ML18139A497

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Monthly Operating Repts for Aug 1980
ML18139A497
Person / Time
Site: Surry  
Issue date: 09/08/1980
From: Dunn S, Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139A496 List:
References
NUDOCS 8009190444
Download: ML18139A497 (47)
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VIRGINIA ELECTRIC AND PO'W"'ER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 80.:..08.

AUGUST,. 1980 APPROVED:

MANAGER

-i-CONTENTS Section Operating Data Report - Unit If 1 Operating Data Report - Unit ff2 Unit Shutdowns and Power Reductions - Unit ff I Unit Shutdowns and Power Reductions - Unit 112 Load Reductions Due to Environmental Restrictions Unit /fl Load Reductions Due to Environmental Restrictions - Unit #2 Average Daily Unit Power Level - Unit #1 Average Daily Unit Power Level - Unit #2 Summary. of Operating Experience Amendments to Fac:ility License* or Tecfrnical *-Specifications Facility Chaii.ges Requiring. :NRC Approval.

Facility Changes That Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Exp~riments That Did Not Require NRC Approval Other.Changes, Tests and Experiments Chemistry Report Description of All Instances Where Thermal Discharge Limits Were Exceeded Fuel Handling Procedure Revisions That Changed the Operating Mode Described In The FSAR Description of Period Tests 'Which Were Not Completed Within The Time Limits Specified In Technical Specifications Inservice Inspection Reportable Occurrences Pertaining to Any Outage or Power Reductions Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance

.. ~_

Page 1

2 3

4 7

8 9

10 11 14 15 15 16 16 17 rs*

19 20 22 23 24 27 28 31

- OPERATING DA'l'A REPOKI' OPEA'ATING STATUS

1. UNIT NAME
2. REPO[{I'ING PERIOD DOCKET NO. 50-280 DATE 10 SEP 80 COMPLETED BY SUE' D. DUNN TELEPHONE 804-357-3184 SURRY UNIT 1 80180 TO 83180
3. LICENSED THER!*fAL POWER (M..IT) 2441

,-------------------~---,

4. NAMEPLATE RATING (GROSS f.Iw'E)
5. DESIGN ELECTRICAL RATING (NET MwE)

.6. NAXIMUM DEPENDABLE CAPACITY (GROSS KwE)

7. !>!AXIMUN DEPENDABLE CAPACITY (NET MWE)
8. IP CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPOP.I. GIVE REASONS 847.5 INOTES I

822 I

I 740 704 NIA

9. POWER IEVEL TO '>>'HICH RESTRICTED. IF ANY NIA (NET Nw'E).
10. REASONS FOR RESl'RICTIONS. IF ANY NIA
11. HOURS IN REPOI?IING PERIOD 12 ~ NUMBER OF HOURS REACTOR WAS CP.ITICAL

. 13. REACTOR RESERVE SHUTDOWN HOURS

14. HOURS GENEP.ATOR ON-LINE
15. UNIT RESERVE SHUTDOWN HOURS.
15. GROSS THERMAL ENERGY GENERATED (!>fwfJ)
17. GROSS ELEC'.i'RICAL ENERGY GENERATED (/6./H)
18. NET ELECTRICAL ENERGY GENERATED (/.fi.IH)
19. UNIT SERVICE FACTOR
20. UNIT AVAILABILITY FACTOR
21. UNIT CAPACITY FACTOR (USING /IJJC NET)
22. UNIT CAPACITY FACTOR (USING DER NET)
23. UNIT FORCED OUTAGE RATE
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE.DATE. AND DURATION OF EACH)
25. IF SHUT DO'riN AT END OF RE'POF{I' PEPJOD.

ESTIMATE DATE OF STARTUP

25. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION THIS MONTH YR~TO-DATE CUMULATIVE 744.0

. 5855. 0 67439.0 509.0 3462.7

... 42214.3.

o.o 182.6 3731. 5 503.0 3440.1 41345.1 a.a 183.6 3736.2 1045464.0 8055870.0 95770742.0 301490.0 24-482.35. 0 31128733. 0 281914.o 2312196.6 2953909s.o*

67.6 o/o

. 58. 8.o lo 61.3 olo 67.6 o/o 61.9 olo 66.8 olo 53.8 olo 56.1 010 62.2 olo 46.1 olo 48.0 olo 53.3 olo 32.4 olo 41.2 010 26.5 olo 9/15180 - SIG REPLACEMENT OUTAGE REFUELING -

1 YEAR FORECAST ACHIEVED

  • ---------------*------------~---- ---*.

