ML20137L009
Text
. - -. .. . . - - _ - _ - . - . . .. - . _ . . - - _ - - - - . . - - . . - _ . _ , .- -
,. PAGE 1 OF 7, i
i ST. LUCIE UNIT 1 4 .
ENGINEERING EVALUATION I
IMPACT OF PAST INCORRECT CALIBRATION OF THE S/G LEVEL TRANSMITTERS ON THE LOW S/G LEVEL TRIP SETPOINTS FOR RPS l
4 JPN PSL-SEIP-96-067 REVISION O i
! SAFETY RELATED i
FLORIDA POWER & LIGHT COMPANY JUNO BEACH, FLORIDA i
ffAnn a . . .
g Jy40;gjj7'97o32s BINDER 96-48s PDR
- ...-PS*.-SEIP-96-067
Revision O Paga 2 of 7 i,
~ ~ -
REVIEW AND APPROV5ENCORD F1.AMT St Lucie Plant UNITS 1 TITLE Imoact of Past Incorrect Calibration of the S/G Level Transmitters on the Low S/G Level Trio Setootnt f or ItPS I
< a l LEAD DISCIPLINE PSL PEG IGC ENGINTERING _
l EwGINEERIwG ORGANI1ATIOw FPL - IGC ENGINEERING i REVIEW / APPROVAL PREPARED VERIFIED APPROVED FPL OROUP INTERFACE TYPE APPROVED
- Iaput Rerww NA unca w/A N/A w/A w/A w/A l
EIacT w/A w/A w/A w/A w/A Isc LsAD gj gM6 ggs ;, w/A CIVIL w/A w/t w/A h/ A' " w/A
~
wuc rEs w/A w/A w/A
)
EsI w/A N/A w/A D/A w/A wuc rEs w/A w/A CfJ/h
- Q >
w/A FUEL '
STAFF w/A N/A w/A N3 w/A
- For Contractor Ivals as determined by Projects
- Review Interface as a min on all 10 CFR 50.59 Evals and PLAs TPL PROJECTS APPROVAL: DATE: 22/94 OTHER INTEAFACES:
. F x u .m ru> wt.= m s?
JPN-PSL-5El?-vb-Lul
- Revicien o Pcgo 3 of 7
_ _ . . _ _ _ _ . TABfI OF CONTENTS ._
SECTION TITLE PAGE Cover Sheet 1 Review and Approval Record 2 l
Table of Contents 3
1.0 Purpose and Scope
4 2.0 Safety Classification 4 -
1 3.0 Evaluation 4 4.0 Verification Summary 6 5.0 Conclusions 6 i
6.0 References 7 ATTACHMENTS :
- 1. Error Determination (6 pages)
- 2. Uncertainty Analysis (1 pages)
- 3. Error Analysis (4 pages) 4 S/G ' Hot' Dimensions (2 pages) l
- 5. Reactor Protection System Monthly Functional Test Completed Data (1 page) k F1LDe AML W t ?
a rre-rn-s e.s c- s o vo s
- - Raviolen o Pag 3 4 cf 7
+
1.0 PURPOSE AND SCOPE The purpose of this evaluation is to assess the past impact from the incorrect calibration of the Unit 1 S/G level tnnsmitters on the low S/G level trip setpoint for RPS. 'Ihe evaluation will determine the magnitude and direction of the past error introduced, and the relative impact on the Tech. Specs. and/or analytical limit for the following' transmitters.
Tar No. Function LT-9013A,B,C,D RPS LT-9023A,B,C,D RPS 2.0 SAFE'IY CLASSIFICATION This engineering evaluation involves the review and evaluation of instrumentation required for the safe operation of the plant, including the Reactor Protection System (RPS). Since the RPS is designed to mitigate the consequences of design basis accidents, this evaluation has been classified as Safety Related.
3.0 EVALUATION 3.1 Error Determination
'Ihe determination of the error for the past calibration of the S/G level transmitters is based on the methodology and data from FPL calculation PSL-1FJI-93-013 (Ref.1). In addition, downcomer density effects are also included consistent with the original CE calculation (Ref. 3). Attachment 1 provides a summary of the input data, formulas, and results along with a sample calculation.
For the purpose of this evaluation operating / reference plant conditions were based on operation at 850 psia, consistent with the CE Calculation. The downcomer density effect is also included based on the CE Calculation which maintains consistency with the original methodology and has no adverse effect on the evaluation. S/G thermal growth was not l considered since excluding it produces conservative results in that additional S/G volume would be present, but not taken credit for. ' Itis again maintains consistency with the l original methodology in order to provide a consistent reference for the comparison of the results. S/G dimensions, however, were based on the S/G as built drawings, while the condensate pot heights were based on Plant walkdowns per the FPL Calculation (Ref.1).
'Ihis overall approach addresses the mconsistencies encountered during the preparation of the FPL Calculation, while maintaining a consistent, yet acceptable methodology in determining the error of the existing transmitter calibrations. j l
Other parameters, such as a reference leg temperature of Ill'F (Ref. 6), were based on more representative Plant conditions so as to not build to much conservatism into the msults, since the results will be used to assess plant operability in the past, not~ operation in the future. .
f1D* 4ML ab4t* t '
i l
- JPN-PSL-SEIP-96-067
.. Revisien 0 Pegs 5 of 7 l 3,2 14op Uncertainty Analysis
~-
Attachment 2 provi the Total Loop Uncertain [(TLU) determination for the SIG level transmitter and bistable for the S/G low level RPS trip function. The TLU in combination with the calibration error determined in section 3.1 provides the necessary data to determine if the S/G low level protection function may have been outside the Technical Specifications and/or analytical limit. Since the setpoint of interest is S/G low level and is a decreasing setpoint, the SRSS Single Sided Approach will be applied (Ref.10).
~
The TLU determination was prepared in accordance with FPL Standard No. IC-3.17 (Ref.
.. 10). .
3.3 EaTor Analysis I
The Error Analysis, included as Attachment 3', evaluates the effect of the calibration error {
and Total Loop Uncertainty (Transmitter / Bistable) in combination with the auctioneered i S/G level transmitter input on the current Plant setpoint of 21% S/G level.
The use of the current Plant setpoint for the analysis is acceptable based on sample data obtained from QA records for " COMPLETED' monthly functional tests of the Reactor Protection System S/G low level bistables. De data, included as Attachment 5, documents the as-found settings for 11 months of Technical Specification monthly functional tests in accordance with Plant procedure 1-1400050. Based on the functional test data, the RPS bistables were always within the tolerance specifications of the procedure for all 4 channels for each steam generator. However, the least conservative value (-1.830 volts) of any channel documented during the surveillance periods reviewed would have yielded a setpoint of 20.75%. His deviation would normally be attributed to instiument drift, accuracy, setting tolerance, and/or M&TE cffects which have been accounted for in the error analysis. Therefore, use of the nominal setpoint in lieu of a more conservative value such as the Technical Specification Allowable Value is acceptable based on the data presented.
ne Error Analysis treats the calibration error as a bias, with magnitude and direction, ,
i about the 21% S/G level setpoint, ne magnitude and direction of the calibration error has been determined in Attachment I and is presented as the % level deviation from true level to the indicated level when true level is 21 %. Total 1. cop Uncertainty is then applied to the indicated level to establish an uncertainty band. The S/G level transmitter inputs are paired by S/G channel (i.e., LT-9013A,9023A; LT-9013B, 9023B; etc.), then auctioneered (low select) by the S/G level channel. His ensures that the. lowest of each of the channel pairs is selected as the bistable input for that channel of the logic matrix.
. De Error Analysis (Attachment 3) documents the worst case auctioneered level for each '
channel pair and ultimately whether the trip function may have occurred outside the Technical Specifications and/or the analytical limit.
l
JPN-vbL-SEIP-ve-vos !
- R:vicien o l Pcg3 6 of 7 (
4.0 VERIFICATION
SUMMARY
l
~
This engineering evaluation identifies an error in Ae past calibration of the S/G level - ~
transmitters for Unit 1. ne impact of this error on the RPS setpoints has been evaluated
~
for the subject instruments.
This engineering evaluation was reviewed to ensure that the overall conclusions met I '
applicable requirements. De criteria and design inputs required to evaluate the results were adequately described, reasonable, and appropriately identified for subsequent reverification.
~
De rationale provided in assigning the safety classification for this evaluation was I verified. His engineering evaluation has been correctly specified as Safety Related. I 1
5.0 CONCLUSION
S 1
ne FS AR (Ref. 7) specifies an analytical limit of 17.5 % for the low S/G level RPS trip.
The results of the Error Analysis calculated in Attachment 3 are summarized in the following table.
Table 5-1 RPS Channel A B C D Transmitters LT-9013A/ LT-9013B/ LT-9013C/ LT-9013D/
(SG 1 A/SG IB) LT-9023A . LT-9023B LT-9023C LT-9023D l 1
Calculated Trip 17.2 % 17.9 % 17.8 % 17.5 %
(Attachment 3)
Analytical limit 17.5 % 17.5 % 17.5 % 17.5 %
ne RPS logic for low S/G level uses a 2-out-of-4 trip logic. The S/G level inputs are l paired by channel then auctioneered (low select) by each S/G level channel nis ensures l that the lowest of each of the channel pairs is selected as the bistable input for that i channel of the logic matrix. However, based on a worst case scenario', that is with the !
best channel (B) bypassed and the next best channel (C) inoperative due to a single failure, it is theoretically possible with the above results to violate the analytical limit of 17.5% as a result of the error associated with channel A. As the logic is 2-out of 4,it would take both the A and D channels to produce a trip, and the A channel portion of the logic would not occur until 17.2%,0.3% below the analytical limit.
' However, as described earlier in section 3.1,6e error determination and analysis do not take into account steam generator thermal growth and therefore there is available margin due to the increase in steam generator height between the tube sheet and the RPS trip etpoint of 21%. Based on Attachment 4 (S/G Hot DimensionyRef,1) and Attachment 1, Figures 1 & 2 (S/G Cold Dimensions /Ref.1) there is an available margin of approximately 1.1 inches due to S/G growth. De 0.3% S/G level deficit for RPS channel rw oa e .
_ . _ . .m.. _ __. - - _ _ _ - _ _
J PN - P r.,L,- S E I F - 9 6-0 6 7 j I*
- Rovielen o 1 F g3 7 of 7 i
A equates to approaimately 0.55 inches. Based on the available margin of 1.1 inches due 15'5/GTrowth@ deficit of-0:55-inchesem beaccommodated with a balance of_l
, i inches margin remaining. Since RPS channels B, C, and D do not exceed the analytical )
j limit and the RPS A channel has available margin due to S/G growth, it can be concluded I that the incorrect calibration of the Unit i S/G level transmitters would not have caused i the Plant to operate outside the analytical limit for the RPS trip on low steam generator level. Additional margin wod 3 also be available in the Rosemount seismic uncenainty l j 1 specification.
6.0 REFERENCES
- 1. FPL Calculation PSL-lFJI-93-013, Rev.1, S/G 12 vel Transmitter Calibrated j
Range.
- 2. Procedure 1-1400153A, Rev. 7, RPS - Loop Instrumentation Calibration of S/G 12 vel.
- 3. CE Calculation 19367 ICE-0613-00, S/G Level Measurement.
4 Condition Report No. 96-1532.
- 6. FPL Calculation PSL-BFJI 92-003, Rev. 2, Environmental Parameters for Instrument Uncenainty Analysis.
- 7. St. Lucie Unit 1 Updated Final Safety Analysis Repon, Amendment 14, dated 6/95.
- 8. St. Lucie Technical Specifications through Amendment 145.
l
- 9. '"Ihe Crane Companion (Ver.1.0) dated July 11,1996.
- 10. Discipline Standard No. IC-3.17, Rev. 5, Instrument Setpoint Methodology for I Nuclear Power Plants.
- 11. Master Work Orders, Reactor Protection System Monthly Functional Test IC 1 1400050. !
94031609 01 95014446 01 95001633 01 95018408 01 95004267 01 95024416 01 95007698 01 95027227 01 95010826 01 95029174 01 95032706 01 F1Li% G4L at.os's *,
JPfd PSL4DP 96-067 RtvisioN O ATTAcMutNT 1 PaGE 1 oF 6
- - - - - - - - ._ _ _ . _ _ ERROR DETERMINATION _ __. __ _____ _ __ _
BACKGAOLTDt The exieting level trane'mitter calibration data contained in I&CItProcedure appears these values 1-1400153A (Ref.2) is based on CE letter F-$F-1086 (Ref. 5) .
were developed using the methodology contained in CE Calculation 19367-ICE-0613-00 (Ref. 3) for the following conditions.
-S/G Operating Pressure = 850 psia
-8/G Saturation Tessperature = 525.24*F
-Reference Leg Temperature = 120*F G 850 psia
-Feedwater Temperature = 435'T 4 850 psia (p, = $2.32 lb/f t')
" -Downcomer Density (pe) = 48.65 lb/ft ,
-Circulation Ratio (CR) = 4.2 6 100% Power
-Calibration Reference = Inches of H O 4 68'T (Ref. 5)2
-S/G Thermal Growth = Not Included Based en the CE Calculation (Ref. 3), the S/G dimensions were obtained from the S/G General Arrangement & Assembly Drawing, 233-601, Rev. 4, and The not the S/G reference for the as-built drawinge utilized in the FPL calculation (Ref. 1).
condensate pot elevations used f or the final CE calibration data (Ref. 5) is unknown.
In addition, S/G growth ef f ects were not included based on operating conditions at het full power, and therefore are based on S/G dimensions at '* COLD" conditions and S/G process at " HOT" conditions.
The purpose of the ERROR DETERMINATION is to establish the magnitude and direction of the past error introduced from the incorrect calibration of the Unit 1 5/G 1evel transmitters on the low S/G 1evel trip setpoints for RPS.
FORMULASI Differential Pressurer (Ref. 1)
AP u,, = ( (H + L)po)
- [(H + L) pal APm = ((L)po + (H - D)pg + (D)pe) - [ (H + L) pal APva = [(H + L - d)po + (d) pe) - [(H + L) pal l where, APa = Delta-P G the min. operating level, lb/ft*
APm = Delta-P G the max. operating level, ib/ft' AP. ,a = Delta-P G variable operating level below feed-ring, ib/ft' H = 5/G Narrow Range tap to tap dimension, ft L = S/G Narrow Range upper tap to ecndensate pot dimension, ft D = Downecaer dimension (L f eed-ring to lower tap), ft d = Variable downcomer level below f eed-ring, 'f t po = density saturated steaa 9 850 psia, 1b/ft va = density reference leg fluid 9 850 psia /111*F, ib/ft' pg = density saturated liquid 6 850 psia, lb/ft' ve = density of downecoor liquid t 850 psia, Ib/ft' povneccer Oensitv t (Ref. 3)
- c = f(CR-1)pt + p,)/CR where, pc = density of devnecoer liquid 6 850 psia, Ib[f t' )
ib pt == density densitysaturated liquid4 6850 of f eedwater 850psia, psia,Ib/ f t' / f t l
- , i CR = Circulation Ratio of 4.2 010C% Pcwer See Figures 1 & 2 of this Attachment for S/G dimensions at cold l Note
- !
conditions. i f
rw at sm v i I
JPN PSL SEIP 96-067 Revision 0 ATTACHMENT 1 Pact 2 or 6
- - ._. INPtFf DATA 1 _ _ _ ,
TARLE 1-1 (All dimensions are given in feet unless noted otherwisei TRANSMITTER H L D ds2i LT-9013A 15.24 1.96 6.0075 3.20 LT-90133 15.24 1.93 6.0075 3.20 LT-9013C 15.24 1.90 6.0075 3.20 LT-9013D 15.24 1.81 6.0075 3.20 LT-9023A 15.18 1.57 5.967 3.19 LT-90238 15.18 1.58 5.967 3.19 -
LT-9023c 15.18 1.72 5.967 3.19 LT-9023D 15.18 1.99 5.967 3.19 NOTE: 1. Dimensions based on Figures 1 & 2 of this attachment.
TABLE 1-2 l STEAM CENERATOR 1A & 1B PROCESS CONSTANTS l Calibration Reference Density (p.) 6 68'T 62.321 lb/ft' Reference Lag Density (pe) 0 111*F/850 psia 61.95 lb/ft' S/G Liquid Density (pt) 9 850 psia 47.505 lb/ft' S/G Steam Density (pa) G 850 psia 1.876 lb/ft' Feedwater Density (p,) t 435'F/850 psia 52.32 lb/ft' Downconer Density (pe) 48.65 lb/ft' Circulation Ratio (CR) 0 100% Power 4.2 SAMPLE CALCULATION:
Steam Generator 1At (LT-9013A)
AP, =
((15.24+1.96)1.876) - [(15.24+1.96)61.95) = -1033.27 lb/f t' or
=
(-1033.27 lb/f t') x (1 f t'/144 in') = -7.176 lb / in' o r -7 .17 6 e s i APm =
((1.96)1.876 + (15.24 - 6.0075)47.505 + (6.0075)48.65)
[(15.24+1.91)61.95)
= -331.01 lb/ f t' or (-331.01 lb/ f t') x (1 f t'/144 i n')
= d .299 lb/in' or -2.299 esi APris = ((15.24 + 1.96 - 3.20)1.876 + ( 3. 2 0 ) 4 8. 6 5) - ( ( 15,. 2 4 + 1. 9 6 ) 61. 9 5 )
= -883. 60 lb/ f t' or (-883.60 lb/ f t') x (1 f t*/144 in')
= -6.136 lb/in' or -4.136 osi runun. m.r = e
JPN PSL SE1P 964.-
REvtssoN' O ATTACHMENT 1 l PAGE 3 or 6 l l
_.. steam cenerator 131_(LT-9023A) - - - - .
j
. APm = [(15.18+1.57)1.876) - [(15.18+1.57)61.95) = -1006.24 lb/f t' or
= (-1006.24 lb/f t') x (1 f t'/144 in') = -6.988 lb/in' or -6.988 est i APm = ( (1. 57)1.876 + (15.18 - 5.967 )47. 505 + (5.967 ) 48.,65 ) - [ (15.18+1. 57 )61.9 5 )
= -306.76 lb/f t' or (-306.76 lb/f t')
s x (1 f t*/144 in') j r
-2.130 lb/in or -2.130 esi I APa,
[(15.18+1.57)61.95)
= -857.03 lb/f t* or (-857.03 lb/fx t')[
s
( 15.18 + 1. 57 - 3.19 ) 1. 87 6 + ( 3 (1 ft ,
= -5.952 lb/in or -5.952 esi
~ Plant calibration will be performed using, test gauges calibrated in in. Hp 9 68'F.
