ML18153B731

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Monthly Operating Repts for Apr 1989 for Surry Units 1 & 2. W/890515 Ltr
ML18153B731
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/30/1989
From: Stewart W, Warren L
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-361, NUDOCS 8905300025
Download: ML18153B731 (26)
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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 15, 1989 U. S. Nuclear Regulatory Commission Serial No.89-361 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 1989.

Very truly yours, Jl~

W. L. Stewart Senior Vice President - Power 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

POW 34-04 VIRGINIA ELECTRIC AND POWER COMP ANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 89-04 APPROVED:

e i 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 Requiring NRG Approval 8 Facility Changes That Did Not Require NRG Approval 9 Procedure or Method of Operation Changes Requiring NRG Approval 17 Procedure or Method of Operation Changes that Did Not 18 Require NRG Approval Tests and Experiments Requiring NRG Approval 19 Tests and Experiments That Did Not Require NRC Approval 20 Chemistry Report 21 Fuel Handling - Unit No. 1 22 Fuel Handling - Unit No.* 2 22 Description of Periodic Test Which Were Not Completed Within 23 the Time Limits Specified in Technical Specifications

e DOCKET NO.

DATE 50-280

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COMPLETED BY L. A. Warren TELEPHONE 804-357-3184 x355 OPERATING STATUS

1. Unit Name: Surry Unit 1 Notes
2. Reporting Period: April 01-30, 1989
3. Licensed Thermal Power (M:t): 2441
4. Nameplate Rating (Gross MWe): ---8"""4-7-.5~----

5, Design Electrical Rating (Net MWe): 788

6. Maximum Dependable Capacity (Gross MWe): ~8:.::2::.:0~--
7. Maximum Dependable Capacity (Net MWe): 781
8. If Changes Occur in Capacity Ratings (Items Number 3 l1lrough 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Moath Yr.-to-Date Cumulative

11. Hours In Reporting Period 719 .o 28179, 0 143375.0
12. Number of Hours Reactor Was Critical 0 0 88478.6
13. Reactor Reserve Shutdown Hours 3774.5
14. Hours Generator On-Line 86605 g
15. Unit Reserve Shutdown Roura 0 0 3736.2
16. Gross Thennal Energy Generated (MWH) 0 0 201171267.0
17. Gross Electrical Energy Generated (HWB) 0 0 65203673.0
18. Net Electrical Energy- Generated (MWR) 0 61840403.0
19. Unit Service Factor 0 60.4%
20. Unit Available Factor 63%
21. Unit Capacity Factor (Using MDC Net) 0 0 56.0'%
22. Unit Capacity FactoT (Using DER Net) 0 0 54. 7%
23. Unit Forced Rate 100% 100% 21.3%
24. Shutdowns Scheduled Over Next 6 Months (Typeb Date, and Duration of Each)r Forced Maintenance Outage on 9/14/88, scheduled on line date of 06/01('89.

25, If Shut Down At End Of Report Period Estimated Date of Startup:

26, Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

,* e DOCKET NO. 50-281 05/0 2/89 DATE COHPLE'rED BY L. A. Warren TELEPHONE 804-357-3184 x355 OPERATING STATUS

l. Unit Name: Surry Unit 2 Notes
2. Reporting Period: April 01-30, 1989
3. Licensed Thermal Power (MWt): 2441
4. Nameplate Rating (Gross MWe): --9""'4=7"""_5-----
5. Design Electrical Rating (Net MWe): 788 6.

7.

8.

Max:l,mum Dependable Capacity (Gross MWe):

Maximum Dependable Capacity (Net MWe):

If Changes Occur in Capacity Ratings (Items 820 781 Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, I f Any (Net MWe):
10. Reasons For Restrictions, If Any:

Thia Mooth Yr.-to-Date Cumulative

u. Hours In Reporting Period 719.0 2879. 0 140255.0
12. Number of Hours Reactor Was Critical 0 0 89§94.J
13. Reactor Reserve Shutdown Hours 0 0 328.1
14. Hours Generator On-Line 0 0 88293.0
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWB) 0 0 206740436.1
17. Gross Electrical Energy Generated (MWB) 0 0 67136244.0
18. Net Electrical Energy- Generated (MWH) 0 0 63647378.0
19. Unit Service Factor 0 0 63.2 %
20. Unit Available Factor 0 0 63%
21. Unit Capacity Factor (Using MDC Net) 0 0 58.2%
22. Unit Capacity Factor (Using DER Net) 0 0 57 .6%
23. Unit Forced Rate 0 0 15%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duratiou of Each)1 Refueling Outage on 09/10/88, scheduled on line date of 06/22/89 1 25, I f Shut Down At End Of Report Period Estimated Date of Startup:

26, Units In Test Status (Prior to Commercial Operatioo): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COHMERCIAL OPERATION (9/77)

PAGE 3 '

UNI'J: SHumowNS AND POWER REDUC'l:IONS OOCl<E'J: NO.

