ML18139A497
| 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) | |
Text
..,
VIRGINIA ELECTRIC AND PO'W"'ER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 80.:..08.
AUGUST, . 1980 APPROVED:
MANAGER
.. ~_....._,_.
-i-CONTENTS Section Page Operating Data Report - Unit If 1 1 Operating Data Report - Unit ff2 2 Unit Shutdowns and Power Reductions - Unit ff I 3 Unit Shutdowns and Power Reductions - Unit 112 4 Load Reductions Due to Environmental Restrictions Unit /fl 7 Load Reductions Due to Environmental Restrictions - Unit #2 8 Average Daily Unit Power Level - Unit #1 9 Average Daily Unit Power Level - Unit #2 10 Summary. of Operating Experience 11 Amendments to Fac:ility License* or Tecfrnical *-Specifications 14 Facility Chaii.ges Requiring. :NRC Approval . 15 Facility Changes That Did Not Require NRC Approval 15 Tests and Experiments Requiring NRC Approval 16 Tests and Exp~riments That Did Not Require NRC Approval 16 Other .Changes, Tests and Experiments 17 Chemistry Report rs*
Description of All Instances Where Thermal Discharge Limits Were 19 Exceeded Fuel Handling 20 Procedure Revisions That Changed the Operating Mode Described In The FSAR 22 Description of Period Tests 'Which Were Not Completed Within The Time 23 Limits Specified In Technical Specifications Inservice Inspection 24 Reportable Occurrences Pertaining to Any Outage or Power Reductions 27 Maintenance of Safety Related Systems During Outage or Reduced Power 28 Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 31 Periods - Unit #2 - Mechanical Maintenance
OPERATING DA'l'A REPOKI' DOCKET NO.
DATE 50-280 10 SEP 80 COMPLETED BY SUE' D. DUNN TELEPHONE 804-357-3184 OPEA'ATING STATUS
- 1. UNIT NAME SURRY UNIT 1
- 2. REPO[{I'ING PERIOD 80180 TO 83180
- 3. LICENSED THER!*fAL POWER (M..IT) 2441 ,-------------------~---,
- 4. NAMEPLATE RATING (GROSS f.Iw'E) 847.5 INOTES I
- 5. DESIGN ELECTRICAL RATING (NET MwE) 822 I I
.6. NAXIMUM DEPENDABLE CAPACITY (GROSS KwE) 740
- 7. !>!AXIMUN DEPENDABLE CAPACITY (NET MWE) 704
- 8. IP CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE LAST REPOP.I. GIVE REASONS
- 9. POWER IEVEL TO '>>'HICH RESTRICTED. IF ANY NIA (NET Nw'E) .
- 10. REASONS FOR RESl'RICTIONS. IF ANY NIA THIS MONTH YR~TO-DATE CUMULATIVE
- 11. HOURS IN REPOI?IING PERIOD 744.0 . 5855. 0 67439.0 12 ~ NUMBER OF HOURS REACTOR WAS CP.ITICAL 509.0 3462.7 ... 42214.3.
. 13. REACTOR RESERVE SHUTDOWN HOURS o.o 182.6 3731. 5
- 14. HOURS GENEP.ATOR ON-LINE 503.0 3440.1 41345.1
- 15. UNIT RESERVE SHUTDOWN HOURS . a.a 183.6 3736 .2
- 15. GROSS THERMAL ENERGY GENERATED (!>fwfJ) 1045464.0 8055870.0 95770742.0
- 17. GROSS ELEC'.i'RICAL ENERGY GENERATED (/6./H) 301490.0 24-482.35. 0 31128733. 0
- 18. NET ELECTRICAL ENERGY GENERATED (/.fi.IH) 281914.o 2312196.6 2953909s.o*
- 19. UNIT SERVICE FACTOR 67.6 o/o . 58. 8 .o lo 61.3 olo
- 20. UNIT AVAILABILITY FACTOR 67.6 o/o 61.9 olo 66.8 olo
- 21. UNIT CAPACITY FACTOR (USING /IJJC NET) 53.8 olo 56.1 010 62.2 olo
- 22. UNIT CAPACITY FACTOR (USING DER NET) 46.1 olo 48.0 olo 53.3 olo
- 23. UNIT FORCED OUTAGE RATE 32.4 olo 41.2 010 26.5 olo
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS 9/15180 - SIG REPLACEMENT OUTAGE (TYPE .DATE. AND DURATION OF EACH) REFUELING - 1 YEAR
- 25. IF SHUT DO'riN AT END OF RE'POF{I' PEPJOD.