Therefore, conversion free psi to in. Hp $ 68'r is required to be consistent with Plant conditions. The conversion factor, in in. Hp ,/ psi, is 27.727 in. E A .,/_p.gi (Ref 1).
Using the conversion facto. and the 6Pa , 6Pm, and 6Pis values for Steam Generators 1A and 18, the actual AP and span can ~be determined in in. Hp $ 68*T and are presented in the following table.
TABLE 1-3 ACTUAL AP Span ACTUAL AP 6Puu, (in. I0.*,) 6Puu (in . Ep.*,) (in. Ep.*,) 6P 3 . (in. E,0..,)
2
-199.0 -63.7 135.2 -170.1 LT-9013A LT-90133 -198.6 -63.4 135.2 -169.8 LT-9013C -198.3 -63.0 135.2 -169.4 LT-9013D -197.2 -62.0 135.2 -168.4 LT-9023A -193.8 -59.1 134.7 -165.0 LT-90238 -193.9 -59.2 134.7 -165.2 LT-9023C -195.5 -60.8 134.7 -166.8 LT-9023D -198.6 -63.9 134.7 -169.9 l
1 I
I ru>aut. ma ss,
sPN PSL blip Sb-Vo /
"
- Revision O -
ATTACHMENT 1 Pact 4 or 6
, . _ . . _ _ _ _ . RESULTSt- - _ _ _ _ _ _ _ _ _ __ ~
The RzsULTS section compares the above ACTUAL APais for the 21% S/C level setpoint to the transmitter calibrated AP for the 21% S/G 1evel setpoint to determine the % Irror in 4 S/G 1evel for each transmitter. See Ref erence 2 for transmitter calibrated AP.
TABLE 1-4 i
Level S/G s/G Dim. Signal Xmtr. Cal. Actual Error
% Level, Level in. mA AP AP Transmitter in. HA. ,
% in. Hp..,
1 I
100 182.88 20 -65.1 -63.7
~
38.40 7.3) -174.0 -170.1 +2.8 e 21 0 0.00 4 -202.9 -199.0 100 182.88 20 -64.1 -63.4 LT-9013E 38.40 7.36 -172.6 -169.8 +2.1 f 21 0 0.00 4 -201.5 -198.6 100 182.88 20 -64.2 -63.0 LT-9013C 38.40 7.36 -172.9 -169.4 +2.5 21 0 0.00 4 -201.8 -198.3 l
100 182.88 20 -63.1 -62.0 LT-9013D 38.40 7.36 -171.8 -168.4 +2.5 21 0 0.00 4 -200.7 -197.2 100 182.16 20 -61.7 -59.1 LT.9023A 38.25 7.36 -169.9 -165.0 +3.6 21 0 0.00 4 -198.7 -193.8 j 100 182.16 20 -60.0 -59.2 LT-90238 38.25 7.36 -168.2 -165.2 +2.2 21 0 0.00 4 -196.9 -193.9 l l
182.16 20 -61.5 -60.8 100 LT-9023C 38.25 7.36 -169.7 -166.8 +2.2 21 0 0.00 4 -198.5 -195.5 182.16 20 -65.9 -63.9
- 100 LT-9023D 38.25 7.36 -174.1 -169.9 +3.0 21 0 0.00 4 202.8 -198.6 Wote: The terror value indicates the deviation f rom true level to indicated level when true level is 21%.
nte..x1_ w u
JPN v3L SElP 96G7 REVISION O j l ATVACHMENT 1 !
Pact 5 of 6 l ,
- '~~ ~- --
STEAM OENERATOR 1A l
j COLD CONDm0NS i
i Conderwta i LT 4013A shown.
P88
! See Tatdo 19er LT pet etevedons.
79.54 h' j ,
}
! '~ L 77.07 -~~- . . . . . . . . . . . .
A o.v. '
@)
rm * ,
i H
...- .Y . . . .
! U*V. p
- dm y l 62.36* . . _ . . . . . . . .. .
4
' i LT P P H L 614.8*
503.81*
I i
37.2r ' ~ '
Top of Tube j g, Sheet ,
t 84'P*'t ! I
'M Base at _ . . . ._ _I_ . .. .f.
- 3ev. g TABLE 1 LT ri n LT-9013A 79.5s LT-90138 79.5:r LT-9013C 79.5CT LT90130 79.41'
' Figure 1
- w. - - . ,
- . . ~ . - _ - . . . . - - - . . . - . . . . . . - . - - . _ . . - -..- ____- - ____________ _ _____
i JPN PSL d LW e t>-vo / l 4 .
REv1SION 0 AWACHMENT 1 Pact 6 of 6 l, j
,i
. - - _ _ _ . . _ . ~~ - - - - - - ..----_--. __
\
l _ _ _ _ _ _ __ _ _
STEAM OENERATOR 1B _
COLD CONDmONS i
j i
N !
! LT 9023A shown. M yg,yg. See Tetdo 1 tor LT pot elevations.
f k ,
l -
N. .
77.80' ~~- f,A l
- osv. '
(>5t)
' I h l Feedring l H I
~T
! 1 l i 6 Lev ..I O I Uct. dm y~
g g. 0% Level (NR)
Dev.
} '
}
4 .
LT i j P P
, H L l l $1L5' I
! sas.u-i
' i d
l l
! ! l f
'4 I
! 37.2r ~
TopofTube
- g, W i .
i
. M I W . . . . . . .
Base at . I .. .. ._. _. . I .. _
Dev. @ TABLE 1 LT F1 EV.
LT 9023A 71.14' LT.90238 79.17' LT 9023C 79.31' LT 90230 79.$r i ,
l-'
Figure 2 FIL% udL W t *1
JPN PSL SEIP 96 067 REVISION 0 ATTACHMENT 2
+
Uncertainty Analy$is PAGE 1 OF 1 ANALYSIS OF ST. LUCIE UNIT 1 SG NARROW RANGE INSTRUMENT UNCERTAINTY I .
~
I i l RPS Bistable SG Lvl Xmtr
% SPAN Ref. % SPAN Ref.
Accuracy 0.125 A 0.25 8 M&TE 0.125 A 0.35 B Set . Tot. 0.25 A 0.25 0 :
Drift 0 25 A 0.17 8
, Temp. Effect 0.25 A , 0.42 8 Static Press. Effect 0 A 0.65 8 Seismic 0 A 0.58 8 SRSS 0.468 C 1.101 C SRSS Total Uncert. (B/S & LT) 1.196 C !
i l
SRSS One Sided Approach 1.00 C e 1 l
Ref. A) ABB,CE Cak:ulaton 19367-ICE.36308. Rev 0 SI Lxe Unit 1 RPS ESF and AFS Setpo.nts and AScwabie Values {
Ref. 8) FPL Calculation PSL.1FJi-93-002. Rev 1. St Luce und 1 RPS. AFAS $!eam Generator Downcomer Levet Tranunmer Uncertarey Ostermnataan (LT 901173A.B.C.D)
Ref. C) Desco ris r Standans IC-3.17. Rev. 5. Instrwnent Setport Methodology for Nuclear Power Plants : 1 Ref. D) W =e 1 1400153A. Rev. 8. RPS - Loop instrumertaban Cahbrwon of S/G Level. '
I i
i l
l i
l Ce 96-067 x!$
JPN.PSL.SEIP.96-067 REVISION 0
. ATTACHMENT 3 PAGE 3 OF 4 ERRORANALYSIS_ .-
ERROR ANALYSIS OF ST. LUCIE UNIT 1 SG NARROW RANGE LEVEL RPS Channel C LT.9013C LT 9023C Error (% of Span) 2.5 2.2 (See Attachment 1)
Indicated Level @ 21 % 23.5 23.2 l Total Loop Uncertainty is +/- 1 (See Attachment 2)
, + Uncertainty 24.5 24.2 ,
Indicated Level @ 21 % 23.5 23.2
- Uncertainty 22.5 22.2 24.5 24.2 A SG B SG 22.5 l 22.2 l
l 1
l l
l Compare both levelloops by selecting the lowest value when levels are at theirlowest and highest values.
SG A SG B Auctioneered Lowest Value 3 Lowest 22.5 22.2 22.2 Highest 24.5 24.2 24.2 max A Highest /B Lowest 24.5 22.2 22,2 A Lowest /B Highest 22.5 24.2 22.5 Worst Case Auctioneered Levelis 24 2 %
when True level is 21%
Worst Case Error 32 %
Calculated Trip Point 17.8 %
i Analytical Limit 17 5 %
i f.!e 95 067 xis
JPN PSL SEIP 96-067 REVISION 0 ATTACHMENT 3 PAGE 4 OF 4 i ERROR ANALYS!S ERROR ANALYSIS OF ST. LUCIE UNIT 1 SG NARROW RANGE LEVEL RPS Channel D LT 9013D LT 9023D Error (% of Span) - 2.5 3 (See Attachment 1)
Indicated Level @ 21 23.5 24 Total Loop Uncertainty is +/- 1 (See Attachment 2)
.- + Uncertainty 24.5 25 1
Indicated Level @ 21 23.5 24 l
- Uncertainty 22.5 23 25 l
24.5 B SG A SG 23 22.5 Compare both levelloops by selecting the lowest value when levels are at their lowest i and highest values.
1 SG A SG B Auctioneered Lowest Vatue Lowest 22.5 23 22.5 Highest 24.5 25 24.5 max A Highest /B Lowest 24.5 23 23 A Lowest /B Highest 22.5 25 22.5 Worst Case Auctioneered Levelis 24.5 %
when True Level is 21%
Worst Case Error 35 %
Calculated Trip Point 17.5 %
Analytical Limit 17.5 %
i file: 96-0671s
. .__ - -- . . . - .~
(.
!. JPN-PSL-SEIP-06-067 l
REUISZOM O l
ATTACHMENT 4 PACE A OF 3 l l . I i
! STEAM OENERATOR1A
! HOT CONDmONS l l
LT4013A shown. @ndensato See Telne _1 forLT gotelevations P'I I Elev. '
L 77,77 - - . . . . . . . . .
Elev. @R) l j Refersnce .
! L*9 I
i H I
~
65Af .,} .
Elev, dm 62AF ~J 0% Lavel(HR)
Elev.
P P Tou t
, H 1 LT ELEY.
LT4013A 71L5s LT40138 79.53' LT4013C 79.5&
LT40130 79A1'
~ ~
37.2f Top of Tube Elev. Sheet Support Skirt (Growth Point) a ___.i # sue of Elev.
t Y
e
. . . - . . - . . . ~ . - - - , _ - - ~ ._ . . - --. - - --_- . -.__-. _.._.. --_ -. _ - ~ ____.
i JPH-PSL-SEIP-96-067 l
REVZS80N O ATTAC10ENT 4
' PAGE 3 OF 3 i ~~ - - - - - _. _.- _ ,_ _ _ , ,_
STEAM OENERATOR1B f
HOT CONDmONS
~
l 1
I l LT 4023A shown.
M SeeTatdo1ter LT potelevadons -
l i
73,1g* ) _
Elev. ?
l -
pL i TI M g ~ ~~ 100% Level Elev. (NR)
Reference Lag e
i H
ss n .L Ek y. dn J' 0% Level (NR) j 82.53' 1 Eky.
i L- L i
H I T j 'l TABLE 1 . , _
1 LT I ELEY.
i -
i LT-9023A 79.18'
{ LT 90238 73.1 7 (
l LT 902SC 79.31'
{ LT 90230 79.58' 6
i l
37 M
' - ^ "
Top of Tube l
Sheet
. Elev.
i
. Support Sidrt '
(Growth PobQ
> - c.
N Elev.
l l
Fireud. e6m'? tt
. - JPN-PSL-ADIP-96-057 REVISION O ATTAC) DENT 5 PACE 1 OF 1
-____ _ _ __.-Reactor- Protection System _
Monthly FunctlOnal Test Completed Data .
The following information represents 11 months of data obtained from PSL QA Records for
- COMPLETED" monthly functional tests of Plant Procedure 1-1400050'(Ref. 11) for the Reactor Protection System steam generator low level bistables. The bistables have a nominal setpoint of -1.840 volts (221%) with a tolerance of -1.830 to -1.068 volts.
$ The work orders for the functional tests required that any out-of-tolerance readings were to be reported to the IcM supervisor, and that the AS-FOUND and AS-LEFT values
- were to be recorded in DATA SHEET 1 of the procedure. No data was entered in DATA e SHEET 1 for the surveillance periods listpd below nor was there any evidence of any adjustments based on the journeymans report. Therefore, the voltage values are considered AS-POUND readings per step 7.2 of the procedure.
i
== w suavEII.u xes srzAu I enAxxxL PERIOD GE N TOR
& 3 C D 4
1/95 1 -1.847 -1.843 -1.855 -1.845 2 -1.853 -1.838 -1.850 -1.848 2/95 1 -1.854 -1.836 -1.857 -1.847 2 -1.843 -1.843 -1.857 -1.841 3/95 1 -1.866 -1.843 -1.863 -1.850 2 -1.865 -1.842 -1.858 -1.851
' -1.847 -1.848 -1.860 4/95 1 -1.853 2 -1.854 -1.838 -1.848 -1.840 5/95 1 -1.855 -1.843 -1.857 -1.846 2 -1.84% -1.839 -1.851 -1.b40 6/95 1 -1.846 -1.839 -1.857 -1.849 2 -1.856 -1.842 -1.848 -1.847 7/95 1 -1.861 -1.840 -1.858 -1.835 2 -1.855 -1.833 -1.851 -1.342 _
-1.860 -1.835 -1.860 -1.557 9/95 1 2 -1.862 -1.840 -1.866 -1.847
-1.860 -1.842 -1.850 -1.830 10/95 1 2 -1.860 -1.841 -1.850 -1.844
,11/95 1 -1.855 -1.841 -1.852 -1.851 2 -1.845 -1.837 -1.841 -1.840 12/95 1 -1.853 -1.847 -1.861 -1.843
-1.858 l -1.842 -1.s51 -1.e42
,m - ,,
,. PC/M 96 -
119 Revision 2 4
Page 1 of 4 HINOR-ENGINEERING-PACKAGE-(MEP)-----
PLANT St Lucie UNIT 1 PC/M NWBER 96-119 SUPPL 2 ORIGINATING DOC &iENT EXPIRATION DATE N/A PC/M CLASSIFICATION X _ SR . QR NNS ADMIN TITLE Setpoint Chance for AFAS ADDITIONAL REQUIREMENTS / INSTRUCTIONS YES NO AS-BUILDING TO C0ttENCE UPON ISSUANCE OF PACKAGE? X
, THIS PACKAGE FAS THE POTENTIAL TO SIGNIFICANTLY X IMPACT PERSONNEL RADIATION EXPOSURE (See Form 71).
IF YES, FORM 72 15 REQUIRED.
, 10CFR50.59 SCREENING YES NO
- 4) COULD THE CFANGE AFFECT NUCLEAR SAFETY IN A WAY NOT PREVIOUSLY EVALUATED IN THE SAR? X
- 5) DOES THE CHANGE REQUIRE A CHANGE TO THE TECHNICAL SPECIFICATICNS? X F;rm 131. :ev 6!9. DGe 10' 3
PC/M 96 -
119 Revision 2 Page 2 of 4 ,
NOTE: IF THE ANSER TO ANY OF THE ABOVE IDCFR50.59 SCREENING OVEST10NS IS YES. THE KP CANNOT BE USED REVIEW / APPROVAL:
INTERFACE TYPE GROUP PREPARED VERIFIED APPROVED FPt. APPROVED
- INPUT REVIE N/A ummmmmmmmmmm mummmmmmmmmmmmmmus---
Fech X ELECT X I&C X civil X NUC" Lead M)fM _%
- g [#MA ;
ESI X k NUC FUEL X
- For Contractor KPs As Determined By Projects " Review Interface As A Mininun Ch All Non Adnin KPs i
FPL PROJECTS APPROVAL: [A/ DATE: d//Vfc i
l l
l l
l I
~
r -
PC/M 96- -
119 Revision 2 Page 3 of 4
_.__ENGINEERINGJUSTIFICATION.__ -
This Minor Engineering Package (MEP) provides for an increase to the S/G level trip setpoint at which AFAS actuation will occur. The new setpoint will be 24.5%
narrow range level. This new setpoint will conservatively bound the uncertainties associated with differences between the "as found" and design S/G instrument level tap elevations.
~
Revision 1 to this MEP includes the verified walk down elevation data (Attachment 1) that confirms the new setpoint as conservatively bounding the uncertainties associated with differences between the "as found" and design S/G instrument level tap elevations.
Revision 2 to this MEP clarifies the FSAR update error regarding the setpoint value for AFAS actuation.
Technical Specifications Tech Spec LCO 3.3.2.1 provides for the AFAS trip setpoint to be greater than or equal to 19.0% and the allowable value to be greater than or equal to 18.0%.
FSAR The limiting analysis with respect to AFAS actuation is the loss of feedwater analysis described in Section 10.5. This analysis bounds Chapter 15 events. In this analysis. the assumed AFAS trip setpoint_is 15.3% S/G narrow range level.
This analysis value includes all necessary uncertainties.
Evaluation The limiting transient for determining the AFAS setpoint is the loss of feedwater
, event. In this event the concern is the loss of secondary side heat sink. AFAS actuation at or above the setpoint presented in the FSAR will ensure that S/G dry out does not occur. Note that this transient is analyzed for Mode 1. full power operation. For Modes 3 & 4. where this re.v setpoint will be in effect, substantial additional margin is available.
No other transient or accident described in the FSAR is adversely affected by this cnange in set;oint. -
Section 7.3.2 describes the AFAS signal incluoing an actuaticn setpoint of 19%.
The stated setpoint value of 19% is in error. The stated value should be greater than or equal to 19%. consistent with the amendment to the Technical Specification wnich cecreased the setpoint frca 29.0% to greater than or equal to 19.0% (Ref 3). ::rditicn recort (9F.775) as accressed *.his FSAR update error and ccrrecucn to tne FSAR will :e Tace at its next scheduled update,
'erefore. changing the AFAS setcoint to 24.5% for Moces 3 & 4 is not ccnsidered a
~
~ge to the plant as cescribed in the FSAR.
r erm 131 se< 6/94. Page 3 Of 2
PC/M 96 -
119
.' Revision 2 Page 4 of 4 Hode Restrictions This setpoint change is limited to Modes 3 & 4 only.
Design Integration A design integration review has been conducted, and the following sources have been reviewed for impact:
'~
- 1) No drawings are being changed.
- 2) Safetyevaluationsarenotaffect(d.
- 3) PC/Ms are not affected.
Conclusion The above evaluation ensures design equivalence and conformance to the original design bases as described in the FSAR. Furthermore, this setpoint change does not affect any procedures discussed in the FSAR. introduce any new test or experiments or affect any Technical Specifications. Based on the above a 10 CFR 50.59 evaluation is not required.