UN l 'J: NAME -----------

50-280

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89-04 04/01/89 F 720.0 F I Unit shutdown due to emergency diesel generator operability concerns.

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Method:

,. Exhibit G - lnatructiona S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data

  • B - Maintenance or 'teat 2 - Manual Scram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) File D - Regulatory Restriction 4 - Other (Explain) (NUREG 0161)

E - Operator 'training 6a License Examination 5

F - Administrative Exhibit l - Saae Source G - Operational Error (Explain)

(9/77) H

  • Other (Explain)

PAGE 4 '

UNl'I SHU'IDOWNS AND POWER ltED\JC'IlONS DOCICE'I o 50-281 N * -----------

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Method:

,. Exhibit G - Instructions S: Scheduled A - Equipment Failure (Explain) l - Manual for Preparation of Data

  • B - Maintenance or rest 2 - Manual Scram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) File D - Regulatory Restriction I+ - Other (Explain) (NUREG 0161)

E - Operator 'training & License Examination 5

F - Administrative Exhibit l - Saae Source G - Operational Error (Explain)

(9/77) H - Other (Explain)

    • I e e PAGES AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. ---e:!5~0._-....,28.._.0.___ _ __

UNIT Surry Unit 1 DATE 05/02/89 COMPLETED BY L.A. Warren TELEPHONE 804-357-3184 x355 MONTH . April 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 . 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 16 0 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.

(9/77)

  • J e PAGE 6 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-281 UN IT Surry Unit DATE 05/02/89

' COMPLETED BY L. A. -Warren TELEPHONE 804-357-3184 x355 MONTR . April 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 2 0 18 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 O* 31 16 0 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.

(9/77)

PAGE 7 e

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR APRIL 1989 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 04/01/89 0000 This reporting period begins with the Unit at CSD.

04/06/89 0431 Loss of electrical transfer bus 1F 1 due to a failed lightning arrestor on # 2 auto-tie transformer. During this evolution, the operating residual heat removal (RHR) pump was lost when the stub bus breaker tripped. The 1B1 train RHR pump was started and RHR flow was restored within one minute. The 1H emergency bus de-energized.

0458 # 1 EDG was started and loaded. 1H er.iergency bus re-energized.

0817 NRC notified of the above event.

04/13/89 1026 Loss of electrical transfer bus 1F 1 due to improper testing of relays in the distribution switchyard. 1H er.iergency bus de-energized.

1 1207 F 1 transfer bus re-energized.

1343 1 H emergency bus re-energized.

04/30/89 2400 This reporting period ends with the Unit at CSD.

UNIT TWO 04/01/89 0000 This reporting period starts with the Unit at CSD.

04/06/89 0431 Loss of electrical transfer bus 1F' due to failed lightning arrestor on #2 auto-tie transformer. #3 EDG automatically started and loaded on 2J emergency bus.

1 0715 F 1 transformer bus re-energized.

0919 #3 EDG secured.

04/13/89 1026 Loss of electrical transfer bus 1F' due to improper testing of relays in the distribution switchyard. #3 EDG automatically started and loaded on 2J emergency bus.

1207 'F' transfer bus re-energized.

1335 #3 EDG secured.

04/30/89 2400 This reporting period ends with the Unit at CSD.

PAGE 8 F AGILITY CHANGES REQUIRING NRG APPROVAL MONTH/YEAR _ _ _ A_PR_I_L_l9_8_9_

NONE DURING THIS PERIOD

. e PAGE9 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR APRIL 1989 DCS3-03 LIFTING LUGS FOR MAIN STEAM SAFETY VALVES UNIT 1 This design change installed lifting lugs in the ceiling of the upper level of the main steam valve house. The purpose of the lugs is to assist in the handling and rigging of the main steam safety valves during maintenance evolutions.

SUMMARY

OF SAFETY ANALYSIS The installation of the lugs did not affect the seismic or tornado resistance qualifications of the main steam valve house structure. The lugs do not affect any other safety related system and/ or structure.

DCS4-67 CHARGING PUMP SERVICE WATER PIPING REPLACEMENT UNITS 1&2 This modification replaced the charging pump service water fiberglass and silver brazed Cu-Ni piping in the Turbine Building - Auxiliary Building pipe tunnel and in the Auxiliary Building with heavy wall socket welded copper -

nickel piping. The valves in these pipe lines were replaced with bronze body flanged valves.

