ML18139A599
| ML18139A599 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/09/1980 |
| From: | COSTELLO O J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139A597 | List: |
| References | |
| NUDOCS 8010200396 | |
| Download: ML18139A599 (41) | |
Text
-2-*.)
I I e OFERA'i'ING DAT A REPORI (CORRECTED REPORT -April, 1980) DOCKET NO. 50-280 DA'l.'E 16 SEP 80 COl*!PLE'TED BL SUE D. Dfil..1N TELEPHONE 804-357-3184 GFCilJ..TING STATUS 1. UNIT NAME: 2.
PERIOD 3. LICE/;SED THERNAL PO;,..'£[;
u>;;..'T)
- 4. liA!*!EPLA'l'E' RATING (GROSS Ni-.'E) 5. Dl'SIGN E'LEC'Tfi.ICAL RA'J.'INC (NET M..rE) 6.
DEPENDABLE CAPACITY (GROSS Mtr'E) 7. MAXIMUM DEFENDABLE CAPACI'J.'i'
\NET f{;,.,.B)
- 8. IF CHANGES OCCIJR IN CAPACITY RATINGS
- 3 'l.'HROUGH
- 7) SINCE LAS'I' REPOR2'. GIVE REASONS SUHRI UNIT 1 40180 'l'O 43080 2441 8 4 7 . 5 I NOT ES I s22 I I s11 I I 775 1------------------------1 NIA 9. PO'i-.'E'R LEVEL TO WHICH RESTRICTED.
IF ANY NIA ( N E'l ) 10. F..EASO!lS FOR RESTRICTIONS.
IF ANY lilA 11. HOURS IA REPORIING PERIOD 12. NUMBER OF HOURS REACTOR k'AS CRITICAL 13. REACTOR RESERVE SHUTDOWN HOURS 14. HOURS GEliERATOR ON-LINE 15. 16. 17. 18. 19. 20. 21. 22. 23. lJNIT F.HSERl/E SHU'l'D0'¥.'N HOURS GROSS THERMAL ENER.GY GENERATED (fr!w'H) GROSS ELECTRICAL ENERGY GENERATED (t..r.IH)
NET ELEC7RICAL ENERGI GENERATED
(!'fw"H) UNIT SERVICE FACTOR Ulil'I AVAILAEIU'IY FAC70F: UHI'I CAPACITY E'ACTOE (USING NDC NET) UNIT CAPACITY FACTOR (USING DER NE:l') UNIT FORCED OUTAGE RATE 24. SHUTDQ';>.;NS SCHEDULED OVER liEXT 6 MONTHS (TYPE .DATE .AND DURATION OF EACH) 2 5. IE SHurr*
Ar.n El'Tl EEPOJ{I' PEPIOD. -EE'IINATE 1Jiu.E VF S'.L'Ar:'.rur
IAITIAL CHITICALITY IAITIAL ELECTRICITY COX!*:ERCIAL OPERATION 801()200 THIS f'rlONTH :tli-TO-DATE CUMULATIVE 719 .0 o.o 0.0 O.D 0.0 o.o 0.0 o.o o.o o.o 0.0 o.o 100 ... 0 o/o clo clo c/c clo 2903.0 1016.2 182.6 1010.4 64487.0 39767.8 3731. 5*. 38915.4 183.5 3736.2 2438340.0 90153212.0 785655.0 29466153.0 746810.0 27973709.0 34.8 clc 60.3 c/o 41.1 o/o 66.1 clc 33.2 °1° 56.0 c/o 31.3 °10 52.8 c/c 65.2 o/o 27.0 olo FORECAST ACHIEVED OPERATING DATA REPORI (CORRECTED REPORT -March, 1980) DOCKET NO. 50-280 DA'i'E 16 SEP 80 co:-:PLE'TED BY. Sli"E n. DUNN TELEPHONE 804-357-3184 OFEi-..A'l'ifr'C S:IISUS 1. UkI'I I.AVE 2. REPO,=:J:Ii,G PERIOD 3. LICENSI:.:u THERNAL (M1lT) 4. iiA!*.'EFLA7E RATING (GROSS l*Fv.'E) 5. DESIGN ELECTRICAL RATif'!G WET i'.fr.E) 5.
DEPENDABLE CAPACITY (GROSS MkE) 7. !*:AXlt-'U!*'
DEPENDABLE CAPACITY (NE2' Mw'E) .8. IF CHAl/Gl::S OCCUR IN CAPACITY RATIPiGS ( I'IE;;.:s 3 THROUGH 7) SINCE LAST RET:-0,={[.
GIVE P.EASONS SURRI UNIT 1 30180 TO 33180 2441 84 7. 5 I NO'IES I 822 I I s11 I I 775 1------------------------1 NIA 9. POwER LEVEL TO RES'IRICTED.
IF ANY NIA (NET !efr.E) 10. F..EASO!.'S E'OR RESTRICTIONS.
IF ANY NIA 11. HOURS IA FiEPOm'ING PEFi.IOD 12
- 0.F HOURS REACTOR WAS CP.ITICAL
- 13. REACTOR RESERVE HOURS 14. l!Ol"RS GEi*BF..ATOR ON-LINE 15. UNIT.
SHUTDOWN HOURS 16. GROSS 'i'HEiiXAL ENERGY GENERATED (NwH) 17. GROSS ELECTRICAL ENERGY GEHEEATED (Jef".,./H)
- 18.
ELECTRICAL ENERGY GENERA'IED (g,.,B) 19. UNIT SEH'ICE FACTOR 20. Ulk"I'.: !.VAILAEILITY FACTOR 21. UNI'I CJ...?ACI'iT FACTOR (USING t.:DC iiE1') 22. Ui.I'I CAPACITY FACTOE (USING DEF. NET) 23. UNIT FCRCED OUTAGE RATE 2 4. SHU'IDC.,., lvS SCHEDULED OT/ER !IEXT 6 MONTHS t'l'i"FE.&A'i'E .AND DURATION OF EACH) 25. IF SHUT D04 1 N AT END OF REPOKI' PERIOD. ESTI(,:A'i'E DI.TE OE' ST.4R'.T'UP
- 26. iJi,I'.:S If.* TES'I STATUS \l:*F.ICF.
ff; CO/lf'l.ERCIAL OPEF.A'IIOil)
I!d'IIAL CRITICALITY I!.I'IIAL ELE;C'.tRICI'i'Y COt-:1-:ERCI AL OPERA'l.'ION THIS MONTH YR-TO-DATE CUMULATIVE 744.0 * ... _ 0 .O* 0.0 0.0 0.0 0.0 o.o o.o 0.0 ojo 0.0 olo 0.0 o/o 0.0 o/o 100.0 o/o REFUELING
= 4/26/8C 2184.0 1016.2 182.6 1010.4 63768.0 39767. 8. 3731.5 38915.4 183.6 3736.2 2438340.0 90153212.0 785655.0 29466153.0
'746810.0 27973709.0 46.3 o/o 61.0 o/o 54.7 o/o 66.9 o/o 44.1 olo 56.6 olo 41.6 o/o 53.4 o/o 53.7 olo 26.0 o/o 9/80 -6 h'KS. FORECAST ACHIEVED
... . 'JPERATING DATA REP'JRT D'JCKET N'J. 50-281 DATE 09 'JCT 80 C'JNPLETED BY 'J.J. C'JSTELL'J TELEPH'JNE 804-357-3184
'JPEP.ATiliG STATUS 1. UNIT NANE 2. R'$P'JRTING PERI'JD 3. LICENSED THERMAL POWER (M.,lT) 4. NAMEPLATE RATING (GRQSS MWE) 5. DESIGN ELE'.:TRICAL RATING (NET MIE) 6. MAXIMUN. DEPENDABLE CAPACITY ( GR'JSS lfl'IE) ?
