ML18152A426

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Monthly Operating Repts for Apr 1990 for Surry Power Station Units 1 & 2.W/900515 Ltr
ML18152A426
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/30/1990
From: Stewart W, Warren L
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-284, NUDOCS 9005180077
Download: ML18152A426 (22)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 15, 1990 U. S. Nuclear Regulatory Commission Serial No.90-284 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of April 1990.

W. L. St art Senior Vice President - Nuclear Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station

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9005180077 900430 I PDR ADOCK 05000280 R PDC

' . - POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT :fl 90-04 APPROVED:

e e TABLE OF CONTENTS SECTION PAGE Operating Data Report - Unit No. 1 1 Operating Data Report - Unit No. 2 2 Unit Shutdowns and Power Reductions Unit No. 1 3 Unit Shutdowns and Power Reductions - Unit No. 2 4 Average Daily Unit Power Level - Unit No. 1 5 Average Daily Unit Power Level - Unit No. 2 6 Summary of Operating Experience - Unit No. 1 7 Summary of Operating Experience - Unit No. 2 7 Facility Changes That Did Not Require NRC Approval 8 Procedure or Method of Operation Changes that Did Not Require NRC Approval 15 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

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OPERATING DATA REPORT DOCKET NO.: 50-280 DATE: --,o=5~/0~3~/9~0-----

COMPLETED BY: L.A. Warren TELEPHONE: -,..,(8=0...,,...4).--:3,=5=-7--=3=13,,....,4,----,x3=5-=-5~

OPERATING STATUS NOTES

1. Unit Name: Surry Unit 1
2. Reporting Period: April 01-30, 1990
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. Reason For Restrictions, If Any: -----------

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 719.0 2879.0 152135.0
12. Number of Hours Reactor Was Critical 719.0 2879.0 95629.8
13. Reactor Reserve Shutdown Hours 0 0 3774.5
14. Hours Generator On-Line 719.0 2879.0 93702.2
15. Unit Reserve Shutdown Hours 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) 1748615.0 6950588.5 218067391. 5
17. Gross Electrical Energy Generated (MWH) 589140.0 2352375.0 70897778.0
18. Net Electrical Energy Generated (MWH) 561280.0 2240484.0 67251414 .0
19. Unit Service Factor 100% 100% 61.6%
20. Unit Availability Factor 100% 100% 64%
21. Unit Capacity Factor (Using MDC Net) 100% 99.6% 57.1%
22. Unit Capacity Factor (Using DER Net) 99.1% 98.8% 56.1%
23. Unit Forced Outage Rate 0% 0% 21.1%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, October 05, 1990, 58 days

25. If Shut Down at End of Report Period Estimated Date of Startup:
26. Unit In Test Status (Prior to Commercial Operation): FORECAST~~A=cH=I=E=v=ED~

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

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e OPERATING DATA REPORT DOCKET NO.: 50-281 DATE: -0=5,....,.7=03""""'/"""90=------

COMPLETED BY: L.A. Warren TELEPHONE: (804)357-3184 x355 OPERATING STATUS NOTES

1. Unit Name: Surry Unit 2
2. Reporting Period: April 1-30, 1990
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. Reason For Restrictions, If Any: -----------

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 719.0 2879.0 149015.0
12. Number of Hours Reactor Was Critical 719.0 2879.0 94077 .6
13. Reactor Reserve Shutdown Hours 0 0 328.1
14. Hours Generator On-Line 719.0 2879.0 92527.9
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 1752618.4 6877077 .5 216487412.3
17. Gross Electrical Energy Generated (MWH) 588175.0 2314845.0 70395444.0
18. Net Electrical Energy Generated (MWH) 560267.0 2203803.0 66744762.0%
19. Unit Service Factor 100% 100% 62.1%
20. Unit Availability Factor 100% 100% 62.1%
21. Unit Capacity Factor (Using MDC Net) 99.8% 98% 57.5
22. Unit Capacity Factor (Using DER Net) 98.9% 97.1% 56.8%
23. Unit Forced Outage Rate 0% 0% 15.3%
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 Startup:
26. Unit In Test Status (Prior to Commercial Operation): FORECAST-----.-A=cR.,...I'""'E.,.,,VE=D,.--

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2

DOCKET NO.: 50-280 ~

UNIT SHUTDOWN AND POWER REDUCTION UNIT NAME: Surry Unit 1 (Equal To or Greater Than 20%) DATE: May 03, 1990 COMPLETED BY: L.A. *Warren REPORT MONTH: -- APRIL

