ML18152A289

Monthly Operating Repts for Aug 1988 for Surry Power Station.W/880914 Ltr

ML18152A289
Person / Time
Site:	Surry
Issue date:	08/31/1988
From:	Cartwright W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-627, NUDOCS 8809200124
Download: ML18152A289 (25)

Text

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• VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-08 APPROVED: ATION MANAGER ' :3809200124 880:::::31 PDR ADOCK 05000280 R PDC -~ POW 34-04

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• SECTION Operating Data Report -Unit No. 1 Operating Data* Report -Unit No. 2 1 Unit Shutdowns and Power Reductions

-Unit No. 1 Unit Shutdowns and Power Reductions

-Unit No. 2 Average Daily Unit Power Level -Unit No. 1 Average Daily Unit Power Level -Unit No. 2 Summary of Operating Experience

-Unit No. 1 Summary of Operating Experience

-Unit No. 2 Facility Changes Requiring NRC Approval Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval

• Procedure or Method of Operation that Did Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments That Did Not Require NRC Approval Chemistry Report Fuel Handling -Unit No. 1 Fuel Handling -Unit No. 2 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1 3 4 6 7 8 9 ll: 12 15 16 17 18 19 20 21 22 PAGE 1 *

• OPERA?ING DATA REPORX DOCKE'I NO. 50-280 DATE 09/08/88 . COMPLETED BY L. A. Warren TELEPHONE 804-357-3184 OPERATING STAXUS l. Unit Name: Surry Unit # 1 Notes 2. Reporting Period: August O 1 thru 31. 19 8 8 3. Licensed Thermal Power (MWt): 2441 -..:::..::..=-=------

4. Nameplate Rating (Gross MWe): _.,;8~4.:.:7:..::*:..::5

___ _.,, __ _ 5. Design Electrical Rating (Net MWe): 788 6. Maximum Dependable Capacity (Gross MWe): ~82:;.,;0;...._

__ 7. Maximum Dependable Capacity (Net MWe): 781 8, If Changes Occur in Capacity Ratings (Items Number 3 nirough 7) Since Last Report, Give Reasons: 9. Power Level Io Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: This Month Yr.-to*Date 11, Hours In Reporting Period 744.0 5855.0 12. Number of Hours Reactor Was Critical 708.7 3437.0 13, Reactor Reserve Shutdown Hours 0 0 14. Hours Generator On-Line 688.0 3316.6 15, Unit Reserve Shutdown Hours 0 0 16. Gross Thermal Energy Generated (HWB) 1637979.2 7682198.9

17. Gross Electrical Energy Generated (HWB) 544765.0 2573560.0

18. Net Electrical Energy Generated (HWB) 516472. 0 2442986.0

19. Unit Service Factor 92.5% 56.7% 20. Unit Available Factor 92.5% 56. 7% 21. Unit Capacity Factor (Using MDC Net) 88.9% 53.4% 22. Unit Capacity Factor (Using DER Net) 88.1% 53% 23. Unit Forced Rate 7.5% 3.9% 24. Shutdown*

Scheduled Over Next 6 Month* (Xype, Date, and Duration of Each), 25. If Shut Down At End Of Report Period Estimated Date of Startups 26. Unit* In Teat Status (Prior to Couaercial Operatioa)1 lH1TIAL CRinCALiff IH1'nAL !L!C'l'llCiff COHHER.CIAL OPERAnON rorecaat Cumulative 137567.0 88160.4 3774. 5 86287.8 3736.2 200402420.3 64948733.0 61598362.0 62.7% 65.4% 57.9% 56 .-8% 17 .2% Achieved (9/77)

• ** OPERA7ING DA:rA REPOJa OPERATING SL\l'US (JULY) PAGE I CORRECT~ COPY 09/0.8/88 PAGE 2 DC>CREl: NO. 5 0-28 0 DA1'B 8/3/88 COMPLETED BY L. A. warren m.EPHONE 804-357-3184

