ML19095A369

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Monthly Operating Report for Month of February 1978
ML19095A369
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/16/1978
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Hartfield R
Office of Nuclear Reactor Regulation
References
Download: ML19095A369 (41)
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Text

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Hr. R~ -A.*Hartfield,. Acting* :Di~~ctor

. Of fico. of Haimgcmcnt Infol'1ik-1t~on and - . - PO&H/DLB:das:. . .

?rogram :coi1trol . -~.. . ****oc

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  • U. S~ ._.* iiuclear R1;!.8ula\:.or~-' C~i?iL1ii.;>sio~1 ." *- :S0:"'.'281 *
  • 20,555 ' * "* Lic~1:1Se* J~O*s. DPR-.32:

Dear* _Hr.** Hartfield:

Enclosed is: the. rforitqiy. Opcra.t:ing: Report for *surry 'I'C!"ie( Sta,t.'j.011 Unit* i:Joa.

i -a~d Z *for *the mont:h.qf_ February i97s *. * - ** * .. :,

.Aiso*attacheJ, :Ls**the re.fueling iniorm~ticu for SUl;ry u.~dt:-'.Lfos. l &~<lZ,*.-a.'8' requeste_d in.your. letter of Ja~111ary rn~ 1978. 'i'l:i.is information will be updated

... in future.. !!!O:;:\t~~ly operating_' l~f:port_s

  • f.W cliarigc1G *oc.~CU:t' ** *.

. . - ~ ,-.-* .

  • ...** zf,il1.dlat1~1~

... * . (; *. H. Stallings *. .

  • Vic.e .President* - -Power .sur;:Ply * **.*.

and 11_roduction Qpi:::rations * ..

1** *.

I .Encio~ures *-( 2* copies).

C**,.. *

. Dr.: _zrilst 7J6igeua:u, Director (io'.~opi-~s)/.  :;.*

. Of flee of Inspectioh .and Enforcement . .

Hr. James P. o~Reilly,. DireC:tor (l copy) . "*'

Office of. Inspection and Bnforccincmt:

.* ~ ..

. * .....  : . '\.. .

. *1' *.::-

!.. Name:

SURRY UNIT NO. 1 ATTACHMENT 1

2. Next scheduled date for refueling shutdown: . 4-.:J.'.~7S
3. Scheduled date for restart following refueling: 5-24-?8 4~ Technical Specifications Changes: Rod Insertion Limits, Update of Fz(z) values (These changes will be reviewed by both the station and system safety committees prior to submittal to NRC).
5. Scheduled date for reload licensing submittal: 3-15-78
6. Important licensing considerations: None
7. Number of fuel assemblies (as of 3/1/78):
a. In the core: 157
b. In the spent fuel storage pool:* 372
8. Licensed spent fuel pool storage capacity:*
a. Current: 464
b. Requested: 1044
9. Projected date of last refueling that can be discharged to the spent fuel storage pool assuming ~urrently licensed capacity: ApriJ 197~
  • Surry Units No. 1 and 2 share a common spent fuel storage pool.

ATTACHMENT 2

1. Name: SURRY UNIT NO. 2
2. Next scheduled date for refueling shutdown: 10/15/78
3. Scheduled drite for restart tallowing refueling;' 4/15/79 (refueling-(outage extended for steam generator replacement)
4. Technical Specifications Changes: No changes are forseen due to the reload core design (The review by both the station and system safety committees will take place by 1/15/79).
5. Scheduled date for reload licensing submittal: 1/15/79
6. Important licensing considerations: None
7. Number of fuel assemblies (as of 3/1/78)
a. In the core: 157
b. In the spent fuel storage pool:* 372
8. Licensed spent fuel pool storage capacity:*
a. Current: 464
b. Requested: 1044
9. Projected date of last refueling that can be discharged to the spent fuel storage pool assuming currently licensed capacity: September, 1977
  • Surry Units No. 1 and 2 share a common spent fuel sto*rage pool.

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 78-02 FEBRUARY, 1978

\,,*-.

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"-~ ~

APPROVED:

, MANAGER

0

. '" OPERATING DA!AR.EPORT 50-281 DOCKET NO.

DATE 2-1-78 COMPLETED BY* O.W. Akins CQRRECTED COPY TELEPHONE

~ Til"'iG STATUS Notes

1. U~t Name: . Surrr Unit 2
2. Reporting Period: 0001 780101 2400 780131 ...
3. Licensed Thermal Power (MWt): 2441
4. Nameplate Ra.ting (Gross MWe): 847~5 . ..  :

S. Design Electtic:tl R~ting (Net MWe): 822

6. Maximum Dependable Capacity (dross MWe): _8_1_1______
7. Maximum Dependable Capacity (Net MWe):
  • _7_7_s_.- - - -
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

N/A N/A . . ' .. . ":. *~

    • 9. P?wer Level To W'hich Restricted;If Any (Net MWe):
10. Reasons For Restrictions, If Any: _._ _ _ _ _ _ _....;N;.;..:/~A;;..__ _ _ _ _ _ _ _ _ _ _ __..;..______..:._

~ .. I

(~.,;-------*-------------------------..---.-,.-..,...._- . - - -*..:_ _~* .!

  • ~. :- *. * ;* ..
  • This Month Yr.-to-Date .Cumul:ltive

.* ~ .