-- 1990

--- TELEPHONE: 804-357-3184 x355 METHOD OF LICENSEE CAUSE &CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENT NO. DATE TYPE(l) (HOURS) REASON(2) DOWN REACTOR(3) REPORT# CODE(4) CODE{5) RECURRENT NONE DURING THIS REPORTING PERIOD (1) ( 2) (3) (4)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure {Explain) 1 - Manual Exhibit G - Instructions for B - Maintenance or Test 2 - Manual Scram. Preparation of Data Entry Sheets C - Refueling 3 - Automatic Scram. for Licensee Event Report {LER)

D - Regulatory Restriction 4 - Other (Explain) File (NUREG 0161)

E - Operator Training &License Examination F - Administrative {5)

G - Operational Error (Explain) 3 H - Other {Explain) Exhibit 1 - Same Source

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  • DOCKET NO.: 50-281 ~

UNIT SHUTDOWN AND POWER REDUCTION UNIT NAME: Surry Unit 2 (Equal To or Greater Than 20%) DATE: 05/03/90 COMPLETED BY: L.A. *Warren REPORT MONTH: - - APRIL

- -1990

TELEPHONE: 804-357-3184 x355 METHOD OF LICENSEE CAUSE &CORRECTIVE DURATION SHUTTING EVENT SYSTEM

  • COMPONENT ACTION TO PREVENT NO. DATE TYPE(l) (HOURS) REASON(2) DOWN REACTOR(3) REPORT# CODE(4) C0DE(5) RECURRENT 04/11/90 s 0.0 B 4 NA TA V Unit ramped down to ill power, 630 MW in order~

perfonn 2-PT-29.1 (turbine governor, stop, intercept and reheat valves exercise test).

(1) (2) (3) (4)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual Exhibit G - Instructions for B - Maintenance or Test 2 - Manual Scram. Preparation of Data Entry Sheets C - Refueling 3 - Automatic Scram. for Licensee Event Report (LER)

D - Regulatory Restriction 4 - Other (Explain) File (NUREG 0161)

E - Operator Training &License Examination F - Administrative (5)

G - Operational Error (Explain) 4 H - Other (Explain)

  • Exhibit 1 - Same Source

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--- e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-280 UNIT NAME: Surry Unit 1 DATE: 05/04/90 COMPLETED BY: L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH: APRIL 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 757 17 788 2 790 18 788 3 662 19 789 4 773 20 791 5 789 21 789 6 789 22 789 7 790 23 788 8 790 24 784 9 790 25 784 10 791 26 783 11 790 27 781 12 776 28 786 13 775 29 785 14 771 30 782 15 773 31 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.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-281 UNIT NAME: Surry Unit 2 DATE: 05/04/90 COMPLETED BY: L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH: APRIL 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 750 17 782 2 780 18 782 3 781 19 781 4 782 20 782 5 781 21 781 6 783 22 782 7 783 23 778 8 782 24 780 9 780 25 777 10 783 26 771 11 754 27 773 12 784 28 773 13 784 29 775 14 784 30 774 15 784 31 16 782 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.

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SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: ~-A...;_P_R....:..:IL"--'-19....:..:9_0~~

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 04/01/90 0000 This reporting period started with the Unit operating at 100% power, 830 MW.

04/03/90 0200 Started ramp down in preparation for performance of 1-PT-29.1 and to secure 1-SD-P-lA due to a seal leak; 100%

power, 830 MW.

0320 Stopped ramp; 86% power, 710 MW.

04/04/90 0227 Started ramp up after completion of 1-PT-29.1 and after starting 1-SD-P-18; 86% power; 700 MW.

0320 Stopped ramp; 100% power, 830 MW.

04/30/90 2400 This reporting period ended with the unit operating at 100%

power, 820 MW.

UNIT TWO 04/01/90 0000 This reporting period started with the unit operating at 100% power; 820 MW.

04/11/90 0921 Started ramp down in preparation for 2-PT-29.1; 100% power, 825 MW.

1135 Stopped ramp; 75% power, 630 MW.

1318 Started ramp up after completion of 2-PT-29.1; 75% power, 630 MW.

1511 Stopped ramp; 100% power, 825 MW.

04/30/90 2400 This reporting period ended with the unit operating at 100%

power, 795 MW.

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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: - -APRIL

--- 1990 1-TOP-3038 TEMPORARY OPERATING PROCEDURE 04/02/90 1-TOP-3039 TEMPORARY OPERATING PROCEDURE 04/05/90 (Safety Evaluation #90-0092)

This procedure is to document the temporary shutdown of the auxiliary ventilation system while the blank flange is being installed in the discharge of fans 1-VS-F-8A/8B, the auxiliary building general area exhaust fans.

