ML20084E502

Monthly Operating Repts for Mar 1984

ML20084E502
Person / Time
Site:	Surry
Issue date:	03/31/1984
From:	Jones V, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Stewart W NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
223, NUDOCS 8405020308
Download: ML20084E502 (45)

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO.

84-03 l

e TTATION MANAGER 4

8405020308 040331 PDR ADOCK 05000280 R

PDR L

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Section Py 1

Operating Data Report - Unit #1 Operating Data Report - Unit i2 2

Unit Shutdowns and power Reductions - Unit #1 3

Unit Shutdowns and Power Reductions - Unit #2 4

i Load Reductions Due to Environmental Restrictions - Unit #1 5

Load Reductions Due to Environmental Restrictions - Unit #2 6

i Average Daily Unit Power Level-Unit #1 7

i Average Daily Unit Power Level-Unit #2 8

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Summary of Operating Experience 9

Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRC Approval 12 Facility Changes 'Ihat Did Not Require NRC Approval 13-16 Tests and Experiments Requiring NRC Approval 17 i

Tests and Experiments That Did Not Require NRC Approval 17 Other Changes, Tests and Experiments 18 j

Chemistry Report 79 Description of AllInstances Where Thermal W

,o Limits Were Exceeded

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Fuel Handling 21-22 l

Procedure Revisions That Changed the Operating Mode 23 Described in the PSAR Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 24 l

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Sdetion Page Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 26 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit # 2 - Mechanical Maintenance 29 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 32 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 34 Maintenance of Safety Related Systems During Outage c,r Reduced Power Periods - Unit #1 -Instrument Maintenance 37 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 -Instrument Maintenance 39 Health Physics Summary 40 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee after Time Limits Specified in T.S.

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OPERATING DATA REPORT i

DOCKET NO. 50-200 DATE 05 APR 84 COMPLETED BY V.11. Jones i

TELEPHONE 804-357-3104 OPERATING STATUS i

1. UNIT NAME SURRY UNIT 1 1

2. REPORTING PERIOD 30184 TO 33184

3. LICENSED THERNAL POWER (WT) 2441 l ~ ~ ~~~ ~ ~~ ~ ~ ~ l

4. NAMEPLATE RATING (GROSS WE) 847.5 l NOTES l

S. DESIGN ELECTRICAL RATING (NET WE) 788 o

6. MAXIMUM DEPENMBLE CAPACITY (CROSS WE) 811

7. MAXIMUM DEPENDABLE CAPACITY (NET WE) 77S i

8. IF CHANGES OCCUR IN CAPACITY RATINGS N/A (ITDIS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS I

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY N/A (NET WE)

10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS NONTH YR-To-DATE CUNULATIVE

11. HOUM IN REPORTING PERIOD 744.0 2184.0 98832.0

12. NUMBER OF HOUM REACTOR WAS CRITICAL 508.0 1818.7 60911.6 l

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 9.3 3774.5

14. HOURS GENERATOR CH-LINE 501.0 1781.0 59648.2

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 3736.2

16. GROSS THE2fAL ENERGY GENERATED (WH) 1187047.7 4213335.1 139139639.4 l

17. GROSS ELECTRICAL ENERGY GENERATED (WR) 337015.0 1359440.0 44579283.0

18. NET ELECTRICAL ENERGY GENERATED (WH) 367491.0 1291367.0

19. UNIT SERVICE FACTOR 67.3 */e 81.5 */*^ 42369103.0 4'

60.4 e/e

20. UNIT AVAILABILITY FACTOR 67.3 */*

81.5 */* '

64.1 */*

21. UNIT CAPACITY FACTOR (USING MDC NET) 63.7%

76.3%

55.3%

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22. UNIT CAPACITY FACTOR (USING DER NET) s2,,s 75,os.

54,4s.