1. Unit Name: Surry Unit # 1 Notes 2. Reporting Period: July O 1 thru 31, 1988 3. Licensed Thermal Power (MWt): __,2.._4_4::..:l=-------

4. Nameplate Rating (Gross MWe): _8:..4.:.:7:..:*:.=5"------

s. Design Electrical Rating (Net HWe): 788 6. Maximum Dependable Capacity (Gross HWe): ----'82_0'------

7. Maximum Dependable Capacity (Net HWe): ___ 7_8 __ 1 __ _ a. 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 HWe): 10. Reasons For Restrictions, If Any: This Month Yr.-to-Date

11. _Hours In Reporting Period D 5111.Q 12. Number of Hours Reactor Was Critical ~lS.Z 2728~3 13. Reactor Reserve Shutdown Hours Q.Q o*o 14. Hours Generator On-Line 33]~0 2628~6 lS. Unit Reserve Shutdown Hours a.a o*o

• 16. Gross Thermal Energy Generated (HWB) Z2UQ~.5 6Q44219~7

17. Gross Electrical Energy Generated (HWB) 23~11Q.Q 20287915 18. Net Electrical Energy Generated (HWH) 221QlQ.Q 1926514~0

19. Unit Service Factor 51;4% 20. Unit Available Factor 51~4% 21. Unit Capacity Factor (Using MDC Ret) 3B.Q% 48;3% 22. Unit Capacity Factor (Using DER Net) 32~2% jz;a% 23. Unit Forced Rate g;Q'.% 2* 9% 24. Shutdown, Scheduled Over Next 6 Month1 (type, Date, and Duration of !acbh 25. If Shut Down At Ind Of Report Period Estimated Date of Startup* 26. Unit1 In Teat Statu1 (Prior to C011111ercial Operation)a rorecaat CUmulative

]36823"0 **.874$.1:7-.

3774~5 85599.8 3736.2 198764441.1 64403968.0 61081890.0 . 62.6% 65~3%. 57. 7.% 56".7% 17~2% Achieved (9/77)

PAGE 3 *

• OPERATING DATA REPORT DOCKET NO. 50-281 DATE 09/QR/RR COMPLETED BY L. A. warren TELEPHONE 804-357-3184 OPERATING STATUS 1. Unit Name: Surry Unit # 2 Notes 2. Reporting Period: Auqust 01 thru 31, 1988 3, Licensed Thermal Power (HWt): 2441 ......::::.......::.:a...------

4.

• Nameplate Rating (Gross HWe): 847.S ____ ........., _____ _ 5. Design Electrical Rating (Net HWe): 788 6. Maximum Dependable Capacity (Gross HWe): _8.;;..2::;.0.;;.._

__ 7. Maximum Dependable Capacity (Net HWe): 781 8. If Changes Occur in Capacity Ratings (Items Number 3 l'hrough 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any:

• This Month Yr. -to-Date 11, Hours In Reporting Period 744.0 5855.0 12, Number of Hours Reactor Was Critical 744.0 4810.3 13, Reactor Reserve Shutdown Hours ,0 0 14. Hours Generator O~~Line 744.0 4776.7 15. Unit Reserve Shutdown Hours 0 0

• 16, Gross Thermal Energy Generated (HWB) 1492661. 9 11193381.0

17. Gross Electrical Energy Generated (HWH) 443590.0 3649135.0

18. Net Electrical Energy Generated (HWB) 414737.0 3464826.0

19. Unit Service Factor 100% 81.6% 20. Unit Available Factor 100% 81.6% 21. Unit Capacity Factor (Using MDC Net) 71.4% 75.8% 22. Unit Capacity Factor (Using DER Net) 70. 7% 75.1% 23, Unit Forced Rate 0 18.4% 24, Shutdowns Scheduled Over Next 6 Months (?ype, Date, and Duration of Each): Refueling outage, 9/9/88, 68 days . 25, If Shut Down At End Of Report Period Estimated Date of Startupr 26. Units In rest Status (Prior to C011111ercial Operation)r INITIAL CRITICALITY INITIAL ELECTRICI?Y COMMERCIAL OPERAl'ION Forecast Cumulative 134447.0 89476.3 328.1 88075.0 0 206363743.7 67021959.0 63541303.0 65.5% 65.5% 60. 7% 60% 14.6% Achieved (9/77)