AFFECTED DOClNENTS Operations and Maintenance will review appropriate procedures affected by this setpoint change.
SPECIAL INSTRUCTIONS \ IMPLEMENTATION REQUIREMENTS The original setpoint is required to be restored prior to entry into Mode 2. The I setpoint change will be to both AFAS 1 & 2.
REFERENCES
- 1. St. Lucie Unit 1 FSAR. Through Amendment 14,
- 2. St. Lucie P1 ant Unit 1 Technical Specifications. through Amendment 142.
- 3. L 90-46, dated 3/9/90.
ATTAC!NENTS Attachment 1: JPN-PSLP 96-0144. 7/19 96. (5 cages including 3 attachments)
, Page i ,
b CALCULATION COVER SHEET Calculation No: PSL-1FSN-96-002
Title:
Containment Atmosphere Gaseous Monitor Response to RCS Leakage Durino Normal Plant Oneration l
.- i l
1
-i
?,
I i I i 1 l !
l t /
f
/
/
I
.i _
/
f_ l
/
l No. Description l Sy Date Chkd Date Appr Date f er REVISIONS Fonn 82A, Rev 6/94
Page :
LIST _0E_. EFFECTIVE PAGES Calculation No.: PSL-1FSN-96-002 Rev.: 0
Title:
Containment Atmosphere Gaseous Monitor Response to RCS Leakage During Normal Plant Operation Page Section Rev. Page Section Rev.
i 0 ii o iii 0 1 0 2 0 3 0 4 0 5 0 G 0 7 0 8 0 i
I I
i I
l l
! i I ,
I I i 9 Form 923, Rev 6e74
.-. . _ - . . - -. . . . . ... -. _. .. . - . . . . . . .- . . . . ~ . . . . . . _ . . _ _ .
r .
i g Page iii 1
i TABLE OF cQNTENTS i
CALCULATION NUMBER: PSL-1FSN-96-002 REV.: 0 l
SECTION TITLE PAGES
- Cover Sheet i
,, List of Effective Pages 11
} Table of Contents lii i
i 1.0 Purpose / Scope 1 i
2.0 References 1 3.0 Methodology 2 4.0 Assumptions / Bases 3 4
l l 5.0 Calculation '
4 l s
6.0 Results 7 j ATTACH NO. TITLE PAGES 4
, 1 Spreadsheet Results Summary 12 2 9/26/96 Memo, Faulkner (Chemistry) to 1 4' Wasik (Engineering)
J i 1 I 4
1
- i. I 1
Form 82C, Rev 6/94
- 1 Colculation No. PSL-1FSN-96-002 Revision 0 Sheet No. 1 e
- 1. PURPOSE / SCOPE Condition Report (CR) 96-2228 was written to document a need to !
validate the design of the Unit 1 and 2 particulate and gaseous radiation monitors since design basis information was not available. The CR raised questions with respect to the following aspects of system design and operation:
-the use of 10%;of scale change as an indication of a 1 gpm increase in reactor coolant "
system (RCS) leakage (as described in the UFSAR);
the requirement for isokinetic sample flow (affects particulate monitor only); ,
- e the current practice of setting the alarm at 2 times background; and the detector response time associated with detecting a 1 gpm increase in RCS leakage.
The purpose of this calculation is to address the above listed items as they pertain to the design and operation of RE-26-32, the containment gaseous radiation monitor.
This calculation supersedes calculation PSL-1FJN-92-011 (reference 2.1).
- 2. REEERENCES 2.1 Calculation PSL-1FJN-92-011, Response Time for the Containment Atmosphere Gaseous Monitor to Detect a 1.0 gpm RCS Leak During Normal Plant Operation, Rev. O.
2.2 Chart of the Nuclides, Knolls Atomic Power Laboratorf, Ninth i Edition.
2.3 Memo from D.H. Faulkner (Chemistry) to Chris Wasik (Engineering),
Subject:
Normal Unit 1 Reactor Coolant Rb-88 and Xe-133 Values, 9/26/96. l l
2.4 St. Lucie Unit 1 Updated Final Safety Analysis Report, through amendment 14, Table 11.1-1.
1 2.5 USNRC Regulatory Guide 1.45, Reactor Coolant Pressure l Boundary Leakage Detection Systems, May, 1973.
i 2.6 St. Lucie Unit 1 Updated Final Safety Analysis Report, through amendment 14, Table 6.2-9.
2
i i
Calculation No. PSL-1FSN-96-002 Revision _D_ Sheet No. 2_ '
. ._ _ ____2._7..___St _ Lucia Uni t 1 Updated-F-inal-Safety-Analysis -Reportv -- - ----- -
through amendment 14, Table 6.3-6.
2.8 Chemistry Procedure No. 1-C-67, Calibration of the Containment Process Monitor, Calibration Certificate dated !
8/5/88. '
2.9 Nuclear Reactor Engineering, Third Edition, Samuel Glasstone and Alexander Sesonske, Van.Nostrand Reinhold j Company, 1981, Chapter 2.
- 3. METHODOLOGY j
3.1 The calculation was performed using an Excel spreadsheet which considered the RCS leakage event in discrete intervals as discussed in Section 4.8.
3.2 Sheet 1 of the spreadsheet was used to calculate, in'one hour intervals,:
1
- 1. the total activity of Xe-133 (uci) in containment based on a given RCS leak rate and a given RCS Xe-133 concentration (uCi/cc) ;
- 2. the containment Xe-133 concentration (uCi/cc) based on the results of #1 above;
- 3. the gaseous monitor detector reading change (cpm) based on the results of #2 above.
3.3 Sheet 2 of the spreadsheet was used to calculate, in one minute intervals,:
- 1. the total activity of Xe-133 (uci) in containment based on a given RCS leak rate and a given RCS Xe-133 concentration (uCi/cc);
- 2. the containment Xe-133 concentration (uci/cc) based on the results of #1 above and factoring in a 14 minute delay time;
- 3. the gaseous monitor detector reading change (cpm) based on the results cf #2 above.
4 e - um
. . _ . . - - - .. _ - . . . ~ .- - .
s l
l 1
. . Calculation No. PS L - 1 FS N - 9 6 - 0.0L Revision __0__ Sheet No. 3 !
l
--4. An m. ..tions/ Bases - - - - - - - - - _ _ _ -
1 4.1 The containment background countrate is defined as the ,
countrate associated with plant operations prior to the l assumed 1 gpm step increase in RCS leakage. This countrate !
i is a function of the initial existing RCS leakage rate and 2
the RCS Xe-133 activity level.
4.2 All dynamic events are asw.med to occur in either one minute l 1
or one hour intervals.
One hour intervals are used in calculating background readings as well as for calculating the time for detection of a doubling of the background countrate (given a 1 gpm step increase in RCS leakage) .
I One minute intervals are used in calculating the time for detection of a lot increase in . the background countrate (given a 1 gpm step increase in RCS leakage).
1 4.3 The only isotope considered in this evaluation shall be j, xenon- 13 3 . (Xe - 13 3 ) .. Xe-133 is an isotope which dominates detector response. The affects of other radioactive isotopes i shall be ignored. l l
'4.4 The radioactive half-life of Xe-133 is assumed to be 5.27 !
days (reference 2.2). l i
4.5 The RCS Xe-133 activity is assumed to be 0.00236 uCi/cc ]
during typical plant operations. This value is based on an j average of RCS sample Xe-133 activities provided by Chemistry (reference 2.3).
4.6 The RCS Xe-133 activity is assumed to be 18.1 uCi/cc during UFSAR defined normal operations of 0.1% failed. fuel (reference 2.4).
4.7 The RCS leakage rate to be detected is assumed to be a step increase of 1.0 gpm. This value is based on N'RC Regulatory Guide 1.45 (reference 2.5).
4.8 For the calculations using one minute intervals, the Xe-133 activity is assumed to be unifonnly dispersed throughout the containment volume after a period of 14 minutes. This value represents the time for the containment coonng system, operating at 180,000 cfm (reference 2.6), to provide one comolete turnover of the containment free volume of 2.5E+6
,ft (reference 2.7). Although radioactive decay is factored in to this delay, the delay is intended more for time line purposes to provide a more conservative calculation of total time (radioactive decay of Xe-133 over a 14 minute period is l "C.13%).
l i
1 Calculation No. PSL-1FSN-96-002_ Revision 0 Sheet No. 4 The 14 minute delay is not assumed in the calculations using one hour intervals since these calculations are looking at !
longer time intervals such that a 14 minute delay would be insignificant.
4.9 All Xe-133 present in the RCS leakage is assumed to be released to the containment atmosphere since, at normal RCS temperature and pressure, any leakage would be flashed to steam.
4.10 The sample flow rate has no effect on detector response due to low system volumes and the'long radioactive half-life of Xe-133.
4.11 Detector sensitivity to Xe-133 is assumed to be 1.25E-07 uCi/cc/ cpm or 8,000,000 cpm /uCi/cc (reference 2.8).
4.12 Typical gaseous monitor readings are assumed to be approximately 80-100 cpm based on discussions with cognizant personnel and personal observation in the control room.
- 5. CALCULATION 5.1 Use of a 10% change in Indication - Tvnical Operations Section 5.2.4 of the UFSAR describes using a 10% deviation in the normal reading of the monitor as an indication of a step increase in RCS leakage from 0.1 to 1.0 gpm. Table 5.2-11 notes that it would conservatively take 15.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for a 10% change to be observed. Since no original design basis calculations are available, it is not clear exactly what was considered as the normal meter indication and how the 15.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> was calculated. It should also be noted that the original plant design considered normal operations with 0.1%
, failed fuel (reference 2.4). Since today's fuel performance is much better, containment activity levels are
' correspondingly lower. With the containment gaseous monitor 4 fluctuating between 80 and 110 cpm under typical. operating conditions as observed in the control room, it would be difficult to detect an 8 to 11 cpm increase as an indication of increased RCS leakage.
h l
3
.- - - . _ - . . - . - . - . - ~ . .-_ ..
Calculation No. PSL-1FSN-96-002 Revision 0 Sheet No. 5
. - - . __.__ __.54_. mssous- Moni-tor-Rasnonne-t e- Res-Le a kag e -W cal-Oc e ra tirnn-- - - -~
This calculation predicts the response of the gaseous monitor to a 1 gpm step increase in RCS leakage based upon typical '
RCS Xe-133 activity levels (Section 4.5). l l
The sections below describe the formulas used in the i spreadsheet.
5.2.1 The rate of Xe-133 leaked to containment atmosphere for each
. 1 minute interval is calculated as follows: 1 i
l Rate = (RCS Xe-133 Concentration) x (RCS Leak Rate) (
Rate = (.00236uCi/cc) x (1.0 gpm) x (3785 cc/ gal) I Rate = 9 uCi/ min 5.2.2 The total curie content (activity) of Xe-133 in the containment atmosphere for each 1 minute interval is calculated as follows: ,
l
)
ActMty = (Rate of Xe-133 Leakage) + (ActMty from Previous interval) x (1 Min. Decay Factor) l The Decay Factor is calculated using the standard radioactive decay formula (reference 2.9) and the 5.27 day half-life of Xe-133 as follows: ;
I 1
Decayed Value = (Original Value) x (e* )
Where: L = 0.693 = 0 693 = 9.132E-05 min" half-life (5.27 d) x (24 hr/d) x (60 min /hr) t = 1 minute Thus:
Decayed Value = (Original Value) x (0 9999)
I Calculation No. PS L - 1'FSN- 9 6 - 0 0 2 _ Revision 0 Sheet No. 6
- 5 2.3-Allowing-a minute--delay-te--aHow-for- containment- - - !
atmosphere mixing, the concentration of Xe-133 in the containment for any given interval is calculated as follows:
Xe-133 Conc. (uCVcc) = (Xe-133 ActMtv) x (14 Min. htcav Factor) !
(Containment Volu,'ne)
Where: Containment Volume = 70800000000 cc t Decay Factor = 0.9987 (calculated as in 5.2.2 above) w .-
t 5.2.4 The detector indication is calculated using the Section 4.11 cpm /uCi/cc conversion l
Indication = (Containment Xe-133 Conc., uCi/cc) x (8.00E+06 cpm /uCL/cc) 6 5.3 Gaseous Monitor Response to RCS Leakace - 'O.1% Failed Fuel !
This calculation predicts the response of the gaseous monitor i to c. 1 gpm step increase in RCS leakage based upon normal RCS
- Xe-133 activity levels (Section 4.6).
5.3.1 In order to assess detector response and alarm setpoint methodology under UFSAR normal operating conditions (0.1% ;
failed fuel), we first need to know the background countrate.
Since typical fuel performance is much better than 0.1% i failed fuel, the typical background countrate of 80-110 cpm cannot be used.
The background countrate is associated with an equilibrium t Xe-133 concentration in the containment. Since Xe-133 has ;
a half-life of 5.27 days, the time to reach equilibrium is on the order of hundreds of hours. Because of this, the background countrate was calculated in intervals of one hour. !
The calculational methodology used is the same as that in ,
Section 5.2, except that the 14 minute delay was not considered. Background countrates were calculated for RCS leak rates of 0.1, 0.25, 0.5, 0.75 and 1.00 gpm.
5.3.2 With the background count $ rate established, we can calculate i the time for detector response to a 1.0 gpm step increase in RCS leakage (i.e., RCS leakage in addition to the initial !
leakage values of Section 5.3.1). Again, the calculational !
methodology is the same as-in Section 5.2. It was determined by preliminary calculations that the time to double the background countrate would be on the order of many hours; therefore, the 14 minute delay was not considered and one hour intervals were used. Since the time to increase the background countrate by 10% is much shorter, one minute i intervals and a 14 minute delay were assumed (results were [
cnverted o hours). i
, . Calculation No. ._ES L _1ESN - 9 6 - O O2 Revision _Q_., Sheet No. 7
. - - 5.4_.Ja n enu a . Monitor- RespoDae--to- RCS- Leakage-- 0. 01% -Fa il ed - Fuel-- --
l 5.4.1 The calculations of Section 5.3.1 and 5.3.2 were repeated for RCS Xe-133 activities associated with 0.01% failed fuel for comparison purposes. The Xe-133 activity for 0.01% failed fuel is simply 1/10th of the value for 0.1% failed fuel.
- 6. RESULTS 6.1 The use of a 10% of indication change in detector reading as l
,, an indication of a 1.0 gpm , step change in RCS leakage is difficult given the current operating environment with improved fuel performance.
6.2 Under typical operating conditions the containment gaseous monitor is incapable of indicating a 1 gpm step increase in RCS leakage. Attachment 1 provides a portion of the spreadsheet results. As shown on the spreadsheet, the countrate increase is negligible after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. This low detector response is due to the low RCS activities experienced during typical plant operations. These results are consistent with NRC Regulatory Guide 1.45 comments regarding the limited value of containment radiation detectors in providing an early warning of very small leaks !
when RCS radioactivity is low. '
I i
6.3 The table below shows the results of the calculations described in Sections 5.3 and 5.4.
RESHLTS For a i gpm RCS Leak Rate Increase Background Countrate: Time for Background Countrate to: ;
i Initial Leak Rate 0.1 % Failed Fuel 0.01 % Failed Fuel Double lacrease 10% j (gpm) (epm) (epm) (bours) (hours) )
0.10 8434 843 19 2.1 )
0.25 21084 2108 52 4.9 0.50 42168 4217 125 9.6 0.75 63251 6325 251 14.5 1.00 94335 8434 1200 19.5 I
1 l
I
i v.
f Calculction No. PSIN FSN- 9 6 0 02 __ Rcvicien O Shsst No. 8 Dt.
The following conclusions can be mad _ej rom.thes_e__results: ___
- 1. The time for detector response with respect to a given percent change in background countrate is independent of RCS activil'y (i.e., failed fuel fraction). This result is expectedgsince a percent change in indicated countrate is a function of the change in Xe-133 concentration in the contaliiment atmosphere which is ~ a function of two fixed values: RCS leak rate (fixed at 1 gpm), and the half-life iof Xe-133. The figure 1 curve- shows the countrate ihcrease as a percent of containment atmosphere equilibriudi concentration of Xe-133.
- 2. It is unaccleptable to use an alarm setpoint of two times '
background as an indication of a 1.0 gpm step increase in -
RCS leakage since the time to an alarm would be too long (except for' initial RCS leakage <<0.1 spm) .
- 3. Except for when RCS Xe-133 activity levels are low, it is acceptable to use a 10% change in countrate as an indication.of a 1.0 gpm step increase in RCS. leakage.
The results'show that the detector can respond within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as n,oted in UFSAR Section 5.2.4.6.
Fiaura 1 COUNTRATE INCREASE vs. TIME 100% 3-- ,. . .
l ! l i i 90 %
d 80% j i!! i , t 4 i
i i
I i
l i :
70% ! I I
)
I60%/~l' I
l y, j
j O 'A% ;
' j i
! ! l' 4% ' ' 1 b l I i i g ,%
@ 20% - '
E i 8 10% -
o ;
. 0%
r k kkkkkk$k TIME (HRS) ;
i I
j
1 Attachmtnt i I PSL-1FSN.96 002, Rev. 0 '
__ i l UNIT 1 CONTAINMENT GASEOUS MONITORI i l l RCS Xe-133 Conc. m ,2.30EOswar uCi/cc RCS Leak Rate ' 1.00 - ~ gpm Activety into RCB 9 uCL/ min b 14 MIN DELAY DETECTOR RC8 RCB Xe-133 ADJUSTED READING TIME ACTIVITY CONC. TIME CHANGE (min) (uCI) (uCifbc) (min) (cpm) 0 0.00E+00 0.00E+00 14 0 1 8.93E+00 1.26E-10 15 0 l 2 1.79E+01 2.52E-10 16 0 3 2.68E+01 3.78E 10 17 0 4 3.57E+01 5.04E-10 18 0 5 4.47E+01 6.30E 10 19 0 ,
6 5.36E+01 i 7.56E-10 1 20 0 l 7 6.25E+ 01 8.82E-10 ,
21 0 1
' I 8 i 7.14E+01 ! 1.01E-09 22 1 0 9 8.04E+01 1.13E-09 23 0 10 i 8.93E+01 1.26E 09 24 0 11 l 9.82E+01 1.39E-09 25 0 12 i 1.07E+02 1.51 E-09 26 0 13 1 1.16E+02 1.64E-09 27 0 14 i 1.25E+02 i 1.76E-09 28 0 15 1.34E+02 ~ ~" 1.89d-09 1 29 0 ,
16 1.43E+02 2.01 E-09 ; 30 ! 0 !
