ML19209C236
| ML19209C236 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 10/01/1979 |
| From: | Willis E CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19209C217 | List: |
| References | |
| NUDOCS 7910120240 | |
| Download: ML19209C236 (12) | |
Text
,
1 A??E'17I'( 5 AVERAGE 05.IL( ?SGR LEVEL DOC ('ET "O.
353-1325 U'iIT 30U'!S1II U:!IT I l
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jg C
L Y EULI3 '!!LLIS TELEPHO'!E 91s-4 7-9521 SE?iE.'55R 79 JAY AV3. DAIL( POnER LEVEL JAY AVG. 0 AIL / DD'!ED LEVEL
( ft'E-:!ET )
('!'rE.iET )
1
$56.
17 203.
2 562.
li 52^.
3 654.
19 447.
4 6l3.
23 64).
6 549.
21 523.
6 667.
22 472.
7 690.
23 690.
3 212.
24
- 704, y
O.
23 566 10 0.
26 741.
Il C.
27 752.
12 O.
2.5 752.
13 0.
29 755.
14 0.
31 749.
I:
0.
16 1.
11'4 108 1.15 - 3 49101201 U
10ER ATI:IG 'ATA TE?CRT CCC::ET "0. 0: J-0325 DATE 10/01/79
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L Q[1l llh{
ll CCN? lit:D 3Y EULIS "ILLIS l
l1j'LL TELEPHO:iE 919-457-9521 j
..? e, u. I s, s t a.
rJ a-o _..
.a t
- l. d'!II NAME: 3RU!!S7 IC.< U'!I I 1 I '?CTES I
2.
1E?ORTI:iG PERICD: SEPTE.15ER 79 I
I
- 3. LICE::SEJ THER"AL ?O VER (:'"!T): 2433 I
I 4
- UtE? LATE RATING (37053 "?!E): 667.0 I
I
- 5. OESI3:1 ELECT 7ICAL RATING ('!ET :'.lME): 821.0 I
I
- 5. li.X DEPEilDABLE CA?ACITY (GROSS.tME)s 315.0 I I
7.
'i AX DEPE:iDASLE C AP ACITY (NET 't.'!E): 790.]
3.
IF CHAdGE3 JCCUR IN CAPACITY RATI?!GS (ITEMS 3 THNU 7) SI?iC: LAST R:? ORT.
JIVE REASONS:
e.
?J 2d.0 LiVEL 20 /.HICH RESTRICTED IF AtlY (:lET 4?:5): NO?:2
- 17. RiASO'!S FOR RESTRICTIC'l I.: A' 't :
THIS Y: TO CU:JUL
'!]'ITH 7iTE ATIVE II. HJURS IM 9E?JRTING ?E?IOD 720.0 6551.0 22248.0
- 12. '!UM3ER JF HOURS REACTOR '!\\S CRITICAL 526.3 3703.4 16014.0
- 13. 7 ACTOR RESERVE SHUTDC":I HOURS 0.0 3.0 1647.1 la. " CURS 3E:iERATO? D': L I.'IE 505.1 351J.7 15060.5
- 15. J1IT RESERVE SHUTJ0W'I HJURS q.0 n.n 0.0 lo. U7 CSS THERM AL E."ER3Y 05:iER ATED ( ' 'H) 1929076.4 722742'.a 311745?3.5
- 17. JRCSS iLECTRICAL E'!ERGY GE::ER ATED (17H) 342047.0 2in75S<.0 1033S966.0
323503.0 2311145.0 9949743.0 19 UlIT SERVICE. ACTOR 70.2 52.5 57.7
- 20. J;;IT A1AILA3ILITY :ACT7R 70.2 53.5 57.7 2I. u.:If CA?ACITY FACTOR (USI'!3 ffDC :iET) 57.9 da.7 35.6 22 J: LIT CA? ACITY FACTOR (USING DER *idT) 55.5 a3.0 54.5
- 23. U: LIT.:2RCED CUTAGE 7 ATE 7.0 2.2 19.9 24 3HUTLJWN5 SCHEDULED OVER 'IEXT $ OFIF3 (T(PE. DATE. A"U JUR ATIJ'1 0F EACH):
- 25. IF SHUIDOP:s AT END OF RE? ORT ?ERIJD, ESTI1!ATED DATE OF STA3T U?:
1/ 7/ 5
- 25. d' LITS I.'! TEST STATUS (PRIOR TO C3:iMERICI A.L GPERATIC'!): FCRC AST AC9EIVED I'lITIAL CRITIC \\LITY
, IdITI AL ELECTRICIT(
CJ.R.ERICIAL OPERATI]M 1.15 - )
ii^4 109
050-0325 DOCKET NO.