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23. UNIT FORCED OUTAGE RATE O.0

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS

• 2.2 */*

9.1 */*

n4_gs g4 l

(TYPE,DATE. AND DURATION OF EACH) oy_2g gg i

25. IF SHUT DOWN AT END OF REPORT PERIOD, n4 1s-a'4 ESTIMATE DATE OF STARTUP I

26. UNITS IN TEST STATUS FORECAST ACHIEVED j

(PRIOR TO COWERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ' ELECTRICITY CONMERCIAL OPERATION 4

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OPERATING DATA FEPORT DOCKET NO. S0-281 NTE 05 APR 84 COMPLETED BY v. n. Jones TELEPHONE 804-3S7-3184 OPERATING STATUS i

1. UNIT NAM SURRY UNIT 2

2. REPORTING PERIOD 30184 TO 33184

3. LICENSED THERMAL POWER (WT) 2441 l~~~~~~~~~~~~~~~~l

4. NAMPLATE RATING (GROSS MWE) 847.S l NOTES l

S. DESIGN ELECTRYCAL RATING (NET MWE) 188

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) 811

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 77S

8. IF CHANGES OCCUR IN CAPACITY RATINGS N/A

)

(ITDfS 3 THROUGH 7) SINCE LAST l

REPORT. GIVE REASONS 4

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY N/A (NET WE) j

10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS NONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.0 2184.0 95712.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 370.0 1786.2 54357.1

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 23.8 328.1

14. HOURS GENERATOR ON-LINE 370.0 1777.1 59353.1

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 f

16. GROSS THERMAL ENERGY GENERATED (NWH) 892024.8 4267433.5 138983306.4

17. GROSS ELECTRICAL ENERGY GENERATED (NWH) 2852po.0 1368470.0 45163329.0 *

18. NET ELECTRICAL ENERGY GENERATED (NWH) 270614.0

'1298460.0 42805520.0

19. UNIT SERVICE FACTOR 49.7 e/e 81.4 e/e 62.0 */e

20. UNIT AVAILABILITY FACTOR 49.7 e/o 81.4 e/o 62.0 e/o

21. UNIT CAPACITY FACTOR (USING MDC NET) 46.9 e/e 76.7 e/e 57.7 e/e

22. UNIT CAPACITY FACTOR (USING DER NET) 46.2 */*

7S.5 e/o 56.8 e/o

23. UNIT FORCED OUTAGE RATE 33.5 */*

15.7 */*

9.3 e/o

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE.NTE.AND DURATION OF EACH) k

25. IF SHUT DOVN AT END OF REPORT PERIOD, ESTIMATE DATE OF STARTUP 04 09.e4

26. UNITS IN TEST STATUS FORECAST ACriIEVED (PRIOR TO COM'IERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY Com!ERCIAL OPERATION i

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IM)CKET NO.50-29e UNIT 58MIThowNS AND FOWER REDUCil0NS IINIT NAME surry 1 l

• pA1E 04-04-na Md.ETED n v_n-a-s __

REroRT MONIH saarn-h - i=='

1El.Eril0NE nna-as7-mina 1

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I Licensee g-e, k

Cause A Conecilve gg g

}jec No.

Date E

Event p

Acelim to N

oE ac jdi Repost #

=> te Psevent Recussence i

84-4 03-11-84 S

243.0 H

1 Continuation of snubber outage which commenced on 02-24-84.

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F: Fewced Ressan:

Metleml:

Enhiliit G-Inteencilinis 5: Scheduled A-Eiguipniens Fathise(Espisia) 1 Menwel ro,pseps,selim ut paia 3-Maineenence of Test 7-Manisal Sesans.

Entey $hecis few I.leensee 1

i C. Refueling 3-Ameomzeic Sessm.

Evens Repose (l.ER) rite (NtlRIE D-Regelsemy Restilcthm 4-Delies (Earisin) 0161)

E-Opeeseew Tesining A Ucense Esaniinschne F-Adadelseesolve Exhibh I - Same Sousie G4)pesselonal Essue (Esplein) j 19fi7) 11 Othee (Emplain) e

v l>OCKET NO.

se_,e1 UNIT $80U1 DOWNS AND POWER REDUC 110NS j

UNIT NAME surry Yr l

DATE na-na-na LETED RY L

H.

Enn REPORT MONI1g March. 1984 TELErtl0NE 804-R59-61;n 3E E

l.icensee gg "L

Cause & Corrective W..

Ikste k

Eg g

3goe Action te Event gg

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M Prevent Recurrence jg Reymi #

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84-10 03-06-84 S

0 11 1

Power was reduced to 86% power (680 MW's)'for load following.

8+11 03-16-84 S

O H

1 Power was reduced to 52% power 1

(400 MW's) for load following.

84-12 03-16-84 F

$74.0

• A 3

Reactor trip caused by "B" RCP 84-005 tripping. The failure was in the 84-006 j

electrical penetration and leads were connected to a spare penetration.