17 1.52E+02 2.14E-09 i 31 i 0
18 I 1.61 E+02 ,
2.27E-09 1 32 I O 19 ~~ 1.70E+02 2.39E-09 i 33 i 0 l
~~
20- 1.78E+02 BI2E-09 34 1 0 )
21 l 1.87E+02 i 2.64E-09 1 35 I O l
22 1.96E+02 i 2.77E-09 ! 36 I O 23 2.05E+02 '_ 2.89E-09 37 0 24 2.14E+02 3.02E-09 , 38 0 j 25 2.23E+02 3.15E-09 '
39 1 0 26 2.32E+02 3.27E-09 1 40 i 0 27 2.41 E+02 3.40E-09 i 41 i 0 28 2.50E+02 3.52E-09 42 0 29 2.59E+02 . 3.65E-09 43 0
~ 30 2.68E+02 ~ 3.77E-09 44 0 31 2.76E+02 3.90E-09 45 0 32 2.85E+02 4.03E-09 46 0 33 2.94E+02 4.15E-09 47 0 34 3.03E+02 4 28E-09 48 0 35 3 12E + 02 4 40E.09 49 ,
0 36 3 21E+02 4 53E-09 50 0 Page 1
i
. l Attachment 1 i PSL-1FSN-96-002, Rev. 0 37 3.30E+02 4 65E-09 51 0 38 3.39E+02 i ~iNE 09 i 52 !
O 39 3.48E+02 1 4.90E-09 '
53 i 0 40 3.57E+02 1 5.03E-09 54 0 1 41 3.66E+02 5.16E-09 55 0 I 42 3.74E+02 5.28E 09 56 i 0 !
43 3.83E+02 5.41 E-09 57 0 l 44 3.92E+02 5.53E-09 58 0 45 4.01E+02 5.66E-09 59 0 46 4.10E+02 5.78E-09 60 0
__ 47 4.19E+02 ; 5.91 F,-09 i 61 - 3 48 4.28E+02 l 6.03E-09 i 62 i 49 4.37E+02 6.16E 09 1 63 > 0 50 4.46E+02 i 6.28E-09 i 64 ! O 51 4.54E+02 1 6.41 E-09 65 1 0 52 4.63E+02 . 6.54E-09 66 1 0 53 4.72E+02 i 6.66E-09 67 I O 54 4.81E+02 , 6.79E-09 68 0 55 4.90E+02 6.91 E-09 69 56 4.99E+02
{
7.04E-09 70
} O i ! 0 57 5.08E+02 i 7.16E-09 '
71 i 0 58 5.17E+02 7.29E-09 72 1 0 59 5.25E+02 7.41 E-09 73 1 0 60 5.34E+02 7.54E-09 74 I O 61 5.43Et02 7.66E-09 75 l 0 62 5.52E+02 7.79E-09 76 l 0 63 5.61E+02 i 7.91 E-09 77 i 0
~
64 1 5.70E+02 8.04E-09 '
78 0 65 i 5.79E+02 ,,_ , _8.16E-09 79 0 66
! 5.88E+02 ~~
8.29E-09 I 80 >
0 67 5.97E+02 8.41 E-09 i 81 1 0 68 6.05E+02 8.54E-09 82 0 69 .
6.14E+02 3.66E-09 83 0 I 70 1 6.23E+02 t 8.79E-09 i 84 0 71 i 6.32E+02 4 8.91 E-09 ! 85 0 72 i 6.41 E+ 02 9.04E-09 i 86 0 73 i 6.50E+02 9.17E-09 i 87 0 74 i 6.59E+02 9.29E-09 ; 88 , 0 75 i 6.67E+02 9.42E-09 i 89 0 76 6.76E+02 9.54E-09 : 90 0 77 6.85E+02 9.67E-09 91 0 78 6.94E+02 9.79E-09 92 0 79 7.03E+02 9.92E-09 93 0 80 7.12E+02 1.00E-08 94 0 81 7.21 E+02 1.02E-08 95 0 82 7.30E+02 1.03E-08 96 0 83 7.38E+02 _ _1.04 E-08 97 0 84 7.47E+02 1.05E-08 98 0 85 7.56E+02 1.07E-08 99 0 86 7 65E+02 1.08E-08 100 0 Page 2
I Attachment 1 l PSL-1FSN.96 002. Rev 0 t
~ ~ ~ ^
~ ~
~~~
^87 7 ~ 7.74E+02 .
109E 08 i 101 l 0 ,
88 I 7.83E+02 1.10E-08 , 102 ! O
~89 ~ ~
- 7.92E+02 1.12E-08 ~ - ~
l 103 i
~ ~ " ~ ~
0 l 90 8.005'~0T
+ l 1.'i3'E-08 104 'O 91 8.09E+02 1.14E-08 105 0 .
92 8.18E+02 1.15E-08 106 1 0 93 8.27E+02 1.17E 08 107 1 0 ,
94 8.36E+02 1.18E-08 108 0 95 8.45E+02 1.19E-08 109 0 96 8.53E+02 1.20E-08 110 0 97 8.62E+02 i 1.22E-08 111 0 ,
98 8.71 E+02 l 1.23E-08 112 0 l
99 8.80E+02 i 1.24E-08 113 0 100 8.89E+02 1.25E-08 114 0 101 8.98E+02 1.27E-08 115 0 102 _
9.07E+02 l 1.28E-08 116 0 103 l 9.15E+02 1.29E-08 117 0 104 i 9.24E+02 1.30E-08 118 0 105 9.33E+02 1.32E 08 119 0 106 9.42E+02 1.33E-08 '1'20 0 107 9.51 E+02 ! 1.34E-08 121 0 108 9.60E+02 I 1.35E-08 122 0 l 109 9.68E+02 1.37E-08 123 0 110 9.77E+02 1.38E-08 124 0 111 9.86E+02 1.39E-08 125 0 112 9.95E+02 1.40E-08 126 0
_ 113 1
1.00E+03 j _1 42E-08 127 0 114 1.01E+03 I 1.43E-08 128 0 4 115 1.02E+03 -
~ 1.44E-08 129 0 116 1.03E+03 i 1.45E-08 130 0 117 -
1.04E+03 1.47E 08 131 0 118 1.05E+03 1.48E-08 i 132 0 ;
119 1.06E+03 i 1.49E-08 i 133 1 0 120 +
1.07E+03 1 1.50E-08 134 0 I 121 1.07E+03 i 1.52E-08 135 0 122 1.08E+03 _ _
1.53E-08 l 136 '
O 123 >
1.09E+03 l 1.54E-08 1 137 I 0 124 1.10E+03 ,
155E-08 138 0 125 1.11 E+ 03 '
1.57E-08 139 0 i 126 1.12E+03 1.58E-08 140 l 0 l 127 1.13E+03 1.59E-08 141 ; O 128 1.14E+03 1.60E 08 142 i 0 129 1.14E+03 1.62E-08 1 143 , 0 130 1.15E+03 __ 1._63 E-08 144 0 131 1.16E+03 _ , _ . _ 1.64E-08 -
145 0
- 132 1.17E+03 165E-08 146 0 133 1.18E+03 _ 166E-08 147 0 134 1.19E+03 1.68E-08 148 0 135 1.20E+03 1.69E-08 149 0 136 1.21 E+03 1.70E-08 150 0 Page 3
6 6,
.., f Altschmsnt 1
, PSL-1FSN 96-002. Rev. 0 i
137 l 1.22E+03 i 1.71E-08 1 151 0 138 1.22E+ 03 1 1.73E 08 1 152 O 139 1.23E+03 .
1.74E-08 i 153 0 140 1.24E+03 1.75E-08 154 0 141 1.25E+03 1.76E-08 155 0 142 1.26E+03 1.78E-08 156 0 143 1.27E+03 1.79E-08 157 0 144 1.28E+03 1.80E-08 158 0 145 1.29E+03 1.81E-08 159 0 146 1.29E+03 1.83E-08 160 0 147 1.30E+03 1.84E.08 161 0 148 1.31 E+03 1.85E 08 162 0 149 1.32E+03 1.86E-08 163 i 0 150 1.33E+03 1.88E-08 164 1 0 151 1.34E+03 1.89E-08 165 i 0 -
152 1.35E+03 1.90E-08 166 0 153 1.36E+03 1.91 E-08 167 0 154 1.37E+03 l 1.93E-08 l 168 1 0 155 1.37E+03 l 1.94E-08 169 I O 156 1.38E+03 8 1.95 E-08 170 1 0 157 1.39E+03 1 1.96E-03 ! 171 1 0 158 1.40E+03 1.98E-08 172 i 0 159 1.41 E+03 1.99E-08 173 0 160 1.42E+03 2.00E-08 174 0 161 1.43E+03 2.01E-08 175 0 162 1.44E+0 - 2.02E-08 176 0 163 1.44E+03 2 n4E-08 1 177 0 l 164 ! 1.45E+03 : 2.05E 08 l 178 0 165 1 1.46E+03 i 2.06E-0C i 179 i 0 166 i 1.4 7E+03 t 2.07E-08 '
180 1 0 167 l 1.48E+03 i 2.09E-08 i 181 1 0 168 1.49E+03 2.10E-08 182 0 169 ! 1.50E+03 +
2.11 E-08 ! 183 i 0
170 1 1.51 E+03 i 2.12E-08 1 184 1 0 171 : 1.51E+03 '
2.14E-08 185 0 172 1.52E+03 2.15E-08 r 186 6 0
173 1.53E+03 2.16E-08 !
187 t 0 174 1.54E+03 '
2.17E-08 I 188 i 0 175 1.55E+03 2.19E-08 i 189 0 176 1.56E+03 2.20E-08 190 0 177 1.57E+03 2.21 E-08 191 0 178 1.58E+03 2.22E-08 192 0 179 1.58E+03 2.24E-08 193 0 180 1.59E+03 2.25E-08 194 0 181 1.60E+03 2.26E-08 195 0
. 182 1.61 E+03 2.27E-08 196 0 183 1.62E+ 03 2.28E-08 197 0 184 1.63E+03 2.30E-08 198 0 185 1.64 E+ 03 '~2.31 E-08 199 0 186 1.65E+03 ~2.32E-08 200 0 Page 4
t Attachment 1 l
- PSL-1FSN 96-002 Rev. 0 4 i
187 1 1.65E+03 j 2.33E-08 201 1 0 j 188 ! 1.66E+03 '
2.35E-08 202 0 189 1 1.67E+03 2.36E 08 203
{
0 i 190 1.68E+03 2.37E-08 204 0 191 1.69E+' 03 2.38E-06 205 0 192 1.70E+03 2.40E-08 206
^
0 193 1.71E+03 2.41E 08 207 0 194 1.72E+03 2.42E-08 208 0 195 1.735!403 2.43E-08 209 0 i 196 1.73E+03 2.45E-08 210 0
, . _ 197 1.74E+03 2.46F.,;08 211 0 i
198 1.75E+03 2.47E-08 212 0 199 1.76E+03 2.48E-08 213 0 200 1.77E+03 2.50E-08 214 0 201 1.78E+03 2.51E-08 215 0 202 1.79E+03 2.52E-08 216 0 203 1.80E+03 2.53E-08 217 0 204 1.80E+03 2.54E-08 218 0 205 1.81E+03 219 0
_ _ 2.56E-08 206 1.82E+03 2.57E-08 220 0 207 1.83E+03 2.58E-08 221 0 208 1.84E+03 2.59E-08 222 0 209 1.85E+03 2.61 E-08 223 0 210 1.86E+03 2.62E-08 224 0 211 1.87E+03 2.63E-08 225 0 212 1.87Et03 2.64E-08 226 0 213 1.88E+03 .
2.66E-08 227 0 214 1.89E+03 i~ 2.67E-08 i 228 l 0 215 1.90E+03 i 2.68E-08 i 229 0 216 1.91 E+03 2.69E-08 1 230 0
~217 i 1.92E+03 ! 2.70E-08 i 231 0 j 218 1.93E+03 2.72E-08 232 0 1 219 i 1.94E+03 2.73E-08 1 233 i 0 220 1 1.94E+03 ! 2.74E-08 i 234 0 221 i 1.95E+03 1 2.75E-08 i 235 0 222 1.96E+03 i 2.77E 08 236 0 223 ,
1.97E+03 i 2.78E 08 t 237 i 0 224 1.98E+03 i 2.79E 08 i 238 i 0 225 -
1.99E+03 i 2.30E 08 I 239 i 0 226 -
2.00E+03 >
2.82E-08 1 240 1 0 227 2.00E+03 2.83E-08 i 241 i 0 228 2.01 E+03 2.84 E-08 i 242 1 0 229 2.02E+03 2.85E-08 243 y 0 230 2.03E+03 2.87E-08 4 244 0 231 2.04E+03 2.88E-08 245 1 0
_232 2.05E+03 _
.., 2.89E-08 , 246 ! O I
.233 2.06E+03 2.90E-08 '
247 0 234 2.07E+03 2.91 E-08 248 ! 0 235 2.07E+03 ,
2.93E 08 249 ,
0 236 2.08E+03 2.94E-08 250 0 l
. Page 5
l Attachment 1 l l PSL-1FSN-96-001, Rev. 0 <
l i
237 2.09E+03
- 2.95E-08 i 251 i 0 238 2.10E+03 i 2.96E-08 1 252 1 0 l
_ 239 i 2.11E+03 l 2.98E-08 253 i 0 l 240 2.12E+03 2.99E-08 254 i 0 ;
241 2.13Ev03 3.00E-08 255 0 242 2.14E+03
{
3.01E-08 256 0 243 2.14E+03 3.03E-08 257 0 1 244 2.15E~+ 03 3.04E-08 258 0 )
245 2.16E+03 3.05E-08 259 0 246 2.17E403 3.06E-08 260 0
.- 247 2.18E+03 3.075-08 261 0 248 2.19E+03 3.09E-08 262 0 249 2.20E+03 3.10E-06 263 0 250 2.21 E+03 3.11 E-08 264 0 251 2.21E+03 3.12E-08 265 0 252 2.22E+03 3.14E 08 266 0 253 2.23E+03 3.15E-08 267 0 254 2.24E+03 3.16E-08 268 i 0 255 2.25E+03 3.17E-08 269 i 0 256 7 2.26E+03 ~~ 3.18E'08 270 i 0 257 2.27E+03 - ! 3.20E-08 271 i 0 258 2.28E+03 l 3.21E-08 272 i 0 259 2.28E403 3.22E-08 273 0 260 2.29E+03 3.23E-08 274 0 261 2.30E+03 3.25E-08 275 0 262 2.31 E+03 ! 3.26E-08 276 0 263 2.32E+03 '
3.27E-08 277 0
~264 2.33E+03 i~ 3.28E708 278 i ~~~~6 265 2.34E+03 3.30E-08 279 1 0 266 2.34E+03 3.31 E-08 280 l 0 267 l 2.35E+03 i 3.32E-08 281 1 0 268 '
2.36E+03 3.33E 08 282 0 269 2.37E+03 '
3.34E-08 283 1 0 270 2.38E+03 i 3.36E-08 284 1 0 271 2.39E+03 3.37E-08 285 1 0 272 2.40E+03 3.38E-08 286 ! 0 273 2.41 E+03 3.39E-08 287 i 0 274 2.41 E+03 3.41 E-08 288 i 0 275 I 2.42E+03 3.42E-08 289 i 0 276 i 2.43E+03 3.43E-08 l 290 i 0 277 i 2.44E+03 3.44E 08 i 291 t 0
278 , 2.45E+03 3.45E-08 i 292 .0 279 l 2.46E+03 3.47E-08 j 293 0 280 2.47E+03 3.48E-08 6 294 0 281 2.48E+03 3.49E-08 i 295 0
- . 282 2.48E+03 3.50E-08 j 296 ! 0 l 283 2.49E+03 3 52E-08 i 297 0 l 284 2.50E+03 3.53E-08 ! 298 0 l- 285 2.51 E+03 3.54 E-08 299 0 286 2.52E+03 3.55E-08 6 300 0 i
j Page 6
. . ._ -. .- . . _ - _ - _ _ - - .- --. - - ~ _ - - .. _ -_ .__ .
AttachmInt 1 PSL 1FSN.96-002, Rev 0 t 4 P 287 ! 2.53E+03 3.57E-08 1 301 0 288 l 2.54E+03 i 3.58E 08 1 302 0 289 J 2.54E+03 3.59E-08 303 0 290 2.55E+03 __ 3.60E-08 304 0 3
291 2.56E+03 3.61E-08 305 0 292 2.57E+03 3.63E-08 306 0 '
- 293 2.58E+03 3.64E-08 307 0 294 2.59EM3 3.65E-08 308 0 295 2.60E+03 3.66E-08 309 0 ,
j 296 2.61E+03 3.68E 08 310 0 297 2.61E+03 3.69E=08 311 0 298 2.62E+03 3.70E-08 312 0
=
299 2.63E+03 3.71 E-08 313 0
- 300 2.64E+03 3.72E-08 314 0 301 2.65E+03 3.74E-08 315 0
) 302 2.66E+03 3.75E-08 316 0 303 2.67E+03 3.76E-08 317 0 I
304 2.67E+03 1 3.77E-08 318 0 305 2.68E+03 j 3.79E-08 319 0 4
306 l 2.69E+03 i 3.80E-08 320 0 j 307 2.70E+03 1 3.81 E-08 321 0 308 2.71 E+03 I 3.82E-08 322 0 309 l 2.72E+03 3.83E-08 323 0 310 2.73E+03 3.85E-08 324 0 4 311 2.74E+03 3.86E-08 325 0 ;
312 2.74E+03 3.87E-08 326 0 313 2.75E+03 3.88E-08 327 0 I 314 ! - 2.76E+03 3.90E-08 i 328 0 315 i 2.77E+03 i 3.91 E-08 329 0
. 316 i 2.78E+03 I 3.92E-08 330 0 317 ! 2.79E+03 i 3.93E-08 331 0'
- 318 2.80E+03 3.94E-08 i 332 l
- 319 ! 2.80E+03 ! 3.96E 08 1 333 0
! 320 i 2.81E+03 i 3.97E-08 I 334 0 321 1 2.82E+03 i 3.98E-08 i 335 0 322 .