UNITSilUTDOWNS AND POWER REDUCTIONS Brunswick #1 UNIT NAME DATE October 1979 COMPLETED BY Eolis A. Willis REPORT MONTil September 1979 TELEPflONE (919)'457-9521
L Licensee
[g f4
.5?
"s
)N'*
Cause & Corrective W.
Date g
3g 4
.g g 5 Event g3 gO3 Action to y:
ji ;g =!
Report a un u Preven Recurrence H
o e
O 018 790908 a
214.9 D
2 11/A ZZ Suport The unit was separated from the grid for pipe hydraulic anubber inspection in the primary containment. Also, repair of the generator hydrogen seals was necessary due to excessive hydro-gen leakage (approximately 15.000 cu ft/ day). The hydraulic anubbers were inspected per PT 19.6.0.1.
The generator hydrogen seals were removed and remachi..ed or replaced as required. Overtime was worked to complete this outage.
O, hl I
2 3
4 F: Forced Iteasini:
Method:
Exhibis G Instructisms S: Scheduled -
A-L quipmen Failure (Explain) 1 -Manual for Preparation of Desa in Mainterunce oi Test 2-Manual Scram.
Entry Sheets fur Licensce C Ite ucting
- 3 Automatic Scram.
Even Repors ILER) File INUllEG-
~
u w
- 1) Itegulaton> lteseriction 4 Other (Explain) 0161)
F-Operanos Ts.siningi Liccuse Examination 5
F Ailm.nistrative G-Operationkl i uns (Explain)
Exhibit I Same Source ps/77)
Il-Oaher (Explain) g
APPENDLX DOCKET NO: 050-0325 UNIT: Brunswick No. 1 DATE: October 1979 COMPLEIED BY: Eulis A. Willis OPERATIONS
SUMMARY
~
BRUNSWICK NO. 1 Brunswick Unit No. 1 operated at a 57.8% capacity factor for the month of September with one major shutdown preventing higher numbers:
September 8 The unit was separated from the grid for 214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br /> and 52 minutes for a pipe hydraulic snubber inspectica in the pri=ary containment.
For more detailed information on this outage see the unit shutdowns and power reductions log (APPENDIX D) included in this report.
Availability factor for the month was 70.2%.
There are 154 PWR spent fuel assemblies and 320 BWR spent fuel assemblies stored in the BSEP 41 spent 62e1 pool.
I APPE:lDIX d AVERAGE DAILY PJeSR LEVEL LCCKET."O. 057-0324
'JNIT 3RU?rs I';< U!!IT 2 DATE 10/01/79 COMPLETEJ 3Y EULI; .'ILLI3 TELEPHC.rE 91->-457-9521 SEPTE::.5ER 7)
JAY
\\V3. DAILY PO?SR LEVEL DAY
\\V3. 7AILY PC'E3 LEVEL (MxE-NET)
U/' tie-:!ET )
I 9.
17 644 2
0.
Id 620 3
0.
19 279 4
0 23 671 5
O.
?!
727.
6 0.
22 101.
7 9
23 434 3
361.
24
$35.
v 522.
25 710.
10 631.
25
- 551, 11 650.
27 709.
12
- 236, 22 743.
IJ Ilo.
29 7 33.
- 4 144.