ESTIMATE DATE OF STARTUP
- 25. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
- ---------------*------------~---- ---*. ... ****-*---------**--*-*-*----~==~
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 SURRY U!II'.l' 2
- 2. 1-.i:.i:!CifSii,G PE11IC£ 50180 'IC 83180
.~. LICE;/.'SE'E TiiEiJ.;/,L PO't..'E,H Ci*;h'T) 2441 ,---~~-----------~----,
- 4. i*k',EPLA'iE M'IING (GROSS ,\!J.r'E) 847.5 I NOTES I
- 5. DESIGN ELE'C'l'lr.'ICAL F..A'II!iG (NET N11E) 822 I I
- 6. f,'A'J.IMUN DEPEi,DABIE CAPACITY (GiiOSS t-f',./£) 811 I I
- 7. f*,AXIi-:U;.; lJE?EHDAELE CAPACITY \NJ:,;T MhB) 775 1------------------------1
~I'lE'/.,'S 3 '1.HROUCH 7) SI!iCE LAST lr.EPGiS. GIVE f.EASONS S. p(;,.,Ef.. LEVEL TO hHICH HESTJ-.ICTED. IE' ANY NIA
- i. ii l::T p.,, E )
- 10. f:EAS01lS EGR RESTRICTIONS. IF Alff NIA THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOljRS IA; f.EPOh":f.'ING PERIOD 744.0 5855.0 64319.0
- 12. l;'[i!YEDH OF HOURS HEAC'l'Oli ,,.,:As CRITICAL 366.1 366 .1 . 34866.0
- 13. F:E.AC'IOR HESERVE SHUTDCkfl' HOUFr.S 0.0 o.o 0.0
- 14. HOi.Jf..S GE'fiElilSOR O!r-LINE 232.2 232.2 34228.4.
- 15. lJi.I'l. h.L'S£2V E SHUTBQJ../N
- h'GURS o.o 0 .o. .. o.o
- 15. CF:OSS THEEJXAL ENE'RGY
- GE/,'EP..ATED (Nw'H) 300919.0 300919.0 7.9495002.0
. 1 7 *. c.;oss ELEC'I.F:IC AL EiiEHCi: GE!;ERATE'D .(MY.'H) 86180.0 86180.G 25955024~0
- 18. j;['J: ELEC'iF.ICAL ENERGY GENERATED lMw'H) 77485.0 77485.0 24614090.0
- 19. UhIT SEii'VICE FACTOR 31.2 ojo 4.0 010 53.2 010
- 20. Ui.IT AVAILAEILI':ZY FACTOR 31. 2 olo 4.0 olo 53.2 olo
- 21. UhIT CA?ACITJ.' FACTOR (USING. /.JDC NET) 13.4 olo 1. 7 olo 49.4 o/o
- 22. l.Jf.IT CAPACI2.'Y FAC'l'OR (USING DER NET) 12.7 o/o 1.6 010 46.6 o/o 2 3. Ui.'IT FORCED OUT AGE RATE 25.6 olo 25.6 a/o 21.1 olo
- 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 ATUS 1 FORECAST ACHIEVED
( PF.IOH 'IC COlr!f/EhCI AL OFERATION)
Ii.'I'IIAL CRI'IICALITY li~ITIAL ELECTRICI'l'Y CC!*i*ERCIAL GPEFr.A'IIOJI
. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50..:.2so UNIT NAME SURRY UNIT 1 DATE September 8, !1980 COMPLETEll BY SUE p DUNN I REPORT MONTH AUGUST, 1980 TELEPHONE (804)-357-3184
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3 4 F: Forced Reason: Method: Exhibit G *Instructions
. S: Scheduled A-Equipment failure (Explain)* I-Manual for Preparation of Dal a D-Maintenance or Test 2-Manual Scram. Erilry Sheets for Licensee
{'-Refueling, * . J-Automalic Scra1n. Event Report (LERl file (NUREG*
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G-OperaUon:.11 Error (Explain) Exhibit I *Same Source (1)/77) l 1-0!her ~Explain)
50-281 DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS Surry Unit 2 UNIT NAME DATE ~ember 8,. 1980 COMPLETED HY Sue D. Dunn REPORT MONTH AUGUST* 1980 TELEPHONE (80lt) 357-3184
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Cl 80-8 8-1-80 s 431. 7 D 1 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.