11. Hours In Reporting Period 744 . *.'l.-1' ,;39
12. Number Of Hours Reactor Was Critic:tl 713.1 713 1
13. Reactor R~n*e Shutdown Hours 0 -~** .* 0 .* .
-14. Hours Generator On-Line 7
U.. 6 111;6 26.640::s
  • 1s. Unit Reserve Shutdown Hours 0 0
  • 16. Gross Thermal Energy Generated (~lWH) *
  • 1 .]?7.003 J 727 na-:i
17. Gross Electric::il' Energy Gener.ired (MWH) 567.105

)

67 J 05 20
13t.' 4~9 1~. Net Electrical Energy Generated (MWH) . 538' 807* 53"8.807 . 19 r)q, 3 0?4
19. Unit Service F:ictor . . 95.6% 95.6%
20. Unit A-.-ailability Factor 25.6% 95 6Z
  • ii. Unit Capacity F:ictor (Using MDC Net) 93.4% 93.4%
22. Unit Cap:icity F:ictor (Using DER Net) 88.1% 88.1% 55. 7%
23. Unit Fori=I Out:tge R:ite 4.4% 4.4% 25".1%
24. Shutdowns Schedulea Over Next 6 Months (Type. D:lte, :ind Our:ition of E:lch ):

S/G Ins'Oection - March 15. J 978 - 4 ~;e<=>ks

25. If Shut Down At End Of Report Period. Estim:ited D:ite of Startup: N/A (J}'>* U11its In Test St:itu:; (Prior to Commerc:i:ll Oper:uion): Forec:ist* . Achie.,*ed INITIAL CRlTlCALITY INITIAL .ELECTRICITY .

COMMERCIAL OPERA Tl ON (ll/77)

. OPERATING DATA REPORT DOCKET NO. 50-280 DATE 3-1-78 COMPLETED BY 0

  • J. Costello TELEPHONE 804~357-1184

~TING STATUS Notes

.~ l. Unit Name: . Surry Unit 1

2. Reporting Period: 0001 780201 . ,. . 2400 780228 Licensed Thermal Power (MWt): --~:"':'!..,,;;.;;;~~--------

3.

4. Nameplate Rating (Gross MWe):

5 .... -: .....

S. Design Electrical Rating (Net MWe):

822

6. Maximum Dependable Capacity (Gross MWe):

811

7. Maximum Dependable Capacity (Net MWe);

175

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A N/A.

..-. "; -~  :

9. P?wer Level To Which Restricted;If Any (Net MWe):

NA.

10. Reasons For Restrictions, If Any:

~

... ~- : ~- ... ; * **

  • This Month Yr .~tO-:Date 672 1416 . 45 ,,48.0. : .
  • 11. Hours In Reporting Period '*

672 1416 30732.9

  • 12. Number Of Hours Reactor Was Ciftical 0  :.-* 0 -~-; .*. 0 ..:
13. Reactor Reserve Shutdown Hours

. : -14. Hours Generator On-Line 1416 0 0 ' .. 0

-

  • 15. Unit Reserve Shutdown Hours 1,635,853 3,447,979
  • 16. Gross Thermal Energy-Generated (MWH)
  • 545,155 1,148, 795 22,508,638
17. Gross Electrical' Energy Generated (MWH) -----------*

519,012 1,092,987 21,360;551 l~. Net Electrical Energy Generated (MWH) .

19. Unit SeI'Vice Factor 100% 100% 65.9%
20. Unit Availability Factor 100% 100% 65.9%
  • 21. Unit Capacity Factor (Using MDC Net) 99.7% 99.5%
22. Unit Capacity Factor (Using DER Net) 93.9% 93.9% 57.1%

0 0 17 .*4%

23. Unit Forced Out:ige Rate
24. Shutdowns Scheduled Over Next 6 Months (Type, Date. :ind Duration of E:ich ):

April 15, 1978 - Refueling. 4.WJss.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: NA
26. Units In Test Status (Prior to Commercial Operation.): Forecast*. . *Achi~ved INITIAL CRITICALITY INITIAL ELECTRICITY .

COMMERCIAL OPERATION

/

DOCKET NO. 50-280 .

UNIT Surry I'*

DATE March 1, 1978 COMPLETED BY o. J. Costello AVERAGE DAILY UNIT POWER LEVEL MONTH~_F_e_h_r_u_a_ry~l_9~7~8-.-~~-

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net) DAY (MWe-net}

772.8 771.9 1 17 774.0 771.5 2 18 772. 7 771.4 3 19 773.1 773.3 4 20 5 773.5 21 774. 3 773.4 774.2 6 22 7 772.1 23 773.8 772. 9 8 761.2 24 771.6 773.2 9 25 10 771.1 26 773.5 771.4 773. 7 11 27 77.2.5 774.0 12 28 771.8 13 29 14 772.4 30 15 772.8 31 771.8 16 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit power level in MWe-net for each day in the reporting month.

Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the*net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

50-280 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Surry 1 DATE 3-1-78 COMPLETED DY O. J. Costello REPORT MONTH Febru.ary TELEl HONE 804-357..:.3184 u

~ ....

~

~

E

  • J Licensee Ev E

UV'l c: u Cause & Corrective

~II. Dale 0. -,.,  ::l

~

~

..c ;- 111 ex: Event QJ QJ

~. :-g 0-o

0. 0 Action to

~*  :; :E ~ ..c ::: Report# VlU Eu O* Prevent Recurrence o--  : ; V) ~ u 4',__~-+-~~~+---+-~~-+---ll--~6+-~~~--+-~-+~~--ll--~~~~~~~~-*~--'--4

(~one during his period)

I I

I*.

3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A*Equipment Failure (Explain) I-Manual for Preparation of Data 8-Maintenance oi Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automalic Scram. Event Report (LER) File (NUREG-D-Regulatory Restricliun 4-0ther (Explain) 0161)

E-Operator Training & License Examination F-Ad mi nisl rat i*1e 5 G-Oper'ational Errur (Explain) Exhibit I - Same Soun:e (9/77) II-Other (Explain)

" I ~

OPERATING DATA REPORT 50-281 DOCKET NO.