-II NO. DATE 11. >-,_ 88-06 8/12/88 s 88.:.07 8/15/88 F , 88-08 8/27 /8_8 IS 88-09 8/29/88 F 1 F: Forced 2 S: Scheduled (9/77) PAGE 4 UNIT SHUIOOWNS AND POWER REDUCTIONS DOCKET NO. _5_0_-_2_80

_____ _ UNIT NAME Surry Unit # DATE 09/08/88 alU'LETED BY L. A. Warren REPORT MONTH ___ A __ U ____ G._u ... s __ T......._l,_9,_88

___ _ TELEPHONE 804-357-3184

.., .. C .... a, 0 0 -N 0 C .. ... II C ... u .. .. 0 '1::1 .. II :::, II 0 II a, 0 .. II! .. CD .s::. :::, :::, J: II .. .s::. 0 II! II C :I: UJ JI 0 0 o.o F 1 56 A 3 o.o B 1 0.0 A 1 Reason: A -Equipment Failure (Explain)

B -Maintenance or Test C -Refueling D -Regulatory Restriction LICENSEE EVENT REPORT# E -Operator Training & License Examination F -Administrative G -Operational Error (Explain)

H -Other (Explain) 3 .. E~ C II ,n II II C II .. '1::1 0 '1::1 CAUSE & CORRECTIVE ACTION to II 0 11. 0 :; a E 0 PREVEN'I RECURRFJ( CE 0 0 Unit reduced to 89% power 730MW to maintair condensate polishing

~p less than 50 psid. Unit reactor trip and safety injection due tc a failed CLS relay during Ini;trument Departmen1 testing. , Unit reduced to 68% 560MW to permit repain to main generator H2 cooling system. Unit reduced to 78% 650MW to repair isolated phase bus duct grounding straps. Method: 4 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (I.Ell) File (NUREG 0161) 5 Exhibit 1 -s.-Source

-1D NO. DA:rE a. >, I-88-12 8/06/88 s 88-13 8/08/88 s 88-14 8/17/88 s 8/18/88 I 88-15 s 88-16 8/20/88 s 88-17 8/26/88 s 88-18 8/31/88 s 1 F: Forced 2 S: Scheduled

.(9/77) UNIT SHUTDOWNS AND POWER REDUCTIONS REPffiT MONTH AUGUST 1988 "' .. C ... CD 0 .. 0 -N 0 C .. LICENSEE C ... .. C ... u E :r II in .. .. 0 'tJ .. 1D II II C II Ill :J m 0 .. II EVENT .. 'tJ 0 'tJ .. 0 1D .r: .. 0 a. 0 :c II :J ~o :J .. .r: REPORT# E 0 C -II en C 0 :a 0 0 C 0.0 B 1 0.0 B 1 0.0 B 1 o.o B 1 0.0 B 1 0.0 B 1 0.0 B 1 Reason: 3 Method: A -Equipment Failure (Explain)

B -Maintenance or Test 1 -Manual 2 -Manual Scram. PAGE 5 DOCKET NO. __ s_o-_2_8_1

_____ _ UNITNAME __ ~s~u~r~rv~u~oi~t

....... U_2.;._ ____ _ DATE 09/08/88 -----------------

COMPLETED BY L. A. Warren TELEPoo~:::so:4:-:3:s1:-~3:1s~4::::~:=

CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE Unit reduced to 73% SOOMW to clean waterboxes and perform waterbox tube cleaning.