80-9 8-19-80 F 15.9 A 3 Reactor trip caused by "B" S/G High .t'-
Level as a result of "B" main feed 1 regulating valve failing open.
The problem was found to be a faulty controller. The controller was re-placed.
80-10 8-19-80 F 1.9 G 3 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.
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~ 3 4 F: Forced *Reason: Method: Exhibit G - Instruct ions S: Scheduled A-Equipment failure (Explain) I-Manual for Preparation of D:ita B-Malntenance of Test 2-Manual Scram. Entry Sheets for Licensee C'-Rerucling 3-Aulumalic Scram. .Event Report (LER) File (NU REG*
D-Rcgu!al<.'iry Rest rictiun 4-0ther (Explain) 0161 l
£-Operator Training & License Examination F-Administralivc 5 G-Opcralional Error (Explain) Exhibit I *Same Snun.:c '.
(IJ/77) ll*Olhcr {Explain)
DOCKET NO. 50-281 UNIT SHUTDOWNS AND POWER REDUCTIONS SURRY UNIT 2 UNIT NAME DATE September 8, *1980 COMPLETED DY SUE D. DUNN REPORT MONTll AUGUST, 1980 (804)-357-3184 TELEPHONE
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/JP signal caused by steam from lift-ing relief valve impinging on steam header pressure transmitter. The rea- I son for the RV lifting was tl et ermi netl V1 I
to be stuck NRV's in steam drain line.
'fhe NRU' s were renaired, 80-12 8-24-80 i F 13.7 H 3 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.
80-13 8-26-80 F 12.1 ll 3 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.
3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled. A-Equipmenl Failure (Explain) I-Manual for Preparation or Data B-Mnintennnce or Test 2-Manual Scrnm. E1t1ry Sheets for Licensee C'-!Rcfueling , 3-Aulomatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-0ther (Explain) 0161)
E-Operalor Training & License Examination F-Adminisl ml ive 5 G-Opcralional Error (Explain) Exhib ii I
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l'l/77) ! I-Other (Explain)
DOCKET NO. 50-281 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME SURRY IJNI T 2 DATE -S..e.p.temher 8 ,, 1980 COMPLETED BY Sl)E D. DUNN REPORT MONTH AUGUST, 1980 TELEPHONE (804)-357-3184
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Electricians working in instrument
- I l 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 I working in instrument racks. °'I 80-15 8-30-80 F 3.6 A 3 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!
I. The instrument technicians were in-structed to insure the* proper leads are* used in the future.
3 4 F: Forced Reason: *Method: Exhibil G - lnsl rue! iuns S: Scheduled A-Equipment Failure (Explain) I-Manual for Prr.parnliun of Dala 13-Malntenance of Test
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E-Opcralor Training & License Examination F-Administrativc G-Opcralional Error (Explain) Exhibil I
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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.l MONTH: AUGUST, 1980 LOAD, MW REDUCTIONS, MW REASON DATE TIHE HOURS Nore during this repo ting per ad.
