ML18152A859

Monthly Operating Repts for Feb 1988.W/880315 Ltr

ML18152A859
Person / Time
Site:	Surry
Issue date:	02/29/1988
From:	BENSON D L, STEWART W L, WARREN L A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-132, NUDOCS 8803180050
Download: ML18152A859 (24)

Text

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• 4' a -. . 8803180050 880229 PDR ADOCI< 05000280 R DCD POW 34-04 e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-02 APPROVED:

Jrvvia. LJr/l14D11. . 0 MANAGER

• ./ SECTION --*-Operating Data Report -Unit No. 1 Operating Data Report -Unit No. 2 i 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 NRG Apprqval Facility Changes That Did Not Require NRG Approval Procedure or Method of Operation Changes that Did Not Require NRG Approval Procedure or Method of Operation that Did Require NRG Approval Tests and Experiments Requiring NRG Approval Tests and Experiments That Did Not Require NRG Approval Chemistry Report Fuel Handling -Unit No. 1 Fuel Handling -Unit No. 2 Procedure Revisions That Changed the Operating Mode Described in the FSAR Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE ' t ' 1 2 3 4 5 6 7 8 9 10-12 13 14 15 16 17 18 19 20 21

' .. -OPERAl'ING DAU REPOR% 1. Unit Name: Surry Unit # 1 Notes 2. Reportin&

Period: February 01-29, 1988 3. Licensed thermal Power CHWt): 2441 It. Nameplate Rating (Groaa MWe): 847,5 5. Design Eleei:i'ied bting (Nei: MWe) i --:.7..;:8:..:.:B;._..;,_..

__ 6. Maximum Dependable Capacity (Gro111 MWe): 820 7. Maximwa Dependable Capacity (Net MWe): 781 PAGE 1 OF 21 DOClCE'r No. __,.s ... 0-.... 2 .... 8 ..... 0 __ _ DAD 3/3/88 _...,...,..........,.,, __ _ COHPLnED BY L. A. Warren ttL!PHONE 804-357-3184

8. If Changes Occur in Capacity Ratings Cltema Humber 3 through 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted, If Any (Net MWe): 10. Reasons lor Restrictions, If Any: ?his Month Yr. -to-Date Cumulative ll. Hours In Reporting Period 696.Q 1440 1 0 133152.0 12. Number of Bour* Reactor Vas Critical 679~5 1423~5 86146.9 13. Reactor Reserve Shutdown Roura o.o o.o 3774.5 1,.. Hours Generator On-Line 672.0 1416.0 . 84387. 2 15. Unit Reserve Shutdown Hours o.o 0. 0 . 3736.2 . 16. Gross thermal Energy Generated (MW) 1606034.0 3417744.2 196137965.6

17. Gross Electrical Energy Generated (HWH) 542760.0 1157695.0

18. Net Electrical Energy Generated (MW) 516-58ft~

Q: . 11Q2405 1 0 19. Unit Service Factor .95:~6% 98~3 *% 20. Unit Available Factor 96.6% ;_98.3 % 21. Unit Capacity Factor (Usina MDC Net) 95% 98% 22. Unit Capacity Factor (Using DER Net) 94.2 97.2% 23. Unit Forced Rate 3.4% 1. 7% v.. Shutdowa Scheduled over llext 6 Months (type, Date, and Duration of !acbh Refuelin2 Outage, 4/2/88 -62 days

• 2S. If Shut Down At !nd Of Report Period Estimated Date of Startups 26. Units_ In Teat Status (Prior to CC11111ercial Operationh Forecast 63532868.0 60257781.0 63.4% 66.2 %. .26f~~

• 57*.4% 17.4% Achiev,ed (9/77)

• .. , e OPERilING DAU REPORT 1. Unit Name: Surry Unit # 2 Notes 2. Reportina Period: February 01-29. 1988 3. Licensed 'l'hermal Power CMWt):. 2441 It. Nameplate Rating (Cross MWe): 847.5 5. Dedsn Electrical l~t!ng (Net !file): 788 __ ...;.::; ___ _ 6. Kaxillum Dependable Capacity (Groaa MWe): 820 7. Maximum Dependable Capacity (Net MWe): 781 .e PAGE 2 OF 21 OOClCE? NO. 50-281 DilE 3/3/88 COHPLErED BY L. A. Warren tELEPHONB 804-357-3184