4 The scheduled snubber outage was started early due to the plant tripping.

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Method:

Exhibit G Inserwetions F: Fawced Reason:

S: Scheduled A Equipnient Fallme(Empisin) 1-Manual for rieparation of Data B-Maintenance of Test 2-Manuel Scism.

Entry 51 ects for I.lcensee C-Refaseling 3 Autosiostic Scism.

Event ReposI (t.ER) File (NUREG-D Reguistwy Restelcllon 4Oher (Emplain) 0161)

E-Opeestew Teelning A tJeense Esensinetton 5

F-Admiinist stive Eshibit I Same Source G-Operattunal E ve (Esplein) r6/77)

ISOlies (Esylein) i

LOAD REDUCTIONS DUE TO DNIRON) ENTAL RESTRICTIONS UNIT NO.

1 MONTH: March, 1984 l

DATE TIME HOURS LOAD, W PIDUCTIONS, W PNH REASON NONE DURIIIG THIS REPoltTING PERIOD.

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M0!.iHLY TOTAL

LOAD PIDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTE: March, 1984 l

DATE TIME HOURS LOAD, }f4 FIDUCTIONS }f4 MWH REASON NOME DURING TEMS REPORTING PERIOD.

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110NTHLY TOTAL 6

DOCEET ';0 50-2R0 U!:IT SURRY I DATE u-1-84 C0!!PLETED Ry V. B. Jones i

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AWRAGE EAILY Ui!IT POVER LEWL E

N0??THs

?lARCil 84 AWRAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY

'LVE-??ET)

DAY fflWE-NET) i 1

0.0 17 755.9 2

0.0 19 755.7 3

0.0 19 754.8 i

4 0.0 20 759.1 5

0.0 21 756.8 6

0.0 22 757.7 7

0.0 23 757.4 8

0.0 24 758.1 9

0.0 25 753.7 10 0.0 26 755.9 11 271.1 27 748.9 12 709.9 28 751.8 13 753.7 29 753.7 l

14 758.0 30 750.8 15 756.8 31 750.4 16 742.0 LWILY UNIT POWER LEVEL FORV INSTRUCTIONS Oll THIS FORN, LIST THE AVERAGE DAILY UNIT POUER LEVEL It! lNE-NET FOR SAC!l DAY I!i THE REPORTING ll0?lTH. THESE FICVRES WILL BE USED TO PLOT A GRAPH FOR EACil REPORT-ING IO!;TH. NOTE T!!AT BY USING !:AXIMit! DE?C'!CARLE CAPACITY TOR T!!E !lET ELEC"'RICAL RATING OF T7E UNIT, THER." llAY PC CCCASIO?lS T! HEN THE EAILY AWR4fiE POWER EXCEEDS THE 100 */* LINE 10R THE RESTRICTED POWER LEVEL LI!C). Ili SUC4 CASES, THE AVERACE CAZLY UNIT POWER OUTPUT SilEET Sil0ULD BE FOOTHOTED TO EXPLAIli THE A?PARC?iT AH0':ALY, 7

DOC' ET NC 53-28i Ui!IT SURRY II DATE 4-1-Rh C0!PLETED BY V.

n. Jones ALTRACE DAILY UNIT POVER LEVEL 1:0!!T!!t MARCH 84 AWRAGE CAILY POVER LEVEL AVERAGE DAILY POVER LEVEL CA1 iI9?E-?!ET)

DAY

( WE-NET) 1 737.9 17 0.0 2

739.9 18 0.0 3

738.3 19 0.0 4

740.5 20 0.0 5

736.6 21 0.0 6

723.4 22 0.0 7

734.5 23 0.0 8

733.2 24 0.0 9

734.0 25 0.0 10 734.2 26 0.0 11 736.7 27 0.0 12 735.4 28 0.0 13 738.2 29 0.0 14 7 37.5 30 0.0 15 736.1 31 0.0 16 240.2 DAILY UNIT POWER LEVEL F0F) INSTl?)CTIO!!S ON THIS FORN, LIST THE AVERACE DAILY UNIT POWER LEVEL IX If/E-NET FOR EACH DAY IN THE REPOR"'ING !!0 NTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING 1:01;TH.1:0TE THAT BY USING !!AXIh7]A! DEPEliDAPLE CAPACITY FOR T4C NET CLECTRICAL RATING OF THE UNIT. THERE ! 4Y PE OCCASIOVS WHDI THE DAILY AVERAGE PWER EXCEdDS THE 100 */* LINE 'OR T!!E RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THL' AVERAGE DAILY UllIT POVCF OU"PUT SilEET SHOULD DE FOOT!!OTED TO EXPL4li' Tile APPARENT AN0!!ALY.