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MONTHLY TOTAL
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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*
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 t *.> !
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.
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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 L
' 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 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 0
at 0313. At 0635 the reactor coolant system (RCS) was at <350 F and was at cold shutdown (CSD) at 1335.
AUGUST 10 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.
AUGUST 11 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.
AUGUST 12 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.
AUGUST 28 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.
AUGUST 29 After repairs completed on "B" MFP and pump returned to service at 0515 commenced power increase. Power reached" 89% at 1500.
AUGUST 31 This reporting period ends with the unit at 83% in coastdown phase at end-of-life (EOL) prior to refueling.
UNIT 2 AUGUST 1 This reporting period begins with the unit at cold shutdown with main-tenance, piping restraint modifications and design changes continuing.
AUGUST 4 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 AUGUST 6 Reactor coolant system at >350 F at 0700.
0 AUGUST 11 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.
AUGUST 12 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 11 C" 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.
Page 3
SUMMARY
OF OPERATING AUGUST, 1980 UNIT 2 The reactor was taken critical at 0310 and the generator placed AUGUST 28 on-the-line at 0510.
At 2240 performed 50% load rejection test from 64% power. At 2307 AUGUST 29 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 AUGUST 30 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 AUGUST 31 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.
A FACILITY CHANGES REOUIRIHG W NRC APPROVAL AUGUST, 1980 None during this reporting period.
FACILITY CHAl~GES TH.AT DID NOT REQUIRE NRC APPROVAL Design Changes UNIT DC/77-35 The Primary Grade Water Tank Overflow modification was initiated 1,2 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- 2 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 2 from 11 B11 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 2 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.
ESTS AND EXPERIHENTS REQUIRING NRC APPROVAL AUGUST, 1980 None during this reporting period.
TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL ST-81 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.
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SURRY POWER STATION CHEi1lSTRY REPORT
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PRIK.\RY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., l-!Ci/ml 1.18 1. 71E-3 4.42E-l 1. 50E-1 6.64E-4 4.46E-2
- Suspended Solids, ppm 2.9 0.0 .29 0.2 0.1 .1 Gross Tritium, l-!Ci/ml l.66E-2 7.81E-3 1. 25E-2 l.41E-2 9.00E-3 l.197E-2 Iodine-131, l-!Ci/ml 3.73E-l 2.88E-3 3.43E-2 7 .37E-5 4.-15E-5 5.88E-5 I-131/1-133 .2801 .1763 .2344 * *
- Hydrogen,* cc/kg 44.6 2.2 20.34* 63.l 13.0 33.4 ..
Lithium, ppm I .28 <.l .21 .28 :<-1 "<-1 Boron-10, ppm +
I 519.4 .196 157.58 /458.836 /197. 568 /263.0298. .~'*.
Oxygen-16, ppm ~
3.6 .ODO 0.31 .000 .000 .000 Chloride, ppm .12 <.OS <.05 .05 <. 05 < .05 pH @ 25°C 8.99 5.35 7.26 6.08 4. 76 5.26
+ Boron-10 Total Boron x 0.196 r r NON-RADiOACTIVE CHEMICAL RELEASES, POUNDS r-. s . 4 .13 . A. *. _g Phosphate 0 Bar.on 1195. 7 Sulfate 278 Chromate. .82
~~~--~~~~~
50% NaOH 350 Chlorine ~~~~~~~~~
- #2RX not @ Steady State Power
- 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.
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
- Exceeded 15°F lT across station August 26, 1980
- 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.
., 1
.. FUEL HAlIDLIHG UNIT 2 AUGUST, 1980 None during this reporting period *
. 4 -
P.DURE REVISIONS TlLl\T CHANGED Tl OPERATING HODE DESCRIBED IN THE FSfU!,
AUGUST, 1980 None during this reporting period.