8. If Changes Occur in Capacity Ratings (Items Humber 3 through 7) Since Last Report, Give Reasona: 9. Power Level 'to Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: Thia Month Yr.-to-Date Cumulative

u. Hours In Reporting Period 696.0 1440.0 130032.0 12. Humber of Roura Reactor Was Critical 696.0 1440.0 86106.0 u. Reactor Reserve Shutdown Bour* 0.0 0.0 328.1 14. Hours Generator On-Line 696.0 1440.0 -84738.3 15. Unit Reserve Shutdown Boun o.o o.o 0.0 . 16. Gross tberaal Energy Generated (MWB) 1673842.0 3484907.7 198655270.4

17. Gross !lectrical Energy Generated (MWB) 557300.0 1163840.0 64536664.0

18. Net Electrical Energy Generated (MWB) 530236 ,.o 1107816.0 61184293.0

19. Unit Service Factor 100% 100% 65.2% 20. Unit Available Pactor 100% 100% 65.2% 21. Unit Capacity Factor (Usin& MDC Net) ~z.sz 98.5 6Q. ft,% :-22. Unit Capacity Factor (Using DER Net) 96. 7% 97.6 59:7% 23. Unit Forced Rate 0.0% 0.0% 14.2% v.. Shutdown*

Scheduled over lext 6 Hontha (type, Date, and Duration of !acb): Refu~l1Dg Ql1tag1;:

2£2£66 -~a da~s 25. If Shut Dow At !nd Of Report Period Estimated Date of Startup: 26. Units In 'teat Status (Prior to Commercial Operationh Forecast Acbie~ed (q/77\

II NO. DATE a. :,,, I-88-02 02-06-88 s 88-03 02-16-88 F I l

• F: Forced 2 S: Scheduled (9/77) UNIT SHUIDOWNS AND POWER REDUCTIONS REPORI K:>NTH FEBRUARY 1988 .. .., .. C .. a, a .. a -N a C .. LICENSEE E :r C ... .. C ... u II on .. .. a 'ti .. II II II C II CD :I II a ., II EVENT .. 'ti a 'ti .. a II .s: :I a: II 0 a. a :I ::c II .. .s: REPOR:r # CJ E CJ 0 -a: II CD C a ::E )I 0 a 0 o.o B 1 24.0 G 3 LER-280/ 88-003 Reason: 3 Method: A -Equipment Failure (Explain)

B -Maintenance or Test l -Manual 2

• Manual Sc.ram. PAGE 3 OF 21 DOCXET No. __ s_o-_2_0...,0

_____ _ UNIT NAME -~S!""u""'!'rry...;.~O-n_l_t_l

___ _ DATE -~3 ... /3 .... /_88 _______ _ COMPLETED BY -~L.~A~ * ..,.W,,...arr~,..,en

_____ _ TELEPHONE

__ 8_04_-_35_7_-_3_18_4

__ _ .. CAUSE & CORRECTIVE ACTION to PREVEN'I RECURRENCE Unit was reduced to 7 f'Plo power, 580 -MW*s to allow monthly testing of turbine valves (PT-29.1 ). During. performance of .PT-8.1, the Train 11 B 11 P-10 button was pushed when T?'.ain 'A'. was

• being .*tested causing a NIS Power Range Lo SP Hi fl~x reactor trip. Corrective action is to ensure proper pre-job briefing and to change some wording in the procedure to give command type steps when referring to which Train to be in*or to go to. e 4 C -Refueling D Regulatory Restriction 3 -Automatic Scram. 4 -Other (Explain)

Exhibit *c -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) 5 Exhibit 1 -Same Source .i I :1

• ---**--***-*"*-----*---'-**----

.........

______ ,. _________ , ___ ~----**-*-----~* ~-******--***-**

... -*---*** UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1988 .., L. C m a .. a -N a C ., LICENSEE E :zo C -... II C ... u 11*.., II .. L. D 'ti ., II II II C II NO. DATE a. II :, II a ., II EVEN'I .. "Cl a "Cl >-L. a Ill s: :, Ill: II D 0.. D ... :, :I: Ill .. s: REPORT# g; u E u C -Ill: II C D ::E en :, u a ,Q 88-02 02-20-88 s o.o *B 1 Unit was PAGE 4 OF 21 DOCKET NO. 50-281 ~~----------