... ****-*---------**--*-*-*----~==~ GFEM1*ING DATA IrEPOhT DOCKET NO. 50-281 DA'i'E 08 SEP 80 C01\\'PLE'.tE£ BY 0.J. COSTE LU

'i ELEPhONf:; 80 4-35 7-3184

2. 1-.i:.i:!CifSii,G PE11IC£

.~. LICE;/.'SE'E TiiEiJ.;/,L PO't..'E,H Ci*;h'T)

4. i*k',EPLA'iE M'IING (GROSS,\\!J.r'E)
5. DESIGN ELE'C'l'lr.'ICAL F..A'II!iG (NET N11E)
6. f,'A'J.IMUN DEPEi,DABIE CAPACITY (GiiOSS t-f',./£)
7. f*,AXIi-:U;.; lJE?EHDAELE CAPACITY \\NJ:,;T MhB)
8. Il CJIAl~GlS OCCUR IiJ C.4l'ACI'IY RA'IINGS

~I'lE'/.,'S 3 '1.HROUCH 7) SI!iCE LAST lr.EPGiS. GIVE f.EASONS SURRY 50180 2441 847.5 822 811 775 NIA U!II'.l' 2

'IC 83180

,---~~-----------~----,

I NOTES I

I I

I I

1------------------------1 S. p(;,.,Ef.. LEVEL TO hHICH HESTJ-.ICTED. IE' ANY NIA

i. ii l::T p.,, E )
10. f:EAS01lS EGR RESTRICTIONS. IF Alff
11. HOljRS IA; f.EPOh":f.'ING PERIOD
12. l;'[i!YEDH OF HOURS HEAC'l'Oli,,.,:As CRITICAL
13. F:E.AC'IOR HESERVE SHUTDCkfl' HOUFr.S
14. HOi.Jf..S GE'fiElilSOR O!r-LINE
15. lJi.I'l. h.L'S£2V E SHUTBQJ../N
  • h'GURS
15. CF:OSS THEEJXAL ENE'RGY
  • GE/,'EP..ATED (Nw'H)

. 1 7 *. c.;oss ELEC'I.F:IC AL EiiEHCi: GE!;ERATE'D. (MY.'H)

18. j;['J: ELEC'iF.ICAL ENERGY GENERATED lMw'H)
19. UhIT SEii'VICE FACTOR
20. Ui.IT AVAILAEILI':ZY FACTOR
21. UhIT CA?ACITJ.' FACTOR (USING. /.JDC NET)
22. l.Jf.IT CAPACI2.'Y FAC'l'OR (USING DER NET) 2 3. Ui.'IT FORCED OUT AGE RATE
24. SiiU'i'DOwNS SCHEDULED OVER NEXT 6 MONTHS (TYPE.liA'iE.A.ND DURA'i'ION OF EACH)
25. IF SHUT DO.'rd'i A1' END OF REPOEi PEF.IOD.

ES'J:Ii-:A'l'E EATE' OF STAR'l'UP

25. 0*1,ITS If;* TEST S2 1ATUS

( PF.IOH 'IC COlr!f/EhCI AL OFERAT ION)

Ii.'I'IIAL CRI'IICALITY li~ITIAL ELECTRICI'l'Y CC!*i*ERCIAL GPEFr.A'IIOJI NIA THIS MONTH YR-TO-DATE CUMULATIVE 744.0 5855.0 64319.0 366.1 366.1.

34866.0 0.0 o.o 0.0 232.2 232.2 34228.4.

o.o 0.o.

.. o.o 300919.0 300919.0 7.9495002.0 86180.0 86180.G 25955024~0 77485.0 77485.0 24614090.0 31.2 ojo 4.0 010 53.2 010

31. 2 olo 4.0 olo 53.2 olo 13.4 olo
1. 7 olo 49.4 o/o 12.7 o/o 1.6 010 46.6 o/o 25.6 olo 25.6 a/o 21.1 olo FORECAST ACHIEVED

No.

Dale 80-12 8-1-80 F: Forced

. S: Scheduled (1)/77)

. UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH AUGUST, 1980

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E-Opcralqr Training & License Examination f *A<lminislratlve G-OperaUon:.11 Error (Explain) l 1-0!her ~Explain) 3 c:

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Reactor primary DOCKET NO.

50..:.2so UNIT NAME SURRY UNIT 1 DATE September 8, !1980 COMPLETEll BY SUE p I DUNN TELEPHONE (804)-357-3184 Cause & furred ive Action lo Prevent Recurrence shutdown due to >.3 GPM to secondary tube leak in "1 c" S/G.

4 Exhibit G *Instructions for Preparation of Dal a Erilry Sheets for Licensee Event Report (LERl file (NUREG*

0161 l Exhibit I *Same Source I w I.