- MAXIM.UN DEPENDABLE CAPACITY (NET MIE) 8. IF CH.4NGES 'JCCUR IN CAPACITY RATINGS (ITEMS 3 THR'JUGH 7) SIN'.:E LAST REP'JRT. GIVE REAS'JNS SURRY UNIT 2 090180 T'J 093080 2441 84 7. 5 I NQTES I 822 I I 811 I I 7 7 5 I I NIA 9. P'JY.,'ER LEVEL T'J WHICH RESTRIC:TED.
IF ANY NI A (NET MwE) 10. REAS'JNS F'JR RESTRICTI'JNS.
IF ANY NIA 11. H'JURS IN REP'JRTING PERI:JD 12. NUMBER OF H 'JURS REACTOR WAS CRITIC: AL 13. REAC:T'JR RESERVE SHTJTDJ..!N H*'JURS 14. ffQURS GENEMT'JR
'JN-LINE 15. UNIT RESERVE SHUTD'JllN H'JURS 16. GR'JSS '?HERNAL ENERGY GENERATED (MwH) 1?. GR'JSS ELECTRICAL ENERGY GENERATED (Mtt'H) 18. NET ELECTRICAL ENERGY GENERATED
(/.fY!H) 19. UNIT SERVICE FACTOR 20. UNIT AVAILABILITY FACT'JR 21. UNIT CAPACITY FACT'JR (USING MDC NET) 22. UNIT CAPACITY FACT'JR (USING DER NET) 23. UNIT FORCED 'JUTAGE RATE 24. S!iUTDJtlNS SCHEDULED
'JVER NEXT 6 N'JNTHS (TYPE ,DATE .AND DURATI'JN
'JF EACH) 25. IF SHUT D'J-;,..'N AT END 'JF REP'JRT PERI'JD. ESTD*!ATE DATE 'JF STARTUP 26. UNITS IN TEST STATUS (PP..I'JR T'J C'Jf.1MERCIAL
'JPERATI'JN) . INITIAL CRITICALITY INITIAL ELECTRICITY C'JMMERCIAL
'JPERATI'JN THIS. M:JNTH
- .CUMULATIVE
.. ?20.0 6575.0 65039.0 717.6 1083. 7 35583.6 .*. o.o o.o o.o 945.7 34941.9 a.a o.o 0.0 1618768.0 1919687.0 811137?0.0 524880.0 611060.0 26479904.0 495153.0 572638.0 25109243.0 99.1 o /o 14.4 o/o 53.7 o/o 99.1 o lo 14.4 o /o 53.7 o/o 88.7 olo 11. 2 o /o 49.8 o /o 83.7 olo 10.6 o lo 47.0 o lo 1.0 o/a 8.4 o/o 20.8 a lo TMI Modification and Maintenance December, 1980 -1 week F'JRECAST Nu. !>ale 80-13 09-14-80 F: Forcell S: Scheduled i (lJ/77) UNIT SllUTDOWNS AND POWER REDUCTIONS
-cu 0. >. s 396.3 Reason: A 1 A-Equipment Failure (Explain)
B-Maintenance oi Test f-Rcfueling D-Regulatury Restriction . . i . REPORT MONTH SEPTEMBER, 1980 licensee Even I Report # I 3 Method: I-Manual c cu,n s cu 0. "O E o OU u 2-Manual Scrnm. 3-Automalic Scram. 4-0rher (Explain)
E-Operator Training & License Examination F-Administ ral ivc G-Operaliunal Error (Explain) 11-0lher (Explain)
DOCKET NO. 50-281 UNIT NAME DA:YE COMPLETED UY TELEPllONE Surry Unit 1 Sue D. Dunn (804) 357-3184 Cause & Correct ivc Aclion lo Prcvc111 Recurrence Normal shutdown for Steam Generator Repair Outage, Primary to Secondary leak.age in "B" Steam Generator was .283 gpm at time of shutdown.
All three Steam Generator lower shells and tube bundles will be replaced.
4 5 ExJ1ibil G -lnsl rucl ions for Preparalion of Dara Entry Sheers fur Lil:cnsec Event Report (LER) file (NUREG-0161) Exhibit I *Same Suurcl! --------
I '° I No. Dale 80-16 9-1-80 80-17 9-4-80 F: Forced S: Scheduled (l)/77) "]*.*I' UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT fr!ONTll SEPTEMBER.
1980 ...... *-0 c: -,.., 0 :::11--0 "' c: 'J C1J *-... 0 -::> *-'"' 0. .... ::I .,, .... C1J ..c: :5 0::: >. 0 '"' I-::I ::c C1J ...c c: 0::: Cl ._. Vl 6 F 2.9 H 3 F 3.6 A 3 Reason: A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction Ui:cnsce Event Report# E-Operator Training & License Examination f-Adminislrative . G-Operational Error (Explain) 11-0lher (Explain) 3 c E..,. Ill," c: u u u 0 "O :; 1o? 0. 0 >. Eu 111 u 0 u Method: I -Manual 2-Manual Scram. J-Aulomatic Scram. .4-0ther (Explain).
Reactor Level as DOCKET NO. 50-281 UNIT NAME DATE COMPLETED BY TELEPHONE
_filJBRY JINTT 2 SUE D. DUNN (804)-357-3184 Cause & Corredive At:tiun lo Prevent Recurrence trip caused by "A" S/G Lo-Lo a result of 11 B" MFP tripping The "B" MFP tripped as a result of Instrument Technicians working on the recirculation flow circuitry.
The motor protection logic circuit sensed a loss of flow and tripped the motor breaker. Repairs to the recirculatior flow switch were completed ai1d the "B' MFP was.returned to service. Reactor trip caused by "A" S/G Lo-Lo Level as a result of the "A" MFRV failing shut. The 11 A 11 MFRV failed shut due to *a breal< in InstJ;unwnt Air line supplying it. The air line was replaced.
4 s Exhibit G -Instructions Preparation of Data Entry Sheets for Licensee Event Report (LER) file (NUREG-0161) Exhibit I
- Sa111c Suun:c . ' .. i Nu. Dale 80-18 09-05-80 f: Forced S: Scheduled (l)/77) UNIT SllUTDOWNS AND POWER REDUCTIONS RErORT MONTH September.