Unit reduced to 73% 5151\1W to repair waterbox tube leak. Unit reduced to 69.5% 510MW to clean water boxes. Unit reduced to 75% 555MW to perform 2-PT-29~ 1 turbine valve freedom test. Unit reduced to 71% 505MW to clean water boxes. Unit reduced to 71.5% 520MW to clea water boxes. Unit reduced to 62% 440MW to clean water boxes. 4 C -Refueling D -Regulatory Restriction 3 -Automatic Scram. 4 -Other (Explain)

Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) E -Operator Training & License Examination . F -Administrative G -Operational Error (Explain)

H -Other (Explain) s Exhibit 1 -Same Source MONTH *

• PAGE 6 AVERAGE DAILY UNIT POWER LEVEL AUGUST 1988 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 760 2 759 '3 756 4 733 '5 739 6 762 7 760 8 759 9 762 10 761 11 760 12 711 1 '3 757 14 758 1 '5 754 16 0 INSTRUCTIONS DOCKET NO, 50-280 ---,.,...._-~-..--

UNI? Surry Unit # 1 DArE 9/8/88 COMPLETED BY L. A. Warren . ?ELEPHONE 804-357-3184 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 333 18 717 19 762 20 764 21 764 22 765 2 '3 767 24 765 25 764 26 764 27 718 28 765 29 745 '30 766 31 769 On this format, list the average daily unit power level in MWe-Net for ~ach day in the reporting month, Compute to the nearest whole megawatt.

(9/77)

• PAGE 7 .. AVERAGE DAILY UNIX POWER LEVEL MONTH AJJGJJST J 988 DAY AVERAGE DAILY POWER LEVEL 1 2 '3 4 5 6 7 8 9 10 11 12 l'3 14 15 16 INSTRUCTIONS (MWe-Net) 625 620 616 611 511 592 560 512 577 571 567 567 566 569 570 DOCKE'.r NO. 50-281 ~:----,,.,,.....,,......,,.--

UNIT Surry Unit # 2 DATE 9/8/88 COHPLE'IED BY L. A. Warren !ELEPHONE 804-357-3184 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 18 19 20 538 21 521 22 530 23 533 24 567 25 547 26 533 27 544 28 529 29 528 '30 514 31 496 On this format, list the average daily unit power level in MWe-Net for ~ach day in the reporting month. Compute to the nearest whole megawatt.

_(9/77)

• *

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR

__ A_U-'-G;..-U_S_T""""l"-'9....c;8_8_

PAGE 8 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 08-01-88 0000 08-12-88 0505 0529 1530 1600 2115 2252 08-15-88 0927 08-16-88 2049 08-17-88 1733 2011 2333 08-18-88 0500 08-27-88 0045 0211 0500 0643 08-29-88 1325 1342 1506 This reporting period begins with the unit at 100% 810 MW. Commenced power reduction at 150 MW /hr to maintain condensate polishing differential pressure less than 50 psid. Holding power at 92% 735 MW. Commenced power reduction at 150 MW /hr to maintain condensate polishing differential pressure.

Holding power at 89% 730 MW. Commenced power increase at 150 MW /hr. Unit at 100% 805 MW. Unit reactor trip and safety injection due to a failed CLS relay. Reactor Critical.

Unit on line. Holding power at 58% 810 MWs. Commenced power increase at 5%/hr. Unit at 100% 805 MW. Commenced power reduction at 150 MW /hr to permit repairs to main generator Hz cooling system. Holding power at 68% 560 MW. Commenced power increease at 150 MW /hr. Unit at 100% 805 MW. Commenced power reduction at 5%/min. to repair isolated phase bus duct grounding straps. Holding power at 78% 650 MW. Commenced power increase at 5%/hr.

• PAGE 9

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR AUGUST 1988 ---------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 (cont'd) 08-29-88 1840 08-31-88 2400 UNIT TWO 08-01-88 0000 08-06-88 0500 0545 1100 1600 08-07-88 0445 0513 08-08-88 0703 0703 08-09-88 0130 1600 1838 2400 08-17-88 2101 2225 Unit at 100% 805 MW. This reporting period ends with the unit at 100% 805 MW. This reporting period begins with the unit at 89% 655 MW due to 3B feedwater heater being out of service. Commenced power reduction at 150 MW /hr to permit cleaning water boxes. Holding power at 79.5% 580 MW. Commenced power reduction at 3%/hr to support waterbox tube cleaning.