37 724 16
- 434, io 655.
P00R ORlB!W.
1i44 1i2 i.is - 0
OPERATI.IG DATA REPORT DOCKET '!O. 050-032a DATE 10/01/79 COMPLETED 5Y EULIS MI*.!S TELEPHOiE 9iy-457-952:
GPERATING STATUS
- 1. U.'JI T ;l A.! E BRUT!SWICK UNIT 2 I NOTES I
- 2. REPORTING OERIOD: SEPTE'43ER 79 I
I
- 3. LICE!! SED THERMAL PO'vER (itWT): 2435 I
I 4
.!At.iEPLATE R ATING (GROSS Tr.'E ) : 367.0 I
I
- 5. UESIGN ELECTRICAL RATING (NET 'tWE): 821.0 I
I 5.
..iAX DEPENDABLE CAPACITY (GROSS :.tNE): 315.0 I I
- 7. ' FAX OE?ENDABLE CAPACITY (NET :D.E): 797.0 d.
IF CHA'iGES OCCUR IN CAPACITY RATINGS (ITE'tS 3 THRU 7) SI'!CE LAST 7EPORT, GIVE REASONS:
9.
?.3tER LEVEL TO 't!HICH RESTRICTED IF ANY (:lET '.tME) : NCNE
- 10. REASOIS FOR RESTRICTION IF At!Y:
THIS YR TO CU!dUL
'!ONTH DATE ATIVE I1. HOURS IN DEPORTING PERIOD 720.0 655I.0 34272.0
- 12. NUU.BER OF HOURS REACTOR WAS CRITICAL 558.9 4001.5 23239.a
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.3 14 HJURS '3ENERATOR ON LINE 502.a 3731.9 21861.0
- 15. U:iIT RESERVE SHUT 00?l:I HOUos 0.0
'9 0.0
- 16. GROSS THER).iAL ENERGY GENER ATED ("wH) 911926.7 6957551.0 39495a85.S
- 17. GRCSS ELECTRICAL E?!ERGY GENER tTED ('tNH) 305504.0 2340505.0 13157012.0
- 13..iET ELECTRICI AL ENER3Y GENERATED (?'13H) 293515.0 2239968.0 12623190.0
- 19. UNIT SERVICE FACTOR 69.d 57.0 53.3
- 20. UNIT AVAILABILITY FACTOR 69.6 57.0 63.3
- 21. U'iIT CA?ACITY FACTOR (USING.'fDC ' JET) 51.6 43.3 46.6
- 22. U;1IT CAPACITY FACTOR (USING DER tiET) 49.7 al.6 Lt.9
- 23. UNIT FORCED QUTAGE RATE 13.1 6.9 i3.d 2a. SHUTDOPCIS SCHEDULED OVER !! EXT 6 '.10NTHS (TYPE, DATE, A'ID DUR ATIC'i -': EACH):
REMIELING 80 02 09 1680 hours0.0194 days <br />0.467 hours <br />0.00278 weeks <br />6.3924e-4 months <br />
- 25. IF SHUTDO'titi AT END OF REPORT PERIOD, ESTI'JATED DATE OF STAR T UP:
0/ O/ 0
- 26. UriITS I:I TEST STATUS (PRIOR TO CD.i!.iERICI AL OPERATIC'!): EqoCAST ACHEIVED I?!ITIAL CRITICALITY I'JITI AL ELECTRICITY CJ:.t!.iERICI AL JPER ATIC'i 1.15 - >
pg GlWA ou m
UNIT SilU1 DOWNS AND POWER REDUCTIONS DOCKET NO.
050-0324 UNIT NAME Brunswick #2 DATE 0ctober 1979 REPORT Af 0NTil September 1979 COMPLETED BY Eulis A. Willis TELEPilONE.(919) 457-9521 e.
f e. 5
=u E
=E 2
s
~4 Licensee Eg g"3 t
Cause & Curreceive
\\"-
Dc 3E 4
2s5 Event uv c.