1930 -<U p.. .::* F Reason: 0 r1 § "' :":I <U oc A 4 A-Equipment Failure (Explain)
B-Malntenance*
or Test C-Refueling D-Regulatory Reslriction licensee Event Reporl It E-Opcrator Training & License Examinalion F-A<lminist ralive G-Operational Error (Explain)
I I-Other (Explain)
E-.:t <U ..... U) lJ Method: 1-Manuai 2-Man.ual Scram. 3-Auturnatic Scram. 4-0ther (Explain)
DOCKET NO. 50-281 UNIT NAME DATE COMPLETEU BY TELEPHONE Surry Unit 2 Sue D. Dunn , (804) 357-3184 Cause & Currcctivc Action tu Prevent Rci:urrence Power restricted to 70% at 0050, 09-05-80 for "B" Main Feed Pump seal repairs, "B 11 MFP returned to service at 1856,09-08-80.
4 s Exhibit G
-Instructions for Preparation nf Dal a Entry Sheets for Lh.:ensee Event Repurl (LER) File (NUREG-0161) Exhibil I
- Same Soun:!! '* .. LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. i MONTH: SEPTEMBER, 1980 DATE TIHE HOURS LOAD, MW REDUCTIONS , 1'fW MWH REASON NonE during this reporting peribd. MONTHLY TOTAL c \, M9PITJ!: SEPTEMBER 80 AVERAGE DAILY P'JilER LEVEL DAY (Mrr'E-NET) 1 526.0 2 525.3 3 525.2 4 524.0 5 509.4 6 507 .9 7 486.8 8 49L3 9 483.5 10 488.0 11 478.2 12 476.0 13 501.0 14 178.6 15 0.0 DAILY UNIT P'JwEE LEVEL FDP.N INSTRUCTI'JNS D'JCKET ND UNIT DATE CDMPLETED BY --280 SURP.X I 10-1-80 SUE D. DUNN AVEP..AGE DAILY P'JY.'ER LEVEL DAY (lf-,.,'E-NET) 16 0.0 17 o.o 18 o.o 19 o.o 20 o.o 21 o.o 22 o.o 23 o.o 24 o.o 25 o.o 26 o.o 27 0,0 28 0,0 29 o.o 30 o.o 'JN THIS F'JRN. LIST THE AVERAGE DAILY UNIT P'JWER LEVEL IN /.fwE-NET F'JR EACH DAY IN THE REPJR'IING M'JNTH. THESE FIGURES i-.'ILL BE USED T'J PL'JT A GRAPH F'JF.. EACH ING WJN'IH. k'JTE THAT BY USING MAXIMUN DEPENDABLE CAPACITY F;JR THE /,ET ELECTRICAL EATING 'JF '1.'HE UNIT. THERE MAY BE 'JCCASI'JNS WHEN THE DAILY AVERAGE P'JwER E'XCEEDS THE 100 ° I 0 LINE ('JR THE RESTRICTED P:NEF. LEVEL UNE). IN SUCH CASES. THE AVERAGE DAILY UNIT PClw'ER 'JUTPUT SHEET SHOULD EE F:J'YIN'JTED TO EXPLAIN THE APPARENT ANOMALY. ... l DDCK .. D UNIT DATE 50-281 SURRY II 10-1-80 COMPLETED BY -SUE D. DUNN AVERA{;E PAI£¥ l:/liIT PQwER £E'llEf, SEPTEJ":EER 80 AVERAGE DAILY PD'w'ER LEVEL AVERAGE DAILY P0'1*/ER LEVEL DAI (M'wE-NET)
DAY (l.f"1E-NET) 1 451.1 16 750.8 2 624.4 17 752.8 3 727.0 18 756.8 4 386.9 19 75900 s 470.3 20 737.0 6 484.5 21 749.1 7 48 5.0 22 754.8 8 503.2 23 755.3 9 715.1 24 759.3 10 737.8 25 7 58. 8 11 742.1 26 758. 8 12 762.4 27 755.3 13 761. 5 28 752. 3 14 718.3 29 759.0 15 743.8 3Q 759 .0 DAILY UNIT P'J',.,'ER LEVEL FDRM INSTRUCTIONS
'JN THIS F'JP.P.. LIST THE AVERAGE DAILY UNIT P'J'1*/ER LEVEL IN M'w'E-NET FDR EACH DAY IN THE REP:JP.:IING
!*.'DNTH.
THESE FIGURE'S WILL BE USED T'J PDDT A GRAPH FDR EACH ING
/,':JTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY F:JR THE NET ELECTRICAL EATING :JF THE Ul.'IT. THEFrE MAY BE DCCASI'JNS WHEN THE DAILY AVERAGE POi-/ER EXCEEDS THE 100 °/0 UNE ('JR THE RESTRICTED P'JWER LEVEL UNE). IN SUCH CASES. THE AVERAGE DAILY UNIT P'JwER OUTPUT SHEET SHOULD BE FDDTNOTED TO EXPLAIN THE APPAP.ENT ANOMALY.
OF OPERATING EXPERIENCE Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in ificant non-load related incidents.
UNIT 1 SEPTEMBER 1 SEPTEMBER 3
4 SEPTEMBER 5 SEPTEMEER 6 SEPTEMBER 7 SEPTEMEER 11 SEPTEMEER 12 SEPTEMBER 14 SEPTEMBER 15 S EPTEMEER 18 SEPTEMBER 23 SEPTEMBER 24 SEPTEMBER 27 SEPTEMBER 30 This reporting period begins with the unit at 83% power in the of-life coastdown phase. Unit at 82% power in coastdown phase. Unit at 81% power in coastdown phase. Unit at 80% power in coastdown phase. Unit at 79% power in coastdown phase. Unit at 77% power in coastdown phase. Unit at 76% power in coastdown phase. Unit at 75% power in coastdown phase. After confirming samples indicated "1B 11 S/G primary to secondary_
leakage was .283 GPM, a unit shutdown at 5%/hour.was.
coI!!Denced at 0323. At Q850 the shutdown rate was increased to 100
- and at 1141 the generator:
was off At 1210 the.* reactor was shutdown by manual-reactor trip. At 1950 *the unit temperature and pressure were <3S0°F/450 PSIG; At 0251 the unit was at cold shutdown.
At 1145 the primary boric acid concentration was increased to 2094 ppm in preparation for refu*ling.
At 2000 the reactor head was removed in preparation for defueling the reactor. At 0001 the defueling of the reactor connnenced.
At 0327 the last fuel assembly was removed from the reactor. At 1125 the reactor head was replaced and left unbolted.
This reporting period ends with the unit at CSD and defueled in preparation for S/G replacement.
UNIT 2 SEPTEMBER l SEPTE..'11BER 2 SEPTEMBER 4 SEPTEMBER 5 SEPTEM:BER 8 SEPTEMBER 9 SEPTEMBER 14 SEPTEMBER 20 SEPTEMBER 21 SEPTEMBER 30 e SUMP.LARY OF OPERATING EXPERIE-This reporting period begins with the unit at 70% power with a power escalation at 3%.per hour in progress.