UNIT NAME Surry Unit 2 DATE 3/3/88 COHPLE'J:ED BY L. A. Warren TELEPH0~:~8:o:4-:3~5~7-:3:1:s:4::::::: . CAUSE 6.CORREC'IIVE AcrION '.00 PREVEN't RECUltREMCE e reduced to 70% power, 580 MW to allow monthly testing of turbine valves (PT-29.1)

! 1 F: Forced 2 S: Scheduled (9/77) Reasons* A -Equipment Failure (Explain)

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

H -Other (Explain) 3 Method: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain) 4 s Exhibit G -InstTUCtion*

for Preparation of Data Entry Sheets for Licensee Event Report (LEll) File (NUREG 0161) Exhibit 1 -Same Source ... e

.1,

• MONTH PAGE 5 OF 21 e e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _s--'o __ -__ 2 __ 80""-----UNIT Surrv Unit I DATE 3l3l88 COMPLE'IED BY L~ A~ Warren TELEPHONE 804-357-3184 F~bruarv f988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 789 17 16.7 2 788 18 561 '3 788 19 787 4 788 20 785 5 789 21 787 6 724 22 788 7 788 23 788 8 785 24 787 9 788 25 788 10 789 26 787 11 790 27 785 12 789 28 787 l'3 788 29 782 14 789 30 15 789 31 16 385 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 b Ut ZI e. e AVERAGE DAILY UNIT POWER LEVEL MON'IH Februazy 1988 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 776 2 778 '3 777 4 777 5 776 6 775 7 776 8 777 9 777 10 776 11 774 12 776 l'3 775 14 776 15 776 16 773 INSTRUCTIONS DOCKE'I NO. __ 5.,.0-......._28

__ 1 _____ _ UNIT Surry Unit 2 DATE 3/3/88 COMPLETED BY L; A; warren ?ELEPHONE 804-357-3184 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 767 18 764 19 774 20 606 21 712 22 775 23 776 24 775 25 774* 26 770 27 671 28 744 29 771 '30 31 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)

---

~~--~-e. e

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR FEBRUARY 1988 PAGE 7 OF 21 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 02-01-88 0000 02-06-88 1047 1258 1430 2101 02-16-88 1143 02-17-88 0410 1144 1225 1440 1616 02-18-88 1113 2100

• 02-29-88 2400 This reporting period begins with the Unit at 100% power, 830 MW s. Commenced rampdown at 150 MW/hr. for performance of PT-29.1 (turbine valve stroking test). Holding power at 70%, 580 MW s. Commenced power increase at 40 MW s/hr. Unit at 100% power, 830 MW s. . Rx trip caused by NIS Power Range Lo SP Hi 0, while PT-8.1 was being performed.

• Rx critical.

Generator on line. Holding power at 30%, 180 MW s. Commenced power increase at 150 MW /hr. Holding power at 57%, 403 Mw* s due to IJ. flux problems.

Commenced slow power increase.

Unit at 100% power, 825 MW s. This reporting period ends with the Unit at 100% power, 825 MW s.

. e.

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR FEBRUARY 1988 PAGE 8 OF 21 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 02-01-88 0000 02-20-88 0455 0515 0712 0841 02-21-88 0528 0730 02-26-88 2230 2315 02-28-88 0604 0737 02-29-88-2400 This reporting period begins with the Unit at 100% power; 815 MW s~ Commenced slow power decrease due to losing condenser vacuum. Holding power at 99%, 800 MW*s~ Commenced power decrease at 150 MW /hr for performance of PT-29.1 (turbine valve stroking test)~ Holding power at 70%, 580 MW s~ Commenced power increase at 150 MW /hr~ Unit at 100% power, 810 MW s. Commenced power decrease at 15 0 MW /hr to allow removal of 11 1 A 11 FW heater. Holding power at 89%, 720 MW s~ Commenced power increase at 150 MW /hr~ Unit at 100% power, 810 MW s~ This reporting period ends with the Unit at 100% power; 810 MW s~

e. F AGILITY CHANGES REQUIRING NRG APPROVAL MONTH/YEAR FEBRUARY 1988 NONE DURING THIS PERIOD PAGE 9 OF 21 T-MOP-2007 TM-Sl-88-3 TM-Sl-88-06 TM-S2-88-8

• PAGE 10 OF 21 e . . F ACIUTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR FEBRUARY 1988 ----------

REPLACEMENT OF RV-BR-109 This temporary operating procedure involved the temporary hookup of fill and vent hoses from the gas stripper feed heat exchangers (HX) to the overhead gas compressors suction to evacuate the stripper feed HX while RV-BR-109 was replaced.