Holding power at 73% 500 MW. Commenced power increase at 150 MW /hr. Holding power at 90% 665 MW. Commenced power reduction at 150 MW /hr to support waterbox maintenance.

Holding power at 79% 600 MW. Commenced power reduction at 0.5%/hr to maintain condenser backpressure less than 5 psid. Holding power at 73% 515 MW. Commenced power increase at 3%/hr. Holding power at 88% 640 MW. Commenced power reduction at 150 MW /hr to clean water boxes. Holding power at 69.5% 510 MW.

• PAGE 10

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR

__ A_U_G_u_s_T_l

_98_8 __ _ 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 TWO 08-18-88 0500 (Cont'd) Commenced power increase at 3%/hr. 0800 Holding power at 85% 630 MW. 2243 Commenced power reduction at 150 MW/hr to perform 2-PT-29.1.

2313 Holding power at 75% 555 MW. 0 8-19-8 8 12 4 7 Commenced power increase at 3%/hr. 1600 Holding power at 84% 600 MW. 08-20-88 2232 Commenced power reduction at 150 MW /hr to clean waterboxes.

08-21-88 0000-2400 Varied unit power and load between 82% 600 MW to 71% 505 MW 08-22-88 0521 0800 08-26-88 1825 1903 2100 2345 08-31-88 1910 2007 2252 08-31-88 2400 too support waterbox cleaning.

Commenced power increase at 3%/hr from 71 % 505 MW. Holding power at 79% 590 MW. Commenced power reduction at 150 *MW/hr to permit cleaning water boxes. Holding power at 71.5% 520 MW. Commenced power increase at 3%/hr. Holding power at 78.5% 590 MW. Commence power reduction at 150 MW /hr to clean waterboxes.

Holding power at 62% 440 MW. Commenced power increase at 8%/hr. This reporting period ends with the unit at 70% 490 MW due to 3B feedwater being out of service, 1 C 1 waterbox removed from service for cleaning and EOL coastdown in progress.

• F AGILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR AUGUST 1988 NONE DURING THIS PERIOD PAGE 11 DC 84-69 DC 86-15 DC 87-32 PAGE 12 *

• FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR AUGUST 1988 ---------PRESSURIZER SAFETY VALVE LOOP-SEAL INSULATION OVENS UNIT l This design change installed metal reflective thermal insulation boxes which will enclose the safety valves loop seal piping. This is to maintain the loop seal water temperature at approximately 400°F. This temperature will allow part of the water to flash to steam after passing through the safety valves. The reduced density of the watersteam mixture will cause reduced fluid transient loads for the piping and supports.

SUMMARY

OF SAFETY ANALYSIS The installation of the boxes will not affect the operation of the pressurizer or the safety valves. The boxes will reduce fluid transient loads to ensure the piping and supports are qualified for the design basis transients once the supports have been modified.

The boxes do not affect any safety related system or component and does not impact any Technical Specification.

LEVEL INSTRUMENTATION TO PREVENT LOSS OF SHUTDOWN COOLING UNIT l This design change installed a permanent standpipe arrangement to replace the temporary polyhose arrangement installed during each outage. Local level indication, control room indication and a control room low level alarm are provided for reactor coolant level during outage periods.

SUMMARY

OF SAFETY ANALYSIS The system will be placed into service only during cold shutdown conditions.

At all other times the system is isolated from other systems. The portion of the system up to and including the second isolation valve is designed to reactor coolant design pressure and temperature.

This system does not affect safety related equipment or the operation of the safety related systems. WEED 9007 RTD REPLACEMENT UNIT l This modification replaced the eighteen (18) narrow range RTDs with RTDs which have adequately demonstrated environmental qualification as set forth by NUREG 0588 Category 1.