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80-8 8-1-80 80-9 8-19-80 80-10 8-19-80

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B-Malntenance of Test C'-Rerucling D-Rcgu!al<.'iry Rest rictiun Lkensec

  • Event Report H

£-Operator Training & License Examination F-Administralivc G-Opcralional Error (Explain) ll*Olhcr {Explain) 3

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  • . ~ Eu It') u 0 u Method: I-Manual 2-Manual Scram. 3-Aulumalic Scram. 4-0ther (Explain) DOCKET NO. UNIT NAME DATE COMPLETED HY TELEPHONE 50-281 Surry Unit 2 ~ember 8,. 1980 Sue D. Dunn (80lt) 357-3184 Cause & Correi:t ivc At:tion to Prevent Recurrence Continuation of shutdown for refuel-ing and steam generator replacement, which began on 2-4-79. Work still underway on piping restraint modif i-cations required prior to unit recovery. Reactor trip caused by "B" S/G High Level as a result of "B" main feed regulating valve failing open. The problem was found to be a faulty controller. The controller was re-placed. Reactor trip caused by "A" S/G Lo-Lo Level while feeding S/G's in manual. Another more experienced operator was placed on the feed control station. 4 5 Exhibit G - Instruct ions for Preparation of D:ita Entry Sheets for Licensee .Event Report (LER) File (NU REG* 0161 l Exhibit I *Same Snun.:c .t'- 1 N11. Date 80-11 8-22-80 80-12 8-24-80 i 80-13 8-26-80 F: Forced S: Scheduled. l'l/77) UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTll AUGUST, 1980 c: - r1 en...... .2 t'.! c: c: 'J u
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    ~ Ci F 23.6 H 3 F 13.7 H 3 F 12.1 ll 3 Reason: A-Equipmenl Failure (Explain) B-Mnintennnce or Test C'-!Rcfueling, D-Regulatory Restriction I* licensee Eveni Report /t E-Operalor Training & License Examination F-Adminisl ml ive G-Opcralional Error (Explain) ! I-Other (Explain) 3 .... c: E~ u,,... c: u u u 0 "Cl .... "Cl VJ ~
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    Eu 111 LI 0 u Method: I-Manual 2-Manual Scrnm. 3-Aulomatic Scram. 4-0ther (Explain) Reactor DOCKET NO. UNIT NAME DATE COMPLETED DY TELEPHONE 50-281 SURRY UNIT 2 September 8, *1980 SUE D. DUNN (804)-357-3184 Cause & for red ive Action lo Prevent Recurrence trip and Safety Injection on spurious steam header to steam line /JP signal caused by steam from lift-ing relief valve impinging on steam header pressure transmitter. The rea-son for the RV lifting was tl et ermi netl to be stuck NRV's in steam drain line. 'fhe NRU' s were renaired, Reactor trip caused by turbit'1e trip as a*result of loss of auto-stop oil pres sure through faulty relief valve. The faulty relief valve was reolaced. Flow surge caused by air trapped in condensate polishing system.air opera-ed bypass valve line resulted in steam header steamline /JP safety injection sigrial. The AOV will be operated in manual to reduce the possibility of a feed flow surges. 4 5 Exhibit G - Instructions for Preparation or Data E1t1ry Sheets for Licensee Event Report (LER) File (NUREG-0161) Exhib ii I
    • Same Sou n:I.'
    I V1 I No. Dale 80-14 8-27-80 80-15 8-30-80 I. F: Forced S: Scheduled llJ/77) UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH AUGUST, 1980 ~ c: - r1 ~- -~ ~ § c:: '..J P-
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    cs F 9.3 n 3 F 3.6 A 3 Reason: A-Equipment Failure (Explain) 13-Malntenance of Test ('-Refueling D-Rcgulalory :Restriction Licensee Even I Reporl # I E-Opcralor Training & License Examination F-Administrativc G-Opcralional Error (Explain) ll-Othcr (Explain) 3 t: E"'1" v,., c., ., <I.I 0 ""O -0
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    I-Manual 3-Aulumalic Scram. 4-0lher (Explain) DOCKET NO. UNIT NAME DATE COMPLETED BY TELEPHONE 50-281 SURRY IJNI T 2 -S..e.p.temher 8,, 1980 Sl)E D. DUNN (804)-357-3184 Cause & Correct ivc Action lo Prcvcnl Recurrence Electricians working in instrument racks interrupted power to Train rrA" reactor trip relays causing reactor trip. The electricians were instruct ed to insure proper procedures and work practices are followed when working in instrument racks. Reactor trip caused by "C" S/G High Level as a result of "C" main feed regulating valve failing open. The instrument technicians were hooking up a visicorder in the instrument racks and used the wrong type of lead! The instrument technicians were in-structed to are* used in 4 insure the* proper the future. Exhibil G - lnsl rue! iuns for Prr.parnliun of Dala Enlry Shccls for Licensee leads Evenl Report lLER) File (NlJREG* 0161) Exhibil I