At 1436 the reactor tripped on 11 A" S/G Lo-Lo Level as a result of 11 B" MFP tripping. "B" MFP tripped as a result of Instrument Technicians working on the lation flow circuitry.
The reactor was taken critical at 1545 and the generator synchoronized to the line at 1733. Cormnenced Power escalation.
The unit achieved 100% power at 1559. The reactor tripped at 0216 on "A" S/G Lo-Lo Level as a result of the "A" MFRV failing shut. The 11 A 11 MFRV failed shut as a result of a ken Instrument air line. The air line was repaired and the reactor was critical at 0336. The generator was synchronized to the line at 0552. Cormnenced power escalation.
At 1725 secured power increase at 79% due to sodium carryover in the main steam system. At 2240 ced power reduction to 60% in preparation for securing 11 B 11 MFP for seal repairs .. Secured power decrease at 0050 5 stopped riBu MFP and cormnenced power escalation to 70%. At 1826 "B" MFP was returned to service. At 1908 cormnenced power escalation.
Unit achieved 100% power at 0615. At 0157 reduced power to 90% for the 11ain Steam Carryover Test. At 0337 reduced power to 75% for Main Steam Carryover Test. At 0549 conducted a 10% step loss of load test and at 0551 conducted at 10% step power increase test. At 0600 commenced power escalation and reached 100% power at 0730. At 1155 reduced power to 90% in preparation for changing Tave Program. After completion of change to Tave Program, a power escalation began and power reached 100% at 1751. At 1828 reduced power to 95% for Main Steam Carryover Test. At 2039, after the Main Steam Carryover Test was completed, increased power to 100%. This reporting period ends with the unit at 100% power. LITY LICENSE OR TECHNICAL SEPTEMBER, 1980 The Nuclea-:-Regulatory Co::!llllission issued, on September 5, 1980, Amendment No. 61 to the Operating Licenses for the Surry Power Station Units No. 1 and No. 2. The amen6ments result fron the NRC Staff's review *and approval of the Surry guards Contingency Plan. Of significance, paragraph 3.J of Operating Licenses D?R-32 and DPR-37 has been added to read as follows: * "-The licensee shall fully implement and maintain in effect all provisions of the Co;:::iission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority of 10 CFR 50. 54 (p). The approved Contingency Plan consists of documents withheld from public.di?closure pursuant to 10 CFR 2. 790(d) identified as "Surry Power Station Safeguards Contingency Plan" dated May 1, 1980 submitted pursuant to 10 CFR 73.40. The Contingency Plan shall be fully implemented, in accordance
>dth 10 CFR 73.40(b), -within 30 cays of this approval by the Co!IIilliSsion." The Nuclear Regulatory Commission issued, on May 23, 1980, a Memorandum and Order requiring that all safety related electrical equipment in operating reactors be fully envirorunental qualified by June 30, 1982. To meet this objective, the Nuclear Regulatory Commission issued, on August 29, 1980, an Order for Surry Power Station Units No. 1 and 1lo. 2 requiring the submittal of all information to support a safety evaluation of safety related electrical equipment by November 1, 1980. ** ,.,_
Design Change FACILITY CHANGES REQUIRING NRC APPROVAL SEPTEMBER, 1980 None during this reporting period. FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL Unit Nos. 1,2 DC/79-57 -CVCS -This change involved modification of existing station drawings to reflect the as built configuration of the VCT level control circuit. Swnmary of Safety Evaluation Insomuch as this design change encompasses only paper work to update drawings so they reflect an inherent construction configuration, the safety of the plant has in no way been jeopardized.
!';':'-, ' ST 52 TEST AND EXPERIMENTS REQUIRING NRC APPROVAL SEPTEMBER, 1980 None during this reporting period. TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL . . UNIT NO. 2 Reactor Coolant system Flow Measurement Data was taken on 3, 10 through 20, 22, 23 September.
The purpose of this test is. to obtain data to accurately determine reactor coolant system loop flow. ST 101 UNIT NO. 2 This test which provides subsequent testing for PT-8.SA (CLS Hi Hi Train) is to verify that the indicated components cycle as designed upon receipt of a CLS Hi Hi Signal. erHER CHANGES, TESTS AND EXP ER.TS SEPTEMBER, 1980 None during this reporting period. e SURRY POWER STATION . . CHEMISTRY REPORT SEPTEMBER, 19_aa__ T
- S
- 6
- 6 . 3 .* d ' PRIMARY COOL.\NT UNIT NO. 1 UNIT NO. ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMtJM Gross Radioact., }..I Ci/ml 5.25E-l 4 ?fi"R-3 l.547E-l 2.24E-l q 40F:-'.' Suspended Solids, ppm 2.3 0.1 .4 .2 .1 Gross Tritium, f,JCi/ml 2.23E-2 2 .12E-2 > 2.175E-2*
- 1. 58E-l 3.21E-2 Iodine-131, }..I Ci/ml 6.18E-2 l.28E-4 1. SlE-2 1.83E-4 6.40E-5 1-131/1-133
.4312 .3372 .3784 .2393 .0622 Hydrogen, cc/kg 55.l** 4.5* 22.5* 62.4** 30.5 Lithium, ppm .63 .16* .40 1.86 1.0 Boron-10, _ppm + 439.82 <l* 315.41 205.60 174.24 Oxygen-16, ppm 5 * .90 .ooo 1.88 .ooo .000 Chloride, ppm
- 05 <.OS <.05 <05 <.05 pH @ 25°C 9.10 5.12 7.12 6. 64 5.97 + Boron-10 = Total Boron x 0.196 Phosphate Sulfate NaOH NON-RADIOACTIVE CHEMICAL(l)
RELEASES, POUNDS T. S. 4 .13 .A .. _g 0 Boron 0 D 1232.8 Chromate . 00 Chlorine 2 AVERAGE 1 fib. F.-] . 1 9.29E-:' -* 1. 20E-4 .. .1212 .-. 42.7. *-* 1.46 186.48
- 000. <.05 6.42 Remarks: ** Resampled and found tape in spec. (SPEC 22-50 cclkg) *RefJects degassing after shutdown
- Lower Limit of Colormetric Boron UNIT #1 Rx off J jne 4-l 4-80 @ 1141 Manual Safet: Injection UNIT #2 Rx trip 9 4-80 @ 0220 (1) These levels of chemicals should present no major adverse environmental impact. DESCRIPTION OF ALL DISCHA."R.GE LH11TS WERE SEPTEMBER, 1980 Due to impairment of the circulating water system on the following days the thermal discharge limits were exceeded as noted. September 2., 1980
- Exceeded 15°F 6T across station September 3, 1980
- Exceeded 15°F b.T across station September 4, 1980
- Exceeded 15°F b.T across station September 8, 1980
- Exceeded 15°F 6T across station September 9, 1980
- Exceeded 17.5°F b.T across station September 10, 1980
- Exceeded 15°F b.T across station September 11, 1980
- Exceeded 15°F b.T across station September 12, 1980
- Exceeded 15°F b.T across station September 13, 1980
- Exceeded 15°F b.T across station September 28, 1980
- Exceeded 15°F b.T across station *Indicates dates where station b.T was less than 15.0°F across the station for sometime during the day. The DeltaT excursions were allowable under Technical Specifications 4.14.B.2.