SUMMARY

OF SAFETY ANALYSIS The replacement RTDs 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 13 FACIIJT.ANGES THAT DID NOT REQUIR.RC APPROVAL MONTH/YEAR AUGUST 1988 AC S2-88-0615 ADMINISTRATIVE CONTROL 08/04/88 This change provides administrative control while closing MOV-SW-205B or MOV-SW-205D in order to accomplish maintenance on the associated valve. Since the valves (MOV-SW-205B and 205D) will remain operable and will be manually opened prior to auto or manual start of the recirculation spray (RS) pumps, the change will not affect the operation of the RS system. Therefore, no unreviewed safety question is created. AC S2-88-0805 ADMINISTRATIVE CONTROL 08/05/88 FS 88-40 TM S2-88-60 This change maintained recirculation spray (RS) heat exchangers service water discharge valves 2-SW-MOV-205B

& D closed under administrative control to prevent service water ingress to the recirculation spray heat exchangers from the discharge tunnel to prevent biofouling of the RS heat exchangers.

Since the valves (MOV-SW-205B and 205D) will remain operable and will be manually opened prior to auto or manual start of the RS pumps, the change will not affect the operation of the RS system. Therefore, no unreviewed safety question is created. FSAR CHANGE REQUEST 08/09/88 Design Change 77-09 modified the usable volume of Unit 1 and Unit 2 R WSTs. The modification affected LC Os for safety injection and* containment spray systems. The 10 CFR 50.59 review resulted in no unreviewed safety question since DC 77-09 did not alter the basic design function of the affected systems. TEMPORARY MODIFICATION 08-19-88 This modification allowed the lead from terminal board 58C-2 to 2AST 1 to be lifted and prevent the mechanical anti-motoring trip from operating.

Removal of the mechanical anti-motoring trip will not have an adverse effect on the turbine overspeed or loss of electrical load analysis.

Therefore, there is no unreviewed safety question.

TM Sl-88-132 TEMPORARY MODIFICATION 08/20/88 A jumper was installed from the sample connection of the VCT gas space to the sample connection of the gas stripper surge tank at the sample sink. Venting the VCT via the sampling system will not increase the probability of an accident nor increase the consequences of an accident.

Protection to the system is provided by relief valves in the system. Hose and fittings are rated in excess of operating pressures for the systems. Therefore, no unreviewed safety question is created.

A PAGE 14 FACIUT.ANGES THAT DID NOT REQUIRlaRC APPROVAL AC Sl-88-810 AC S2-88-8 IO MONTH/YEAR AUGUST 1988 ADMINISTRATIVE CONTROL 08/20/88 While the charging pump component cooling (CC) pump's drain valve is open to feed and bleed the system to increase chromate concentration, an operator will be stationed at the drain valve to close it immediately should the head tank level drop .s_ 30%. Feeding and bleeding the charging pump CC system by opening the charging pump CC pump's drain valve will not affect the operability of the charging system. It will enhance corrosion control by the addition of chromates.

Therefore, this administrative control does not constitute an unreviewed safety question.

AC Sl-88-0820 ADMINISTRATIVE CONTROL 08/20/88 This change maintained recirculation spray (RS) heat exchanger (HX) service water (SW) discharge valve (1-SW-MOV-lOSA) closed under administrative control to prevent SW ingress into the RS HX from the discharge tunnel to prevent biofouling of the RS HX. Since valve 1-SW-MOV-lOSA will remain operable (as per EWR 88-326) and will be opened prior to auto or manual start of the RS pumps, the change will not affect the operation of the RS system. Therefore, no unreviewed safety question is created. AC Sl-88-0821 ADMINISTRATIVE CONTROL 08/21/88 This change allowed manual control over the 'C' RSST tap changer with constant communication with the control room due to failure in the automatic control. Manual control of the 'C' reserve station service transformer tap changer is required due to a failure in the automatic system. Manual control ensure voltages on the emergency buses will remain in spec and will reduce the chance of loss of off site power to 1 H and 2J emergency buses. Manual operation will maintain voltages within the intent of GDC 17. AC Sl-88-0823 ADMINISTRATIVE CONTROL 08/23/88 The dike at the emergency switchgear room was temporarily removed and a flood watch was placed at the door and at the turbine building pit areas. The dike was reinstalled in the event of a flood. The removal of this dike will not adversely affect any safety related equipment or create an unreviewed safety question.