    • S:imc Soun:~
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    • . LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.l MONTH: AUGUST, 1980 DATE TIHE HOURS REDUCTIONS, MW REASON LOAD, MW Nore during this repo ting per ad.
    t--. MONTHLY TOTAL ~~.. ~~-~~ .... -=-~....... _ ... ~ ............. ~.;;._............,.~,---_......~-~-~..::....,. :, _. ___ r--~-....>._.,...,.__,_, - ,...._._.,._.,._i._,_..._...,..__ --.--* -* -* *- ____.:;_~*-**-** *-****-~-~---*- --~---------*~-~ LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTH: AUGUST, 1980 DATE TIHE HOURS LOAD, MW REDUCTIONS, MW REASON None lluring this report:"mg period. 0 G MONTHLY TOTAL* [: t DOCKET NO 50-280 UNIT SURRY I DATE 9-1.::80 COMPLETED BY SUE D. DUNN AVERAGE PATb¥ l:i'i-/I'E HJ-,,,,:f,'k £EV'££ ,~g;.;';_'f.:': AUGUST 80 AVEP..AGE DAILY. FOi-/ER U'VEL AL'ERAGE DAILY POwER LEVEL DAY (Mi-.'E-NE'l.') DAY (MwE-NET) 1 20.8 17 599.2 2 o.o 18 598.0 3 o.o 19 596.8 4 o.o 20 595.0 5 o.o 21 597~6 6 o.o 22 598.8 7 0.0 23 594.5 8 0.0 24 589. 5 9 o.o 25 582.2 10 0.0 26 571.8 11 268~ 0 27. 562.9 12 480.8 28 528.3 13 595.3 29 519.2 14 593.3 30 539.4 15 591.5 31 527.9 16 595.9 DAILY UNIT FCi-lER LEVEL FOPJ.; INS1'RUCTIONS Oli' THIS FORN. LIST 1'HE AVERAGE DAILY UNI!i' POWER LEVEL IN g.,.fE-NET FOR EACH DAY IN THE REPOiU:ING MONTH. 'IHESE FIGURES WILL BE USED TO PLOT A GRAPH. FOR EACH F.EPORI'- ING f.;QfiTH. NOTE THA'I BY USING MAXIMUM DEPENDABLE CAPACITY FOE THE NET ELECTRICAL RATING OF THE UNIT. THERE MAY BE OCCASIONS w'HEN THE DAILY AVERAGE PO~iER EXCEEDS THE 100 o/o LINE (OR THE RESTRICTED POY.'ER LEVEL LINE). IN SUCH CASES. THE AVE'RAGE DAILY UNIT POWER OUTPUT SHEE:.I' SHOULD BE FOOTNOTED TO EXPLAIN THE APPAft.ENT ANOMALY. L ---~-.. ~-*--***-*--**** DOCKET NO 50-281 UNIT SURRY II DATE 9-1-80 COMPLETED BY SUE D. DUI\\TN AVERAGE DAI£¥ Yl:r'Pl' Pldi*lER bEVEb Mr; fi'J! li : AUGUST 80 AVERAGE DAILY POw'ER LEVEL AVEMGE DAILY POwER LJ:,'VE'L DAY (Ml-.'E-NET) DAY (MWE-NET) 1 0.0 17 0.0 2 o.o 18
    0. ().
    3 o.o 19 54.2 4 o.o 20 256.6 5 0.0 21 323.1 6 0.0 22. 306.0 7 0.0 23 58.7 8 0.0 24 234.5 9 0.0 25 219.9 10 0.0 26 382.1 11 o.o 27 108.1 12 0.0 28 228.8 13 0.0 29 320. 3 14 o.o 30 292.9 15 0.0 31 442.9 16 o.o DAILY UNIT POWER LEVEL FORM DiSTRUCTIONS ON THIS FORN. LIS1; THE AVERAGE DAILY UNIT POWER LEVEL IN l..f>vE-NET FOR EACH DAY IN THC F.E!!Oi?IING MONTH. THESE FIGURES ¥/ILL BE USED 'IO PLO'l' A GRAPH FOR EACH REPOl:CJ.'- ING lveDNIH. NOTE THAT BY USING MAXIJ.:UM DEPENDABLE CAPACITY FOR THE NET ELECTPJCAL RATING OF 'IHE UNIT. THERE MA'i BE OCCASIONS i-.'HEN THE DAILY AVERAGE POWER EXCEEDS THE 100 ° / 0 LINE:; (OR 'THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGE DAILY UNIT POWER OU1'PUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN 'IHE APPARENT ANOMALY. euMHARY OF OPERATING EXPERIENC I Listed belo~ in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents. UNIT 1 AUGUST 1 AUGUST 10 AUGUST 11 AUGUST 12 AUGUST 28 AUGUST 29 AUGUST 31 UNIT 2 AUGUST 1 AUGUST 4 AUGUST 6 AUGUST 11 AUGUST 12 This reporting period begins with Unit at 58% power and a shutdown in progress due to primary to secondary leakage in "lC" of >.3 GPM. The generator was off the line at 0242 and the reactor shutdown at 0 0313. At 0635 the reactor coolant system (RCS) was at <350 F and was at cold shutdown (CSD) at 1335. The leaking tubes were plugged in "l~" S/G and a unit recovery com-menced with the RCS temperature >350 F at 0425. The reactor was taken critical at 2210. The generator was placed on-the-line at 0342 and a power increase began. Power increase was halted at 69% reactor power at 0900 due to sodium carryover in the main steam (MS) system. At 1820 power was decreased to 