

...................................................................................................

18

-Surry Monthly Operating Report No. 92-05 Page 3of 18 OPERATING DATA REPORT Docket No.: Date: Completed By: 50-280 06-05-92 D. Mason 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 May 1992 2441 847.5 788 820 781 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 YTD Cumulative

11. Hours In Reporting Period ..........................

744.0 3647.0 170423.0 12. Number of Hours Reactor Was Critical ..........

715.8 2003.8 110238.0 13. Reactor Reserve Shutdown Hours ...............

0.0 0.0 3774.5 14. Hours Generator On-Line ...........................

676.8 1948.6 108188.8 15. Unit Reserve Shutdown Hours .....................

0.0 0.0 3736.2 16. Gross Thermal Energy Generated (MWH) ...... 1438237.0 4165844.2 251282520.9

17. Gross Electrical Energy Generated (MWH) .... 481915.0 1401580.0 81916768.0

18. Net Electrical Energy Generated (MWH) ........ 456100.0 1327253.0 77701319.0

19. Unit Service Factor ...................................

91.0% 53.4% 63.5% 20. Unit Availability Factor ...............................

91.0% 53.4% 65.7% 21. Unit Capacity Factor (Using MDC Net) ...........

78.5% 46.6% 58.8% 22. Unit Capacity Factor (Using DER Net) ...........

77.8% 46.2% 57.9% 23. Unit Forced Outage Rate ............................

1.8% 8.4% 19.1% 24. Shutdowns Schedule 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 INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED

-Surry Monthly Operating Report No. 92-05 Page 4of 18 OPERATING DATA REPORT Docket No.: Date: Completed By: 50-281 06-05-92 D. Mason 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 May 1992 2441 847.5 788 820 781 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: 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 1814580.7 600865.0 571267.0 100.0% 100.0% 98.3% 97.4% 0.0% YTD 3647.0 3647.0 0.0 3647.0 0.0 8831788.7 2944175.0 2801773.0 100.0% 100.0% 98.4% 97.5% 0.0% Cumulative 167303.0 108855.1 328.1 107107.9 0.0 249710470.8 81378024.0 77165711.0 64.0% 64.0% 59.2% 58.5% 14.9% 24. Shutdowns Schedule 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 INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED (1) Date Type 920507 F 920515 s 920519 s (1) F: Forced S: Scheduled (4) -Surry Monthly Operating Report No. 92-05 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: May 1992 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-05-92 Completed by: Anthony Xenakis Teleehone:

(804) 365-2145 (2) (3) (4) (5) Method Duration of LER System Component Cause & Corrective Action to Hours 12.6 0 0 Reason G B B (2) REASON: Shutting Down Rx 3 4 4 No. 92-007-00 NIA NIA A -Equipment Failure (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction Code Code TA V SJ p SJ p E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

Prevent Recurrence Contract personnel performing maintenance on the Thrust Bearing Trip Test Valve inadvertently lifted the disc from the seat, causing a reactor trip by turbine trip. To prevent recurrence, a root cause evaluation was initiated and the vendor was directed to perform an investigation.

The resulting recommendations will be reviewed by station management and appropriate work control measures will be implemented prior to the vendor performing future maintenance activities.

Reduced unit power to 57% to repair seal leak on the "B" Main Feed Pump. Reduced unit power to 59.4% to repair a motor bearing on the "A" Main Feed Pump. (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.

(1) e -Surry Monthly Operating Report No. 92-05 Page 6of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: May 1992 (2) (3) (4) (5) Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-05-92 Completed by: Anthony Xenakis Telephone:

(804) 365-2145 Duration Method of Reason Shutting Down Rx LER No. System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1) F: Forced S: Scheduled (4) (2) REASON: None during this reporting period. A -Equipment Failure (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

(5) Exhibit 1 -Same Source.

Month: May 1992 Day 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 92-05 Page 7of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-05-92 Completed by: M.A. Negron Telephone:

(804) 365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net) Day (MWe-Net) 0 17 478 0 18 781 123 19 759 304 20 432 496 21 602 546 22 780 242 23 781 583 24 781 752 25 783 782 26 783 785 27 783 785 28 782 783 29 783 783 30 784 728 31 782 438 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.

Month: May 1992 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 92-05 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-05-92 Completed by: M.A. Negron Telephone:

(804) 365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 771 17 766 765 18 763 766 19 771 763 20 772 756 21 772 773 22 769 771 23 767 773 24 746 772 25 767 768 26 771 763 27 771 767 28 770 769 29 768 771 30 770 771 31 771 772 On this format, list the average daily unit power level in MWe -Net for each day in the reporting month. Compute to the nearest whole megawatt.