DATE 3-1-78 COMPLETED BY- 0. J. Costello TELEPHONE 804-357-3184 OPERATING STATUS Notes

  • 1. Unit Name: ---_,~s..;.u-=r~r~y~U~n~i;;.*t;;,.. ..;2:;...____..........;__ __

_2. Reporting Period: _0_0_1.....7_8_0_2_0...;;1;.___;;.24.._o;.;o;;.....:7..:;8~0~2=2~8----

2 3_ Licensed Thermal Power (MWt): 441

4. Nameplate Rating (Gross MWe): 84 7
  • 5 S. Design Electrical Rating (Net MWe):

822 811 . -*

6. Maximum Dependable Capacity (Gross MWe):
7. Maximum Dependable Capacity (Net MWe):

715

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
  • N/A * *
  • .. N/A
9. P~wer Level To Which Restricted,"lf Any (Net MWe):
10. Reasons For RestrictiOns. If Any: _ _ _ _ _ _N~/A:;:....._.....,.._ _ _ _ _ _ _ _ _ _ _ _~_.__:....:.._

.. .':.... *. . .. i. **

  • This Month Yr.~to-Date. *
11. Hours In Reporting Period _ 672 1416. 42,360
12. Number Of Hours Reactor Was Critical 672 1,385.1 27,797.9
13. Reactor Reserve Shutdown Hours 0 *i** ** o*

. ; -14. Hours Generator On-Line 672- 27,312".5* ..

- 15. Unit Reserve Shutdown Hours 0 0 0

  • 16. Gross Them:ial Energy Generated (MWH)
  • 1~638,679 3,365, 772 63,076,006
17. Gross- Electrical' Energy Generated (MWH). 536,215 20,670, 714
18. Net Electric:il Energy Generated (MWH) . 509,619 1.048 ,426 19 ** 601, 543
19. Unit Service Factor 100% 97. 7% 64.4%
20. Unit Availability Factor 100% 97.7% 64.4%
  • 21. Unit Capacity Factor (Using MDC Net) 97.9% 95.5% . : 59_;7%
22. Unit Capacity Factor (Using DER Net) 92. 2% 90% 56.2%

0 24.-6%

23. Unit Forced Out:ige Rate 0
24. Shutdowns Scheduled Over Next 6 Mouths (Type. D:ite, :md Duration of E:ich ):

S/G Inspection - March 24, 1978 3 Weeks

25. If Shut Dowrt At End Of R~port Period. Estimated D:ite of Startup:

N/A

26. Units In Test Status (Prior to Commercial Oper:ition_): Forec:ist*. . 'Achi~ved INITIAL CRITICALITY . *. *' ..

INITIAL ELECTRICITY COMMERCIAL OPERATION

/

  • I DOCKET NO. _ 5_0_-_2_ 81_ _

UNIT _su_r_r_y_r_r__

DATE Marchl, 1978 COMPLETED BY _o_._J_._c_os_t_e_llo AVERAGE DAILY UNIT POWER LEVEL MONTH February 1978 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net) DAY (MWe-net) 1 760.9 17 759.7 2 760,{i 18 759.3 758.8 758.7 3 19 4 759,9 20 759.6 760.1 760.0 5 21 760.3 760.0 6 22 7 761.5 23 759.2 8 733.3 24 758.5 9 758.0 25 758.1 10 759.7 26 758.0 11 758.9 27 757.7 12 757.8 28 756.8 13 759,J 29 14 760.1 30 15 760.7 31 16 759.0 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit" power level in MWe-net for each day in the reporting month.

Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the* net electrical rating of the unit, there may be occasions when the daily average power level exceeds the l 00% line (or the restricted power level line). In such cases, the average* daily unit l?ower output sheet should be footnoted to explain the apparent anomaly.

DOCKET NO. 50-281 UNIT SHUTDOWNS AND POWER REDUCTIONS Surry Unit 2 UNIT NAME DATE March 1 1 1 978 COMPLETED BY 0. .I. Costell p REPORT MONTH Februftry TELE( HONE 804-357-3184 Licensee Cause & Corrective

'.\111. Date Event Action to Report# Prevent Recurrence (None during ... his p~riod.)

I

""I 3 4 F: Forced

  • Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee

('-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-0ther (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

~

G-Operational Error (Explain) Exhibit I - Same Source

- (lJ/77) II-Other (Explain)"

s.&:Jt1ssrr *= uz; pap: 1 :. Ji.'

  • ' LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS .

UNIT NO. 1 NONTR: FEBRUARY, 1978 DATE

- - ITIME *HOURS LOAD, MW. REDUCTIONS 2 uw MWH

--* REASON NONE DURING THIS REP ORTING -

PERIOD. ---

I l

I HONTHLY TOTAL 0 I

LOAD REDUCTIONS DUE TO ENVIRONHENTAL RESTRICTIONS UNIT NO. 2 MONTH: FEBRUARY, 1978 DATE

- - ITi:UE HOURS LOAD, MW, REDUCTIONS 2 HW MWH

-- REASON NONE DU ,ING THIS REPORTING PERIOD. -

I HONTHLY TOTAL 0 I .. .. .

~ . ~

~

SUMMARY

OF OPERATING EXPERIENCE~

FEBRUARY:., 1978 Listed below in a 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 February 1 This report period begins with the unit at 100% power.