There were n,o reported instances of significant adverse env'iroilmental impact. On September 1, 1980 the temperature change at the station discharge exceeded 3°F per hour due to a Unit 2 r_eactor trip.* On September 4, 1980 the temperature change at the station discharge exceeded 3°F per hour on two occassions.
The first event was due to a Unit 2 reactor trip and the second event to a rapid rampdown in power to remove the "2B" MFP from service. These events were allowable in accordance with Technical 4.14. .-.* FUEL HAHDLIHG UNIT 1 SEPTDIBER, 1980 There were no fuel shipments during this reporting period. The entire core from the reactor was moved to the Spent Fuel Pool. DURE REVISIONS THAT CHA.NGED T TING MODE DESCRIBED IN THE FS , SEPTEMBER, 1980 None during this reporting period.
DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT -COMPLETED WITHIN THE TIME LE IN TECHNICAL SEPTEMBER, 1980 None during this reporting period, e INSERVICE SEPTEHBER, 1980 1. Unit 1 Inservice Inspection is in progress and is being conducted by Westinghouse in accordance with VEPCO Surry Technical Specifications.
To date the inspection has been satisfactory.
- 2. Conducted a Magnetic Particle Inspection of all three main feed water piping tration welds. No indications were noted. 3. Completed an Ultrasonic Inspection of 10 low point welds in the Recirculation Spray System and 10 low point welds in the Containment Spray System with no reportable indications noted. 4. Commenced a Radiographic and Ultrasonic Inspection of the main feedwater 16 11 x 14" reducer welds and radiography on the 3" auxiliary feedwater tie-in lines. I '
I ! . ' I 1 ! *1*)1: I I '* I' i J (-' I I ( . I I I I ('* 11 <' I r ! I c* i I I I ( ., I i* ! . I I ... \ I r I .. -. :
.. ** **1' 1 VE'lJ';flf)T UNI'l'1-(NAJN'l't'NANCf.'
OF SM'l!,'7'f Jj/','f,ATl!.'O SYSTEMS DI/RING OU'l'AGt:
OH m:oucw p,'Jh'E'U l'l'.'HlfJDS) m.:'l'S/<:l1V/J1' S'iS C'JML> MAh'KN.'J Sl/MMAIIY WKl'l!."liP u MN 'l"J'l'WN'l'M 09/17/80 SI l'Il'lN(,'
Hf.MOVE: A/IC 1'6'11 /:,'NGINl:."E'llIN<;
JU0Gc'MEN1' 1 009101817 5U 09/'/2/00 HI l'IPJNG ND'l' l'b'NB'l'UA2'1','JN l./l':LDS M7' f'li'N'l' E'Ol/UV JS INVlCA'l'IUNS 1 00117131(1 177 VIW'l' 'lJT AL 235 . I BLE OCCURREHCES PERTAINING TO OUTAGE OR POWER REDUCTIONS SEPTEMBER, 1980 None during this reporting period.
Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT ill Mechanical Maintenance
.. ,.,. ,, (\ 1! ' i *l 1/ ( '\ .. ; j. *--.... _.JJEP'l'
=MECll :j **., 'i *:1 Ji/STSEllV/I'./'
SYS l\'JMI' 09/03/UO li'M P/JNl' ' 09/03/80 BH VAL.Vt.' . ' ' _ ........ 09/011/AO . Cl/ .INS7'R I OY/05/80 1..:r: l'll'ING ,I 09/l l/80 [I(; l'Il'.INr;
- 1 09/11/60 ST l'll'WG (e ... 09/11/BO hM l'UMl' 09/11/80 cc /JX OY/ll/UO cc l'llNI' ( 09/12 /0() GC l'UMI' 09/12/UO cc l'llf>IP O!J/12/00 cc l'IJNP 'I O!l/12/!JO t:F. 1'1 l'ING O!l/12/UO CV P/JNI' 09/13/00 IA VAlVf: (" 09/13/00 MS l'Il'ING 09/13/80 MS l'Il'ING 0911*1 l!JO IA C.'JNl'RESS O!J/1'1100 liH l>'VAP cb 091111100 BR VAL.Vt: . 09/111/80 llR VAlVE 1 (' 0911'1/80
/ill VAL.VF.: I 0911'-l/80 CV l'/JNP I 09115/00 cc /IX I ! ( 09115100 VS f'IlTC'R . I 09/15/80 vs L"l lSf.'R *I -* ... -09116/80 Jr 7'ANK :1 Iv ( . 09116180 SW /'IP.I NG e 09/17/IJO NS Pl l'ING I 09/17180 MS l'll'lNG ; ( 09117180 /IC '.l'ANK i I I. I 1 / (' .. ***=-r**
- ,'* UNI7'1-10I06IBO (NAIN7'ENANCb' OF SAFf.'1'Y RElll7'ED S
- tS7'EMS DURING OUTAGB OR RE'DUCED l'OwER l'ERIODS)
MA/i'KNO h'./l.-(,'j.,'-lOl-102 /J!.'*2011 F-1-SW-101-C 24-b'Xl/ lIN/i: 2-VG-112 3-SI-111*1 llM-*vc-1091110 1-CC-f.'-lC 1-CC-P-2/J 1-CC-l'-18 1-CC-P-1C 1-CC-l'-llJ 36
SUMMARY
llJ/OKE BEL7' B?DY T? fl.?NNET lEAK FL'JAT STUCK --*--****
., ..... -DIC 79-S32A INS2'AlL-SUPl'Oll'l' MOD DIC 79-S32C INS7'AlL SUPPORT DIC 79-S32C INS7'flli i2'b'M 111 l'UMl' REMOVED Cl.t.'AN l/X i'l!ML; IS NOISY h'Kl't.'IW INSTAll Nf..W l1f.'l7' /i'f:IJUI lD VALVE Flll'F. FLOAT FOUND lf.'AK AND PWGGl::O 20 TUBES COMPlE7'1::
INS'l'AlllW AS l'ER DESIGN REQUES7' li'F:l' LAC EIJ l'UNl' Cl.t.'ANF-:D
/IX C lf.'ANf.'IJ I/Ji l,r:lc'FO/i'N l'MS l'BUFO/i'MEIJ l'NS l'ERFOUM f'MS l'f.'lllo'Oh'Mf..'D l'MS . l'l\'11'f'ORM PMS l't.'J..'f'OllMl!..'D n:s . IJIC 19-S32C INS1'AlL SUPl'OR'l' MOD JNS'l'Af,f.lW C0Ml'll::1'E
!IANGf..'R WW now l1'f..'l'LAClW PUMP 1-CC-l'-1A 1-IA-D-1 3-S//P-30
- 1-S//l'-26 I-IA-C-1 111.'-EV-llJ 1-llli-237
... _____ IA DUYER lJUAIN VlllVE Will. NOT WORK ....... Clf..'ANW OU1' BWW VAlVE J -/IR-232 1-UR-234 Sl"'JRE 1-CC-EID 1-VS-f'L-38 1-VS-l-'L-3A 1-RC-7'K-2 8-h'Nll'./'D-2-151 1 1/2-Sl/PD-5 1 1/2-SllPD-5
.. 1-RC-'I/(-2 DIC 79-S32A lNS7'ALl SUPPORT IN51'AlU'V I7'b'folS 1 DIC 79-S32A INSTALL SWAY S7'RM7' INS1.'1lll I1'/\'f.J 1 OIL PUMP LF.AKS RF:l'AI/lf,'D COMP INSl'f..'C7' Hl::E'WX NOZZlE INSPEC1'EIJ li't:l-'LUX Noziu.; VAlV/i: LEAK Rf..'PAIREO VAlVB VALVE LEAK ON 8 TANK ..... -----------*-
li'EPAIRED LBAK. lEAK 7'1/RU REPAIHED Lf..'AK HF:BUI lD SPOllE VACUUM Cl.E'AN llX Rb'UUILD PUMP BOX CLE'ANEV lJY OPS AND NIGl/TSllIFT.