PTION OF PERIODIC TESTS WHICH E NOT
.COMPLETED WITHIN THE TIME LIMI SPECIFIED IN TECHNICAL SPECIFICATIONS AUGUST, 1980 None during this reporting period.
I ___ _
- 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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Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 Mechanical Maintenance
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("" OllU05 l 130 520 OB/20100 /Ill Pll'INC 3-Dc-111 DIC 79-S32C INS2'/ILL SUl'PO/(J' NOV. COML'LF:'l'EV 1 00/20180 cs l'Il'If/C 8-CS-3 11 DIC '/9-S32C INS1'/lf,L SUl'l'0/1'1' MOU. COMl'LF:'l'W 1 OOBO!Jll100 520 08/20100 cs I'll'ING 3/IJ-SJ-160 DIC 19-S32C INS1'/l[,L SU/'1'0111' MOD. CONPlb'Tl:.'IJ 1 000001501 *100
"'" 00/20180 cw FJ[,1'f.R 1-(,'h'-Fl-18 li'li'l'LllCE l/f,'l'A f'JL2'f,'/1 CllllNGBD f'1 L2'b'U 1 OOB21J 10'10 1 00/20180 B/i' VllLVt: 1-8/f-106A E'l/INGE WAK ON 1-Bft'-.10GA VOl/J CONl'U:rnv ON llNO'l'llb'lr' MR 1 9011072330 0 00/28180 SI l'Il'INC 1-SI-221 2'//fiWADS LF:llKING A1' unow VOilJ £XJNF: UNVl>'ll llNO'l'llf.11 MT.' 1 905221 1!00 0
(. 9052211101 0 00/20180 SI VALVE 1-SI-21 VALVE f.X'l'lr'fo.'Hf."f,Y Vlfi.'lC/1£,1' TO Ol'l':/1'117'f; VOIV [)()Nii IJNVf:,'U lllVO'l'l/l*."li' Mii 1 00/20180 CH f!L'ff:R 1-CU-E'l-1 DRAIN LINE PLUGGED VOIIJ C0Hl'f,fi'7'@ UNDb'll P/i'EVIOUS MU 1 907051605 0
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- Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT 112 Mechanical Maintenance
- - - DF:l"l'=MECll 2 Sb"l' 80
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OU/01/80 /'Ii SNIJIJ/lr.'U 2-Sl-llSS-198 lif,'f.f(}VI\ SNUll/lf.'lo' FIJ/ll'1'10Nl1L, 1't.'ST M.NOVL\' 7'/*:sr INS1'/ll,l 2 001111n11J J:J?
00/01/00 /'Ii' SfiU/J/!/Jh 2-Sl-llSS-20 111,-MOV f; SNIJUIU.:11' F/Jl~C1' lONAl 1'1:.~'iT f{f\MUVf,' Tl\S1'MJ ll\'S7'11ll..f.'V 2 001111v1111 1100 00/01/80 l'll SNIJ/J/Jt:li 2-Sl -/ISS-'nB lo'f.'f.'OVTI° SNIJ/Jli/~*11 f/IJNC7'10f/Af, TllS7' li'l;'MUVE: 7'{;',)1' JNS'/'11{,f, . 2 UU'/1112?.116 1100 011/01/00 l'li' SNUll/ll\H 2-ft'll-llSS-368 l1'/o.'INS1'ADl SNIJIJ/lf;fl n;ww+m:INS1'11llED SNIJ/llW/1' 2 007150000 3~l2 00/01/00 Pf,' S/IU/3/Jli/1 2-Ml-/ISS-36A Rl\l"NS1'11lf, SNUB/If,'/,' 7'b'S1'6'D~/i'l"'INS1'Alf.f.'IJ SNUIJll{;'f{ 2 007150001 392 00/01/80 l'li' SNU/31.ll-:R 2-lo'C-llSS-102 /if.'NOVF. SNU/i/11\'U fUNC7'IONAl T/151' 1'b'S1'T:;D1 lili'J NS1'Al,f, 2 0011sn2r. 'J'/'/