February 8 Severe icing was experienced at Low Level Intake Screens commencing at 0410. In order to maintain canal level,main condenser outlets were throttled. Load reductions were begun at 0530 in order to maintain vacuum. At 0800 the unit was at 95%. Conditions were improved at the river front and at 0945 the unit was returned to 100%.

February 28 - This report period ends with the unit at 100% power.

UNIT 2 February 1 This report period begins with the unit at 100% power.

February 8 Due to the same icing which occurred as noted in Unit 1 summary, a rampdown was begun at 0524. At 0630 with the load at 72% low level pumping conditions improved and a load increase ~~as begun. At 0930 the unit was returned to 100%.

February 28 - This report period ends with the unit at 100% power.

e

  • I

.AMENDMENTS FACILITY LICENSE OR TECHNICAL -CIFICATIONS FEBRUARY, 1978 The Nuclear Regulatory Commission has issued Amendment Nos. 36 and 35, January 28, 1978, to the Operating License for the Surry Power Station Unit Nos. 1 and 2. These changes are the result of a NRG request to modify reporting requirements. Of sign:ificance are the

_following changes:

1. Revision of the reporting requirements to allow the use of Monthly Operating Report formats.
2. Deletion of the Annual Operating Report while re-taining the requirement that occupational exposure data be reported annually.
3. Change in frequency from semi-annual to annual for submittal of Non-Radiological Environmental Moni-toring Report.

FACILITY CHANGES REQUIRING NRC APPROVAL FEBRUARY, 1978 There were none during th+/-s reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL FEBRUARY, 1978 The following facility changes were implemented during the month of February. None of the changes constitute an unreviewed safety ques-tion per 10CFR50.59.

Design Changes Unit

1. DC 75-48 Travelling Screen Wash Pumps - Low Level 1&2 Description - The originally installed vertical turbine pumps failed to operate properly, apparently because of cavitation which caused severe vibration. These have been replaced with close coupled horizontal centrifugal pumps which are designed to improve the reliability and signifi-cantly reduce maintenance problems.

Summary of Safety Evaluation There are no safety implications involved since this design change does not effect .the circulating or service water availability, flow path, or flow rate.

2. DC 77-31 Level Indicator - Primary Transfer Tanks 1&2 Description - In order to allow the Control Room Operator's monitoring the primary transfer tank level a computer pickup point has been inserted on the tank level indicator which gives a .display ori the Control Room CRT.

Summary of Safety Evaluation There are no safety ramifications surrounding this design change which impact upon the FSAR or Technical Specifications.

3. DC 75-45 Count Room Air Conditioning 1&2 Description - On hot days count room humidity and temperature could not be maintained if chill water supply to the air hand-lers was lost. This design change installed a backup cooling system to the main air conditioning system in the eve.nt a loss of chill water should occur.

Summary of Safety Evaluation This design change effects neither the FSAR nor the Technical Specifications since this backup system alters present conditions only by providing added assurance the system will be operable.

FACILITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL

( CONTUIDED)

Unit

4. DC 76 Liquid Waste Treatment Utilizing Disposable 1&2 Ion Exchangers Description - The initially constructed means for disposing of liquid waste via the evaporator proved impractical for processing the amount of waste generated. An alternative, utilizing resin beds and filters, was installed, and while not the final solution has proved an acceptable and safe interim measure.

Summary of Safety Evaluation _

This system does not constitute an unreviewed safety question. The probability of an accident is lessened with the elimination of a requirement for high temperature, pressure, 1

and flow rates; fluid boundary failures would not permit un-monitored releases; and discharge points are continuously monitored.'

-TESTS AND EXPERIMENTS REQUIRING9 NRC APPROVAL FEBRUARY, 1978 There were none during this reporting period.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL FEBRUARY, 1978 There were none during this reporting period.

&R CHANGES, TESTS AND EXPERIME~

FEBRUARY, 1978 There were none during this reporting period.

Page 16 .

e**

  • , l * *

.. (. **-~ --~~R~Y POWEP-. ST!.TIO:{

. .. ~ ! CHEHISTRY RE:P.O!t'r FEBRUARY 1978 T.* S.6.6.A.ll PRIHARY COOL.\:."IT UNIT NO. 1 UNIT ~O. 2 M~ALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM HINI!-Iill1 AVER.AGE

  • Gross Radioact., µCi/ml 3.88E-l 2.72E-l 3.24E-l l.18E;_l 7.81E-2 9.40E-2 Suspended Solids,* ppm 0.4 a.a 0.2 0.2 0.0 0.1 Gross Tritit".::l, µCi/ml 1. 79E-l l.60E-i 1. 70E-l 2.00E-1 1.52E-l 1. 72E.-l Iodine-131, UCi/ml 3.02E-2 l.OlE-2 1. 60E-2 5.27E-4 l.12E-4 3.41E-4 I--l.31/I-133 0.6215 0.2960 0.4328 0.7227 0.0228 0.142-7.

Hydrogen, cc./k.g 45.7 20.0 31.3 50.3 25.2 33.0

.... 0.74. .. ..

- L65 1.18_-- .

Lithium, pp:::i .. i.oo* - 0~'82 1.49 .. -* .

Boron-10, pp-::i + 38.2. '1.6-~7.. 3.1. 6 .. il,S .. *106. no ..

Oxygen-16, pp:i 0.000 0.000 0.000. 0 .000 . 0.000 o.ooo 0.05 0.05 0.07 0.05 0.05 Chloride, pp::i 0.05 0

7.39 7.30 7.16 6.82 pli @ 2s c 7.18 16. 91

+ Boron-10 = Total Boron x 0.196 I

NON-RADIOACTI'i.1E CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate o.o Boron 2016.