55% in order to reduce carryover. At 0130 increased power 5%1 At 0540 increased power 5%. At 0950 commenced power increase to 90% power at 5%/hour. Power at 90% at 1600. At 1314 commenced power decrease at 3%/hour to remove "B" main feed pump (MFP) from service to repair leak on suction pressure switch *. At 2230 halted power decrease at 69% reactor power and 450 MWE and removed "B" MFP from service. After repairs completed on "B" MFP and pump returned to service at 0515 commenced power increase. Power reached" 89% at 1500. This reporting period ends with the unit at 83% in coastdown phase at end-of-life (EOL) prior to refueling. This reporting period begins with the unit at cold shutdown with main-tenance, piping restraint modifications and design changes continuing. After all piping restraint modifications and necessary design changes and maintenance were complete the reactor coolant system (RCS) heatup began with the RCS at >200°F at 1504. 0 Reactor coolant system at >350 F at 0700. 0 At 1918 a cooldown to an RCS temperature of <350 F was commenced to allow containment to be hogged to the minimum containment pressure for operation. The RCS was at <350°F/450 psig at 0606 and containment hogging com-menced. At 0650 the hogging was secured and a heatup commenced at 0 0652. At 0815 the RCS temperature was >350 F and the RCS was at hot shutdown at 1630. er-L;RY Or OPERATIJ;G EXPERIENCE e UNII 2 (Continued) AUGUST 14 At 1204 the reactor was taken critical and low power physics testing cormnenced. AUGUST 15 At 1819 the reactor was manually tripped because the "C" Boric Acid Storage Tank (BAST) and ff2 Boron Injection Tank (1!2 BIT) were at a boric acid concentration (CB) of greater than the Technical Specifi-cation limits. At 1908 the "C" BAST and 1!2 BIT were within specifica-tion and at 2228 the reactor was taken critical. AUGUST 16 The reactor was manually shutdown at 0033 due to less than Technical Specification minimum volumes in the #2 Refueling Water Storage Tank (RWST) and #2 RWST Chemical Addition Tank (CAT). At 0248 both tanks were above minimum volumes and at 0300 the reactor was taken critical. The low power physics testing was completed at 2148. AUGUST 18 The reactor was manually shutdown at 1605 due to less than minimum Technical Specification volume in "C" BAST. The "C" BAST was filled to greater minimum volume and the reactor was taken critical at 1723. The generator was placed on-the-line at 2340. AUGUST 19 The reactor tripped at 0718 due to a high water level in the "B" S/G when the "B" main feed regulating valve failed open. The reactor wa~ taken critical at 0913, and the generator was_ placed on-the~line at 2312. At 2341 the reactor was tripped on "A" S/G Lo-Lo water level signal while feeding S/G's in manual. AUGUST 20* The reactor was taken critical at 0007 and the generator placed on-the-line at 0137. AUGUST 22 At 1045 a reactor shutdown was commenced from 70% power due to 11C" BAST and #2 BIT being at greater than Technical Specification CB. At 1152 "C" BAST and #2 BIT were in specification and the reactor shutdown was halted and a power increase began. At 1736 a reactor trip and safety injection occurred due to a s:Purious steam header to steam line LP signal. AUGUST 23 The reactor was taken critical at 1428 and the generator placed on-the-line at 1710. AUGUST 24 A reactor trip occurred at 1530 as a result of a turbine trip caused by a faulty auto-stop oil relief. The relief valve w_as replaced** and the reactor taken critical at 1920. AUGUST 25 At 0513 the generator was placed on-the-line. AUGUST 26 At 2205 a reactor trip and safety injection occurred as a result of a steam header to steam line ~p signal caused by feedwater flow surges due to air entrapped in the condensate polishing system bypass line entering the main feed pump suctions. AUGUST 27 The reactor was taken critical at 0842 and the generator placed on the line at 1011. At 1954 a reactor trip occurred due to an electrician working in the instrument racks interrupting power to the Train "A" reactor trip relays. UNIT 2 AUGUST 28 AUGUST 29 AUGUST 30 AUGUST 31