00/01/00 ,c;w mv 110~* -si. -20*1v R/'.'NOVI\ F.Xl'A/ISIUI~ ,/OJ N7' INS1'11UJW f.'XP JOIN7' 2 007.lRI t!;l nu 00/01/110 :.:w NOV MOV-Sh' -2 0 SV r.m.:ovr:; fl°Xl'. JOl NT .l l'IS1'11l,l./i'/! f.'Xl' JUI N7' 2 0071011!>1 no 00/01/00 /'Ii' SNU/i/.ll','f1' 2-Nl/-llSS-20 lo'f:liVS1'Al,l SNIJIJ/lf"'U 7'1*.'S1't:D* ma NS1'All.f:f) SNUIWL*.'11 2 00'//lOlllU 7(,<J 00/01/00 I'll .'i/l'l//i/l/i/I 2-SI-ll.'JS-101 HF.NOV/': SNIJ/Jnl\11 Tf:S7' RF.IJIJllD '/'f.'S'.l'F./J AN/J Uf.'JNS1'Af,lfllJ SNIJ/Jlil'.'/1' 2 007210UOU 2h9 00/01/BO NS V/ll.Vf\ tV-NS-201C h'l [,[, N01' OL'f.'11'!17'/'.' Jo'/*,'l'LACt: VAlVl1' 2 00'/23151111 I ~!2 00/01/BO cs VAf,Vf.' 2-cs-~12 f,Al' V11[.Vf.' S/:,'/17' /if.'l'AlM.'/J T.RAKING VC.V 2 ()0'/3012/5 11<)
00/01/80 cs VM.V/i.' 2-cs-*19 i11P JN v111,v1:: l<f.'l'Al/1B/J U'Af(I NG Vf,V 2 00'/3012'../ l1'J OA/01/80 OU/02/80 TJS hC 01'/IW V/11,VI;' 2-/o'c-1115 CO/o'liECT VANIOIJS Pli'O/Jf,f;M.'i VlllVE Al'J-'/',"l1US 7'0 lJI*: SWCK ll/Wl1lli'f,'IJ l'ROBUIMS W17'/I llA1'Cll v111,v1;* cu:1111 2
2 0073llJ0.10 0000121115 II N w) 00/02/00 CV v111.vr: 2-cv-11 VAT.VI': 11l'l'f..'11/o~'i 1'0 /Jf. S1'/JC K S/1117' V/ll,Vf,' Cl,f,'11N 2 0000171"6 u I 00/03/00 F*~ l'lPI NG 1/-75 <lT.'OUT Nb't:IJS 2'0 fJb' RF.'L'l.ACb'IJ /i'f,'GliOIJ'L'lW l'll17't: 2 00'/18111211 11'.l OR/03/80 Cf{ VALVI*: llCV-2310 VAlVL'.' DOC.'SN'7' S1'/o'OK6' 11/IJIJSTW l'ACKING 2 00'/311112 (;3 00/03/80 BS 01'/W'/1' INS1'Af,l T\QUll'+b'SCAl-'f;; llA7'Cll INSTADlfi"D 1111'1'Cl/6S 2 0011011010 51 OB/O'l/80 SI V11£,Vf;' 2-Sl-345 VA[,VE U'l1KS '.l'/1/1'1/ 1 NS'l'Af,lf.'V l'Il'l'.'CAl' 2 005221933 71111 08/05/80 SW l'NI' M1'11 2-,5"'-l'-5A l'l/Mf'S SI E:zr.:v FU/il'.'IJ PU/oil' CU'l1Nb'D CASING 2 ounso115u 17li 00/05/00 SW IWL' m*u 2-Sk'-l'-'58 l'l/Ml'S Sl/lf,f..'/J f/1'/i'li'O l'/JMl' CU::11NEV CASINGS 2 00'/250'159 17G 00/05/UO SW l'Ml' M1'H 2-Sff-l'-50 /'I/MI'S Sl f,"l.fl°/) f'/11'.'W l'UMl' CLF:l1Nf:,D CASJN(,' 2 OU'/2505lJl I 7(i OB/06/80 Sl VALVE' 1'V-SI-201A Vllf,Vf.' I/AS /JODY 'l'U IJONN/:;'I' ll\11K /o'l'.Pl11/1'/W lfl'AK 2 OOOOlllJGOO !i 1 00/06/80 S*{ JNS1'/o' Uf.'MOVf: Gl,ASS ANV fo'W117' INS1'Al/,W FL0/11' GlASS 2 000051700 :./'I OU/Ofi/80 00/0'//00 08/11/llll MS fW