This change will not have an effect on the volume control tank (VCT) or waste gas decay tank (WGDT) rupture analyses as the gas concentration and release rates are unaffected and no condition exists wherein the relief capacities of the tanks relief devices are exceeded.

TEMPORARY CCW MAKEUP SUPPLY FROM PG A temporary modification connected a hose from a primary grade water service connection to a connection at the component cooling water (CCW) pump suction header in order to work l-CD-372.

Since a source of makeup is provided to CCW system and CCW remains operable and reliable, accidents are not affected or created. TRANSFER OF ION EXCHANGE RESIN A temporary modification installed a fitting and flexible hose for transfer of ion exchange resin. This modification does not constitute an unreviewed safety question because its probability of failure was not increased (due to appropriate pressure rating of components and pre-use testing of installation) and consequences of failure are previously evaluated.

ADMINISTRATIVE CONTROL OF TV-SS-202A

& TV-SS-202B This temporary modification

failed 11 closed (by lifting solenoid valve leads and isolating instrument air) and placed under administrative control the sample trip valves TV-SS-202 A/B. No unreviewed safety question exists due to this modification because alternate PASS flowpaths via RHR sample lines, RCS -Loop Hot Leg Sample lines and eves demineralized sample lines will remain available.

02-12-88 02-01-88 02-23-88 02-02-88 PAGE 11 OF 21 e. -FACILJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR FEBRUARY 1988 ----------

TM-S .2-88-10

• CORROSION PRODUCT STUDY . SP-88-08 A temporary modification installed sampling lines for the following Unit 2 components/systems:

A and C blowdown, feedwater, and 2A feedwater heater. No

• unreviewed safety question exists due to this modification since additional sampling lines do not increase probability of tube rupture and consequences of main steam line rupture are previously analyzed

• PLANT COASTDOWN Setpoints of various plant instruments*

were changed to allow an end of cycle plant coastdown.

Accidents and equipment were reviewed for the proposed average temperature.

Proposed reduction was within previously reviewed range resulting

• in no unreviewed safety question.

SCAFFOLD REQUEST A temporary scaffold platform was constructed in the Unit 2 Main Stearn valve house at 27 1 elevation to work on 2-MS-176 (steam supply check valve to 2-FW-P-2).

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.

ADMINISTRATIVE CONTROL OF CH HEAT TRACING Heat tracing circuit 2Al-25 (CH) was placed under administrative control to provide increased surveillance of the heat tracing circuit and, if required, manual operation of the circuit to maintain temperature within the required band. Manual control of CH heat tracing does not constitute an unreviewed safety question because it will be under administrative control ensuring that fluid temperatures are maintained between l 20°F and l B0°F. 02-25-88 02-25-88 02-10-88 02-22-88 I I !

--* e . FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR . SCAFFOLD REQUEST FEBRUARY 1988 A temporary scaffold.

platform was constructed in the Auxiliary Building at ten feet elevation to work a vertical ladder. 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.

SCAFFOLD REQUEST A temporary scaffold platform was constructed in the Auxiliary Building at five feet elevation to work on a vertical ladder. 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.

• SCAFFOLD REQUEST A temporary scaffold platform was constructed in the Turbine Building Basement . at nine feet elevation to work on 1-CW-MOV-lOOA.

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 OF 21 02-23-88 02-23-88 02-26-88

e. PROCEDUREORMETHOI>

OF-QPERATION-GHANGES THAT-DID NOT-REQUIRE NRG APPROVAL MONTH/YEAR FEBRUARY 1988 EMP-P-RT-13 PROTECTIVE RELAY MAINTENANCE FOR CB I5Hl A procedure deviation was approved to place the H and J bus cross connect breaker in test to perform the preventive maintenance procedure while at power; Placing the H and J cross_ connect breaker in test while at power will have no effect on the H & -J buses because the breaker will not be placed in the connect position; PAGE 13 OF 21 02-25-88 IMP-C-RPI-32 ROD POSITION INDICATION SYSTEM MAINTENANCE UNIT 2 02-10-88 MOP-12.4 Procedure deviation to allow use of the Prodac 250 computer to monitor control bank 'B' rod positions during repair of benchboard

!RPI.

• Control rod position indication from the P-250 computer is an acceptable substitute for benchboard

!RPI provided that T.S. 3~12.E is complied with and duration of substitute is minimized.