SUMMARY

OF SAFETY ANALYSIS The seismically qualified replacement piping will perform the same function as the fiberglass piping. The piping will not be as susceptible to fire damage. No changes other than material replacement were made to the charging pump service water system. The flow rate and heat removal capacity of the charging pump seivice water system which is used to ensure proper cooling of the charging pumps will not change from the existing requirements. The applicable technical specifications are not affected.

DC87-33 WEED 9007 RTD REPLACEMENT UNIT2 This modification replaced the eighteen (18) narrow range RI'Ds with RTDs which have adequately demonstrated environmental qualification as set forth by NUREG 0588 Category 1.

SUMMARY

OF SAFETY ANALYSIS The replacement Rills are essentially one for one replacements of an enhanced design and will not affect any of the operations or ability of equipment important to safety to perform their safety functions.

PAGE 10 e e FACILITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR APRIL 1989 SCAFFOLDING REQUEST 04/01/89 This request erected temporary scaffolding located in Unit 1 containment 1

C 1 loop room to work l-RC-FE-1482.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/01/89 This request erected temporary scaffolding located in Unit 1 containment

'A' loop to work l-RC-FE-1480.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/01/89 This request erected temporary scaffolding located in Unit 1 containment A, B, and C loop room to work various valves and flanges.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/02/89 This request erected temporary scaffolding located in Unit 1 containment

'A' loop room to work 01-RC-FE-1490.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/02/89 This request erected temporary scaffolding located in Unit 2 containment seal table room to allow disconnect and layout of thermocouple cable.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

. e e PAGE 11 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR APRIL 1989 SCAFFOLDING REQUEST 04/06/89 This request erected temporary scaffolding located in Unit 2 containment pressurizer cubicle to work NDE of 4" pressurizer spray line.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

TM-S 1-89-69 TEMPORARY MODIFICATION 04/(17/89 Temporary modification to secure the exhaust damper for 1-VS-lB in the open position.

This change does not constitute an unreviewed safety question because the containment air recirculation system is not required to function during design basis events.

TM-Sl-89-70 TEMPORARY MODIFICATION 04/07/89 Temporary modification to secure the exhaust damper for 1-VS-F-lC in the open position.

This change does not constitute an unreviewed safety question in that the containment air recirculation system is not required to function during design basis events.

SCAFFOLDING REQUEST 04/12/89 This request erected temporary scaffolding located in Unit 2 containment to allow disassembly and inspection of safety injection check valves.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST . 04/12/89 This request erected a temporary scaffolding located in Unit 1 containment 2' level to work l-SI-225.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

PAGE 12 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR APRIL 1989 SCAFFOLDING REQUEST 04/12/89 This request erected temporary scaffolding located in Unit 1 containment 27' level to work l-SI-148.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/'JJJ/89 This request erected temporary scaffolding located in mechanical equipment room # 1 to work piping insulation.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/'JJJ/89 This request erected temporary scaffolding located in Unit 1 emergency switchgear room to work on hanger installation.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

1&2-EWR-88-495 ENGINEERING WORK REQUEST 04/21/89 Request to install instrumentation for obtaining an accurate measurement of each of the three emergency service water pumps discharge pressure and flow during pump testing and operation.

The addition of flow instrumentation is an enhancement to the service water pumps providing the ability to obtain more accurate flow rate data to help improve system operability. Therefore, an unreviewed safety question is not created.

e PAGE 13 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR APRIL 1989 1&2-EWR-88-467 ENGINEERING WORK REQUEST 04/21/89 This request was generated to ensure the capability of the emergency service water pumps to provide make up water to the Intake Canal for the thirty day Loss of Off-site Power Accident.

The changes reviewed enhance the plant capability to mitigate the effects of an accident. The procedural changes decrease the probability of equipment malfunction. Failure of the added equipment results in the same failure modes previously evaluated. Therefore, an unreviewed safety question is not created.

SCAFFOIDING REQUEST 04/Z.3/89 The request erected temporary scaffolding located in Unit 1 containment 27' level to work MOV- l 720A repack.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/23/89 This request erected temporary scaffolding located in mechanical equipment room #3 to work l-VS-P-23 and l-SW-PCV-101B.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOIDING REQUEST 04/Z.3/89 This request erected temporary scaffolding located in Unit 1 containment elevation 13' to work l-RH-E-1 B outlet.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in mechanical equipment room # 3, elevation 9'6 " to work mechanical equipment room #3 charging pump and seIVice water pump room penetration.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

PAGE 14 e e FACIIJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR APRIL SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in Unit 1 containment 1

C 1 loop room to work l-RC-102.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in Unit 1 containment 1

C 1 loop room to repack l-RC-81.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in Unit 1 containment 1

C 1 loop room to work flange leak (1-RC-FNC).