2.83E+03 3.99E 08 j 336 0 323 1 ' 2.84E+03 4.01 E-08 j 337 0 324 l 2.85E+03 4.02E-08 i 338 0 325 2.86E+03 ,
4.03E-08 i 339 0 326 2.87E+03 i 4.04E 08 i 340 0 327 2.87E+03 4.05E-08 341 0 328 2.88E+03 4.07E-08 342 i 0 329 2.89E+03 4.08E-08 343 i 0 330 2.90E+03 4.09E-08 344 i 0 331 2.91 E+03 4.10E-08 345 i 0 '
332 + 2.92E+03 4.11 E-08 346 1 0 l 333 2.93E+03 4.13E-08 347 '
0 334 2.93E+02 4.14E-08 348 i 0 335 2.94E+03 4.15E-08 349 0 336 2.95E+03 4.16E-08 350 i 0
Page 7
m All chmInt i PSL 1FSN 96 002, Rev. 0
__.____._--'~
337 2.96E+03 4.1_8.E-08 ,__ 3 51, _ , _0 338 2.97E+03 4.19E-08 352 0 3T, 2.98E+ 03
_ 4.20E-08 353 0 340 2.99Et03 _ 4.21 E-08 354 0 341 2.996+03 4.22E-08 355 0 342 3.00E+03 4.24E-08 356 0 343 3.01 E+03 4.25E-08 357 0 344 3.02E+03 4.26E-08 358. 0 345 3.03E+03 4.27E-08 359 0 346 3.04E+03 4.29E-08 360 0
, , , 347 3.05E+03 4.30E-08 361 0
_l' 8 3.06E+03 4.31 E-08 362 0 349 3.06E+03 4.32E-08 363 0 350 3.07E+03 4.33E-08 364 0 351 3.08E+03 4.35E-08 365 0 352 3.09E+03 4.36E-08 366 0 353 3.10E+03 4.37E-08 367 0 354 3.11 E+03 4.38E-08 368 0 355 3.12E+03 1_ ,,4;39E-08 369 0 356 3.12E+03 4.41 E-08 370 0 357 3.13E+03 4.42E-08 371 0 358 3.14E+03 4.43E-08 372 0 359 3.15E+03 4.44E 08 373 0 360 3.16E+03 4.46E-08 374 0 381 3.17E+03 4.47E-08 375 0 362 3.18E+03 4.48E-08 376 0 363 3.18E+03 4.49E-08 377 0 364 3.19E+03 4.50E-08 378 0 365 3.20E+03 i 4.52E-08 379 0 366 3.21 E+03 4.53E-08 380 0 367 3.22E+03 4.54E-08 381 0 368 3.23E+03 4.55E-08 1 382 1 0 369 3.24E+03 i 4.56E-08 383 0 370 3.24E+03 4.58 E-08 384 0 371 3.25E+03 4.59E-08 385 0 372 3.26E+03 1 4.60E-08 386 0 373 ! 3.27E+03 i 4.61 E-08 387 0 374 i 3.28E+03 i 4.63E 08 388 0 375 i 3.29E+03 : 4.64E-08 389 0 376 1 3.30E+03 1 4.65E-08 390 0 377 i 3.31 E+03 +
4.66E-08 I 391 0 378 i 3.31 E+03 <
4.67E-08 l 392 0 379 t 3.32E+03 4.69E-0C 1 393 ! O 380 , 3.33E+03 4.70E-08 r 394 1 0 381 '
3.34E+03 4.71 E-08 1 395 j 0 382 -
3.35E+03 i 4.72E-08 i 396 0 383 i 3.36E+03 i 4.73E-08 i 397 0 384 3.37E+03 1 4.75E-08 1 398 0 385 3.37E+03 4.76E-08 399 0 386 3.38E+03 4.77E-08 400 1 0 Page 8
- S, !
, Att: chm:nt 1 PSL 1FSN 96-002, Rev. 0 i
~~~
387 ~ 3'.79E+ 03 4.78E-08 401 ; O 388 3.40E+03 l 4.80E-08 402 l 0 389 3.41 E+03 4.81E 08 403 i
- 0 390 3.42E+03 4.82E-08 404 0 3
l 391 3.43E+03 4.83E-08 405 0 392 3.43E+03 4.84E-08 406 0 393 3.44E+03 4.88E-08 407 0 394 3.45E+03 4.87E-08 408 0 395 3.46Elt03 4.88E-08 409 0 396 3.47E403 4.89E-08 410 0 397 3.48Et03 4.90E,08 411 0 398 3.49E+03 4.92E-08 412 0 399 3.49E+03 4.93E-08 413 0 400 !
3.50E+03 4.94E-08 414 0 '-
401 3.51 E+03 4.95E-08 415 0 402 3.52E+03 4.97E-08 416 0 403 3.53E+03 4.98E-08 417 0 l 404 3.54E+03 4.99E-08 418 0 405 3.55E+03 5.00E-08 419 0 406 3.55E+03 5.01E-08 420 0 1
407 3.56E+03 5.03E-08 421 i 0 408 3.57E+03 5.04E-08 422 O I 409 3.58E+03 5.05E-08 423 0 410 3.59E+03 5.06E-08 424 0 411 3.60E+03 5.07E-08 425 0 l 412 3.61E+03 5.09E-08 426 0 413 3.61E+D3 5.10E-08 427 0 414 3.62E+03 5.11 E-08 428 0 415 3.63E+03 5.12E-08 429 0 416 3.64E+03 5.13E-08 430 0 417 3.65E+03 5.15E-C3 I 431 0 418 ! 3.66E+03 5.16E-08 i 432 4 0 419 ! 3.67E+03 ! 5.17E-08 l 433 1 0 4?0 ! 3.67E+03 l 5.18E-08 I 434 1 0 421 l 3.68E+03 4 5.19E-08 .I 435 1 0
_422 l 3.69E+03 1 5.21 E-08 i 436 i 0 423 i 3.70E+03 i 5.22E-08 : 437 i 0 424 1 3.71 E+03 i 5.23E-08 i 438 i 0 425 l 3.72E+03 i 5.24E-08 1 439 i 0 426 1 3.73E+03 i 5.26E 08 I 440 1 0 427 3.73E+03 5.27E-08 1 441 ; O 428 3.74E+03 5.28E-08 '
442 ! O 429 '
3.75E+03 5.29E-08 i 443 i 0
430 '
3.76E+03 5.30E-08 t 444 i 0 431 3.77E+03 >
5.32E-08 , 445 i 0
432 i 3.78E+03 5.33E-08 6 446 i 0 433 ! 3.79E+03 5.34E-08 i 447 ! O 434 3.79E+03 >
5.35E-08 448 0 435 3.80E+03 5.36E-08 449 0 436 3.81 E+03 5.38E-08 450 0l Page 9
3 Attachment 1 PSL 1FSN 96-002. Rev 0
\'
437 ( 3.82E+03 1 5.39E-08 i 451 1 0 438 i 3.83E+03 l 5.40E 08 1 452 1 0 439 ,
3 84E+03 1 5.41 E-08 i 453 1 0 440 3.85E+03 5.42E-08 454 0 441 3.85E+03 5.44E-08 455 0 l 442 3.86E+03 5.45E-08 456 0 443 3.87E+03 5.46E-08 457 0 444 - 3.88E+03 5.47E-08 458 0 445 3.89E+03 5.48E-08 459 0 448 3.90E+03 5.50E-08 460 0 447 3.91E+03 5.515s08 461 0 448 3.91E+03 5.52E-08 462 0 449 3.92E+03 5.53E-08 463 1 0 l 450 3.93E+03 5.54E-08 464 0 451 3.94E+03 5.56E-08 465 0 452 3.95E+03 5.57E-08 466 0 453 3.96E+03 5.58E-08 467 0 454 3.96E+03 5.59E-08 468 i 0 i 455 3.97E+03 5.60E-08 I 469 0 I 456 3.98E+03 ! 5.62E-08 i 470 0 457 3.99E+03 5.63E-08 471 1 0 458 4.00E+03 5.64E-08 472 0 1 459 4.01 E+03 5.65E-08 473 0 l 460 4.02E+03 5.67E-08 474 0 461 4.02E+03 5.68E-08 475 0 462 4.03E+03 5.69E 08 476 0 463 4.04E+03 5.70E-08 477 0 464 4.05E+03 5.71 E-08 478 0 465 ! 4.06E+03 ! 5.73E-08 479 1 0 I 466 i 4.07E+03 .
5.74E-08 480 i 0 467 i 4.08E+03 i 5.75E-08 481 ! O 468 4.08E+03 5.76E-08 482 0 469 i 4.09E+03 5.77E-08 483 0 470 t 4.10E+03 1 5.79E-08 484 0 471 1 4.11 E+ 03 5.80E-08 l 485 0 i 472 ! 4.12E+03 5.81 E-08 486 i 0 l 473 1 4.13E+03 ! 5.82E-08 1 487 i 0 474 -
4.14E+03 '
5.83E-OS i 488 i 0 475 4.14E+03 5.85E-08 i 489 0 476 4.15E+03 5.86E-08 i 490 i 0 477 4.16E+03 5.87E-08 491 0 478 4.17E+03 5.88E-08 492 0 !
479 4.18E+03 5.89E-08 493 0 480 4.19E+03 5.91 E-08 494 0 481 4.20E+03 5.92E-08 495 0
. 482 4.20E+03 5.93E-08 496 0 483 4.21 E+03 5.94E-08 497 0 484 4.22E+03 5.95E-08 498 0 l 485 4.23E+03 5.97E-08 499 0 486 4.24E+03 5.98E-08 500 0 i
Page 10
- 1 I I
AttachmInt 1 PSL-1 FSN-96-002, Rev. 0 487 i 4.25E+03 i 5.99E-08 '
501 0 l 488 4.25E+03 l 6.00E-08 I 502 i 0 489 490 4.26E+03 4.27E+03 6.01E 08 6.03E-08 i 503 504 0 !
0 l 491 4.28E+03 6.04E-08 505 0 ;
492 4.29E+03 6.05E-08 506 0 1 493 4.30E+03 6.06E-06 507 0 494 4.31E+03 6.07E-08 508 0 495 4.31E403 6.09E-08 509 0 ,
496 4.32E+03 6.10E-08 510 0 l 497 4.33E+03 6.11E-08 511 0 498 4.34E+03 6.12E-08 512 1 0 499 4.35E+03 6.13E-08 513 1 0 500 4.36E+03 6.15E-08 514 i 0 501 4.37E+03 6.16E-08 515 l 0 502 4.37E+03 6.17E-08 516 I O I 503 4.38E+03 6.18E-08 517 ! 0 !
504 4.39E+03 l 6.19E-08 i 518 i 0 505 4.40E+03 6.21 E-08 l 519 i 0 l 506 4.41E+03 6.22E-08 520 i 0 l 507 4.42E+03 6.23E-08 521 1 0 508 4.42E+03 {
6.24E-08 522 0 509 4.43E+03 6.25E-08 523 1
{
510 4.44E+03 6.27E-08 524 1 j 511 4.45E+03 6.28E-08 525 1 l 512 4.46E+03 6.29E-08 526 1 513 4.47E+03 6.30E-08 527 i 1 514 4.48E+03 i 6.31 E-08 1 528 1 515 4.48E+03 l 6.33E-08 I 529 i 1 516 i 4.49E+03 i 6.34 E-08 I 530 i 1 517 ! 4.50E+03 >
6.35E-08 531 '
1 518 i 4.5 ? E+03 6.36E-08 ! 532 4 1
519 ! 4.52E+03 i 6.37E-08 i 533 l 1 520 I 4.53E+03 i 6.39E-08 j 534 ! 1 521 ! 4.53E+03 t 6.40E-08 1 535 1 522 i 4.54E+03 -
6.41 E-08
- 536 i 1 523 1 4.55E+03 1 6.42E-08 I 537 ! 1 524 I 4.56E+03 i 6.43E-08 I 538 i 1 525 1 4.57E+03 6.44E-08 i 539 i 1 526 i 4.58E+03 6.46E-08 I 540 i 1 527 4.59E+03 6.47E-08 541 1 528 -
4.59E+03 6.48E-08 542 1 529 4.60E+03 6.49E-08 543 1 530 4.61 E+03 6.50E-08 544 1 531 4.62E+03 6.52E-08 545 >
1 532 4.63E+03 6.53E-08 '
546 ! 1 533 4.64E+03 6.54E-08 547 1 534 4.65E+03 6.55E-08 548 1 535 4.65E+03 6.5EE-08 549 1 536 4 66E+03 6.58E-08 550 1 Page 11
_- . - - _. . -. . - . . ~ . - - - _ _ - _ - . . . - - . - - - .- .. -.
h l
- l. Attachment 1 PSL 1 FStJ-96-002, Rev_._0. _,, _
537 1 4.67E+03 i 6.59E-08 1 551 1 538 4.68E+03 6.60E-08 552 1 539 4.69E+03 6.61 E-08 553 1 540 4.70E+03 6.62E 08 554 1 541 4.70E+03 6.64E 08 555 1 542 4.71E+03 6.65E-08 556 1 ;
543 4.72E+03 6.66E-08 557 1 l 544 4.73E+03 6.67E-08 558 1 545 4.74E+03 6.68E-08 559 1 546 4.75E+03 6.70E-08 560 1 547 4.76E+03 6.71 E-08 561 1 548 4.76E+03 6.72E-08 562 1 549 4.77E+03 6.73E-08 563 1 550 4.78E+03 6.74E-08 564 1 551 l 4.79E+03 6.76E-08 565 1 552 ( 4.80E+03 6.77E-08 566 1 1
553 j 4.81E+03 6.78E-08 567 1 i 554 i 4.81 E+03 6.79E-08 568 1 ,
555 6 4.82E+03 6.80E 08 569 1 556 i 4.83E+03 6.81E-08 570 1
)
557 4.84E+03 6.83E-08 571 1 558 4.85E+03 6.84E-08 572 1 559 4.86E+03 6.85E-08 573 1 560 4.87E+03 6.86E-08 574 1 561__ 4.87E+03 _ , _ _6 87E-08 575 _1,.
562 4.88E+03 6.89E-08 576 1 563 4.89E+03 1 6.90E-08 577 1 564 1 4.90E+03 6.91 E-08 578 1 565 l 4.91E+03 6.92E-08 579 1 565 4.92E+03 i 6.93E-08 580 1 567 4.92E+03 6.95E-08 581 l 1 568 4.93E+03 6.96E-08 582 1 1 569 6 4.94E+03 1 6.97E-08 583 1 1 570 4.95E+03 i 6.98E-08 1 584 1 571 4.96E+03 ) 6.99E-08 l 585 1 572 i 4.97E+03 i 7.01E 08 586 1 573 4.97E+03 i 7.02E-08 587 1 574 4.98E+03 7.03E-08 I 588 1 575 4.99E+03 ' 7.04E 08 l 589 1 576 5.00E+03 7.05E-08 i 590 ! 1 577 5.01E+03 7.06E-08 591 ! 1 578 5.02E+03 7.08E-08 592 1 579- 5.03E+03 7.09E-08 .
593 > 1 580 5.03E+03 7.10E-08 594 1 581 5.04E+03 7.11 E-08 i 595 i 1 582 5.05E+03 . 7.12E-08 i 596 1 583 5.06E+03 7.14E-08 597 .
1 584 5.07E+03 7.15E-08 598 l 1 585 5.08E+03 7.16E-08 +
599 1 586 5.08E+03 7.17E-08 600 1 Page 12
a j.
l ,- A He< % 4 2 4 PSL- 2Fw-9f-cc.1, Au 1/2 l - - . - _ . --_ _ . . _ _ _ _ _ __ _ _ _
_ .,_ Pa_ La__ _.
FROM: D.H. Faulkner DEPT: CHEMISTRY
SUBJECT:
Normal Unit 1 Reactor Coolant Rb 88 and Xo 133 Values UNIT 1 REACTOR COOLA'NT SAMPLE ANALYSIS Aaivity reported in uCi/cc. <
SAMPrR DATE/ RIME RB 88 XE-133 26-SEP-1996 09:05 1.98E 01 2.86E-03 24-SEP-1996 09:05 -
1.75E-01 2.47E 03 22-SEP-1996 00:50 1.78E-01 2.72E-03 12-SEP.1996 08:48 6.51E-02 1.64E-03 .
10-SEP-1996 06:50 5.46E-02 1.29E-03 8-SEP-199614:10 1.01E-01 1.39E-03 6-SEP-1996 08:45 6.70E-02 1.48E-03 5-SEP-1996 08:30 4.22E-02 1.16E-03 31-AUG-1996 22:20 2.57E 03 3.45E-03 31-AUG-1996 01:50 1.62E41 2.65E 03 27-AUG-1996 02:20 1.10E-01 2.09E-03 25-AUG-1996 00:50 1.11E-01 2.03E-03 23-AUG-199610:20 1.80E-01 2.87E-03 21-AUG 1996 09:45 1.48E-01 3.33E-03 20 AUG-199610:25 1.26E-01 2.92E-03 18-AUG-1996 01:40 1.72E-01 2.37E 03 17-AUG-1996 01:30 3.24E-01 2.55E-03 16-AUG-1996 08:45 2.38E-0? 3.29E-03
'Ihese values represent typical activity levels for this time in core life and with little or no fuelleakage.
If you have any questions or need more data, please contact me.
Thanks, Dave Faulkner Chemistry Supervisor
i..
!* STEAM GENERATOR _.
l REPLACEMENT PROJECT-PROGRESS REPORT
- MARCH - APRIL 1996
/
l 1
l
/
?
s I '
' s
/ <
/
i
/
Cie N tf
/ \,0 / .
/
/
i o* x r
- /e Refu f
?.
- i. _-.. - -- -_ , .- . . _ .
- .-2.---
TA B L~E="r *^ a hlTEN TS
~ ' ~
l t
i General .
The Steam Generating Team (SGT)
B&W Canada Steam Generator Fabrication Engineering i
l Quality Replacement Outage Preparation i !
Attachments:
I '
SGRP Budget Status - Capital Dollars 1
SGRP Budget Status - O&M Dollars 1 Summary Bar Chart for SGT Engineering / Design Pkg. Development Status Graphs .
. Construction Work Pkg. Development Status Graphs Steam Generator Fabrication Status Schematic 4 Summary Bar Chart for B&W I
Photographs l Steam Generator Replacement Outage Schedule ;
t i
0 eseep . m,. * .=e e m_
"~~'~ ~ b l ... .....-. , ~ ....:. ,- ~ ;.L. : --
ST. LUCIE UNIT I SGRP IllGilLIGilTS REPORT l
~ _ MARCII - APRIL 19% . j GENERAL l
The MK-F contract organization responsible for engineering, procurement and construction has been l renamed. The previous organization ,was comprised of Morrison Knudsen (MK), Duke Engineering (DE&S) and Framatome Technologies (FTI). "Ihe new organization is called the Steam Ovnerating Team (SGT) and is a 50/50 partnership between MK and DE&S. Each of the three entities is still responsible for the same scope as before. MK is still providing overall project and construction .
management while DE&S is providing design engineering an licensing support. FTI continues to )
provide technical services for reactor coolant pipe measurements, decontamination and RCS pipe I machining / cutting and narrow groove pipe welding.
TIIE STEAM GENERATING TEAM (SGT, Ltd) l The structural steel and bolts for the Main Steam Trestle PCM have been delivered.