    SUMMARY

    OF OPERATING AUGUST, 1980 Page 3 The reactor was taken critical at 0310 and the generator placed on-the-line at 0510.

    At 2240 performed 50% load rejection test from 64% power.

    At 2307 performed a 10% load rejection test from 64% power.

    At 2313 per-formed a 10% step increase in power from 54% power.

    At 0225 a reactor trip occurred on nc" S/G high level signal when 11 c' 1 main feed regulating valve failed open.

    The reactor was taken critical at 0427.

    At 0535 a turbine over speed trip test was per-formed with the turbine tripping at 1970 RPM.

    The generator was placed on-the-line at 0602.

    This reporting period ends with the unit at 72% power and a power increase in progress.

    AHEHDl1ENTS T CILITY LICENSE OR.TECHNICAL S IFICATIOHS AUGUST, 1980 The Nuclear Regulatory Commission issued, on July 28, 1980, Amendment No. 59 to the Operating License for Surry Power Station Unit No. 1.

    The amendment results from the NRC Staff's review of the Steam Generator Inspec-tion Program.

    Of significance, the conditions limit the operation of Surry Unit Ho. 1 and have the following provisions:

    (1)

    Unit No. 1 shall be brought to the cold shutdown condition in order to perform an inspection of the steam generators within six months of equivalent operation from May 11, 1980.

    Nuclear Regulatory Commission (NRC) approval shall be obtained before resuming power operation following this inspection.

    Equivalent operation is defined as operation with the reactor 0

    coolant at or above 350 F.

    (2)

    Reactor coolant leakage from the reactor coolant system (RCS) to the secondary system (SS) through the steam generator tuQes shall be limited to 0.3 gpm per steam generator, as described in the NRG Safety Evaluation of May 6, 1977.

    With any steam generator tube leakage greater than this limit the reactor shall be brought to the cold* shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

    NRC approval shall be obtained before resuming reactor. operation.

    (3)

    Reactor operation shall be terminated if RCS to SS leakage which is attributable to two or more steam.generator tubes occurs during a 20 day period.

    NRG approval shall be obtained before resuming

    ~eactor operation, (4)

    The concentration of radioiodine in the reactor coolant shall be limited to 1 µCi/gram during normal operatidn and to 10 µCi/gram during transients as defined in Appendix A-1 to the.Technical Specifications of the license.

    Appendix A-1 was issued with the May 6, 1977 Order and shall remain in effect for six equivalent months from May 11, 1980.

    The Nuclear Regulatory Commission issued, on August 1, 1980, Amendment No. 59 to the Operating License for Surry Power Station Unit No. 2, which was designated as Technical Specification Change No. 66.

    The changes are the result of modifications to the Containment Spray System implemented dur-ing the Steam Generator Replacement Outage.

    Of significance are the follow-ing changes:

    (1)

    A revised figure which relates containment pressure, containment pressure~ containment temperature, and service water temperature.

    (2)

    A revised requirement for a Unit 2 Refueling Water Storage Tank level of 387:100 gallons.

    (3)

    A requirement for specific limits for Safety Injection System leakage outside containment.

    Design Changes A FACILITY CHANGES REOUIRIHG W

    NRC APPROVAL AUGUST, 1980 None during this reporting period.

    FACILITY CHAl~GES TH.AT DID NOT REQUIRE NRC APPROVAL DC/77-35 The Primary Grade Water Tank Overflow modification was initiated to prevent overflowing the tanks and allowing the water which coul4 contain radioactivity, to enter the storm drain system.

    'ifnile there are no safety implications surrounding these tanks, this change will prevent further uncontrolled or unmonitored releases. from this source.

    DC/80-30 This Expansion Loop Installation in Containment Spray Line 4'1-CS-105-152 was made to rectify an overstressed condition discovered during analysis of the piping.

    (*

    No changes to either Technical.specifications or the FSAR were involved with this modification.