A blank flange will be located in the non-safety related portion of the system which is isolated during an accident. Adequate precautions and guidance are provided in the controlling procedure to closely monitor the charging pump temperatures during the short period of time the auxiliary building general area exhaust fans are secured. If the charging pump temperatures exceed 180 degrees, the auxiliary ventilation system will be restarted and the exhaust duct will be clamped and covered. Both trains of the auxiliary ventilation system filtered exhaust system will remain operable and in automatic during this activity. Therefore, an unreviewed safety question is not created.

MEMO TO L. MORRIS FROM J. KELLY UNITS 1&2 04/5/90 (Safety Evaluation #90-0095)

This memo investigates the use of a resin dewatering hose directed to the auxiliary building sump. l~ater drained from vessels in the decon building was designed to go to the local sump which would overflow into the pipe tunnel and into the auxiliary building sump during high flow conditions. This change will install a hose that will direct drains to the auxiliary building sump to reduce the potential for the spread of contamination.

The change reduces the potential for the spread of contamination.

A safety question does not exist because the liquid will be directed to the auxiliary building sump by a hose rather than the floor.

S2-TM-90-05 TEMPORARY MODIFICATION 04/09/90 (Safety Evaluation #90-0096)

This modification provides for bypassing the rod bottom turbine runback module for the individual rod position indication (!RPI) for control rod L-11. This bypass prevents a turbine runback signal on a rod bottom indication for !RPI L-11.

The !RPI runback is a backup to the Nuclear Instrumentation (NI) dropped rod runback. In the event a dropped rod occurs, it would cause a significant flux change that requires a power reduction.

Since protection for this flux change event is provided by_ the NI dropped rod signal, an unreviewed safety question does not exist.

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--- e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: APRIL 1990 SCAFFOLD REQUEST UNIT 2 04/10/90 (Safety Evaluation #90-0097)

This request is for the erection of temporary scaffold to support the repairs on valve 2-MS-120 per job order #092444. The scaffold will be located in the Unit 2 safeguards building at floor elevation 27 1 611

  • The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 04/10/90 (Safety Evaluation #90-0098)

This request is for the erection of two temporary scaffolds to support the maintenance of broken light fixtures in mechanical equipment room #1 per work order #3800090355.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 2 04/10/90

{Safety Evaluation #90-0099)

This request is for the erection of temporary scaffold to support the maintenance on valve 01-VS-FCV-241 located in mechanical equipment room (MER)# 2 per work order# 3800089805.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

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e e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: - - APRIL

--- 1990 SCAFFOLD REQUEST UNIT 1 04/10/90 (Safety Evaluation #90-0100 &#90-0103)

This request is for the erection of temporary scaffold in Unit 1 turbine building to support installation of cable tray covers and to label the trays per engineering work requests89-132 and 89-293.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 2 04/10/90 (Safety Evaluation #90-101)

This request is for the erection of temporary scaffold to install smoke detectors in the Unit 2 main steam valve house per design change package (DCP) 89-10.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 04/10/90 (Safety Evaluation #90-102)

This request is for the erection of temporary scaffold to install smoke detectors in the Unit 1 safeguards and main steam valve house basements per DCP 89-10.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

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-- e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: APRIL 1990 NE TECHNICAL REPORT 770, REV 1 04/12/90 (Safety Evaluation #90-0104)

This report was prepared to document the evaluation of potential emergency core cooling system (ECCS) flow inconsistencies reported by Westinghouse under 10CFR21.

A review of existing accident analyses concluded that only the small break loss of coolant accident (LOCA) event is impacted by the ECCS calculation revision. The evaluation of small break LOCA has resulted in increases in the peak clad temperature (PCT), however, the results remain within the acceptance limit in 10CFR50.46. Therefore, the current margin of safety is maintained and* no unreviewed safety question exists.

Sl-AC-90-418 ADMINISTRATIVE CONTROL 04/19/90 (Safety Evaluation #90-0106)

This request placed administrative control over 1-SA-226, a manual valve which isolates service air to the emergency switchgear room (EGSR). This request also ensures that the main control room (MCR) pressure envelope can be maintained.

Administrative control over 1-SA-226 in accordance with SUADM-0-26 ensures the ability to maintain the MCR/ESGR pressure boundary in the event of a radioactivity release. The valve will be closed immediately upon notification by the MCR. In addition, control over the valve will ensure that the integrity of the pressure boundary is maintained for assurance of operability for the MCR air bottle dump system. Therefore, an unreviewed safety question is not created.