Engineering completed review and preliminary approval of work packages which have incorporated FRG comments.
SGT is continuing to interface with Mammoet, the rigging contractor, to review heavy lift / rigging designs and resolve comments.
MK-F SUBCONTRAGTOR
SUMMARY
SUBCONTRACTOR SERVICF1 MATERIAL STATUS 1 Davenport Mammoet Steam Generator Rigging and Engineering 2 Transco Products Inc Transporting Development 3 LAW Engineering- Steam Generator insulation Engmeering OSG Storage Facility Soil Boring Development Completed 4
.t.
ST. LUCIE UNIT I SGRP IIIGIILIGIITS REPORT MARCII - APRIL 1996 B&W CANADA STEAM GENERATOR FABRICATION Curwnt Status i
Assembly of the heat exchanger sectio'ns in Cambridge, Ontario is nearing completion. After completing the machining of base supports, the units will be cleaned, closed, nitrogen filled and prepared for shipment to Mt. Vernon, Indiana where final manufacturing and assembly will take )
place. l 1
1 The new steam generators will arrive on site prior to June 1,1997. '
The table below shows that five of the six new contract milestones have been completed ahead of schedule. All other B&W activities are also proceeding ahead of schedule.
B&W MILESTONE STATUS M/S S/G MILESTONE STATUS TARGET ACTUAL NO. NO. DESCRWrION COMPLETE COMPLETE j i #1 Final Weld Repatr - Weld #4 (Stay Cylinder to 2/1/95 12/24/94 Pnmary 11 cad).
2 #2 Weld ID Seal Pass - Weld #4 (Stav Cylinder to 2/1/95 11/18/94 '
Pnmary Head)- l 3 al Complenon of Pnman llead to l'ubesheet to Shell 5/9/95 2/28/05 Assembly Welds through MT repairs of Support 4 Base to Shell Weld a: Completion of Primary Head to Tubesheet to Shell 7/5/95 4/14/05 5 Assembly Welds through MT repatrs of Support 6 Base to Shell Weld Both Completion _of Tube to Tubesheet Seal Welding 6/l1/96 !6/06 Roth Final Delivery of S/G's at PSL 6/1/97 M:iior Accomplishments Cambridge, Ontario - lleat Exchangers First Unit Lower Assembly
- Com,pleted hydrostatic test of primary side Completed post hydro UT exammation Completed eddy current testing of heat exchanger tubes.
- Machinine of base support is in progress
I ST. LUCIE UNIT 1 SGRP IIIGIILIGitTS REPORT
~ ~~
--MARCII -APRIIr1996 -- - - - -.
Second Unit Lower Assembly
- Completed hydrostatic test of primary side.
- Completed post hydro UT examination.
- Completed eddy current testing of heat exchanger tubes.
- Machining of base support is'in progress.
Mt. Vernon, Indiana - Steam Drums First Unit Steam Drums
- Drum has been upended for assembly of intemals.
- Completed installation of secondary deck seal skirt and primary support skirt.
- Completed welding gooseneck to feedwater header.
Second Unit Steam Drums
- Completed installation of sec. manway covers and linkages.
Intemals
- All Ove separator modules are assembled for both units.
ENGINEERING FPL has been working closely with B&W in the review and acceptance of the B&W Engineering Reports. These reports cover all performance, stress and design issues. There are only five reports I
of the 26 t,otal that are still outstanding. The final report is the wrap-up ASME Design Report ,
which will be issued 12/1,96.
B&W's transportation plan for shipment of the heat exchangers from Cambridge, Ontano to Mt.
Vemon Indiana was reviewed during a Design Review. One of the actions that resulted was that FPL will perform a manne survey of the channel depth from the intracoastal waterway to the barge slip after the 1996 hurricane season. In addition, FPL will do a depth survey of the area west of the si p, which will be used as the unloading area The steam g[enerator disposal effort requires a characterization of both the extemal dose rate and the radioisotope content of the primary side. Dunng the current outage, radiation profile surveys were performed and will be sent for radioisotope analysis of the cleaning material used during tube pluggmg. The information will be transmitted to the vendors for fmal bid development. Bids are expected by August 1,1906
. l
. ST. LUCIE UNIT 1 SGRP IIIGIILIGIITS REPORT i MARCII - APRIL 1996 l OU AIIIT l Surveillance continued at both the Mount Vernon and Cambridge manufacturing locations.
l Acceptable RSG quality was evidenced at both locations. The eddy current test cycle was completed l for both RSGs. The results are that the tubes are acceptable, crevice depth is acceptable, no missed Gxpansions, and no tubes required plugging. All tolerances were in accordance with the applicable drawings. ,
REPLACEMENT OUTAGE PREPARATION Attached are preliminary schedules of the activities leading up to the outage and the breaker to breaker outage schedule. l 1
i Distribution: j T.F. Plunkett i l
J.A. Stall W.H. Bohlke K.R. Craig -
C.L. Burton l D J. Denver H L. Fagley J W Connor
- J. Marchese C.A. Pell J.C. Scarola C.D. Marple SGRP 4
d 4
I
ST. LUCIE UNIT I SGRP BUDGETSTA TUS - CAPITAL DOLLARS
-l l' N ! $ l U 9fi 6.000 y
- 20.000
_?
s 18.000
! =
' MONTHLY BUDGET ' I 5.000 ' mMOhHLY ACTUAL 9
- CUM DVDGET .1 16 000 a
+ CUM, ACTUAL
_l ,
g y 14 000 >
- G
, .iu.__.____.._._. _ - . _ _ _ _ . . _
__ o , _
5 z ,
o 3 b #o, 12.000
- s 3
m #
B
, g a m
n %
g a non m
O s
{e '
i 10 000 g a
m a g ,' - e 000 O
g fn .D g ,000 m 5
g E ,
,' e.000 g
,o
- o' a nno t 000 - a" i
~
~
, '( ' _ m l C . uuu
- ' s Y g s *
- u-__..._______.
4 g 9 g y g
= 2 , ,
e : m 2 - . y a : r 1 s = ,
- a o e e
($000)
CURR MONTH YR TO-DATE TOTAL TO-DATE YR-END FCST BUDGET $752 $3.968 $65.209 S18.881 ACTUAL /FCST $407 $1.373 560.892 $13.033 VARIANCE ($345) ($2.5,95) (54.317) (55.848) lSignificant contributors to the Year-To Date budget underrun: I
- SGT payment schedule was changed due to the rescheduling of the SGRO fro 9/97 to 2/98 ($1.791 K)
Deferred payment for blowdown line analysis done by SGT (5100K)
- Deferred QA/QC contractor support. ($245K)
- Neactiated ehrt,unation of BWI scope change for barge transportation of new S/G's. (236K) f 'ULCR$EOWDRCv'*CPSRT&SW AR\C AP9t,04 KL.W rem Daie 5/17Ev6 WJC
ST. LUCIE UNIT I SGRP BUDGETSTA TUS - O& At DOLLARS l 1/>R// / 996 1
1
. . . . ~ . .
80 r 1 600 l
=
MONTHLY BUDGET l !
MMONTHLY ACTUAL ,0 70 - #
{
o - CUM DVDGET -- -
+ CUM ACTOAL ,O )
Soo 1 60 - - - -
8 '
H h
Z ' 400 b !
O 50 - D i E :E i p 3 ma m
~
}O 40 - -
0 - - - -
g i
O 300 d I u ,0, O O O I m
, u. I
, O l o e i 5 30 e
@ l
- 200 $
O , a b '
20 , * --
inn I 19 , _ - . _ - _
n . . .- - - .- .- 6
$ $ $ $ 5 $ $ $ $ $ $
,E 9
- 4 ? E 3 0 ? s M M a :.- t n + -
.i e u ;- a (s000)
CURR MONTH YR TO DATE TOTAL-TO-DATE YR END FCST suDcET $57 $189 S1.293 $550 ACTUAUFCST $15 $51 $944 $550 i VARIANCE ,(5,42) (S350) 50
($138} !
~
Significant contributors to the Year-To-Date budget unde ~rrun: ;
Project Support eff0Ms are DelOW the 10 Vel estimatea for the 1996 buaget due pomanly to the hoia '
aced on thc 000 Stora3c Facaty iMauscl cum) end tb.c chmination of the Main Steam Trcstle PCM from the 1996 Outaga scope The Mausoleum will remain on hold until August 1996 when it ic anticipated tnat the OSG on 'ite storage vs disposal alternative weil be decided upon. The Main i Steam Trc ; tic PCM has becn defctred until the SGRO in 1998. !
l 4
r w,CRSEOWDRCf.RErWate. AACMA;4 X,.N
- nnt Da:e S/;GW A;;
a S 1 n'
e
.j
,L s A d 1 o .
u 0 c . .
n /
4 0 e r
K '0 9 t . u n . . ,
, . s.
o . , .
n i
s .
, , e s
A . , . , , . , ,
r 1 0 ,
. e :
r 0 0 . ,
.o .
o /
1 9 2
. ,', . c M 0 9 1 . . . , r n e a
. 2,
,O A . . , , . , ._
1 o , , .
=
o 0 '
/
0 7 t . .
1 9 i
) ' ,
t 1 o n . , . . ,
s 0
/
o .
e 7 7 m 0 9 s B ,
(
A ,
< 1 0
o o
8 /
4 7 2 . .
9 E 0 9 1
. i,
/ .
2 G .
A ,
. 2 1 o .
C
- A 0
/
o .", ,
O 1 F 2 0 9 1 i
3 R T . , ,
.N i
C _
G .
.I y
O S U n G
.S
.N 5 o A E . 0 0 c G .C e 0 /
0 6 2 L
G N
E
.I
.L t
1 9 1 A - .
o S _
P Y
- i - -
l R
l O 2 2 _
G E - .
R E E k .
3 R 1 o S ~ .E S
0 o H A L
A _
P / -
I H
A 1 6 P t H _
0 9 i .P E i.
i I > E S ,,l C -
U -
U G 0
0 4
D E A
(
0 0 f f
0 1
0 11 0
0 4 H 01 9
0 0
9 D
3 1
0 3
0 2
0 0
6 it L l I
e I
i M
m y 8
7 1
7 3
F t l 7
8 7
l
?
l F
8 7
8 W
l 8
0 8
F t
9 8
F l
P 1
F 8
1 1 1 I l 1 i l 1 1 l 9 l 1 l 1 1 8 8 1 I I 1 t i B 1 I 0 I 8 I 8 8 T
S t
in i
/
1 7 5
7 1
l V L
1 1
7 9
/ NN /
E 7 9
/ N 7
5 55 /
7 9
5 B
/
l l
E 1
/2 2
/
3 f
l 2
H 5
1 1
/
2 R
H f
3 4 D
/
5
/
5 2
/
7 1
I 1
R /5 5
/
3 7
/ I 1
1 2
B C I 1 1
8 I 5
8 2
8 7
1 9
8 91 !1 1 1
5 0
2 1
1 1
t s
a K
t E E l A K
l E E K E l A l !
K a
t s
t ot K A t z
l E
1 0 0 4 L E
0 8 1 g t t t t 1 t t f
4 g t
a t
t 8
8 8
1 t
s t
8 t t
I 3 I.
8 8 f I 8 8 f 2 E 7 7 1 i '. 7 7 i 1 ? 1 7 7 1
ft N 5 1
N1 3
8 5 N
?
S
?
3
/
11 52 5 S 5 5 J 8 5
5 5 5 3 15 R
I 1 1
- i U 1 1 1 C t 1 li * @C # / 1 1 f
II
'e !
l / / / / / / /
J.."-
t ? 1 '4 5 5 5 6 6 F 7 t 4 8 !
c I t l 1 1 D C 8 8 0 O 4 i 1 1 !
P
.- u i
E'
.i
% R 1 TI 5 M s . .
- 5 I E 5 E F .: . -
I
. 4 n tt $ ig Er t
aa A
I .
_R
.!n ID l
g i i. p P 3 r t f r M5 r I
l F
'N 5
W . i I 5 5 t
I 4
u D F4 .. s,.,i ..
a 5
[ _E l s m t
s P P M
t a 5 C ! .
i
% T _m i
l' i 4 v C !n I
. ii .
. ,..!! r 1 E
l t l ; / I ; L
- s.._ i l
a 4
A E s t I it i
f; 9
5 I
l Mw f T
l m SEI 3 % 5 O
3 I
R i i.e- n.. -cc.i iN R 9N t
, P il I
C f ia 4 il 3 % /
b Il l
I8 0 15 II K ta
- x. 1-. "
I t l
, l s u D a tt E i
R i
[
f f
5 K / A f ti K l I
R 3
A B
I R C t i e,..
g I t l s C 4 I 4 5D: v C i I l 4 t
-asm A
oc ac
. F 8 f IT9 1
_ Il 1 a
ct
( is H*
t s ' [H E QE _X G9ih T
l t 4 g
(
P r
i U8 P
L I
P WI s' F 4 E 4 TI H'U 1
- KT 5
1 3
s 2 h
. : a P
t 7
1 1
t ' S 4 4 W I I P [ 3 W' [ 2 I
3 9 5 t
o
. . ': : s i ) E 5 l 7 O 1 i ei l W 2 a s P P D M E B a a I $'1 F Tr 3
E I t 1
. 0:l 1 2 l t
T T U 1 D' T
'1 1 1 U D T T T t
o w =
w e
CJ E .
i- -i -
. li o 8
- 8 c s, - k. .
. . . . t g a3 . . . . . . . .
3 C . . . . .
. e O * * * * * *
- C M
sn : *
- : a e ; *
- g. o g
C. o o : . .
- a ..a >..
o g u.. .
.g .
l
=
g ,g
.e.-
4
. . 1
- 4 :. .:
o 8 * * *
- . . . . .M oN h, .
.': - . . . . ..4 *
- 1
- m= : . . . - :
- l .. :-:
I 4
I
,. .; .. . . j l
M =
4 LO o E .
. . . i l
O > h h, om= . : .
CO I l . .
I l
l 1
V o 8
- O .: - - +
i l
C %
mW ; ; b, i i N *
- cil C.9 .
. b. . . . : : : - :
- m
.::t o 8 = - -
u l s -
- i. . .
O .c, !
- k z, o n, . . . . . g 3 9 ..
C 5 + + . .
(.D U
o w . : .- .
. x WD $ *
. i i : .
- o
. g i u -
e i O R W O i i o eA
- m
- e c. : c M o C. I *:: '
M C m:.
. N
(.O d a h .g fD C 5 8 3: e C- s~ eN :
y om- :t -
H A a ~~
C) l
--) l il : #
J . R! 8 E .2 X! R- D- S
- R E R lie,E R: lek!
2 R 8 8 m R G
e
- a. a.
. . n.
m =. . a. m a.
a
. a.
. a. a.
. . u. h.. .an. .n a. a. . .a. .a. a.
. m. k g = = = = = = = ::: = = = c c' c::: == c c = = = =
(g 5 t' P ~
E E E E F E E F g N dE fE!" E P' E F P g c G b G 'S E E IS P =: W .s EE=;=EZ" E # E i 4 ==
$. 2 = d = = = d = d - w = = = = =
i:.r' = =
a a a a a u a a w s
-. L.L -
a a a u ==.u = a a a E a E E = = = = = = = = = = = = =f c =! == = = = = E s b W E E P E ~~ E E E E E E # E'E E:E E E E E E E 4
c P
d s. # M d =
E si E 6 is a a W E
=
E T2
= d d
i5 = Ei E -=E2E E =
E
E E
=
E a
g -
..= . -.
l ,
- n e t:' - cs M
- g -- .
g
,, d . n v -
., [. 4, e., 22 - g - *
- c-t w g
. r _ s . . . , e w = =
cc 3 G -_.
- - e ===.r a 8 l y.: y
=::
2
! =. =
r3 i
ie ,g e _. = ,. .
= = , E e .:
s = ec y ce - -
e =- - g j :.: i e: --
- -c= . *.
. ;, ._y M g a .g -
- c. c . .
i
=. a .., .
i ,- .m
.... , _ . e = , =r g s e , ,,, -
lo....
4-
- n. .., s = - - m g u e ,_ a -
= w
-c l= Ig 5g
,. c %
- r k.
s e a
- c. G .e a ewm "u .E.
tr e M m an .a . =
= _
r na..r.
... a, e, .m- .--
wg m m .
i .__ -
m w a -
e , E. - la 5 ma ee +-q - -
o
.- p a. - .-vg g e w m ..
.es g ..-
a '4.-
g w-g =
a g g w_: c .r. -= m =
, y
'a g s : cs.-.-g G =:. -- na g ., ;;,,, o g ~ g g9Ba b gt .c. @g -- d E h m.a@er. c= = .M =M = g g gE.
-- - - ,r
... ... E' 0,I e rm i t ; & ; .", = g E ~3 0
~ ~0 5 ~ ~
U E U G
- ~ ~
S
~ ~
G 5 ~ W GY1.~SS -- .
E .e .s 5 -
0 0 _
..-. -,..... ST LUClE SGHP - SGRO: 2/98 (Best.) Mirrison Knudsen 0:'::'...:";",:;, , .. ... '"
=:....
- n --> PRE - 0 U T A G E <--
07/ot so/ot 01/05 04/ot 07/01 10/01 01/08 04/01 c 96 96 97 97 97 97 98 98 9 12 00A 12 00 A 12 OOA 12 OO A 12 OO A 12 00 A 12 OOA 12 004 1 Il GUIP110lt _ ITati [jLii[ E Eill
+
Sa pt rinbl - lent nes St,n 141E-0UT4GE - Con tinued ps12 - mest a v - tant muen l'HASE 2 - PROCUREMTNT - Con :1nued its Filin7IPmai(ctp a 12/r5N sa sta 12/12/97 81 8 7 00 A ' '
' " "A""""
t'
~
li's til 10 SIP Filf t IIst111% 12mM 88804 12/tw IIBF 00 tn .... ... .. .. .. . . . .
G Kittlil!5 FPL ACTIVITIES U42 R Reif t t AMD6 AfdTs 82/357 98 M4 81/2?51Ilar CD ' ' ' " ' ' ' "
77E R 10 Ftfl1 E ti, 84/14N it E4 14/11/97 818DP 90 g
1 outel* m ss ma . . . .. . .. .
T348 A.% BW5 I4 EVIL # 1 14173N ill:4 C6/R3/518117 10 tPtn ' ' "" '
12 5 R TO P0Y1319 Caf 84/ESI 88 804 14/I/37 87 821 05 "[
ctIrlmts a ss initu ' ' " '
C6 4teive 114 5 3 kiess frs 11/BtSi 85 001 15/E!97 I18@ 00 N' S I'd E ... . . . .. . ... .... .. . .