1'00K Cl/AllCOAL SAMPlf..'S 7'00K CllARCOAl SAMl'lt.'S 7'AKE Cl/AllCOAl SAMPLES FOR HP 7'AKC' Cl/AllCOAl SAMPlf.'S fOR l/P JWIYJ.'IJRE DISK BLOWN -------.... RF.PLACF:D DISK SW l.EAK DIC '19-S32C INS7'All SUPPOliT DIC 79-S32C INS1'ALL SUPPOl{f MOD ..... RUlTUR/i:
DISC Lf..'AKING INS7'AllED Tf..'MP PA2'Cll COMl,LCTE COMPLf..'TE INS1'AllElJ Nf..W REP'l'URf..'
DISC IJ MH 2'0'1'l!W N'./'M 1 1 1 1 1 1 0083112'15 009022220 00021111150 OOl12l>Oll09 0082115'15 0011290630 009110225 009110300 1 007110932 1 00711093 3 1
- 0071109311 1 009081100 1 0091107*1 S . 1 .... 009101028 1 009121500 1 009121501
- 1. 00731053 1 1 1 009130735 1 009131L31 1 ... 009131633 1 009131700 l 0091512 1 15 l ... 009110226 1 009151000 1 009151001 . 1 ... 0091513*12 1 1 1 1 0091611311 . 005291650 00529lG51 009170603 78 8 35 8 25 1 1'1 336 q11 l 1 *111 119 110 95 22 2 1 1 16 16 27 27 22 311 15 7 50 ,, 211 6 1002 1002 7 ----*--..
., *I I °' I D.IW1'=Mf.Cll 09/18/00 09/18100 09/19/00 *.l , .... ---*
09/19/80 ---**--**a91191ao 09/20/80 09/20/00 I i.J9i22/UO r a 09n2100 . .., 09122/80 ----*--.
09/23/00 09/2'1/00
--cc 09/25/UO Cl/ 09/25/80 li/J --69/25/00 IW 09/25/BO Git' 09/25100 Cl/ *-----b!i/25/80 l1S 09125100 RS 09/2 5100 JiS 09125100 f,;5 09125100 /IS 09125100 NS * --*-----09/25100 r.s 09/25100 /i.'J ... 09/25100 f:t: 09125180 i { 09/76100 llr' i i l i I::, ! (';. ('. 09l2GIOO l'U *--*-* 09126100 (,'Ir' 09126180 Cll 09l2Glll0 lJ[) 09l26IBO Cll 09/26100 11/r' 09126100 Cl/ --*-**-09/26180 Hf, i -09/2GIOO 09/?6100 09/26180 09/26/80 /IS liS liS NS l!Jl!JNG 0'1'1/f;h' l'll'ING l'll!lt/G Pil'ING l'll'lNG ')1'/1£11 CQMPJ.'l:'SS VAlVf:' caN1 1 1.*r.:ss /:'UN!' f'If,7'E'/I
/!I [,7'1:.'11 VALVf: l'JPl Nr; fll'lNG l-:11'/NG l'll'lNG l'l f'1 NG Pll'lNC l'il'lNG l'l l!lNG l'I l'1 NU l!ll'lN(;
VAL.VE VAl.Vli' VAL.Vil' VALVf VAL.Vt' VALVF.: VAl.Vli' VAi,V/; C*'JNPm:ss Vlll,Vt.'
l'I /'IN(; l'll'ING l'll'ING l'I l'fNG l'll'lNG l'll'l N<: v111,vr.*
l'Ufoll' Pif.1'fH VtllVf,' VllLVli' VAf.Vli' Vll/,VE UNIT1-10I06IBO (MAIN2'1'..'NANCF.
'JF SAFf;TY li'l:'LA7'W SYSTI:'MS DURING 'JU'l'AUE Oil /(f..'DUCW P'Ji-U,'R l'EllIODS)
MAMiNO SUMMA UY WKl'ENF u MU W'l'IJWN'l'M 10-SJ-lliU l>IC 19-snA H'S1'ALL SPRING 1 NS'l'All£'D l'JCK //ASl' AS nm iit'QUl:.'S'l' 0091'/l IOO N * ."PIU,.O/t/ol MMP-P-CH-015 l'/','/!PONMIW PMS 1 0091UOUOO
/JC 79-83',/C
!.'1'.'MOVF:
CONSWAINT llt.M'JV1'.'D l'll'i'..'
SUl'P'Jlr"l' I 00 1 IOU 1119 DIC 79-S32C SUPP0/1"1' WJD. BtJXE'O IN 1'..'HXlNG ANGL1'.' lliON 1 0011190701 DIC 19-S32C !1'£:..N()Vf:
SUl'C'tJll'f ilt:NOVt:D BXIS1'lf/G Sl/Pl'Oll'l' 1 00112:.!1111 Y DIC 79-532/J INS7'All NW SNllBIJt:R INS7'AU. NE:.*w S/Ji'l'Oli"l.'
1 00102 t 1 1 :?0 1-C/r'-2Ci/1
- 1-liU-17 3-wr;c1J-106
- 3-C//-113
'J-SVl/V-2 1-t'/J-lj 1-IJU-C-llJ 1-/i'C-29 1-IA-C-1 **---*--*
n:kf'i)Ji'N i'NS . ---*-* ---------**
l'£'Nf.'ORNl::D l'MS 1-** 007110919 l-/Jh'-l 1-1 1A 1*VS-fl-3A 1-vs-n.-ao 1-l'V-5 2-Cll-13 CONPRF:SSOU NOISY ANV WIU, NOT PUMP W,'l'[.ACJ::D VIAP/fHAGMS l 00911111153 KN?l'Kt'll VALVE //AS NO HANDL8 INS7'AlUW 11/illVLC.'