l-TOP-2027 OCEDURE OR METHOD OF OP AT DID NOT REQUIRE NRG APP MONTH/YEAR AUGUST 1988 TEMPORARY OPERATING PROCEDURE PAGE 15 08/01/88 This change provided a means for flushing the primary drains transfer tanks (PDTT) discharge lines to the primary drains tanks (PDT) and to inspect PDTT pumps discharge check valves to clear/identify blockage in PDTT discharge lines. An unreviewed safety question does not exist because the probability and consequences of a liquid waste release are unaffected.

All liquid waste released from the check valves will be contained and directed to floor drains and the containment sump. Flush water will also be directed to the PDT and will be contained.

Any uncontrolled release will be stopped by closing l-DG-74. This valve can also be immediately shut if containment isolation is necessary.

JUSTIFICATION FOR CONTINUED OPERATION 08/11/88 This Justification for Continued Operation documents plant operation with three out of four Radiation Monitoring Pumps operable on Service Water Discharge Lines from Recirculation Spray Heat Exchangers (RSHX). The reviewed condition does not affect the function of the RS system. Significant increases in exposure or releases will not occur because a backup radiation monitor exists and under the postulated failure of the RSHX, the heat exchanger can be

• isolated without reducing the required heat removal via the RS system. Therefore, an unreviewed safety question does not exist.

• PROCEDURE OR METHOD OF OPERATION THAT DID REQUIRE NRC APPROVAL MONTH/YEAR AUGUST 1988 --------NONE DURING THIS PERIOD PAGE 16

• PAGE 17 TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH/YEAR AUGUST 1988 ----------

NONE DURING THIS PERIOD

• PAGE 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR AUGUST 1988 -----------

NONE DURING THIS PERIOD

• VIRGINIA POWER SURRY POWER STATION

• CHEMISTRY REPORT 19 88 -----------

AUGUST PAGE 19 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS -MAX. Gross Radioact., l!Ci/ml 8.88E-l Suspended Solids, PPm o.o Gross Tritium, µCi/ml 2.23E-l '

• 131 Iodine , µCi/ml 3.73E-3 1 131 1 1 1 *n 0.16 Hydrogen, cc/b. 31.9 Lithium, ppm 2.35 Boron-10, ppm* 267.0 Oxygen, (DO), 01>m <0.005 Chloride, ppm 0.010 pH@ 25 degree Celsius 6.50

• Boron-10

• Total Boron X 0.196 REMARKS: MIN. l.18E-l o.o l.51E-l 4.57E-4 0.09 25.5 2.06 184.0 <0.005 0.003 6.27 AVG. MAX. MIN. . AVG. 6.87E-l 2.00E-1 9.17E-2 1. 55E-l o.o o.o o.o o.o 1. 93E-l 6.47E-:i 3.78E-2 5.29E-2 2.54E-3 2. 04E:.L 6.23E-5 1. 30E-4 0 .12 0. 15 0.05 0.09 27.8 131. O 26.1 29.0 2.21 0.47 0.29 0.37 202.9 0.764 ~0.196 0.439 <0.005 <0.005 k0.005 <0.005 --0.007 <0.010 kO~OOl <0.002 --6.41 8.68 7.44 8 .11 UNIT I: Started month at 100%. Ramped down to 96% on 8-4 because of condensate polishing differential pressure and were back to 100% on 8-6. On 8-12, 0500 started to ramp down to 90% again due to condensate polishing differential pressure but were back to 100% by 2252. On 8-15 at 0927, a reactor trip occurred and the unit stayed in hot shutdown until the reactor was cr1tical on 8-16 at 2049. The unit was at 100% on 8-18 at 0500. On 8-27, started at 0025 to ramp down to 68% to repair a hydrogen cooler and was back to 100% by 0643. On 8-29, started at 1300 to ramp down to 79% due to fire in main generator leads and was back to 100% by 1855 and ended the month at 100%. Lithium was added 8-8 at 2010, 180g; 8-12 at 1025, 420g; 8-15 at 1830, 480g; 8-18 at 0515, 502g; 8-19 at 1300, 389g; 8-27 at 1100, 400g; for a total of 2371 grams of LiOH. UNIT 2: Started the month at 89%an~ coasting to refueling.