1228 R ID PCf;I E/T illfil% Mili? It El 11!2B/37.8117 IM
Ran 10 Ji " '~" ' ' ' ' ' " ' ' '
T211 R IB 15IDlait SR II/IW 8t 304 11/31/37.31 8 7 El f'
- -- r-SiglitR avisiff - - -- - - - - - - - - - -
- n. R ,, -, ,, n, ,ma ,t ,,, ,ma ,, ,, .
- n. ;"M"" , ,a,E ,, ,, Ima ,,,, .
r -
CfIII:silm in sa PREW M L E OF.HO I i Signetween
' e a-r i . ... . .. !
A - s i . . e ..n . Sc. area Dy C3. C2 s>c e ss .
l umme-cc . . e r o i l" . -.
. . _ . . . . . .. c r-
~ . . . - , . - ST LUCIE SGRP - SGRO: 2/98 (Best) Norrison Knudsen
- 'o..:" T :L.,.. ...
=:
_*st e e.
,, w ::-..
._1.
--> PRE - 0 U T A G E <--
01/01 04/03 a 07/01 10/01 I31/01 04/01 07/03 10/01 9G 96 97 97 97 97 98 98 9
[I'D;PTICn ITG DMI{ ll O 12; OO A 12 OOA 3 2- 00 A 12- 00 A 12- 00 A
. 12- 004 12 004 12: 00 A 1 13 ga N <tf u SGil l'itE-OlH AGE ESSE 54 G itillir r4E W SG S1 ]AAGE FAC (LITY g IQ tUI 11 SA I!h? ',:JG 88l'IN 03 Es tW N 81ty 100 O , f IEIllIl II T M L. . .. . .. ....... .. ... . . . . . ....... ... ........
j ED % 53G TKIllir BLD SG Si lRAGE FAC ILITY I
- m. .
4415 Gia 5/5 Drosion tr IPL - IU2/1 tiKi ta/I/Iil17 to A Streer g _ , ,,,, , ,, ,
4419 G7 SK SU!IIsl5 8 ft 81'UE Ct EA 31515 IlBT 100 NI'JI . ... . . .... . ..
40 (UI S/E 5ttG f editlif - O!!MI #3 E4 01%T 11IF M frlyd tr iM ,
Rt:l l3 t*3 PL AtJT ISL AtJI)
CC (UI tait ml fil:0 ilII:15 C45tN 09 KA E4/?t/511187 IT 9,,, , , , ,, ,
CE NP fAI aa F04 G 84!2?N CR EA 84/2 Big; 31sy 3 0,, , ,
cc AIIt SIP itIHL illt 84!2BS1It El 85/l5/11I127 100 O BATIMS I[tA0 E CS ,,,, ,, , ,, , , ,,, ,
C4 NPA15/5 9tDA3N, G4 Ai l'it5/91 It 21 8599/57 31ty 3 0 9IP 82 8 EI SIIni E'tillI% KilHD 15/!BN It El 85/18N 81til IS I IN . . . .... . .. ... .. . .. ..
491 IM 33/5104 Eu STI(8 15/11M lt 54 65/35 (18P i/S O EviTE , , ,, ,,, ,,, , ,,,,, ,
CSI 5tta nR!aG E sto !F OB,T,4510t En !!!31/37.811F EM ' '
a us , , , , , ,,,, , ,
4ZE IGill l[f fl[CI PMR I!LUN lt 21 11/17N 8117 E ' '
Ol%11 419 R t1tiinE SIMI 105tallt El ll/B/E llt? N , , ,,,, ,,,
42 4 (Lil I41TX:5 - As %$ !!/315111EA 82/28/911IF B10 , ,, ,, ,, ,, , ,,',, _ , , , ,
CI [1tCi ElDDE 80Cli6 8 IID it!IW lt 004 11/215.118T 12 C3 E . ... . . . . . ...
LEGEHd l SignatuPet
_,.i....... :
A - u s n e ,, , .... .
l :ior't ets Oy C3. C2 pr.. a :
l M.C.
.. e- t t i e se L . ..
n o l' R ;'
, li . ,, . _ J j , '
e! .
s 4 m d 1 0 e
u A
0 0
/ e n 4 6 21 u
K 0 9 t n a N
o n g
s . ,
i i ,
f, ,
A ,
e 1 0 l .
=
S -
r o
0 0 . ,
[ .8 p
k2[]
/ - ,
0 .
M 1 0 21 l .
r 0 9 ,3 .
,C,C
, I, e l .J
,l, f,C,',,
i .C=
A ,
L
.I
=
1 0 0 0 .
/ - ,
0 7 2 1 9 1 E
)
t s 1 A
0 R c B
e /
0 7 7 2 0 9 0
1
) .
( .
A
< 1 0
0 0
8 /
4 7 2 9 E 0 9 1
/
2 G ,
A ::
2
- 0 , ,
- .A 7. 0 : ' '
C O /
2
,G R T
t 1
, 4 3
C
- ,I l
G S U :: ,D
,L
,,I y
D 1
4 0
- 'U E
,J
_t d
- 0 0 0
- ,B e
/ O ,
0 6 2 1 9 1
- br
,T i
r 4
o P -
b u ,. E' S
R E
,M Z
,N G E A 'T
,I
,A S R 1 0
0 0 N ,I P ,N
/
7 i H 2
,O k
E 0
- 1
'I I >
C -
g 3
U -
B 0
2 0 0 0 0 T 0 T D 0 9 2 S S 2 D L R 3 0 5 6 ! 6 0
I E
2 0
1 1 E I 2 I
E R
7 8
7 1
7 7 T 7 F ? 7 7 y 7 F 7 ? 7 0 8 C 0 D l 0 1 l 1 C 0 t 1 1 1 1 1 I 1 1 l 1 l l 1 T [
1 8 $ 1 I 1 8 i 1 i l 8 7
1 !
! l l
1 1
I 1 1 E E E B 1 E a E E E S I M 5 5 W / f W fM f $ /
W /
E
}'
W fV 1
] 8 3 M f] !
3 &
1 f
2 2
1
/
1
/
2 1
t
/
?
l t
/
2 E
/
2 1
l
?
I l
t s
2 1
t I It
/1 1
D
/
6 2
0
/
2
&1 fl 8 8 1 I 4 4 1 l A l l A A t A l 1 l 4 A E
0 0
0 0
0 0 E E E E E E E E E 0 0 E E E T
A 8 d 8 t 8 t t R t t R t 2 ? t t 0 B 0 I 0 I I O B I O l T 1 7 1 T 8 ! 8 I 5 fB 1 7 1 1 A A5 S 1 7 E L E E f
i 5
0 5
11 54 34 1 1 t ?
5 4 3 O f
/
9 f /
1
/ ?
- 3 1 2/ f?! R
/
1
/ # # B 0 ? 1 1 1 ? l*
! / / / / / /
. 1 ? ? 2 / /
11 1 1 2 t I 4 ? 1 1
~
1 1 1 ! ! 1 1 1 S I 9 I 1 1
.' 2 5
- 5 E M I[
t !
! g .
.. n G Q(y I I
t 5
G 5 % t ni i
n.
I T3 l t L;
t w I 1 Y ![ 2 i /
S A E ta i N
i 3 if3 G IE R f
- M 4
lr U
I
., e.. i
.0;a
.! ) :
U I
I i
4 R-I-
f R _
E 4 G E
% M 4
1 t !4 R
l 3
T t
Il N
A E
N R
'll
. fl 0
e M
E f
f E
le t
r u
[
i E 2 M D
I e.
i e.
n i 5 ll % % (s ttr IEl l
i I X14 I R A h ,.:. ".,,
i P
- wI 0 :
4 F3 %1 1 E I E d s 1 T 1 e 1 t a sev .
it. i E f TA U AI 9 I
0 A 1 I ! 5 i 5 n 1 3 f s e D lgII A a IA 1 A t D EI l3 O l I t C A C R R Na M 1 4 iA 1 I I 3
I e r a
O t 3.
a
. i
- iu'J S I 4 J l E 4I 1
f I
i M gI s
I IC i l t 4 G11 N
Ik I
l 9 E i R
lnt i u a
&M i
J IN Ae-m-
P L
.C. - : q 2 P I : N L I
1 F
- t l
E a D l
P E 1
(
l l
I 81 it l
f U
R I
P 0 S L M !?
I 4
M mh t T IC M
)
m-as .:n.. : I R
t 4
G E
M % ; ,.
3 3
1
- 8 1
5 4
I I
C 3
4 1
i t
t 4
E et 1n f
4 4
5 4
E 7
4 I
T4 l
a i
d 3
5 4
51 1
1 A
PL 4 2
1 E
9 1
iD C T
't l
t 3
1 0
0 L E
h.. s .elu Pape ce 9. usee m. .
sm Y r An nOMn rWE5 Mn CAN CAN CAPA M ML t; e sanont nEAo snerr sntu sntu cANcoNr cout ar a2 Assv
_. s 5
g i i ii i
. ,- _E_ . $%. ,
U' u P l l N n
MWNg *9+n 0.!
, t p
- i M, hnd. h. m.r
!' im :
- e
- . ;: :233 - z.
- i - gar i i_E D[L:
5 y ? *r. N, *la I* I A, $ 1 yI j
- I
^
~
,, t.
}
- i , '
t* I@ i 2 -5 .-'*[ 1; 2
i +e 7 A
- A -
f $gy ' _
o $ . C h- a - -
e r
{-
'; [4 *' ,- .;
" J -'
2- /
2 ,
- tx
, ; 4 - +
. C t 1 I Q
2 ,,,,,.
z '; ; ""
. ,' * !. J k ,, J p-
- e. ;t *.5 - ~ - #
1* tr., -
+ > . =
g
- T
? {
I ; Cg @ f,
. , I *.'s L C * * ~
C r-
, ; v: 2,a o # - $2 cz - :
w -
7 C
(
At men 2 ; s e - :: : -
~
- - 2
- ; y A
- 24 r .
\ . t . ' , . ' z: ",' ;' s-
- : -- ;I= -
c- - - ~- +
l
~
fi 7 -# l' ~'
? ,0 E
~I dQ D .%.
r g%
l $ u g'I == % ' .ma, ,
., . . . . . . . . ...A % %
%% N m: '
3 L
e L3:e>
seconoAM SHEu
~
STEAM DRUM w %N O w %,
sur su mer muAny rter. ' neca. secoNanny towwn ' itses MEAD sNffT SNEu sNEU CAN
'sma can cAn CAP & PErAL Q>
kA,%
CONE CONG c1 c2 ass'r W - ,
j IEE M% - b -
5 p D
. commmaq,j s . ~ a r
!!=
E 9 . .7 3 , E-k- , *i-
'N
. n =m e e r s .= c y e e
- 5j dE-s g 3, r. = - .- -
2 5 ;; 503 - j 0 c g; j h l; l o =
R d 9 ,3 e
- g z o
- o - oo *E : 3 : ;-r 5 ,3 e 5;
8
$ a=ii,0 g*
6 -
1 -
g! A"J' ev 3.e 0
- o
- p;* o b' s* s 9a 5 i 3 :=
'y,- E- =a
- 4 . - 5- - 'M # wA '*
2 o 'd Q'
'f a 91 E, <
- 3$P 8 3g do 3 wm -
2, a 5 - 2 ? ). $ h 2 -
- J. _ 5 $ e A 2' ,3 5 ? $6 b M 'E 3 ,
O C
M *6;$3 c 7:$ 5 5%
% T s' ;% c h 7, 8
O
- 1 s m A <
J E :
$7 l
?; TV13 : : { g5) ,
, 6 ;- -i 3? .- ?. ;; O 7
, ~ ? oc 2534 + .r3 *
- e . t 'a c s - e ;
gg 3O?; 6 {'3b WS ? $ k 6 C 0% 3 $ E 4 P.
T t
I wm G
- j yI'
? 4? 3 5j s% 3 's @ 9; 0 6
' ~
FF .f C 48 : ;$ 5 : $ ~-
~
E
, n- ,. = 2 : es ; s -
3 - o
- ; = 's F '
g l
',- a r
~
W P
- l. I sI "e F
.a m .-
- . ~ . . , - _ _ . .
h
fAEY EARLY ICTL 1964 14th 1996 START FINISH FLT 1991 NOV 4EC .JLN FE B W APJ iMAY JUN JUL .A'.JG SEP rOCT NOV .DEC :J Am FES MAJt APA .MAY JJN JUL . Adr, SE P GC* NOV C EC J AN f[$ ogA3 . App MA y
, CAMBRIDGE 5 HOP MANUFAC"TURING 21 Jt. ele ta 298BP9ta M 14 939 PULJ, LAT'rtC1 Ga!D MST 140Cr84A - 41stANS4A - AAaS20 SSJat 3EEAD TO T/A Iln AMELA Met Smaf flA 22AUD9tA M 34 939 PWiff SMELL TO HEAD AS$v 11JUL95A 18AUU9tA '
'M 34 948 Df5Th&4 SMRCKD 23aAE391A 340cT96A i M 34 952 INSTALL 1ATTICB CR. 05 21CTT9tA 31DeC9tA j i M ; 34 955 1 META 141UBS8 6 U-DEPEJS 11NN9 tA 13J&pl6A M 34 951 $$AL IPE$a CF TWEB { j 1a=9. it,.9u ,
- i 3. 999 4..r. T.,7 A. n=1, Ei,uD .i n,=9. n M9u g I ' {'
mem l n.9n evt.o.mie Tuf LAPR96A 31MAY94 44
~
- '[ 344999 F*NkL A55Y alfN94A 3ss0V94A l 35 199 TUB 83MEST A88f. [, ( ~
F t3CT94A 31DSC94A AssY 310CT94A suwsea M l 36 389 58r'a=Ty#
l 35 399 ptZus.sf =AD AA5Y.
, [
l l j u fu -D u A nummmmmme n.nt ,Uu. auD i&mC. M.,
l l j 19.cT9. oh.,9= .mm u. 01 + - M., i l !
l 1JEUV94A 16Jtsetu 39 920 rain BEAD 19 T/s To suR14 i
$JtEf9u 240CT9 tA e 35*939 PetNT SMELL TO EEAD MSY 29aEP964 250cT9tA I l *
( l W 35 940 3 META 11 ru.mm j )
33 CIT 9EA 1*IEN9th M 35 992 INSTALL 1 ATTIC 3 QR2D5 I TNOV9 6A 18Jhsr94A M 35-999 INSTRId TUpas AND U SENDS 14DSC9u 2 FED 96A
- M 3S 957 $8AL trEIA OF TLESS e
GFEB9&A 12MAA94A M 35 996 EELItse TRST AND FINhk E1FAND 13mutu asAretu ;
j ls 9n svDaarraf C Tart
,i t n a&astu '
14.ns.u 30A789 th 12JApr$6A
.4 j i l mb '3s.uf rtshL ust 43-623 PEEDMATk2 aED8EZA 4 EDS MfY 15JWe94A GeeM 9u j M 43 035 ptIssaar MaAD MMul&V 21maa 94 A 1 ? rg3 95A M 43 031 SMS SUPPORT I l
3 3Jutta a sseav9ta m 43 047 SHROUD ImmTIss3 p1sts ISAUG94A 14JUL9 &A 43 052 FU14 GRID EDE18- ,
33Jaae95A tes&T91A !43-854 ENLID BUProrf 6 trEDGES -
3 S FES91A 4JaJe96& j 43 964 U-SEND SUPPORTS .
SDSC94A 11.%gx39ta M . M' 43+051 FULL WJD 1ATT13 BAAA f
14NDV94A SMhA9EA 43 083 stAMMkr CUVER 6 OPENTMi PORGIMG g 23eeha.tu 25AII395A l '
43*090 SE1FFEE3 & NYr40 tas? l l ,
178EW95A ' 35JaJe9&A i l . I* ' l l M 43-301 katanc WOth.J Pr.mG23E3 & C17 e
- wr.vErd ON SHOP MANUFACIVRING j j i ,
&cJuta nottu l mamanumme u *40 ;s=cEm c== ;
l i i 10ausu 12 str9sh n e44 sumouD mars s3 a 03 l
, _, l 2SJtB'94A 16 PEB 94A l 34 04 9 SMROUD EITEMSICus & Ctedt alert 94A 2 9=wu A sua u.004 375= Dem suIu. cu uMOvt4A nahntu m 34 909 sseanDaar ces saevices 1seaf 9ta 3Jtset ta j $4 409 Susp0UD Chr AASV ,
14880V14A 90sc14A M 34 001 STRAN DRitt IlkAD Assy' ;
19DBC94 A 9MA2 96 A 34-403 STRAM IEt34 SNELL M8Y j 4A7R914 13 Aft 96 A 34 891 SSFERATca noDU1J AsssMBLY l ,
.aulu uJt n u i 1 >
memensF o n 009 er? . ,,E1o cri. D.m T==s 15JULC4 280CT96 41 ,
34 909 FIT STRAss 13tes 614GL Pulff 2 9 CIT 94 1 *DEC95 $1 ! !, 34 9f1 TIC TE3" 10 DSCC4 20FEB97 51 ! 34 999 FIMhL A55Y l ,
l 3JUDSA S tJhp9 tA 3 39-084 STRAM Datse OJr ! i I s tJamtla 13Jt38954 36 040 ENDOUD Om3 l
~
18JAMORA 31asAY95A 35 *044 SMRaUD ChMS 83 6 3 3 ,
1SJUL9tA seeAa 94A ! 35 049 EERtXE) E2Tm81rps & Crats
'noe93A t e rEs9u - 3 s-0'a4 rrBam Dem' on '
umov9 th i sJAm,sa m 3s est snuwr ces sect:Ces l l 1JtN'91A 3 0JUL914 I l
_ _'___ _ M__3 5 4 09 1HROUD CM A551. __. _ _ _ _ _ . . .
1 TJMll A I SMA9 94 A 3$ 002 STEAN DRIBe 540t1L AS5Y
~--
4BP0 95A 15staYte 4 35 807 $EFERATOS teODUta ASSEMBLY 3 3Apa 914 3 ALE 394 el E 3 5 409 PIT 4 erE12 STEAM ES 34 DrTERMA J LtJULCM 19ssN94 45 35 980 FIT STEM Datae 61$cM, perirr 29ssN94 19 Jut t 45 35 991 arrDectTkTIC TEST 3k!wD* 13ata3 91 et 36 999 p;NAL M8Y tocT9 .a tocT9 sa i 43-023 PEEowATEm Gr> sia a une usy I loJUL81A 33 ssp 9u m4 4 3 2 0 3 RsCt aC Norsla romarm a os NED - EARBERTON ^
1s em9sa IJesetu m 43-On3 9 314 card a:m3s TRM fMRTATION ~ -"
u=u ti a 4=Aa t' 64 _ *mussesTATr:se C
. = . . ,,, .