Action to
$5 E
j5y McPo, o
- 0 fu Prevent Recurrence 6
015 790901 S
141.8 D
2 N/A ZZ Suport Separated from grid for pipe suport inspections.and modifications.
Snubber inspection was per Technical Specification 3/4.7.5. All defective snubbers found were repaired and returned to service.
t l
I 2
3 F: Foseed Reason:
4 hicihod:
5 Scheduled A liguipmens Failure (Emp!ain) 1-Manual Exhibit G Instructions for Preparation of Data ll-Maintenance or Test 24fanual Scrarn.
Enity Sheets for Licensee C Re~ochng 3 Automatic Scram.
D Regulatory Hestsiction Event Report (LERI File (NUREG-4 Othes (Esplain) 0161) 1:-Opesalor Trauung & License Examination F Admimsesative G Operasiimal l' arm llaplain) 5 r8177l ll Oiher lihplaini Exhibit I Same Source
-- ^
4
050-0324 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS Brunswick #2 UNIT NA5f E october 1979 DATE Eu11s A. Willis COktPLETED BY REPORT h10NTil September 1979 TELEPilONE (919) 457-9521 w.
!E 3
h' 4 Licensec Es Cause & Corrective 3
Action lo No.
DJ:e i
3E j
.3 ~5 Event
(?
gO
,~i 5 !::
Report a 64 0 Prevent Recurrence jE c2 H
o 1
u 6
016 790907 F
21.5 B
1 N/A CC VALV0P Thd unit was separated from the grid to repair a steam leak in a main steam line drain valve in the Reactor Building. Apparently, a valve travel limit switch fails to operate at the proper setpoint causing the operator mounting bolts to break when the motor continued to run.
This caused a bent valve stem and a steam leak past the valve stem packing. The stem was straightened enough to repack the valve.
The operator will be installed at a later date after a new stem is insta11eu. All main steam drain valves were checked for proper operation on both units. Overtime was worked.
I 2
3 4
Exhibit G. instructions F: Forced Reason:
i.tethod:
S: Scheduled A Fquipment Failure (Explain) 14tanual for Preparation of Data D41aintenance of Test 24tanual Scram.
Entry Sheets for Licensee
~
C.Reiueling 3 Automalie Scram.
Event Repura (LER) File (NUREG-
.p.
D llegulatoo itesiriction 4-Other (Explain) 0161) l' Opeuios Tuining & Ucense Examination 17 Admimstrative 5
G Operational 1:nus (Expl.:ml Exhibit 1. Same Source t'8/77 )
w Il-Olher ( Explain)
UNIT SilVTDOWNS AND POWER REDUCTIONS C T NO' un k #2 A E DATE October 1979 September 1979 COMPLETED BY Eulis A. Willis REPORT MONTil TELEPHONE (919) * ~9 *
!E 3
hE' Licenscc Ev, b,
Cause & Corseelive Dale c-52 4
2s5 Event u '2 Action to S
j@
Ji (55:
Repost #
50 Prevent Recurrence e
u 6
017 790912 F
24.95 B
1 N/A WA Pipexx The unit separated from the grid due to a nuclear service water leak..
The leak was caused by defective cement lining on the inside of a pipe re-ducing elbow exposing the carbon steel pipe to salt water corrosion. The defective cement lining was caused by erosion. The area surrounding hole was ultrasonically tested to assure that the problem was localized. The elbow was repaired in accordance with Approved Plant Modification 79-200.
The defective elbow will be replaced during the next refueling outage. A study is in progresa to determine long-term suitability of all cement-lined piping. Overtime was worked.
1 2
3 4
F: Forced Reason:
Method:
Exhibit G. instaus tions S-Scheduled A l' guipmens Failure (Explain) 1-Manual for Preparation of Data H Maintenance oi Tesi 2 Manual Scram.
Enity Sheces for Licensee
~
C Reincling 3 Aulumatic Scram.
Even Report (LERI File INURE'G.