1 00!.11912 1 10 /Jt:JWO/r'M PMS .. l'E'N/."'JliMlW
/:'NS .. '*** ....
- 1. 007110058 l'E/1'FOI1'M l'MS Cllb'Ck CASING /o'OH LEAK{i AND CU'AN 007110901 Uf,'PlACf,'
CllAh'C'JAl Fll7'E'R COMPLE'J'f,'D 1 OU!J161323 UE'l'lAC!'
CJIAJ,*cOAl l'I l'liE'i(-!'Al ll::ti *--**---*-*
' .
- *--.**.* 1 -** .. 00916 l 32** C/lf.'CK Vt1f.VE IJllJCKI:'D VALVt CI.OSED 1 0091Gl 123 DIC 79-S32C SUl'l'lJH7' Mo?D. INS7'A£,U.'D ANG/,/!.'
1 00 1 1251 1 10*; 2-VA-111i
/JIC 79-S32C INSTiiLi SUPl'O/ff ltiS1'Ail.
i'll'f.' SUl'l'.'Jli'l' f'Oll OV1'.'/1..ii7'Ul:.'SS i 00112c;ouou 3-CC-152 UIC 79-S32C /.IODif'Y SUl'l 1 QRT CONl'f,1':'1.'E' 1 00530J110l 3-Cl/-11 DIC 79-S32C INS1'ALL SUPPOllT MOD. INSTALll'.'D SUl'P'JJl'l' NOD 1 006111259 3-CC-13-*----D/C 'Hf-S32C
--**-----****--*
i---006261019 3 -Cl/-99 3-WCCIJ-106
'J-WGCIJ-2 6-UW-15 '2-Cll-26 1-RS-30 1-HS-39 1-RS-31 1-115-1 1-h'S-3 1-/i'S-5 l-Rs-11 1-fiS-35 6 -Ii' Al'D-50 'l-PG-21 3-Glr'-30 3-Cl/-99 3-w'(lCll-2 11 -Cl/-112 l-IJ/i'-236 l-Cll-l'-2A 1-J.'f,-l:'-1 1-li'S-27 l-RS-0 1-US-32 1-li'S-12 DC 79-S32C INS'J'All CONS7'RAINT INS'l'AllED
/JASEPl117'E AN/J J.'UIIE Sl'£'E:l 1 0011001129 DIC 79-S32C 1NS1'All SUPf'OJ{J' INS1'All6'D AND liEWED SUE-'P0/17'S 1
nit 79-S32C SUl'PONi.*
- -------*-1NS1.'ALl.
SUPl'OJ(J' J.'1'..'R S!it."l'CI/ . -* 1 . 0011:?60ll07 l>IC 79-S32C SUPP'Jh"l' MOD. INST/illE'V SlllN AND WBI:' STll'l:.'L 0011260U1 1 1 JJIC 19-S32C lllS'l'ALL SUPP[)ll'l' JNSTALLEIJ BASf,'l'LA7'l:'
AND '1'011£:.'
S7'f,'/,;l 1 005070005 Jll:."PLACE BOL7'1NG***-
- -******--*-*****---------***-*VALVE D*?ES.N?T llAVE-S'l.'UDS--**-
-*---***-*-*1*
009171016
!i'f.'l'LACE IJ?l7'ING NO l10l7'ING 1'0 /JE REPLACE[)
1 lOl 7 I/El'LACE
/KJ[.1'ING VALVE lfJI:'S N01' /JAVE STUDS 1 009171010 JIEPLACf B'JL2'ING
... **-**** ----** REPLACC:IJ IJ0/,7'.ING 1 009171019 Rt::PLACI:'
n?l'l'ING l/El'LACI:'D IJOLUNG 1 009171020 m:l'lACl:.'
IJ,'JLTING llf.'l'LACED BOL7'1NC; 1 0091710'11
.. HE'PlACf:
fJ'Jl,7'INC
-* -*-*-*--** **-REPLACfo,'D IJ'JL7'ING .. .. 1 ---0091'/l022 RF.:l'LACE IJ.?l1'1NG Rl:'l,LACtm H?L'l'l/IG 1 009171023 r.;LEC COMP IN N*?l I/AS AN AIR LE'AK RC'l'lACElJ llEAV GASKf,l' 1 009231135 J.'f,PlACl:.'
IJ."JL'l'
'1'1/IS IS A SWEGEWCK VALVE. 1 U0925001Ci IJIC 79-S32C 1NS7'All SUPPOllT CONl'LE'l'E' 1 CJ0 1 1221 1 122 VIC 79-S32C 1NS7'All SUl'POh"l' INS'l'Af,l,£:.'I>
BASE Pl.A7'l:.'
1 00 1 12 1 110 1 13 DIC 79-S32C SUPP0/1"1' MO[). INS7'Alll:.'D ONf: l'f.'JCE OF ANGlli' 2 1/2 B 00 1 12511!00 VIC 19-S32C SUPl'Olr1' MOD.* AVD£'D 7'UllE S1'£:.'E'l, AN/J 7'WO PLA7'E'S 1 00 1 1251'102 DIC 79-S32l' INS1'All SUl'lJR'l' INS7'Al,/, PI l'l*: SUl'P?liT 1 00 1 126llU05 /JIC 19-S32C lNS'l'All SUPl,'JlrT WJD. JrJXf:D IN 11 Cl/ l'lPE UN1'.' 1 OOG2Cil020 INSl'f.'CT 7'/lf,' VAf,Vr: VOID MR 1009131632 COVERS '1'1/IS MH 1 0072 1 115311 /Jf:V I 117'1 tJN SU/Jft.'I7'7'f:D Nl:'l'AIRE'IJ EU:C'l'li'JC f.J,'J1'0R 1 009192150 P.ll7'/::R Nb'f:l>S CIJANGillG Rl:.'PlACfW 1/11.'l'/'.'Ji 1
- 009:.120227
/i'E:PlACE ll?l'J' VOID VC,V JS N'J'l' 'lJ /Jl:.' WO/r'KED 1 009250009 ll&PLACf:
B'Jl.'l'lNU Rt:PLACED STUDS /IND NUW 1 009251501
/1'EPLACt.'