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SUMMARY

OF OPERATING EXPERIENCE March, 1984 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 1 03-01-84 0000 This reporting period begins with the unit at cold shutdown and at mid-nozzle with head evacuation in progress.

03-05-84 0510 Secured head evacuation, filling reactor coolant system.

03-06-84 0456 Completed RCS fill and vent.

03-07-84 0051 Bubble in pressurizer.

03-09-84 1303 RCS > 200*F.

2020 RCS > 350*F, 450 psig.

03-09-84 0621 RCS at HSD.

03-10-84 2002 Reactor critical, 03-11-84 0306 Main generator on the line, commenced 3t/hr.

power increase.

03-12-84 0745 Unit at 1004 power (780 MW's).

2300 Failed open C & D moisture separator drain receiver LCV'S, generator MW'S increased to 790 MW'S.

03-31-84 2400 This reporting period ends with the unit at 100%

power.

Unit 2 03-01-84 0000 This reporting period begins with the unit at 1004 power (780 MW's).

03-06-84 0037 Commenced power reduction for load following.

0115 Stopped ramp at 864 power (680 MW's).

0341 Commenced power increase.

0446 Unit at 1004 power (780 MW's).

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0249 Stopped ramp at 52% pcwer (400 MW's).

0415 Commenced power increase.

0710 Unit at 100% power (780 MW's).

I 0957 Reactor trip caused by "B" RCP tripping, commenced snubber outage.

1200 RCS borated,' commenced cooldown.

1447 RCS < 350'F, 450 psig.

2110 RCS > 200*F.

03-17-84 1335 RCS degassed.

2334 RCS at mid-nozzle.

03-27-84 0324 Commenced filling and venting RCS.

03-28-84 0513 Complated RCS fill and vent.

03-30-84 1212 Bubble established in the pressuriser.

03-31-84 2400 This reporting period ends with the RCS at 170*F, 325 psig, bubble in the pressurizer.

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AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS March.1984 The Nuclear Regulatory Commission issued, on January 31, 1984, Amendment Nos.

94 and 93 to the Operating License for Surry Power Station, Units Nos. I and 2, respectively.

These amendments revise the Technical Specifications to remove eight (8) snubbers from auxiliary feedwater system and emergency diesel generator exhaust piping from Table 4.17-1. In addition. Specification 6.4.B.1.b is revised to add the Supervisor of Health Physics as an administrative controller of keys to locked barricades at radiation areas.

The Nuclear Regulatory Commission issued, on February 24, 1984 Amendment Nos.

95 and 94 to the Operating License for Surry Power Station, Units 1 and 2, respectively.

These amendments revise the Technical Specifications to change the minimum Boron Injection Tank boron concentration from 11.5% to 0% and to change the Boric Acid System boron concentration from 11.5% to 7%.

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FACILITY CHANGES REQUIRING NRC APPROVAL March,1984 i

NONE DURING THIS REPORTING PERIOD.

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I FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL i

March,1984 l

UNIT

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DC 80-96 Reactor Vessel Level 2

This design chnage installed redundant microprocessor-based monitoring systems to monitor Reactor Vessel Level.

The system utilizes differentialpressure measuring transmitters which measure water level and relative void 4

content of the circulating primary coolant system fluid and thus provides direct readings of the reactor vessel level.

Summary of Safety Analysis j

This modification provides redundant safety-related l

Indication of reactor vessel water level thus providing j

an indication of inadequate core cooling.

l DC 81-33 VCT Redundant Indication 1

This design change added a redundant Volume Control Tank level indicator to the control room. The second level indicator in the contori room will enable the j

operator to manually control the related valves if the existing loop malfunctions in any way.

a Summary of Safety Analysis i

The modification enhatices the safe operation of the I

plant because it increases the reliability of the Chemical and Volume Cotnrol System.

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FACHJrY CHANGES TIAAT DID NOT REQOIRE 1]RC APPROVAL N

March,1984_

UNIT I

DC 32-19 DV Underfrequency Testing Modificatfo:1 1&2 s

'The BCP n:otor electrical supply is mohitore'd by under-

,fre@ency and undervoltage relays. An uriderfrequency eslays is Iristalled on each phase of the' electrical supply bus. Tnise\\ relays provide rapid senMng of a system overMd.), The, Technical Specifications required a mrathly stest to be performed on the logic circuitry.