    DC/80-550 The Relocation of the Safety Injection Sample Lines discharg;ing from 11B 11 accumulator was. implemented to elminate interference with a neY pipe support installed in the system.

    There are no safety implications involved with this modification.

    DC/80-71 Relocation of Drain Line 3/4"-CV-121-152 on the containment vacuum pUiilp suction line was made to avoid interference with a new support brace which was installed.

    This design change has-no safety implications and creates no need to* c~ange the FSAR or Technical Specifications.

    UNIT 1,2 2

    2 2

    ST-81 ESTS AND EXPERIHENTS REQUIRING NRC APPROVAL AUGUST, 1980 None during this reporting period.

    TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL This special test on the Pressurizer Relief Tank was completed on Unit 2 on 8-7-80.

    This test verified that the pressurizer relief tank, the associated valves, and instrumentation functioned in conformance with prescribed requirements.

    ST-86 Reactor Coolant Pump Vibration Test on Unit No. 2 was completed on 8-14-80.

    This procedure *provides the base line vibration measurements for Reactor Coolant Pumps A, B, and C.

    ST-87 RTD Bypass Flow Verification on Unit No. 2 was completed on 8-15-80.

    This test verifies the flow rate in each bypass loop to ensure that the actual reactor coolant transport time i~ acceptable and to verify the low flow alarm and reset the setpoints for total bypass loop flow in each reactor coolant loop.

    ST-88 Reactor Coolant System Cooldown on Unit No. 2 was completed on 8-7-80.

    This special test performs all required functional checks on components and instrumentation utilized during a plant shutdown.

    ST-96 Atmospheric Steam Dump Valves (MS-PORV) test for Unit 2 was completed-on 8-1-80.

    This procedure verifies the mar:iual and automatic response of mainsteam PORVv s RV-MS-201A, B, and C at three selected setpoints.

    ST-100 Cross Train Safety Injection on CLS HI Initiation for Unit 2 ~yas completed on 8-6-80.

    This special test was to verify the CLS HI logic for Cross Train Safety Injection Initiation.

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    -::;:.....-----;;,::__-~ -- * ~R CHANGES, TESTS AND EXPERIHE~

    AUGUST, 1980 None during this reporting period.

    -:.-~---*

        • ----------...;;- ------~--..
    • SURRY POWER STATION CHEi1lSTRY REPORT

    -=A=U::....:G=-=U=S..::,T __, 19 _§Q_

    T. s. 6

    • 6. 3.* d PRIK.\\RY COOLANT UNIT NO. 1 UNIT NO.

    ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM Gross Radioact., l-!Ci/ml 1.18

    1. 71E-3 4.42E-l
    1. 50E-1 6.64E-4
    • Suspended Solids, ppm 2.9 0.0

    .29 0.2 0.1 Gross Tritium, l-!Ci/ml l.66E-2 7.81E-3

    1. 25E-2 l.41E-2 9.00E-3 Iodine-131, l-!Ci/ml 3.73E-l 2.88E-3 3.43E-2 7.37E-5 4.-15E-5 I-131/1-133

    .2801

    .1763

    .2344 Hydrogen,* cc/kg 44.6 2.2 20.34*

    63.l 13.0 Lithium, ppm I.28

    <.l

    .21

    .28

    <-1 Boron-10, ppm +

    I 519.4

    .196 157.58

    /458.836

    /197. 568 Oxygen-16, ppm

    ~

    3.6

    .ODO 0.31

    .000

    .000 Chloride, ppm

    .12

    <.OS

    <.05

    .05

    <. 05 pH @ 25°C 8.99 5.35 7.26 6.08

    4. 76

    + Boron-10 Total Boron x 0.196 NON-RADiOACTIVE CHEMICAL RELEASES, POUNDS r r Phosphate Sulfate 50% NaOH

    • #2RX not @ Steady State Power 0

    278 350 r-. s. 4.13. A. *. _g Bar.on 1195. 7 Chromate.

    .82

    ~~~--~~~~~

    Chlorine ~~~~~~~~~

    2 AVERAGE 4.46E-2

    .1 l.197E-2 5.88E-5 33.4..

    "<-1

    /263.0298.

    ~'*.

    .000

    <.05 5.26

    1. 2RX trips on following dates:

    8-16 @ 0040; 8-15 @ 18eO; 8~19 @ 0820; 8-19 @ 2371; 8-22

    @ 1736 (Safety Injection); 8-24@ 1532; 8-26@ 2210 (Safety Injection); 8-27@ 1955; and 8-30 @ '0225, v'Borons for 8 8-16 Phvsics Testing OD #?RX not ref] ected in above a*.rerage fo:r fi'2 (1)

    These levels of chemicals should present no major adverse environmental impact.

    t.*

    ESCRIPTION OF ALL INSTANCES Rl1AL DISCHARGE LH1ITS WERE AUGUST, 1980 Due to impairment of the circulating water system on the following days the thermal discharge limits were exceeded as noted.