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08/ll/BO I'll SNIJIJIJC'R li'/l/JllI W W11'// f.'I' Ml11'f,'/ll 111, fll>'NOV/','I! .I NS'/'11!,[,f,'/J 2 9Ul230!JOU 1:7917 00/13/00 cs V11{,V/I ?-Cs-119 !i0/J1' TO IJUNNl::T WAK loW/'111/o'IW U'Af( 2 0011101553 11 00/13/80 Sl TANK 2-Sl-l'-1/J SM007'/I INSID8 OF Sf,'Al IU..'A/J 7'K SM001'/lli'D 111*.'11/J AND ASSt*:~mT.RI! 2 OOUI 3ll!OlJ ')
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00/16/80 cc l'IJML' 2-CC-l'-W SC:Al lf,'AK VOID N/1' /.l/~l NG lt'0/1Kb'V 2 0001110100 (I 011/17/00 /JS O~'l/e'li fll-:OllJ!f.'f1' ANO m:l'f,ACF.' Sb'/rf,S l"Oll f.'Q /IA'l' m:l'LACt:o S/\Al 2 007090310 597 00/17/80 MS VM.V II 2-MS-169 Al!J. 1-'ACKING S1'0L'L'f:/J lf,'AKS 2 000151201 .112 00/20/llO BS 01'//llN VAi.VE.' I/AS U:AKl1GF. itlJJUS1'EV VAlV/;' 2 000101202 G 00/22/80 /JS 07'/IC.'H FAllllICA7'6'+1.VS1'AL£, l'll°h'SUNNF:I, /IA7'CI/ VOID WO/i'K /JNDl:.'U MU S 2007010007 . 2 0070101106 0 08/22/80 VG VALVL\' 2-DG-9 li'f.'PLl1CT\° 80NiV/;'7'+Sl'l NIJTJI Olo'l NGS VOID WO/o'f( UNDf"'11 NU S 20072911100 2 9111500[11 u 00/23/80 SJ VALVf.' 2-SI-11 /if1'l 1ACK Jil*:l'ACKt:Ll 2 OOB?JU90G l
Df.PT=NECll 2Sl'.1'B0* l:)(i/'M /'AL'f-.L UNI2'2- 9/02/00 (MllJN1'/i'NANC[': OF Sllf'fi'1'Y li'f:J,/11'W SYS1'1-.'NS VUHING OUT/IC:!> 011 mwuct:JJ l'OWF.:11 l'l:.'/ilODS) llF.7'Sf~HV/Yf SYS CON/' Mll/1KNO S/JMNll/i'Y WKl'f:."Nf u f.:Ji' 'l'OT/JIOi 'i M 00/2J/OO SI VA/,V/\' 2-SI-11 SllN/'Lf,' l.lN~: l'/,/J(;(,'f:/J vorn ltOllK UNVEIR NII s10011122001 2 911201115 30 OU/25/80 MS VllT.Vf*,' 2-MS-150 VllLVl:' LBllKS 1'/1110/JGll I* VOl D CONl'LF.1'/;;{) urm~;u 111'101'/lch' Mii 9022 2 9021'11 1110 u 00/2G/80 Ill CONl'//f*:ss 2-111-C-211 Rli'f10VE AN/) liMllI f.lJ COMI'/if,'SSO/I VOlU COMl'UJ:SSOR II/IS /il::MOVIW UND/ili I'll 2 0051BDO'/ u 00/2li/80 MS v11r.v1*: 2-NS-2lCi Hf.PAI h' OH H/*.'!'f.ACb' VOl/J VAl.Vb' CllNN01' Ur:; WCll1'1W 2 9121J3.ll 113 !>L 1 S l'IN JS f'Hf.'E 2 001l220U35 ? 11