/JOLT ING m:I'LACI:'D S'l'UlJS AND NU1'S 1 Hf:PC.llCE' D 0'JL'l'll\'C m.:l'LAClfD S7'UVS ANIJ NU7'S 1 009251503 27 11 72 72 40 175',/ 26 136 21 530 !>30 53 50 160 105 176 191 904 191 20'/ 2011 1n 102 204 6 6 6 6 f> 6 6 6 21 1 228 225 225 225 216 231 0 !i6 6 0 1 1 l l'.: '";_/*' **1' ,, i ---* ... --**. I *, 1_ I 'I *-* . !'11 ., DE.'l"J'=MfC//
I I ... UNI'.1'1-10/06/BO (NllIN7'b'NANCf.'
f'JF SAFf'.'7'1 m:LA'J'b'O S1S7'EMS DURING OUTAG/:,'
OU Hl!:OUCt:lJ P*'JWf'.'U n:llIOOS)
L I I .. , llt.'1'Sf,'f{V
/J7' SYS C'J/.ll' MA HK NO Sl/MMAIIY WKl,/:,'h'P u Mii 2'02'VWN7'M I . ! I i 09/26/00 loS VALVt: 1 Rt:Pf,ACE:
lJ"Jf,7'INC RJ,,'1:'£.AC/.W SWOS ANO NU1'S l 0092515011
' I I r* O!J/26/80 lo'S VALVE-.' l-W)-13 liF:l'f.ACf:,'
B'JL1'INC llt:l'LACIW SW/JS llNU NU7'S 1 1 O!J/2G/00
/iS VALVt: 1-us-111 f.'C.'Pl.ACI!:
- f!.'Jf,7'.lNC Hi-.'l'LllC(!;O llN/J llU1'S 1 00925150(, 1 I 09/26/UO /IS VALVf; 1-115-15 hE'l'l.AC(:,'
lJ'Jf,1'1 NG J.'f:l'LACF.'/J S7'UOS Alm NU7'S 1 OO!J251507
! ' :-09/LGIBO loS Vllf.Vf: l-Rs-211 HEl,LllCl:'
b.Jl.7'1N(;
JU*:l'l.ACIW SW/JS llN/J UU7'S 1 OO!J251512 I O!J/;>t,;/Oll
,.,.
J -NS-25 lo'r:l' l.llCf: 11-'J f,7'1 N(; 11/WLllCf,'/J S'l'IJ/IS AND NllTS I 00!1251S13 l \ .. ' ,,, i9' O!J/26/UO
/IS VAl.Vr.' 1-HS-21 Ji'r:l'LACf.'
IJ.'Jl.'l'IN<J VJlD l'l.V lS !101' 7'.'J 118 li'Jl1'Kt:D 1 OO!l1li0B05
() O!J/?U/00 UC l'f."/if'OUM MMl'-C-liC-035 111:.W:JV/o,'/J CON!JS/'.'11/,S l OO!J l 2ll!l03 I 09120100 J.'C ut: vt:s5 l'i'.'/1'l*J/IN MME'-C-UC-036 ut:M-'JV r,*o {NSUl.A'l'lON 1 OO!Jl 209011 232 I O!l/29/00 Cl/ 1'11'1 N(; 2-C/1-50 JJ/C '19-SJ2C lNS'l'Al,L SUl'/'OliT INS7'ALl.
l'LA'J't*:-'l'IJ/Jf:
52'£*,'f.'l AND Pil'E' S'l' 1 00112111 Ql(J 3011 Ii ( 09/29/IJO Ii'/. 1'11-'JNG 3-Uf,-5 0/C JNS'l'ALL SUl'l'OliT .lNS7'A/,/.t:/J 1111.%' l'lA1'1'.'
1112'lt:ll 8-'Jl,'J'S 1'U I 00*1'.1 1 110!>2 3011 O!J/29/00 Cl/ l'l PIN<: !1-Cl/-*1!J*1 lJ/C 7!J-S32C SUf'l'Oli'l' MOD. 1NS1'Al.f.W l'll'i': S1'//Al' li/i,'l/JJW 1'-'J l'lll7't:
1 0011300!JOl1 3011 09/29/ OU IJ/1' M'JV lJU-lOlD C//EC/i OU7' VALVEi/i'fPAIU V*'JIIJ MR 1912131510 C'JV1RS 2'1/IS MR 1 OOGOblOOU
() ,-O!J/29/00 Iii/ VALVt: l-/Jlt'-23'/
I NSPt:C'l'
'J'llf: V Ill.VE V:JI D Mii IOO!Jl3163l CQVf,'/IS
'l'IUS MU ! 001*11115'l9
() ' O!J/n/OO /IR VAl.Vf: 1-lili'-2311 1 NSl'f'.'C7' 1'1/t: VALVli' VOIV NU 1009131700 C'JV/o:lo's 7'1115 NII 00*12111530 0 O!J/29/BO
/Iii' V Ill.Vt-: 1-/Jll-232 INSl'fX7' 1'1/f: V Ill VOID Mii JOO!J131G33 COV/i/i'S
'l'lllS MR OU'l:.>111533 0 I'., 09/2!J/UO
/jf/ VAl.Vf,' 1-UJl-C-1/l
/JAD GllS l./:.'AK
- 117' SUCTION l.lNE' VJ.lfJ Ml/ IOO!JJl1t1153 COV/;'/,'S 7'1115 NU ()(J"/2!>11110 0 \ 09/29/00 I.Ill l'IJP/' 1-/J[(-J'-llA llEA/IJNGS II/IE IJ/ID V'JID Nii l00'.1110900 C.'JVL*:us 7'/JIS Mii 007292250 0 O!Jl29/ll0 1.c l'Ef.'/!'JllM fiC 70-S25 COMf'l,f'.Tl':IJ . 1 009751100 79 I c* O!J/30/00 Cl/ l'1 Pl NG 11-CI/ -1911 DIC 79-S32C .INSTALL Slll'lJliT C0Ml'lf'.'1'f:V 1 00111 !JO'/O!i J211 0 09/30/00 /J/) l"ll'l N<: 3-Wl:CIJ-101 D/C 7!J-532C JNS'l'ALL SUl'P'Jl(r lNS'J'ALLW Ni;'W ANC/Jf.J/I Slll'PO/i'.l' 0011221*11U 32 1 1 C") I 09/30/00 Cl/ /'I PING 11-CJI -1911 DIC 19-SJ'lC INS7'11LL SUl'l'Jm' INSTllUE.'D Nl'W Sl'UII/<;
CllN . 1 001121110*10 302 ' (' .* O!Jl30/00 Cl/ l'l /'JN<; 3-C//-25 DIC 79-S3<'C lNSTAf,L SUl'POll'J' INS7'11l.L1','lJ Nf.'W l'Il'f,' SIJl'l'0/1'1.'
1 OOl1211 J05U 302 l I i O!J/30/00
/)/) l'I/'l Nf; 3-J.'GCll-2 DIC 19-S32C lNS'l'll/,L SUl'J'.'J/(J' IN.51'11UBIJ Sl'UlNG CANS 'I'll/JEN
/JASf,' l'/,11 1 ()()11250'/00 321 I O!l/30/00
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NIN llANCl:.'li
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--.. > ' . HEALTH PHYSICS SEPTEMBER, 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. r' ..
HO. Unit PT39B-2 2 OP22.5 1 OP47.10 2 PR OCEDURE 11 ATIONS REVIEWED BY STATION .EAR SAFETY AND vPERATING COM11ITTEE AFTER TIME :C ITS SPECIFIED IN TECHNICAl, SPECIFICATIONS SEPTEMBER, 1980 Title Date Deviated Visual Inspection-7-29-80 "Inaccessible Snubbers" As Found Contaminated Drains System Makeup Water Treatment 9-7-80 System-No.
2 Makeup Water Demineralizer System Date SNSOC Reviewed 9-11-80 9-18-80 9-25-80 . ' ., ..