T.ie circuitry,was, mndified to allo,w this testing.

i This design change installed an swiliary relay in the i

logic circuitry of train A and B. It elso installed a three position test selector switch to be used to ' select the s

s taaln to be tested.

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Sbstmary of Safety Anal [ sis-4 The installatlUn 'obtest sw:tches for RCP undcrfrequency logic test does not trente a safety problem. This modifi-s cation will not effect the operation of any safety related system. The functional characteristics _ of the RCP l

logic circuitry remain upyhanged.

3 DC S3-29 Boron Concentration Raduction Modification 1&2

'\\

This design change diluted the Cedicated Boric Acid Storage Tanks, isolated the Boron infection Tank recircu-1 Intion, lines and responded /recalibrated the level instru-mentation of the Boric AesJ Storage Tanks.

c Nmmarv of Safety Analysis A detailed operational review and 'saf' ty,9nalysis was e

conducted and it was concluded that the plant can continua to be operated in a safe and efficient manner followind the change.

The concentration reduction offers signiDennt benefits

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and safety features.

The concentration' l reductions

,, s in the HIT and Boric Acid System will increase operational reliability, reduce maintenance coste and decrease o

personnet radiation exposure.

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FACtIJrY CilANGES THAT DID NOT REQUIRE NRC APPROVAL l

j March.1984 UNIT DC 84-02 IIP lleater Drain Piping Modifications I

l Operation of the IIP IIcater Drain Pump Suction isolation Valves was very hazardous. This design change modified the suction piping as follows:

1.

Relocated Suction Line Expansion Joint 2.

Redesign and Upgrade Expansion Joints 3.

Reorient isolation Valve Operators 4.

Add flypass Around Suction Isolation Valves 5.

Relocate Spring Supports Additionally, existing platforms were modified and i

new sump pumps were installed.

Summary of Safety Analysis f

The modifications were made to improve the operator safety considerations related to the 4

isoaltion of the li.P. Heater Drain Pumps.

3 These modifications will reduce the hazards associatedwi th pump isolation activities.

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FACILITY CHANGES THAT D_ID NOT REQUIRE NRC APPROVAL March,1984 UNIT

'DC 84-03_. ~

HP Heater Drain Piping Modifications 2

Operation of the HP Heater Drain Pump Suction isolation Valves was very hazardous. This design change modified the suction piping as follows:

,./

1.

Relocated Suction Line Expansion Joint

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2.

Redesign and Upgrade Expansion Joints 3.

Reorient Isolation Valve Operators 4.

Add Bypass Around Suction Isolation Valves 5.

Relocate Spring Supports Additionally, existing platforms were modified and new sump pumps were installed.

Summary of Safety Analysis /

The modifications were made to improve the operator safety considerations related to the isoaltion of-the H.P.

Heater Drain Pumps.

These modifications will reduce the hazards associated with pump isolation activities.

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TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL March, 1984 NONE DURING THIS REPORTING PERIOD.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL March, 1984 NONE DURING THIS REPORTING PERIOD.

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OTIIER CIIANGES, TESTS AND EXPERIMENTS March, 1984 NONE DURING THIS REPORTING PERIOD.

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CHEMISTRY REPORT March 19 84 T.S.

6.6.3.d M+

OON UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM' MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., uCi/mi 1.91EO 2.32E-2 1.11EO 1.72EO 2.06E-2 2.76E-1 Suscended Solids, pom 0.00 0.00 0.00 0.00 0.00 0.00 Gross Tritium, uCi/ml 9.68E-2 1.43E-2 4.89E-2 2.11E-1 7.07E-2 1.47E-1 31 Iodine nCi/ml 1.35E-1 3.22E-3 5.38E-2 3.25E-4 8.37E-5 1.66E-4 131 133 I

/I 0.71 0.15 0.42 0.31 0.07 0.15 Hydrocen, ec/ka 33.6 14.1 (A) 26.5 39.3 1.9(C)

19. 9 (C)

Lithium, com 2.65 0.71 1.11 2.74(c) 0.79 1.77 Boron-10, com*

362 54 139 308 122 181 Oxyaen, (D.O.),com 1.000(B)

<0.005 0.064 1.700 (C) <0.005 0.369 Chloride, opm

<0.02

<0.02

<0.02

<0.02

<0.02

<0.02 pH @ 25*C 6.90 5.83 6.43 6.66 5.68 6.18

• Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S.

4.13.A.6 Phosphate Boron.