" 08/27/80 08/27/80 IJS NS 01'1/l-,'/i V/1£,I'/~' 2-MS-15U VOO/I l'lN Wlf,f, NOT CON/': 0112' m:CON/JH'lON AND /l/'.S/';111' VLV hl':CONDI'l'ION VllLVE 2 90225002!1 l :wuo 00/28/80 IA l'll'ING 2-llCC-11-218 lINli U:AKING 111' JOIN2' SOLflf,'// VOJIJ f'OUND l'ACKINC rnAKillG '1'1Gl/1'b'N I:' 2 0060*1??37 u
- 00/28/80 00/29/80 liC RS E'll'ING 1NS111' 2-liC- -129 LT-US-25111 IJC 79-S32C 1NS1'11£,f, CONS1'li/IINT VF.CK l'l,/17'E lS LOOS!';
VOID h'OHkliD ON 9.10131022 VOID Sb'CUllF.D DINl' Rf;QUlRl:' NU 2
2 9101:11021 0032 111'11(;
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08/29/80 BS 01'1/f;/{ llE.MOV!:; COVf:R VOID COMl'lf.'1'l::D ON f>U/'.'VlOUS NII 2 OOCiOl 1'150 0 08/29/80 BS 01'/lt:/{ Pf.ANG{;' COVl':U VOIV N07' li'E'QUIREV 2 0070101107 0 08/29/80 /IS PIPING RS-111-153 VISllllL IN/JlCll2'ION OF Pil:'f: C/i'llCKS VOJ/J lJUPLlC/17'{!,' 2 902120901 u 73~011 l
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2 SEI' 00
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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.
PROCEDU EVIATIONS REVIEWED BY STATION SAFETY OPERATING COMMITTEE AFTER TIME SPECIFIED IN TECHNICAL SPECIFICATIONS AUGUST, 1980 Date Date SNSOC No. Unit Title Deviated Reviewed 2 Containment Integrity 12-3-76 8-7-80 OP-lE Checklist OPL l 2 Unit Startup Operation_ 6-26-80 8-7-80 (Solid Plant Operation)
OPl. 2 2 Unit Startup Operation 8-06-80 8-21-80 (Solid Plant Operation)
OP22.3 1 Waste Disposal 2-02-80 8-28-80 Evaporator Operation OP22.3 1 Waste Disposal 2-04-80 8-28-80 Evap~rator Operation (Deviated 3 times this date)
OP22.3 1 . Waste Disposal 2-05-80 s..:23-so Evaporator Operation (Deviated 2 times this date)
OP22.5 1 Contaminated Drains 2-02-80 8-28-80 System (Deviated 3 times this date)
OP22.S 1 Contaminated Drains 2-03-80 8-28-80 System (Deviated 3 times this date)
OP22.S 1 Contaminated Drains 2-04-86 8-28-80 System (Deviated 3 times this date)
OP22.S 1 Contaminated Drains 2-05-80 *s-28-80 System (Deviated 4 times this date)
PT38.5 2 Secondary Coolant 8-20-80 Beta-Gamma and Tritium Activity HOP28 .10 1 11 A" Steam Generator 1-13-77 8-14-80 900 PSI Leak Test With Primary Plant Filled*
MOP28. ll 1 "B" Steam Generator 1-13-77 8-14-80 900 PSI Leak Test With Primary Plant Filled MOP28.12 1 "C" Steam Generator 1-13-77 8-14-:-80 900 PSI Leak Test With Primary Plant Filled