Sulfate 1668. Chromate 0. 09

--,...~~~~~~~~

50% NaOH 2100 Chlorine O O

~-=-=-=-~~~~~~

I ..

SCRIPTIONS OF ALL INSTANCES WHEI!!P' THERMAL DISCHARGE LIMITS WERE EXCEEDED FEBRUARY, 1978 Severe weather conditions during much of the CTonth resulted in portions of the circulating water system out of service in order to allow the units to maintain full power with a system wide power short-age due to weather.

On February 8, 1978 severe icing at the low level intake resulted in temperature changes greater.than 3° and cooling water 6T between river water ambient and the station high level intake in excess of 23°. The thermal discharge excursions on Februa~y 8th,were allowable under Techni-cal Specifications 4.14.B.1 when the loss of another generating unit would have resulted in serious load curtailment and hazarded system stability. The remaining 6T ~xcursions were allowable under Technical Specification 4.14.B.2 while maintaining full power with portions of the circulating water system out of service for repairs.

The thermal excursions were as follows:

February 1, 1978 Exceeded 15°F 6T across station February 2, 1978 Exceeded 15°F 6T across statiori February 3, 1978 Exceeded 15°F 6T across station February 5, 1978 Exceeded 15°F 6T across station February 6, 1978 Exceeded 15°F 6T across station February 7, 1978 Exceeded 15°F t:.i across station February 8, 1978 Exceeded 3°/hour temperature change at the discharge control structure.

Exceeded 23°F 6T across station February 9, 1978 Exceeded 15°F 6T across station February 10, 1978 Exceeded 15°F 6T across station February 11, 1978 Exceeded 15°F t:.T across station February 12, 1978 Exceeded l5°F 6T across station February 13' 1978 Exceeded 15°F 6T across ~tation February 14, 1978 Exceeded 15°F 6T across station February 15, 1978 Exceeded 15°F 6T across station February 16, 1978 Exceeded 15°F 6T across station February 17, 1978 Exceeded 15°F 6T across station February 18, 1978 Exceeded 15°F 6T across station February 19, 1978 Exceeded 15°F 6T across station February 20, 1978 Exceeded 15°F 6T across station February 21, 1978 Exceeded 17.5°F 6T across station February 22, 1978 Exceeded 17.5°F 6T across station February 23, 1978 Exceeded 15°F 6T across station February 24, 1978 Exceeded 15°F 6T across station February 25, 1978 Exceeded 15°F 6T across station February 26, 1978 Exceeded 15°F 6T across station February 27, 1978 Exceeded 15°F 6T across station February 28, 1978 Exceeded 15°F 6T across station The travelling screens at the low level intake were made inoperable on February 8th in order to meet system power demands and operation has continued throughout the month without the screens.

FUEL HANDLING FEBRUARY, 1978 There were 22 new fuel assemblies received as part of the coming refueling of Unit 1. All were removed from shipping containers and stored in the new fuel storage area**

. UNIT 1 .

  • FUEL HANDLING PagEA9 FEBRUARY - 1978 W DATE NO OF /ANSI NO, NEW OR SPE?IT FUEL SHIPPED/RECEIVED ASSE.'iBLIES PER SHIP~o::NT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL 2-15-78 10 LM04TE/3.4 2.5 mrem/hr.

LM04TU/2.9 II II LM04UE/2.9 II II II L..'104TZ/ 3. 4 " II II LM04TG/2.9 II II II LM04TL/2.9 II II II II II II LM04TY/3.4

. LM04V2/3.4

  • II

" II

. LM04TQ/2.9 " " II Ll104TV / 2. 9 " " II 2-22 78 12 LM04UL/3.4 2.5 mrem/hr.

LM04UZ/3.4 II

" II LMP4U9/3.*_4 II II II LM04UM/3.4 II

.. II II LH04UP/2.9 II  !'

LM04UF/2.9 II II LM04TJ/2.9 " " II II LM04UX/2.9 " "

LM04U5/2.9 II II II II II LM04UT/2.9

. II II II LM04UA/3.4 LM04V3/3.4

  • II II

UNIT*2 ,

FUEL HANDLING Page FEBRUARY, 1978 DATE NO OF /'.ANSI no. NEW OR SPENT FUEL  !

  • SHIPPED/RECEIV'ED ASSE..'iBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPiNG CASK ACTIVITY LEVEL i HONE DUR.n [G '!'HT<:: p,.-~

I i:i1-: Pl<' lnnn I

I I

I

/

II I '

_i

I -

P CEDURE REVISIONS THAT CHANGED Til!I' OPERATING MODE DESCRIBED IN THE FSAR FEBRUARY, 1978 There were none during this reporting period.

a a

,/

DESC~TION OF PERIODIC TESTS WHICH WE!il'NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS FEBRUARY, 1978 There were none during this reporting period.

INSERVICE INSPECTION FEBRUARY, 1978 There were no inservice inspections performed during this reporting period.

a -24.:. A lWl'ORTABLE OCCURRENCES, PERTAINING~

ANY OUTAGE OR POWER REDUCTIONS FEBRUARY, 1978 There were none during this reporting period.

MAIN-ANCE OF SAFETY RELATED SYSTEMS ING OUTAGE OR REDUCED POWER PERIODS MECHANICAL, ELECTRICAL, INSTRUMENTATION DEPARTMENTS There was none during this reporting period.