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in Unit 2 containment to work 2-RC-PCV-2455B.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in Unit 1 containment to work l-SI-228.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

PAGE 15

' e e FACILITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR APRIL 1989 SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in Unit 1 containment basement to work l-SI-MOV-1865B.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/27/89 This request erected temporary scaffolding located in 'C' loop room Unit 1 containment to work electrical junction box (1-EPL-MISC-Box)

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/28/89 This request erected temporary scaffolding located in Unit 1 containment

'B' loop room to work l-SI-238.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/28/89 This request erected temporary scaffolding located in Unit 1 containment

'B' loop room to work l-RC-50.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 04/28/89 This request erected temporary scaffolding located in mechanical equipment room #3 to work l-VS-287/291; l-VS-P-2AlB outlet isolations.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

PAGE 16

' e e F AGILITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR APRIL 1989 SCAFFOLDING REQUEST 04/30/89 This request erected temporary scaffolding located in Unit 2 containment 31 elevation to work 2-SI-224, Tc discharge check valve.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

e e PROCEDURE OR METHOD OF OPERATION CHANGES PAGE 17 REQUIRING NRG APPROVAL MONTH/YEAR APRIL 1989 NONE DURING THIS PERIOD

e PAGE 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR APRIL 1989 1 & 2-TOP-2096 TEMPORARY OPERATION G PROCEDURE 04/10/89 This procedure allows filling a reactor coolant system loop and opening its loop stop valves following cold shutdown maintenance.

The procedure requires greater than 5% shutdown margin, the loop be filled with water from the reactor coolant system, the containment ambient temperature be within 20°F of reactor coolant temperature and sufficient initial reactor coolant system inventory. These actions ensure an unreviewed safety question is not generated.

l-TOP-2097 TEMPORARY OPERATING PROCEDURE 04/15/89 During ST-244 testing, VB I-III, circuit 15, will be opened rendering a residual heat removal (RHR) system valve controlling heat exchangers bypass inoperable (l-RH-HCV-1758). In order not to place a bypass flow or temperature transient on the system, HCV-1758 will be placed in the full open position and flow will be controlled by l-RH-19 manually.

In accordance with ST-244, this procedure ensures that during the testing of VB-I-III, circuit 15, that the residual heat removal (RHR) system does not receive a temperature or flow transient. RHR flow will be maintained during testing. Therefore, this temporary procedure does not create an unreviewed safety question.

PAGE 19

. . e TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR _ _ _A_PR_IL_l9_8_9_ __

NONE DURING THIS PERIOD

PAGE 20 e e TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR APRIL 1989 NONE DURING THIS PERIOD

). \ e VIRGINIA POWER SURRY POWER. STATION CHEMISTRY REPORT

  • PAGE 21

_ _ _ _AU,LP.,R.._II..,_,_ _ _ 19 89 PRIMARY COOLANT UNIT NO. 1 ANALYSIS UNIT NO. 2 MAX. MIN. AVG. MAX. MIN. AVG.

Gross Radioact., µCi/ml 7.80E-4 2.58E-4 5.15E-4 3.28E-3 9.70E-4 l.94E-3 Suspended Solids, ppm 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, µCi/ml - - - - - -

Iodine 131 , µCi/ml - - - - - - .

I Il31 / Il33 - - - - - -

Hydrogen, cc/kg - - - - - -

Lithium, ppm 0.55 0.49 0.52 0.21 0 .14 0 .17 Boron-IO, ppm* 422 395 404 434 422 427 Oxygen, (DO), DDm 1. 000 0.500 0.800 0.050 0.005 0.007 Chloride, ppm 0. 010 0.004 0.006 0.013 0.006 0.009 pH@ 25 degree Celsius 5.24 5.02 5.13 5.01 4.75 4.90

  • Boron-10
  • Total Boron X 0.196 UNIT ONE: The unit remained at cold shutdown with RHR and B-MB in service for the entire month. 1e 1 loop was isolated on 04/03/89 and drained on 04/10/89 for maintenance on-valves. 1e 1 loop has remained drained and isolated through 04/30/89.

UNIT TWO: The unit remained at cold shutdown with RHR and A-MB in service for the entire month. 1e 1 loop was isolated on 04/0 l /89 for normal valve maintenance, and filled and returned to normal line-up on 04/11/89 at 0945 hrs. Letdown was secured from 0935 to 1725 hrs. on 04/11/89 for maintenance to eves and charging MOV s.

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..,. e PAGE 22

-* FUEL HANDLING UNIT 1&2 DATE April 1989 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC SHIPMENT II RECEIVED PER SHIPMENT II II ENRICHMENT CASK ACTIVITY LEVEL NONE DU RING THIS l>ERIOD

~-

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  • e DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED PAGE 23 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR APRIL 1989 NONE DURING THIS PERIOD
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