-Surry Monthly Operating Report No. 92-05 Page 9of 18

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR:

May 1992 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 05-01-92 05-03-92 05-05-92 05-07-92 05-10-92 05-15-92 05-17-92 05-19-92 05-21-92 05~31-92 UNIT TWO 05-01-92 05-31-92 0000 This reporting period started with the Unit approaching the end of a scheduled Refueling Outage and at Hot Shutdown (HSD). 2211 Reactor critical.

0628 0514 1006 Unit on line. Unit at 69% power, 530 MWe. Automatic reactor trip by turbine trip due to personnel error while performing maintenance on Thrust Bearing Trip Test Valve. 1756 Reactor critical.

2242 Unit on line. *1158 1834 Unit at 100% power, 825 MWe. Started ramp down to repair seal leak on 1-FW-P-18, "8" Main Feed Pump; 100% power, 820MWe. 2138 Stopped ramp; 57% power, 470 MWe. 2002 Started ramp up; 58% power, 470 MWe. 2320 Stopped ramp; 100% power, 820 MWe. 2101 Started ramp down to repair a motor bearing on 1-FW-P-1 A, "A" Main Feed Pump; 100% power, 820 MWe. 2348 Stopped ramp; 59.4% power, 485 MWe. 1112 Started ramp up; 59% power, 480 MWe. 1436 Stopped ramp; 100% power, 820 MWe. 2400 0000 2400 This reporting period ended with the Unit operating at 100% power, 820 MWe. This reporting period started with the Unit operating at 100% power, 81 O MWe. This reporting period ended with the Unit operating at 100% power, 81 O MWe.

-Surry Monthly Operating Report No. 92-04 Page 10 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

May 1992 DR S-92-0696 JCO C91-3-004 QA Topical Report Deviation Reports 04-20-92 (Safety Evaluation No.92-093) This Safety Evaluation was performed to evaluate Deviation Report DR S-92-0696 concerning the operation of the auxiliary ventilation exhaust filter system fan 1-VS-F-58B in the manual control mode. This method of operation was initiated as a temporary measure to return the affected ventilation train to service following high vacuum fan trips that occurred in the automatic control mode. An evaluation of this operating condition concluded that the affected auxiliary ventilation exhaust filter system train is operable and capable of fulfilling its intended safety function with the train in the safety injection alignment (safeguards building and charging pump cubicles exhausted to the filter train with the air flow rate established at 36,000 cfm). Therefore, an unreviewed safety question was not created. Justification For Continued Operation (Safety Evaluation No.92-103) 04-27-92 Justification For Continued Operation JCO C91-3-004 was revised to eliminate the need to open the Unit 1 discharge tunnel vacuum breaker valve 1-CW-117 to break tunnel vacuum, upon notification of a Hi Hi Consequence Limiting Safeguards signal. This change reflects the implementation of Design Change Package 91-12-3 that added two inch suction lines and check valves to the suction of recirculating spray heat exchanger service water radiation monitoring pumps (1-SW-P-5A, B, C,D) to ensure proper pump operation in the presence of discharge tunnel vacuum. The performance of Special Test ST-299 illustrated that this modification eliminated the need to open valve 1-CW-117.

Therefore, an unreviewed safety question was not created. Quality Assurance Topical Report (Safety Evaluation No.92-109) 04-30-92 The QA Topical Report was revised to satisfy the requirement for an annual update. The changes are primarily of an administrative or editorial nature and serve to enhance administrative controls and improve the effectiveness of the quality control program. The changes do not reflect or affect changes to the plant. Therefore, an unreviewed safety question was not created.

e Surry Monthly Operating Report No. 92-04 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR:

May 1992 TM S2-92-03 DR S-92-0257 FS 92-28 [continued]

Temporary Modification (Safety Evaluation No.92-112) 05-07-92 This Temporary Modification (TM) blocked main steam system valve, 2-MS-86, in the closed position to allow the replacement of the yoke bushing. 2-MS-86 is the manual isolation for the Unit 2 steam generator (SG) "A" power operated relief valve (PORV). Prior to the yoke bushing replacement, the subject valve was in the closed position, rendering the SG "A" PORV unavailable.

This TM permitted implementation of the bushing replacement, the return of 2-MS-86 to its normal (open) configuration, and made SG "A" PORV available.

SG PORVs are not required by Technical Specifications.