RETURN OF RM-SS-113 TO SERVICE UNIT-I Procedure deviation to align blowdown of two steam generators (B & C) through RM-SS-113 which contradicted UFSAR 11;3;3~8; UFSAR 11~3;3~8 states that all three steam generator blowdown flows are through one radiation monitor~ Changing the UFSAR assumed alignment of steam generator blowdown flow through the radiation monitors enhances the ability to detect primary-to-secondary leakage. Therefore; SGTR accident analyses and consequences are not adversely affected; 02-16-88 r--, t l

• I . l : f ' ' ( e. -*PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID REQUIRE NRG APPROVAL -NONE-PAGE 14 OF 21 PAGE I 5 OF 21 e. TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR FEBRUARY 1988 ----------

NONE DURING TIITS PERIOD PAGE 16 OF 21 e. -TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR FEBRUARY 1988 ---=-===:.:.:.=:......;a..;:a...:;..::e---

NONE DURING TlllS PERIOD PRIMARY COOLANT ANALYSIS VIRGINIA .POWER SURRY POWER STATION CHEMISTRY REPORT February 19 88 UNIT NO. 1 **-e PAGE 17 OF 21 UNIT NO. 2 MAX. MIN. AVG. MAX. MIN. AVG. Gross Radioact., µCi/ml 1.63 E+( 4. 60 E-1 1.16 E+O 2.43 :8:-1 1.54 E-1 1.83 E-1 Suspended Solids, DDm o.o o.o o.o o.o p.o o.o Gross Tritium, µCi/ml 6.90 E-2 3.40 E-2 4.60 E-2 1.59 E-1 1.20 E-1 1.40 E-1 Iodine 131 , lJCi/ml 9.30 E-l 5.53 E-3 7.08 E-2 f!i..13 E-~ 12.91 E-5 1. 50 E-4 11'31 / 11'31 0.24 0.12 0.18 0.23 k).06 0.10 Hydrogen, cc/kfl. 33.9 25.6 28.3 33.6 ~6.2 29.8 Lithium, ppm 0.63 0.26 0.40 0.90 P.63 0.79 Boron-10, ppm* 43.9 1.18 10.3 69.0 ~2.9 61.5 -Oxygen, (DO), ppm 0.005 o.oos 0.005 0.005 p.005 0.005 Chloride, ppm o. 010 0.001 0.006 0.010 0.001 0.007 pH@ 25 de2ree Celsius 7.98 6.65 7.31 6.81 p.56 6.70

• Boron-10

• Total Boron X 0.196 REMARKS: Unit One: Lithium additions on 2-8@ 1430 290g. 2-17@ 0210 290z. 2-18@ 0905 380 g, and 2-19@ 0555 400g for a total LiOH addition of 1360g. Unit One A Deborating Bed was in service on 2-24 at 2040 until 2-25 0327 for Boron removal; Operations also put A DEB in service as needed for Boron control. Unit Two: No Lithium additions; Cation Bed in service for Lithium removal on 2-3 from 0600 to 0838 and 2-16 from 2000 -2237.

PAGE 18 OF 21 e. UNIT I FUEL HANDLING DATE FEB 1988 --NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT#

RECEIVED PER SHIPMENT (I (I ENRICHMENT CASK ACTIVITI LEVEL NONE DUF ~G TIIlS Pl RIOD -

e PAGE 19 OF 21 UNIT 2

• FUEL HANDLING DATE FEB 1988 NEW OR

• DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR . ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT I RECEIVED PER SHIPMENT I , ENRICHMENT CASK ACTIVITI LEVEL NONE DUF ING THIS Pl RIOD -

e PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR MONTH/YEAR FEBRUARY 1988 NONE DURING THIS PERIOD PAGE 20 OF 21 I. I L r e -PAGE 21 OF 21 . DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR FEBRUARY 1988 ----------

NONE DURING TlllS PERIOD * * * * **r**. **** * *

• __..1.-..

• -**,,111*

.. *c.*,1 <1_*,*1 *:.l'*.,...,-

.. -*L",1***-'f/',;;.""'*a."1.*

l~*'"'lo'.'\..*I~

J~--\ -. ' . .... *~ . .._ . . ' . *. *~~*. . VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS March 15, 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/DAS:vlh Docket Nos. License Nos.88-132 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 February 1988. Very truly yours, lJL~ W. L. Stewart 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 \