    August 24, 1980 August 26, 1980 Exceeded 15°F lT across station Exceeded 15°F lT across station

    • Indicates dates where station!:::. T was less than 15. 0°F across the station.

    for sometime during the day.

    The !::il excursions were allowable under Technical Specifications 4.14.B.2.

    There were no reported instances of significant adverse environmental impact.

    On August 22, 2~, 26, 27 and 30, 1980, the temperature change at the station discharge. exceeded 3 F per hour due to Unit 2 reactor trips.

    These events were allowable in accordance with Technical Specification 4.14 *

    • FUEL H..AlIDLIHG UNIT 1 AUGUST, 1980 None during this reporting period.

    .. FUEL HAlIDLIHG UNIT 2 AUGUST, 1980 None during this reporting period *

    . 4 1

    P.DURE REVISIONS TlLl\\T CHANGED Tl OPERATING HODE DESCRIBED IN THE FSfU!,

    AUGUST, 1980 None during this reporting period.

    I ___ _ E NOT PTION OF PERIODIC TESTS WHICH

    .COMPLETED WITHIN THE TIME LIMI SPECIFIED IN TECHNICAL SPECIFICATIONS AUGUST, 1980 None during this reporting period.

    1-

    \\

    • INSERVICE INSPECTIOt~

    e AUGUST, 1980 UNIT 1 Unit No. 1 was shutdown due to leaking tubes in "C" steam generator.

    Four (4) tubes were identified as being leakers.

    An inspection program using eddy cur-rent was conducted on the leaking tubes and the surrounding adjacent tubes.

    Nine (9) tubes were plugged for O.D. wastage in excess of ~40%. One (1) tube was plugged for denting and twenty five (25) tubes were plugged as a preventa-tive measure and one(l) tube was plugged by mistake.

    The eddy current inspection was conducted in accordance with VEPCO NDT Procedure 14.1 at 400 KHZ using a.720,.700,.650, and.610 probes.

    Visual inspection of the hangar modifications is in progress.

    UNIT 2 The VEPCO NDE group portion of the Inservice Inspection Program per Technical Specifications is complete in conjunction with the Westinghouse portion of this inservice.inspection of Unit #2, Visual inspection of the hangar modifications is still in progress.

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    I eoRTABLE OCCURRENCES PERTAININ ANY OUTAGE OR POWER REDUCTI AUGUST, 1980 None during this reporting period.

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    '/2 2*1 39 11y*1 35 () I '/\\HI! e ' I -1'-- w I I I HEALTH PHYSICS AUGUST, 1980 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 10CFR20. No. OP-lE OPL l OPl. 2 OP22.3 OP22.3 OP22.3 OP22.5 OP22.S OP22.S OP22.S PT38.5 HOP28.10 MOP28. ll MOP28.12 PROCEDU SAFETY EVIATIONS REVIEWED BY STATION OPERATING COMMITTEE AFTER TIME SPECIFIED IN TECHNICAL SPECIFICATIONS AUGUST, 1980 Unit Title 2 Containment Integrity Checklist 2 Unit Startup Operation_ (Solid Plant Operation) 2 Unit Startup Operation (Solid Plant Operation) 1 Waste Disposal Evaporator Operation 1 Waste Disposal Evap~rator Operation 1 1 1 1 1 2 1 1 1 . Waste Disposal Evaporator Operation Contaminated Drains System Contaminated Drains System Contaminated Drains System Contaminated Drains System Secondary Coolant Beta-Gamma and Tritium Activity 11A" Steam Generator 900 PSI Leak Test With Primary Plant Filled* "B" Steam Generator 900 PSI Leak Test With Primary Plant Filled "C" Steam Generator 900 PSI Leak Test With Primary Plant Filled Date Deviated 12-3-76 6-26-80 8-06-80 2-02-80 2-04-80 (Deviated 3 times this date) 2-05-80 (Deviated 2 times this date) 2-02-80 (Deviated 3 times this date) 2-03-80 (Deviated 3 times this date) 2-04-86 (Deviated 3 times this date) 2-05-80 (Deviated 4 times this date) 1-13-77 1-13-77 1-13-77 Date SNSOC Reviewed 8-7-80 8-7-80 8-21-80 8-28-80 8-28-80 s..:23-so 8-28-80 8-28-80 8-28-80
    • s-28-80 8-20-80 8-14-80 8-14-80 8-14-:-80
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