Therefore, an unreviewed safety question was not created. Deviation Reports 05-09-92 (Safety Evaluation No.92-111) This Safety Evaluation was performed to evaluate Deviation Report S-92-0257 concerning battery charger 2-MS-BC-2 being out of service for a period greater than 30 days. This battery charger provides 24 volt DC power to energize solenoid operated valves (SOV) SOV-MS-201AE, 201 BE and 201 CE to close main steam trip valves (MSTV) 2-MS-TV-201 A, 2018, and 201 C, respectively.

Thus, during the period the battery charger was out of service, operation of the Unit 2 MSTVs from the 1 o CFR 50, Appendix R panel located in the emergency switchgear room (ESGR) was not possible.

It was determined that during the period in which the ESGR Appendix R switch was inoperable, the requirements of 1 O CFR 50, Appendix R could have been

• met by operations personnel using the Fire Contingency Action, Abnormal, and/or Emergency Operating procedures.

In addition, the MSTVs could have been closed by operations personnel by locally interrupting the air supply to the valve closure mechanism.

Therefore, an unreviewed safety question was not created. UFSAR Change 05-21-92 (Safety Evaluation 92-116) The Updated Final Safety Analysis Report (UFSAR) section 8.5 will be revised to correct the undervoltage setpoint value for the 4 KV transfer buses D, E, and F. The existing setpoint value does not provide a margin above the safety analysis limit and will be changed from 45.8% to 46.7% of the rated voltage, as stated in Technical Specification (TS) table 3.7-4, item SD. This is an administrative change that provides consistency between the UFSAR and the TS. No physical changes to the plant will be made. Therefore an unreviewed safety question will not be created. _ ___j e Surry Monthly Operating Report No. 92-04 Page 12of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR:

May 1992 TM S2-92-04 TM S2-92-05 AC S1-92-0527

[continued]

10 CFR 50, Appendix R Report (Safety Evaluation 92-118) 05-26-92 The 10 CFR 50, Appendix R Report was revised to incorporate changes to Chapter 1, "Introduction", Chapter 2, " Identification of Fire Areas", and Chapter 7, "Exemption Requests" and to add a new Chapter 12, "Appendix A And SER Commitments".

The changes to Chapters 1, 2, and 7 were administrative or editorial in nature. The new chapter provides documentation of commitments and responses to Branch Technical Position APCSB 9.5-1, Appendix A. These commitments form part of the licensing basis for fire protection for Units 1 and 2. No physical changes to the plant were made. Therefore, an unreviewed safety question was not created. Temporary Modification (Safety Evaluation No.92-119) 05-26-92 These Temporary Modifications (TM) installed electrical jumpers to maintain electrical circuit continuity during the replacement of failed Unit 2 reactor

• protection system test switch, 02-RP-CS-43.

These TMs enabled both trains of the Safety Injection (SI) system actuation circuitry to remain in service during the replacement of the test switch. Following jumper installation, checks were made to ensure a SI or reactor trip had not occurred.

Upon removal of the jumper, the replacement switch was tested in accordance with the applicable instrument periodic test procedure.

Therefore, an unreviewed safety question was not created. Administrative Control (Safety Evaluation No.92-121) 05-28-92 Administrative control of ventilation system valves 1-VS-208, 1-VS-224, 2-VS-208, and 2-VS-224 was established to enable the valves to be throttled in order to raise the main control room temperature.

The subject valves are controlled by a licensed operator who is capable of restoring the design flowrates within 12 minutes. This operator action ensures that the design basis bulk temperature will not be exceeded in the event of an accident.

Therefore, an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 92-04 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

May 1992 TM S1-92-29 DR S-92-0734

[continued]

Temporary Modification (Safety Evaluation No.92-120) 05-28-92 This Temporary Modification (TM) installed a new type ultrasonic level transmitter in waste neutralization sump "A" in place of the existing disabled transmitter.

The sump manhole cover was modified to allow insertion of the ultrasonic probe. This installation will enable a determination to be made as to whether an ultrasonic transmitter is suitable for this application.

The waste neutralization sumps and the associated equipment are related and are powered from a nonsafety-related power supply. Operation of the level transmitters is not required for emergency conditions or for safe shutdown of the plant. Therefore, an unreviewed safety question was not created. Deviation Reports 05-29-92 (Safety Evaluation No.92-122) This Safety Evaluation was performed to evaluate Deviation Report S-92-0734 concerning operation of the Unit 2 charging pump service water system with flow rates below the 90 gallons per minute (gpm) described in the station design basis document.

An evaluation of plant opera.ting experience and previous technical studies concluded that Unit 2 can safely operate with charging pump service water system flows of less than 90 gpm and provide needed heat removal under accident conditions.

Recent operational data indicate that current service water flow rates maintain the charging pump lube oil temperatures below 110°F. An engineering evaluation established a maximum allowable lube oil temperature of 160°F. Therefore, an unreviewed safety question is not created.