SCAFFOLD REQUEST UNIT 2 04/19/90 (Safety Evaluation #90-0107)

This request is for the erection of temporary scaffold in Unit 2 safeguards/main steam valve house basement to install piping and supports per DCP 88-19.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

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.- L FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: APRIL 1990 SCAFFOLD REQUEST UNIT 2 04/19/90 (Safety Evaluation #90-0108)

This request is for the erection of two temporary scaffolds to install piping and supports per DCP 88-19.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 2 04/19/90 (Safety Evaluation #90-0109)

This request is for the erection of two temporary scaffolds in Unit 2 safeguards/main steam valve house basement to install piping and hangers per DCP 88-19.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 2 04/19/90 (Safety Evaluation #90-0110)

This request is for the erection of temporary scaffold to support maintenance on dampers 2-VSP-MOD-200A & B per work order #3800088434 and 3800088437, respectively.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

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--~ e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: APRIL 1990 SCAFFOLD REQUEST UNIT 2 04/19/90 (Safety Evaluation #90-0111)

This request is for the erection of temporary scaffold to replace heat trace circuits 2A2-29 and 2B2-29 per job order #049518.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 04/19/90 (Safety Evaluation #90-0112)

This request is for the erection of temporary scaffold to support maintenance on dampers 2-VSP-MOD-58A & B per work order #3800088436 and 3800089862, respectively.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 04/19/90 (Safety Evaluation #90-0113)

This request is for the erection of temporary scaffold to support maintenance on dampers 2-VSP-MOD-lOOA & B per work order #3800088431 and 3800088433, respectively.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: - - APRIL

--- 1990 Sl-TM-90-08 TEMPORARY MODIFICATION 04/25/90

{Safety Evaluation #90-0llBA)

This temporary modification is to document electrical isolation of the LCR relay associated with the control of the radiator louvers on the Unit 1 emergency diesel generator. The isolation of this relay allowed the radiator louvers to open.

The temporary modification will not change the operation or function of the emergency diesel generator. The modification will not increase the probability of an accident, the consequences of an accident or create a potential for an accident of type that has not been previously analyzed. Therefore, an unreviewed safety question does not exist.

SCAFFOLD REQUEST UNIT 2 04/30/90 (Safety Evaluation #90-0119)

This request is for the erection of temporary scaffold to gain access to the Unit 2 11 D11 waterbox to support tube sheet cleaning.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded, that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

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PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: APRIL 1990 NONE DURING THIS REPORTING PERIOD 15

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/'t.'EAR: - -APRIL

- -1990 NONE DURING THIS REPORTING PERIOD 16

VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR: APRIL 1990 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX. MIN. AVG. MAX. MIN. AVG.

Gross Radioact., µCi/ml 9.02E-1 5,55E-1 7.07E-1 2.44E-1 1. 48E-1 2.02E-1 Suspended Solids, ppm o.o o.o 0.0 o.o 0.0 0.0 Gross Tritium, µCi/ml 1. 79E-l l.75E-l l.78E-1 4.59E-l 4. llE-1 4.37E-l Iodine-131, µCi/ml 1. 03E-2 3.80E-3 5.14E-3 1.09E-3 3.60E-4 5.54E-3 Iodine-131/Iodine-133 0.21 0.10 0.13 0.13 0.06 0.10 Hydrogen, cc/kg 33.6 27.2 31.3 33.6 21.2* 28.6 Lithium, ppm 2.29 1.61 1.90 2.32 2.06 2.15 Boron - 10, ppm* 58.0 38.8 46.4 143.50 127.80 135.20 Oxygen, (DO), ppm 0.005 0.005 0.005 0.005 0.005 0.005

<0.010 0.003 0.005 <0.010 0.006 0.007 Chloride, ppm pH@ 25 degree Celsius 7.21 7.07 7.15 6.70 6.55 6.62

UNIT ONE: 'B' mixed bed was replaced by 'A' mixed bed on 04/28/90 at 0640.

UNIT TWO:

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  • UNIT 1&2 FUEL HANDLING DATE: APRIL 1990 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT I OR RECEIVED PER SHIPMENT NUMBER ~UMBER ENRICHMENT CASK ACTIVITY LEVEL NONE DURING THIS REPORTING PERIOD 18

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DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: ~-AP_R_IL~19_9_0~

NONE DURING THIS REPORTING PERIOD 19

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