/

UNIT NO. 1 MONTHLY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE

.. \-,.,

FEBRUARY, 1978 1, MAINTENANCE ORDERS COMPLETED -MAJOR *OR- SAFETY RELATED ITEMS 0 2.. DESIGN CHAUGES BEING WORKED Dc-74-55F, DC-76-18*, DC-77-37

~~~~~~~~~~...-........~~~~~~~~~~~~~---~~

I N

3. PERIODIC TESTS *PERFORMED 2 "'I PT-39.1 PT-24.4A

UNIT NO. 2

.MONTHLY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE FEBRUARY, 1978 1, MAINTENANCE ORDERS COMPLETED -MAJOR* OR* SAFETY RELATED ITEMS 0

2. DESIGN CHAUGES BEING WORKED~~~~~--~~~--~~------,.~~~~~~~~~~~-

DC-74-55F DC-76-18 DC-77-37 I

N

3. PERIODIC TESTS *PERFORMED 1 -...J I

PT-39.1

UNIT NO. 1 MONTI-IL Y OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE I'

FEBRUARY, .1978

1. MAINTENANCE ORDERS COMPLETED SAFETY RELATED ITEMS 0
2. DESIGN CHANGES BEING WORKED DC-76-18, DC-75-36, DC-75-48, DC-74-55 I
3. PERIODIC TEST PERFORMED 19 N 00 I

PT-34 (4)

PT-23.6 (4)

PT-23.lA (4)

PT-23~.l PT-24.4B PT-31.3 PT-24.6 PT-24.6A PT-27 PT-23.2

UNIT NO. 2

. MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE FEBRUARY, 1978

I
1. MAINTENANCE ORDERS COMPLETED SAEETY RELATED ITEMS 0 I
3. PERIODIC TEST PERFORMED 6 N

'f PT-34 (4)

PT-23.1 PT-27

FEBRUARY, 1978

'I MONTHLY OPERATING SUPPLEMENT SHEET INSTRUMENT MAINTENANCE UNITS 1 & 2

1. MAINTENANCE ORDERS COMPLETED SAFETY RELATED.ITEMS 0 2.

I w

0 I

3. PERIODIC TEST PERFORMED 58

.!~PIR'l' OF RAlllOACTt\1-11 EFFLUliNTS PAGI~ 2 F.i\C I Ll 'l'Y 1_-".1-"r-'-r,,_y-'-P"'""m'--'.::.er"--S~ta""t_i"'-o~n~~

l. l.lQUTn ltl\l.f\A~l;S (CONl')

Il.

J. Total Noble Gnses C.u1:1.f-"L- 4. 25E+2 l.08E-3 6.74E+2 3.071H-3 (i!7.98E+2 1.46E+3 7.52E+3 '.6. 39"+2

}  :{~ ~~ i :~~,~~i-a_t_e--=c-r_o_s_s_R_a...,<l""'!_o______ ~£.1L- __l_._.6_3_1_,__l_ _,,,________1. 691l-l ._-l~~~~-il 5 .16F.-2 ___Ll!!i.E=2- ] .51iE::L 1.87E-3 ~~ 4.07E-2

... ____a_c ti vJ ty_~y)._ _ _ _ _ _ _ _ _ _ __,,. c.u r_i_!':.2_ ___7._._6_9_E_-_5__ 11_ _l.2UE..:4 1. 92E-S 1. 34E-5 1.67!~ 2.b2E-4 2.23E-5

~-:t~ft-*

4. Total Tr j t1u111 2.23E+l C.ude'-'"-ii--=3"-'.'-'5'-"7-'-E'--'+-"'l-- 11_...=..~'-"-'--'--ll------*jl----'----tl*--=~c=~

2.l9Inl 3.66F.+O l.28E+2 -w*~ 2.02E+l I ,:1'.

3. Total Particulate Cross Alpha I

--*-~'\~n,~<1,..:.i~on~c~.t~i~v..:.i.::.t~y-----------#~C.~u,~r~i~e~s_ 11 ._ _3_._4_S_E-_7.,...__H--- 5.orn..:1 3. 81,E-7 . ".56£-7 5.531\-6 2 .1191,-6 t-----

_J.lJ..lidL__ -Jl...2,',1'- *'~ .:r.: *.

1. 331':-~3

_6_.____M_a~x_l_m__11_111_t_lo_._l~'-le_*_C~*~1s~*~R_u~*l~e~a~~~*e~R~a~t~e----;i~l~*t~'.i~./~s~*'~'""-ll*--1-'-.2_5~E~'+_2_ _ _~~~-'-=--ll---'-~~o...-H--------tt--~~~~-lf-~~-~~--, -------H-----

11 7. 251~+3 2.95E+2 l. 31E+3 6.89E+2 1

H~-----------------------~**---lf-------111-------11-------lr------H*------,r----,-.---il-------11----~

7. Percent of Applicable Limit for Techn lcal ~'"! (I.cation<>
  • r-*  ! .

(n) Noble_(_~._a~_,*e_*:-_,----------11-~P~c~r:~c~c~"'-r;_ -3....9.~ __9_. 2_5_E_-_l__*__6_.7_9_E_'-_1__ 11_ _ _z:n_._1~_E_+_-u__ ,,_-l@_S_._2:.i~'.l_,__1_ 1. 02E+O 1.....

r.'.

==---{b) _ _!Jal1ll'.~:1._>11...,>>_____________ 11 _,l'i'.!.'..'~~t,,__.,,.3_.7.,...7.,...1""";;-_10,.---;,i--2-*..,9..,7_F._-..,.l_ ~lE-1 __Li.4.!~*:-_1~_,.___3_._6_1._E_-_2_

_ 1,_._3_2_E-_l_1 __ , _______* - - - - - (

_(~_c_,)___P_11_r_L_l_c_11_l_a__L__.,_,;_ _ _ _ _ _ _ _ _ 11_"1~~".:S:.!:!l!:.. 6.90E-3 l.02E-2 8. 76E-2 4 .14E-11 2.26E-3 . l.~§_E_-.3--**-------H------