On 8-6 at 0545, ramped back to 73% to clean waterboxes and returned to 90% on 8-7 at 0840. On 8-8, ramped down to 72% to clean waterboxes and returned to 88% on 8-10 at 0035. On 8-18, ramped down to 73% to perform PT-29.1 and clean waterboxes and returned to 84% on 8-19. On 8-21 at 2204, ramped down to 71% to clean waterboxes and returned to 79% on 8-22 and end of month at 76%. The B Debora tor was in service from 8-7 at 2015 to 8-9 at 0035; from 8-26 at 2255 to 8-27 at 0925. Lithium was added 8-11 at 1330, 180g; 8-22 at 1250; 145g; 8-25 at 1115, 225g; 8-27 at 1100, 178g; for a total of 728 grams of LiOH.

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PAGE 20 *

• GNSI CASTOR V/21 #500-11-008 (ISFSI) UNIT 1 FUEL HANDLING DATE August 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT II RECEIVED PER SHIPMENT fl II ENRICHMENT CASK ACTIVITY LEVEL CV/21 500-11-008 08126188 NIA C50 --3.12% NIA CV/21 500-11-008 08126188 NIA C51 -3.12% N/A -

PAGE 21 .NSI CASTOR V/21 1500-11-008

• . (ISFSI) UNIT 2 FUEL HANDLING DATE August 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT()

RECEIVED PER SHIPMENT () 11 ENRICHMENT CASK ACTIVITY LEVEL CV/21 500-11-008 08/26/88 N/A P24 -3.11 N/A CV/21 500-11-008 08/26/88 N/A P05 -3.11 N/A CV/21 500-11-008 08/26/88 N/A P09 -3.11 N/A C'J /21 500-11-008 08/26/88 N/A P23 -3.11 N/A CV/21 500-11-008 08/26/88 N/A P04 -* 3.11 N/A CV/21 500-11-008

• 08/26/88 N/A P07 -3.11 N/A CV/21 500-11-008 08/26/88 N/A P02 -3.11 N/A CV/21 500-11-008 08/26/88 N/A P06 -3.11 N/A CV/21 500-11-008 08/26/88 N/A PI4 -3.11 N/A CV/21 500-11-008 08/26/88 N/A PI7 -3.11 N/A CV/21 500-11-008 08/26/88 N/A POI -3.11 N/A CV/21 500-11-008 08/26/88 N/A P03 -3.11 N/A CV/21 500-11-008 08/26/88 N/A P27 -3.11 N/A CV/21 500-11-008 08126188 NIA PIO -3.11 NIA CV/21 500-11-008 08126/88 NIA P28 -3.11 NIA CV/21 500-11-008 08l?fll88 NIA P08 -3.11 N/A CV/21 500-11-onR ORl?.fl/88 NIA Pl2 -3.11 NIA CV/21 -500-11-008 08/26188 NIA P22 -3.11 NIA CV/21 500-11-008 08/26188 NIA P29 --3.11 N/A

.. PAGE 22 *

• DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR AUGUST 1988 ----------

NONE DURING THIS PERIOD

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' . . \ * * . .../ VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 14, 1988 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 MONTHLY OPERATING REPORT Serial No. NO/RPC:vlh Docket Nos. License Nos.88-627 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 August 1988. W. R. Cartwright 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