~~
D Regulatory Ressiiction 4-Other (Explain) 0161) l'-Operator Training & Ucense Examinalion F Admimserative 5
G Operational l' inn (laplaint Exhible i. Same Source t's,7 71 ll Othe Ilhplain)
050-0324 DOCKETNO.
UNIT SliU1 DOWNS AND POWER REDUCTIONS Brunswick #2 UNIT NAhf E DATE October 1979 September 1979 COhlPLETED BY Eulis A. Willis REPORT Af 0NTit TELEPliONE (919) 457-9521 e.
E E
3E
'h j E' 2 Licensee
,E v, g%
Cause & Corrective Date R
?
4
.3 s 5 Event g?
^ ' " " ' "
E U Prevent Recurrence y:
j ;g g Repost a mO P-g 5
018 790914 F
17.1 A
3 N/A IIA Instru The Reactor scrammed from an apparent load reject. The EllC System was checked and the output from an elec-tronic speed converter card was found to be unstable. The card was replace (
from stock and the unit returned to service. Overtime was worked.
I 2
3 4
F: Forced Reason; hiethod:
Exhibit G Instructions S: Sched uled_,
A l'quipment Failure (Explain) 1 htanual for Preparation of Data ll-Maintenance e i Test 2 htanual Scram.
Entry Sheets for Licensee C Reiucting 3 Automatic Scram.
Event Report (LER) File (NUREG-D-Regulator > Resirieijon 4-Osher (Explain) 0161) li-Operator Tra, iing & Liecuse Examination
~
F Administrative 5
. - ^
G Operational 1:: or (lixplain)
Exhibit ! Same Source es/77)
N li-Ot her ( Explain)
e DOCKET NO. 050-0'l24 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Brunswick #2 october 1979 DATE Eulis A. Willis COMPLETED BY REPORT MONTil September 1979 (919) 457-9521 TELEPffONE e.
E E
-, ". !E
- h
$ $ 5' Licensce
[v,
{%
Cause & Corressive W.
Date c-EE i
iE5 Event u9 a.~8 At:sion to F
j@
5 3 ;j, g Report n 650
$0 Preveni Recurrence e
o O
019 790922 S
12.4 B
1 N/A RB Instru The unit was separated from the grid
~
to remove a stuck detector from Channel 7 of Transversing in-core Probe "D".
A slight dent in the tubint caused the detector to stick. The stuck detector was removed and the section of tubing containing the slight dent was removed and replaced.
The system was checked for satisfactor3 operation. Overtime was worked.
1 I
2 3
4 F: ForceJ Reason:
Method:
Exhibit G Instructions S: Schedtded A.figuipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram-Enity Sheets for Licensee C Retueling
- 3 Automatic Scram.
Event Report (LER) File (NUREG-
~
s A
D-Itegulator) Itestriction 4 Other (Explain) 0161) 150peratus Trainmg a License Examination F-Adminntrative 5
G-Operational II:sur (Explain)
Exhibii ! Same Source p#/77) m Il-Olher ( Explain)
APPENDIX DOCKET NO: 050-0324 UNIT: Brunswick No. 2 DATE: October 1979 COMPLETED BY: Eulis A. Willis OPERATIONS
SUMMARY
BRUNSWICK NO. 2 Brunswick Unit No. 2 operated at a 51.6% capacity factor for the month of September. The following changes and shutdowns occurred during the month:
September 1 Separated frem grid 141.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at the beginning of the month for pipe support inspections and modifications.
September 7 The unit was separated from the grid for 21.5 hcurs to repair a steam leak in a main steam line drain valve.
September 12 The unit was separated from the grid for % 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> for a nuclear service water leak.
September 14 Reactor scram from an apparent load reject. Off line time 17.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> September 22 The unit was separated from the grid for 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to repair a "TIP" machine.
Monthly availability factor was 69.8%.
There are 132 BWR spent fuel assemblies and 70 PWR spent fuel assemblies stored in the BSEP #2 spent 62el pool.
i144 ii9