9.

'.:j*. .

1..

l:

I;*.*

i..

--~~

HEALTH PHYSICS FEBRUARY, 1978 There was no single release of radioactivity or radiation exposure specificallly associated with an outage that accounted for more than 10%

of the allowable annual values in 10CFR20.

/

REPORT m* RADIOACTIVE EFFLUENTS PAGE 1 Facility: Surry Power Station DOCKET: 50-280 and 50-281 YEAR: 1978 1: ( c) Maximum Concentration Re.leasetl UCi/ml , 5. ll1E-9 3. 47E-.LO i

1

(.1)

(b)

Te>t.tl f(dc.10.i:-d I Cud.cs 1.161,-5 3. 70!\-7

  • -"---------~--~~~-~-ff-~-,-,,---~l----=~---~-------*11--------~-------l'-------ll---------li--------ll

,\v1~. Co11cc111:r;1tion Rcl.eaRcd

  • __l.!fi_/_r_*L_l____4_.__11_J_E_'-_l_.l_1_j1__1.;c.._7_11_E_-_1'-5'---ll~------l~-------l~--------l!-------11-------- ------*i,
}.,___\'.::_~:_!_:~t_o Disch. C:mal I Li.tern 3.37E+7 7.17E+7 . ..,..,

ji!,_ \'o.l. of. Dil11tion_r'- ..:'-'n.=t-"c-"r--~-------"ll l.i ters 2. 62E+ll 2.] JE+l l 1

'f'

-=;-:--i~c;-rnrcs Re lc;:13.;cl MPC uCi/ml *-Cud.es

!I r---l---f)2 T-131 ] 10-'-'

tl x 10..:-,-.---------~----

1-1 . 117.E=l__

1. 71 E-11

_.1L_2_ftg,_._-"3'--ll---------ll-------lf--------~------*H-------11-------

!l. 9(>"-'*

il 1-1 J3 l x Hi-" ,., 3. 72E-11 6. 06E-l1

j 1-1J~ 2 x io-*-.---------~. ------;i--=5-'.-'1~5~E'-._-4'---~,-""s~.~3~.3~F~.--4,;.__-ll--------11-------11--------i1--------1i.-------11----*--*~

1,_ _ _ _1_-l.J_~ l1 x 10-t. 1 l.38E-4 6.7Cm-4 t=--====~~i-=+[:_:

if C:;- J.3 7

___ i2, x~ 10- .t~.,. ~- . .,.': __________*~------

11

1. zJE-2

. -:f:-]0!:::Z-

-~-_:_}r>__SE-1, *

~_
-;_=-*_;~~~~~.ff~~~~~~~~~~~~~*-------11--------*>--------11-------ff-------11
l l____ _!::;- l.JB II _2-"._2_2-"E'---'1,_ _,,~,.......,*~c--.---tt--------11------*ll-------!f------H-------11-------;1

'L- Co-57 11 x 10 *-----ll--'.l=-.,c5~_lc1 ,J"'-'-.'..>--l- l..5hl'-~- *-------<<---------

i
:*;;:5r, 9  ;:rn-, _I i.11iE-1 1 r.541,-2

! c~6o Jx1~* 1.03~1 l~ir-,1-~-2--~,~-----~-------------~--------------------

~

if- ~~'.~~'!.'

!\;1-!.l1

_____l__::_l_O_~'t 3 X L()-C,

--1----- __!!..:2!!.!::-'3 -- _-3.:.!0_1_*~-:_:_l- -

l.5'JE-2

H------ --*----1*,1~.---1>--------*-------

! . ..,'i-o/1_,l*,..:-...,2_ __, _______-11--------!I-------

1

cr=:ii 2 x ir::.;:_ ., ~-3-:r,m~:-2-- ri*.H.iE-:J ,

!l 11"-Yl 5 " JO-* . 9.09E-4 1.SJE-11

~ Nb-93 1 x LO-* l 3.SlE-3 8~3~~-~4--~-------tt--------11-------~i------_,~------~~----~~i

~ r.1-r.u-j.'..O 2 x io s

. -----R*-,.,-_-s-s'------------------,1-----_,. 'I i.srn-3

.~

1.83E-4 1.361'-3 :1 1, 1 1!

~--------------'-----------------"'-------"-------'-'---------------------

REPORT OF Ri\!lIOACTlVE EFFUJE:~TS PAGE 2

-"~\ ... iL:iY: s~i=-rv p,... ;..*c*r  :::r.::tion DOCKET: 50-21JO and 50-281 YEAR:_~~l_9_7_8~~~

.i I

w f

1. Ol1E-6 for

,1 _ _ _ _ _ _ _ c_c_-_r,_~o--------~~----'f----,1-~-s*~l*71E_'-_*s.,.---11~1~*~3~6=E_-=s-~11--------l+--~-~-~11-------tt---~-~-1~~------l1----~~1'

_______ ,_\
}-';!! 3.34E-6 s. 1sE-9 '

1

~-,__,_, _,_,_......~ *-* ...:_;_;~'.=t~ ~&,, ~"--~=-==~==**~- .t .,...*"***-==J *-~=~-~,;}1;::.~.=~- -~.l;J,7!::-~~==* =~=~=*=~-=*: -==*=~~=-=~*=* !-."*==~=*~-. . ~==**.t*=*,==*==* *~"""I\.===*==~. ~-****=*.-~. ,,... . I

...... "'=

I

~i

/ -,

l\EPORT OJ! R/\DIO/\CTIVE El!FLUENTS PAGE 3

!!AGILITY: Surrv Power Station _ _ __

YEAR:~_l_97_8 DOCKET: 50-280 and 50-281

  • =~~~r-*=-a.~~_.....~~=-=-===

-*== ~=======,..-==~==~