826 Sulfate Chromate 0.0 50% NaOH Chlorine 0.0 REMARKS: (A) - 3/12/84 Unit I ramping during startup (B) Unit 1 shutdown 2/24/84 spring outace (C) Unit 2 shutdown for maintenance on 3/16/84 decassina ccxnoleted 3/17/84 (D)

Lithium additions Unit 1: N bN. 3/10 762 cms. 3/11 300ams. Cation bed placed in service Unit I for lithium remval 3/6. 3/7. 3/14. 3/15, 3/17. 3/18. 3/20. 3/21. 3/25.

3/28.

(E) Lithium naaitions Unit 2r 3/3 100ams.

3/7 195ams.

3/16 2150ams.

3/30 l

1260cmq.

cnH nn hoa pinnna in norvien fn* T,i rmrnrn1 e 1/R. 1/11. 1/1 ? _ 1/14 (F) Tho inen1 nf thneo chnmicale ehnnla pmAiv-o m nAveven omri mnmemen1 i mna*

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i DESCRIPTION OF ALL INSTANCES WHERE f

THERMAL DISCHARGE LIMITS WERE EXCEEDED March, 1984 NONE DURING THIS REPORTING PERIOD.

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FUEL HANDLING UNIT 6 1 March, 1984 DATE NO. OF ANSI NO.

NEW OR SPENT FUEL HIPPED / RECEIVED ASSEMBLIES PER S$IPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL NONE DURING THIS REPCRTING PERIOD.

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FUEL HANDLING UNIT 1 2

March, 1984 DATE NO. OF ANSI NO.

NEW OR SPENT FUEL EIPPED/ RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL NONE DURING THIS REPOl TING PERIOD.

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4 PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR March, 1984 No.

Unit Title Date AP 20 1

Main Control Room Inaccessibility 3-08-84 (Change)

OP 8.3.1 1

Placing Boric Acid In Operation 3-08-84 (New)

OP 8.3.2 1

1-CH-P-2B to Recire. 1-CH-TK-1B 3-03-84 (New)

OP 8.3.3 1

1-CH-P-2B to Recire. 1-CH-TK-1B 3-08-84 (New)

OP 8.3.4 1

1-CH-P-2C to Recirc. 1-CH-TK-1B 3-08-84 (New)

OP 8.3.5 1

Boric Acid Auto Makeup 3-08-84 (New)

OP 8.3.6 1

Boric Acid Dilution 3-08-84 (New)

OP 8.3.7 1

Boric Acid Alternate Dilute 3-08-84 (New)

OP 8.3.8 1

Boric Acid Borate 3-08-84 (New)

OP 8.3.9 1

Boric Acid Manual Makeup 3-08-84 (New)

OP 7.8.1 1

Filling the Boron Injection Tank 3-08-84 (Delete) 1-SI-TK-2 After Safety Injection Initiation OP 7.8.2 1

Filling the Boron Injection Tank 3-08-84 (Delete) 1,SI-SK-2 After Tank Maintenance OP 8.3 1

Boron Concentration Control 3-08-84 (Delete) i l

i l

23

DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS March, 1984 NONE DURING THIS REPORTING PERIOD.

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MAINTEMARCE OF SAFETT RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERTODS I

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MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO.1 ELECTRICAL MAINTENANCE i

March, 1984 31

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MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 ELECTRICAL MAINTENANCE March, 1984 33 l

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There was no single release of radioactivity or radiation exposure specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFT20.

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PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR SAFETY AND OPERATING COMMIT'i'EE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS March, 1984 Date Reviewed by No.

Unit Title Deviated SMSOC PT 25.2 1

Testing of Service Water Valves 02-18-84 03-08-84 to Recirculate Spray Heat Exchangers s

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VI HO INI A EI.I?CTHIC AND POWI!H COMPANY Hicn> onn,Vinoixir eneret W. L.NTatwAur

'YBCE I'U RR IIsE NT w. r w m o,...,,,,, a April 16, 1984 s

Mr. N. M. Haller, Director Serial No. 223 Office of Management and Program Analysis N0/JDH:acm U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 DPR-37

Dear Mr. Haller:

Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos. I and 2 for the month of March, 1984.

Very truly yours, 3

g W. L. Stewart Enclosure (3 copies) cc:

Mr. R. C. DeYoung, Director (12 copies)

Office of Inspection and Enforcement Mr. James P. O'Reilly (1 copy)

Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station l

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