O-TOP-4052 2-0PT-CT-201 e Surry Monthly Operating Report No. 92-04 Page 14of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

May 1992 Temporary Operating Procedure (Safety Evaluation No.92-113) 05-15-92 Temporary Operating Procedure (TOP) O-TOP-4052, "Control Room And Relay Room Ventilation System Operation During Chilled Water Loop Tie-Ins For DCP 90-07-3," was revised to permit two control room envelope air conditioning system chillers to be operated in parallel in a single chilled water loop. This mode of operation is required to allow each chilled water loop to be isolated and drained so that piping connections associated with the implementation of Design Change Package 90-07-3 can be made. During the performance of this TOP, two of the three chillers will be operable and the appropriate Technical Specification limiting conditions for operation will be adhered to. Therefore, an unreviewed safety question is not created. Operations Periodic Test Procedure (Safety Evaluation No.92-115) 05-22-92 Operations Periodic Test Procedure, 2-0PT-CT-201, "Containment Isolation Valve Local Leak Rate Testing (Type C Containment Testing" was revised ("one-time only") to temporarily extend the Unit 2 containment boundary from gas vent header containment isolation valve 2-VG-TV-209B to gas vent valves 2-VG-1 and 2-VG-2. This action will allow maintenance work to be performed on 2-VG-TV-209B while maintaining containment integrity.

This extension of containment integrity to valves 2-VG-1 and 2-VG-2 does not reduce boundary integrity since the as-built configuration was verified to be consistent with the code/design requirements for the containment boundary.

An approved leak test will be conducted to verify that the extended boundary does meet leakage integrity requirements prior to declaring it in service. In addition, valves 2-VG-1 and 2-VG-2 will remain under administrative control while being used as the containment boundary.

Following completion of maintenance and a successful leakage test, 2-VG-TV-209B will resume its function as contai.nment boundary.

Therefore, an unreviewed safety question is not created. I e Surry Monthly Operating Report No. 92-04 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL 1-ST-300 MONTH/YEAR:

May 1992 Calibration of Steam Flow Transmitters Using ChemTrac Chemical Tracer Method (Safety Evaluation No.92-019) 05-21-92 This special test was performed in order to correct inaccuracies associated with the Unit 1 main feedwater flow venturis.

Chemtrac testing, which uses a lithium nitrate chemical tracer, was performed during the shutdown for the 1992 Unit 1 refueling outage to determine actual feedwater flow. The results of this testing were used to rescale the Unit 1 steam flow and feedwater flow transmitters.

Additional test data was collected during the startup from the refueling outage which validated the new scaling for the steam flow loops. Therefore, an unreviewed safety question was not created.

Primarv Coolant Analvsis Gross Radioact., uCi/ml Suspended Solids, com Gross Tritium, uCi/ml 1131, µ.Ci/ml 1 131/I133 Hvdroaen, cc/ka Lithium, oom Boron -1 O, com* Oxvaen, (DO) oom Chloride, oom pH at 25 dearee Celsius

• Boron -10 = Total Boron x 0.196 Comments:

None. CHEMISTRY REPORT MONTH/YEAR:

May 1992 Un~ No. 1 Max. Min. Ava. 3.06E-1 4.76E-3 2.06E-1 0.0 0.0 0.0 1.86E-1 1.00E-2 8.87E-2 6.66E-4 1.48E-4 3.96E-4 0.09 0.07 0.08 37.6 14.5 25.4 3.00 2.05 2.32 432.8 237.9 287.1 < 0.005 < 0.005 < 0.005 0.007 < 0.001 0.003 6.49 4.89 6.32 e Surry Monthly Operating Report No. 92-04 Page 16 of 18 Unit No. 2 Max. Min. Ava. 2.37E-1 1.12E-1 1.75E-1 0.0 0.0 0.0 5.81E-1 5.37E-1 5.63E-1 5.38E-4 1.88E-4 3.44E-4 0.13 0.07 0.09 35.3 26.0 31.2 2.34 2.06 2.18 161.1 143.1 151.5 ' < 0.005 < 0.005 < 0.005 0.006 < 0.001 0.002 6.78 6.55 6.71 New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/VEAR:

May 1992 Number for Assemblies per Shipment Assembly Number ANSI Number No Fuel Stored or Received in May, 1992 e Surry Monthly Operating Report No. 92-04 Page 17 of 18 Initial Enrichment New or Spent Fuel Shipping Cask Activity Surry Monthly Operating Report No. 92-04 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/VEAR:

May 1992 None During This Reporting Period.