1 II. AIRBORNE RELEASES (CON T)

~*'il-:---=~=j:~-;;--c*;;;;*~'.~~~r;;;y~;.~~<l'~(c~~?t)~~=~* \C¥Zff~~- =*~l~.H\!Afff= =1'.:HUH!l'l}J'.==* .,

  • I (b) 1.~la-'l~o~P,~P.-.11~n'------------11-----~-------11-------Jt-------11------,t-------l'--------11-------~------tl ,,.,

ii I-131 7.39E-6 2.~7~2~E--~~-~ff------11-------+------;r-------11------tt------11

!I I-lJ2 1.04E-6 i<

~ 1-l:JJ 2. 7511-6 1.lllE-6 I I-134 * *

~------:~{c~--"l3~J=--------------l'-----lt---'9~.'-4~3~lc~-+~l'----l~-r,--'*-b_7_J_f.i.._2_ _~1--------+f------;1-------jl,--------tt-------11----~11 Xc-lJ3"'n"-1------------'l*-----!I---'*_,----11--l.;...':...*7r.6'<it"°--'l;---~------ll'-------11------+------__,!f-------*ff------ll f ______~Xc~:_:-_1 1

Kr-tl5:'1

.. f~'-'--------------~------ _J__._9_'*!~ --'*-

2, 41E-l1 IJ_1,:~1-_

I,. 271*:-:J 1_-tt*-----~------ff-------:t*-------H-------tt------11 Kr-83

  • 7.0~7'-E'--~l--;~------tt-------tt-------lt-------~------tt*-----ll
---------'-K~r---~-~z,_ _ _ _ _ _ _ _ _ _ _ _ _ ff-----tt---'~~-----jl---,-* -----jl*-------tl------11-------tt-~------ff-------tt------

Kr-88

  • 5.lrZE-:J
-t--.--=-----------=====:~_:.:':J:..__

iifIL. ~'(

snr.rn ;;,\ll!OACTIV-r:_\.1_:\_S_T_ll_O_l_S_l'_O_S_/\_T._ _ _ ,ll-----H-------*u-~*~~.*---~--------,l-------ll---------------lf-------ff------

9 B7r 3 11

n-:---(;-r--Tota.l Amount Solid Waste ...,I
I l'.1-'-'*":l..c""~*'"'"'~c"-'<."-l- - - - - - - - - - - l f F'J'l 60 ( t. J V*

I I/ (b) Estir.1atcd Total /\ct.lvit}' Curies 1. 1. 625

~ (c) Date of Shipment and Barnwell, Barnwell,

!~ DI snosltion s.c. s.c.

- =--*- --~* --*==*--- .J'--***_.,________,.._"

  • =*=~'G==~==="'"======="""'====~=*~=*=~=~'-'=~===~=='==~===~=~~=

01-23-78 2-2-78 2-21-78 2-22-78

'I

  • SENSITIVITY DATA
1.
  • HiniI!lum Detectable Activity*
a. Gross Alpha; 5.27E-9 µCi/ml
b. Tritium; 4.0E-6 µCi/ml
c. Strontium-89; less than 3.0E+l pCi per total filter composite.

<l. Strontium-90; less than 2.0E+O pCi per total filter composite.

e. C02-14; less than 7.0E-10 µCi/ml.
f. Strontium-89; less than 9.0E-9 µCi/ml.
g. Strontium-90; less than 8.0E-10 µCi/ml.
2. Hultichannel Analyzer - GeLi
a. Liquid and/or Radiogases - lOOcc Ba-La-140 2. OE-7 I-131 5.lE-8 Xe-133 5.4E-8 Xe-135 2.9E-8 Cs-137 9.2E-8 Cs-134 7.2E-8 Co-60 l.5E-7 Co-58 9.SE-8 Cr-51 - 3. 8E-7 Hn-54 l.OE-7 Fe-59 2.4E-7 Ar-41 1. 6E-7 I,-134 l.lE-7 I-132 l.OE-7 Na-24 1. 7E-7 I-133 6*. 9E-8 I-135 4.5E-7 Kr-85 l.36E-5 Kr-88 5.SE-8 Kr-87 5.3E-8 Kr-85m 2.3E-7 Xe-138 4. 7E;..9 Xe-135m 5.8E-8 Xe-133m 1. 7E-7 Rb-88 8.SE-7
b. Ra<lioiodines I-131 2.3E-6 I-133 3.lE-6 I-132 4. 7B-&

I-134 4.8E-6 I-135 2.0E-5

      • ," PROCED _ DEVIATIONS REVIEWED BY STATIO~CLEAR SAFETY AND OPERATING COMMITTEE AFTER TIME LIMIT SPECIFIED IN TECHNICAL SPECIFICATIONS FEBRUARY, 1978 Number Unit Title Deviation PT-32.1 1,2 HEPA and Charcoal Filter Step 6.1.1 not accomplished Tests Deviation occurred January 18, 1978 and was reviewed by the Station Nuclear Safety and Operating Committee February 9, 1978.

MHP-C-RS-43 2 Recirculating Spray Heat Step 5.1 - Remove upper Exchanger Repairs head from heat exchanger 2-RS-E-lB and lower service water elbow.

Step 5.2 - Remove upper diaphragm by grinding off 3/16" weld.

Deviation occurred November 21, 1977 and was reviewed by the Station Nuclear Safety and Operating Committee February 9, 1978.

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