- - * = =
- =*.
= a .p.a.
. . ..m , . . . _ 70... ;".*.".*
+ .
BABCOCK AND WILCOX 'NTERNATIONAL 3,4. **
gg,, ******".*- _
FLORIDA POWER AND LIGHT - ST. LUCIE
! CAMBRIDGE / WT.VERNON / N.E.D.
942.-aJm.J:.ae.44..Aansga M.g m ,, wh_a _ w4,.4..,A.,4,,,__m..a,,aa,.mmea.pitam.4 am m Amm_gtJg .ha.,un.-M.mm adedm+mmm4w m mamm-m- .,
- I l '
i l
I l- FLORIDA POWER & LIGHT s
l '. 222-7698 y
l . e.
l_ l
~
l t
& 7 '
~
l
.. e .:sw a m u sa m m u m M N
~
.a .
s/ s y. M J . .
. i
. 4i ll : ..
t 4
l- q .g- ('p' f;
- : g!
s .
l f .p < j po i. .
pi t ryk.
i ,s - 9.f i. j;
- l 7 ,
j dEM,
,. > l s
a
}
. k.. .
'q:'J y.. <
' M*%
h4 ,.1l. f . s _- :.. d '
- 6
,. 4,._ i. ,.
- j ._ . I 't "H v.gi = e M i
- , .l _.
- l. s. j . _.. s., _ , - -*gsi!UE
- \
b y; ,
- . +. \
f i
1 UPENDED STEAM DRUM - MT. VERNON f- APRIL 1996 s
~
)
. . _ . . ,, ,,. -..._,.m....
i.
1 i
FLORIDA POWER & LIGHT
! 222-7698 1
j __ '
! + 3
. ~
! a
.. 2
[ .
i
~
b f- e ..
y, W g .
.s ,My
. . ili i ~~
i h I - l p,
j
.'s' .c ' : .
,\ ,[ Y .
~h}.llll -
)
P* '!g a _'i= = = 'j l
I m J '8 l
'I 4
y // rj A .;
I W!
- - -- 4
-.5.
l '% jf ' ===--;=~-=.
l _ fk >(J . ;_
_ r.. :3 p_ . .. _ - L ; -
i 4
i l
MODULE TRIAL ASSEMBLY - MT. VERNON APRll 1996
4 l-
\
. 9** \
l l
a j FLORIDA POWER & LIGHT 1 j 222-7698 l _.
l l
l i
I
- k . $.
)
- o' Q
4 I L ~ .; i l$.
I ..?
m \ ..
- ., ( I }, '. ; l , p 1 f . .; . ,
gg my p- a~
gg6
~ >.
l' 3% ~
.nx .. ,_ w =
fl5 -
-- + & ..
l .. ..
j_ 'c III "
J aga =_r_n__
wm , . .=4s, ,
1
, . .. g% . , n , 5;.. :
p . r:. - m, - . .
v, ;s. m.
) ~ . ,a.( _. . 34,.4. -
......,.,, ;... g 4 y\'fg W.:g.,3. } ,l .ya.,fh we 3,%g p i:.;9.: }., . .:9;_ky.,
qr ;.g ' 4gk y; 4: ,
. pN./ ,?V ~ . A J , .
, y 'b '4 ? ; .1. Y ;% 2:d* :,
i
- ,[. k ., l ' $hi' n,
-Q r ! ' D b,'%a kS1 a:- J -
gec ', n, 3
.- ~.
( , ~it w ;. ~ _ -4..
.. . ,1>.s
- g-+
%m fi.A,-'
, . $. y . .
L M 7 $ $(T A f ,,
J f.'
.<.. s n -
4 1
4 4
4 j
j MODULE TRIAL ASSEMBLY - MT. VERNON
,' APRIL 1996 f . . - - __ -. .
i
?-
i
!- FLORIDA POWER & LIGHT 222-7698 l~ l l :
L_
l l
i ~
l 1
!~ ,
(
). i
~
!- 3 l
1-A '
>@M *Y
.o .. ., .;-yjj:.
~
i i
l l
) -
i
)
l ASSEMELY OF S/G 1B MODULES - MT. VERNON APRIL 1996
l /
i b
I l
l- FLORIDA POWER & LIGHT 222-7698 l
I i-t i
l l $
j i :.t . : ,' 'f . ? . , ' (-
~ y... _ ,
a 4, ,
j ,3 : _:-
}-
a :.u-- @ , 's ,_ ', )
,4 ,
I ' 1, r *, ' '
> v ra,, '
,,~ ' A s
, s, :
s
[ mt : ,. "N Tv
}- - ' h~ A:, .~. a_ -V ..,~,.N g-
,; , . y z. -. * ,, P. ; .'. - - .
. gQ 4 . fg .r;y. ,f-
- .,,s ..
.9:4W,. y , .
,., , . .y.,gerg
_. aa.n,,- ) . y ,,
. g,&
i I
~
.e p se.g
. .46 ,7. +f,.a 1
. 7 @i n,
- h. 4 .
) , _y, y C
. 'lt.
1
. . .g + e \
s., .:r . ..- .i L $\L
.f. y& -
. t .-
I 4
i l
i 1
4 1
APRIL 1996 i.-
d
,, ,_..m _.
1 i
t -
l J_ .- - - .
- - FLORIDA POWER & LIGHT 222-7698
!~
l 1
~ M "'
^~
.,.m.. ., . ., s , , ..
.., .f.x_ _ . . 2 n. u{_.> g. . ..t e i .m i U =d' I . *.'
,'J j,..- .%.
r i
v , -Q ~. .3
$ o,. j* 3
, I .-
,. #4 p .
- t. . ml , eru
..: w :..n ; .y
~._
~ _- . ..
f ,- @, M EC ~
s [ c. s .. -
4 m y .. .
~
&,u,,, .nr,,- . . . , .-
'J. j
, q, g:. \
\
^** [*.
..e . ,
g ,. ; ,
~ . r - -
, . . . . e' f,. ..
.< ,. m .-
es.
. . : . . .. ...1, .
.m
- - y . * ;.saf.;* .'.. . . . - -. _ ...
c
.,.L.l,g :.,4 s . .
g ,
- . . ' , ,. p , ,.7 ; + g.
wy-a-+
%. . _4 .4 . , , -
nRe .
l .-
'; " , J .py./
4 l
) . /gi. Ws . - -
? . ..
,_,,, #n7~'.,,,'#[fytj
~
i
,. n
-; y Wg,,fk-
~ '
d :- ... 1 r l i
l i
j e e
I f
l SHIPPING SADDLE FABRICATION @ AVENUE ROAD l APRIL 1996 l-l 1
,----.~...~~-~n. --- -n.-,.----+.- -n-- - - - - - - - - - - - - - .-- _ --
}
.E2 I
. FLORIDA POWER & LIGHT 1
222-7698 I
l f I
I i
F
\
I'
. em ~ . 2 ,
- ? . .
- e g
, _ . e6 %
I I
. i .- ,..i s
_J.W-- -
g ee -gf5 7 ,,5~~A -
/*
son 4 m ee '- -
V . ,,1 4 a
e M A*?
. .s;. ~ set 4m i
L . AL . . _ - .
. ~ K Q ,'"_.5 ,c' a
I
~ ' ' '
-'r '
_. m. mo , ~
- h. zu
.,....v>< .
c . :
- ' ~
. Y .
', ,,e.
I -(; . . , ,
,,- ' F E" '.'j. '.', .c p ...'
u .h . a .
I i
4 4
1 1 -
1 J ACKING WINGS
! APRll 1996 1
m gf f
4 4
was unable to verify in TEDB the ollowing instrument setpoints during a
- walkdowrrof-both units ICW sysi. ems.
O "
i t 1_
/ PDS-21-25A1. M nunciator E-9 LUBE WTR SPLY STRNRS DELTA P HIGH
/
l PDIS-21-6A. B z.5pspAnnunciator E-31 CCW HX STRAINERS DELTA P HIGH
/ PDIS-21-7A. B r.rno Annunciator E-32 TCW PPS/HX STRAINERS DELTA P HIGH g A FIS-21-9A 4/yp f @ Annunciator S-3 CCW HX 1A ICW FLOW LOW hFIS-21-9B #fr4/h Annunciator S-4 CCW HX 18 ICW FLOW LOW i Unit 2 p
- fop _ PDIS-21-25-1A1. lA2 Annunciator LA-4 LUBE WTR SUPPLY STRAINERS HIGH 9 DIFFERENTIAL PRESSURE MSit usio PDIS-21-25-1Bl. 1B2 Annunciator LB-4 LUBE WTR SUPPLY STRAINERS HIGH' DIFFERENTIAL PRESSURE I4000 6
, z ppo PDIS-21-6A.B[g,gss0AnnunciatorE- CCW HX STRAINER DELTA P HI
'., 2 /5 0 PDIS-21-7A. B 2.51/0 Annunciator -32 TCW PPS HX STRAINER DELTA P HI FIS-21-9A 7 foo gry Annunciator S- CCW HX 2A ICW FLO LO 0
F- FIS-21-9B 7feo#rt Annunciat CCW HX 2B ICW FLO LO <-o o r w <-eA /sz 7 -os 30/3 /
l i
Mfti:0 '@l'JdV Gell plA!834]
TIMD334 COMPONENT / ASSOC arefuru raRAMErsas 04/18/96 17:00 Melp Data Print Roadmap Exit Facility =-PSL. Unit = 01-System.=_21._ Comp. Type w.IB. Sub-Type AS1__
Component = PDS-21-25A1 Associata= SWITCH . UTC:
NCae : PRESSURE DIFF SWITCH FOR SEAL WATER SUPPLY STRAINER SS-21-3Al
_ _ _ =. -- _ _ _
0 Parameter Name Type value UOM C1s Data By
_ ACTION #1-1 I INCREASING N/A B 03/19/95 MEDOLWD_
_ FUNCTION #1-1 I HI A N/A B 03/19/95 MEDOLND_
_ PROCESS SETPT #1-1__ I 4 N/A B 03/19/95 MEDOLWD_
_ PROCESS RESET #1-1__ I N/A B
_ PROCESS UNITS #1-1__ I PSID N/A B 03/19/95 MEDOLWD_
_ ACTUATION SETPT #1-1 I N/A B ACTUATION RESET #1-1 I '
N/A B
[ ACTUATION UNITS #1-1 I N/A B
~ ~ -
More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd FB-Pwd F12= Cancel m ., s u,w :a my,e m es uger.cs ec, e wgu
i TIND034 COMPONENT /ASEO , - . . E. 04/18/96 17:01 l Melp Data Print Roadmap Exit Fccility- -PSL- Unit- = System---21_ Comp. Type = IB Sub-Type-= SI _
C;mponent= PDS-21-25A2 Associate = SWITCH UTC:
Name : PRESSURE DIFF SWITCH FOR SEAL WATER SUPPLY STRAINER SS-21-3A2 o Parameter Name Type Value UOM C1s Date By
_, ACTION #1-1 I INCREASING N/A B 03/19/95 MEDOLWD_
I HI A N/A
_ FUNCTION #1-1 B 03/19/95 MEDOLWD_
_ PROCESS SETPT #1-1__,I 4 N/A B 03/19/95 MEDOLWD_
_ PROCESS RESBT #1-1__ I N/A B 1
_, PROCESS UNITS #1-1_ I PSID N/A B 03/19/95 MED0 LWD,
_ ACTUATION SETPT #1-1 I N/A B ACTUATION RESET #1-1 I ~
N/A B
[ ACTUATION UNITS #1-1 I N/A B
~ ~ ' ~
4 More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=PP.wd F8=Fud F12= Cancel l
t r
om en a gM Ag WWt # p. e a MMJ e p r 9 ,Aq p put 9 sg p
TIMD334
_ E31p Dato COMP 00GNT/
4 Print Roedm p $Exit dh N _.e mm b . '
Facility = PSL 04/18/96 1 Component = PDS-21-25BlUnit System Name __
= 01 = 21_,
=-
DS***1"4E- DIFF SWITCH FOR S_ Associatee SWacMicomp. Ty
- Parameter Name UTC: _
valueEAL WATER SUPPLY STRAINE
,, ACTION #1-1_ rype -
. _1
! _ FUNCTION #1-1_ _ I INCREASING DON C1s -_
_ N/A_ ante By
_ PROCESS SETPT #1-1 _I4 I RI A _
,, PROCESS RESET #1-1 I
_ N/A_ B 03/I9/95 MEDOL i _ PROCESS UNITS #1-1 N/A_ _ B 03/19/95 MEJ0L N/A_ _ BB_ 03/19/95 MEDOL!
_ ACTUATION SETPT #1__1 I _I PSID_ ] N/A ] B 03
_ ACTUATION RESET #1-1 I _
_ ACTUATION UNITS #1-1 I _ N/A_ _ B _ /19/96 h woLi
_ N/A__ _B_ _ __
_ N/A_ _B__ _ _
( Fl=HelpFS TO VIEW LOCATION OR.UTC HISTORY F4= Prompt .
F5= Search i
F6= Refresh F7=Bkwd F8= Fwd
- F12= Cancel s
i, 1
1 124 d
<d35 CW: ?34 '54 >n m oc ~~
TIND034 CONPONENT/ ASSOC!f.'_ df . 0 ! . ..RAME .'_tj, p a a l a n g 04/18/96 17:01 Nelp Data Print Roadmap Exit
-F cility = PSL._. Unit ar_01 . System =.21_ __ Comp. Type = IB Sub-Type = S1__
UTCi Component = PDS-21-25B2 Associata= SWITCH Name : PRESSURE DIFF SWITCH FOR SEAL WATER SUPPLY STRAINER SS-21-3B2
_________g____ _ _m m
_ - - - - _ ._-= -_ - ___,____
Type Value UON C1s Data By
, o Parameter Name I INCREASING N/A B 03/19/95 MEDOLWD_
_ ACTION #1-1_ I HI A N/A B 03/19/95 MED0LMD_
_ FUNCTION #1-1 N/A B 03/19/95 MEDOLWD,_
_ PROCESS SETPT F1-1__ I 4 N/A B
_ PROCESS RESET #1-1__ I N/A B 03/19/95 NEDOLWD_
_, PROCESS UNITS #1-1__ I PSID N/A B
, _ ACTUATION SETPT #1-1 I N/A B
_ ACTUATION RESET #1-1 I <
N/A B
_ ACTUATION UNITS #1-1 I -
More: -
F9 TO VIEW LOCATION OR UTC EISTORY. F8= Fwd F12= Cancel Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd 1
J l,
1
- ~ ' - ' HJe38 ONnt 93d lSd Wd4T:SO 96, 8I Bd6
TIMD034 COMPONENT /ASSOChff.Id.3 S5 Y
.RAME I^ E Help Data Print Roadmap Exit 04/18/96 17:06
] Fccility =-PSL Enit = 01--System =-21--Comp.-Type -= -ID Sub-Type = Gl__
C$mponent= PDIS-21-6A Associate = SWITCH Nrme : UTC:
PRESSURE DIFFERENTIAL
.= - - - = . = -INDICATING SWITCH FOR CCW HX 1A STRAINER
__ _ = ----
o Parameter name Type value UOu C1s Date my ACTION #1-1 I INCREASING N/A
~
FUNCTION #1-1 I HI A B 03/19/95 MEDOLWD ~
N/A B 03/19/95 MEDOLWD
_ PROCESS SETPT #1-1_ I 2.5 +/- 0.03 N/A B 03/19/95 MEDOLWD_
_ PROCESS RESET #1-1__ I FIXED N/A B 03/19/95 MED0 LWD _
,_ PROCESS UNITS #1-1__ I PSID N/A
_ ACTUATION SETPT #1-1 I 2.5 t/- 0.03 B 03/19/95 MEDOLWD_
N/A B 03/19/95 MEDOLWD_
_ ACTUATION RESET #1-1 I N/A B
- ~ ACTUATION UNITS #1-1 I PSID N/A B 03/19/95 MEDOLWD,
~ ~
~
More: -
F9 TO VIEW LOCATION OR UTC NISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel
. x ,,~ e- -. ..-- -- --
att TIMD034 COMPONENT / ASSOC).(f.t t 91 :C.'J. ;dy,
.m. JUQt3. i paalasag 04/18/96 17:06
. Help Data Print Roadmap Exit FCcility =-PSL Unit _=.01- System _= 21_, Comp. Type = ID Sub-Type = Gl__
Componente PDIS-21-6B Associata= SWITCH UTC: ~
Nrme : PRESSURE DIFFERENTIAL INDICATING SWITCH FOR * = " " - " -
- --- ". - - - mis- - .-,s. .
value UOM C1s Date By O Parameter Name Type
_, ACTION #1-1 I INCREASING N/A B 03/19/95 MEDOLWD_
I HI A N/A B 03/19/95 MEDOLWD_
_ FUNCTION #1-1 N/A B 03/19/95 MED0 LWD _
PROCESS SETPT #1-1__ I 2.5 +/- 0.03 B 03/19/95 MEDOLWD_
__ PROCESS RESET #1-1__,I FIXED N/A N/A B 03/19/95 MED0 LWD _,
PROCESS UNITS #1-1 _ I PSID B 03/19/95 MEDOLWD_
~
_ ACTUATICN SETPT #1-1 I 2.5 +/- 0.03 N/A N/A B
,_ ACTUATION RESET #1-1 I B 03/19/95 MEDOLWD_,
_ ACTUATION UNITS #1-1 I PSID N/A
~
~~
More: -
F9 TO VIEW LOCATION OR UTC HISTORY. F12= Cancel Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd I
l m-a W E CM'I 93d "Sd ud8T:50 % BI BdO ;
1 l
TIMD034 N 'Q [ '; d y Help Data COMPONEltT/ ASSOC"f.t Print
.. t..".
- 0 . RAME.3"
- t
- 034!i082 -
04/18/96 17:09 '
Roadmap Exit Facility r.--PSL-Unit -01 System -21_ -Comp. Type - ID sub-Type ~= G1' ~
Cc ponent= PDIS-21-7A .
dame : Associate = SWITCH _ UTC: '
PRESSURE DIFFERENTIAL
.____________ _ -- INDICATING SWITCH FOR TCW HX o parameter name Type value
_ ACTION #1-1 vox C1s Date my I INCREASING N/A
_ FUNCTION #1-1 I HI A B 03/19/95 MEDOLWD_
N/A B 03/19/95 MEDOLWD_
_ PROCESS SETPT #1-1__ I 2.5 N/A__
- PROCESS RESET #1-1 I B 03/19/95 MEDOLWD_
N/A B
_ PROCESS UNITS #1-1 [ I PSID N/A
- ACTUATION SETPT #1-1 I N/A B 03/19/95 MEDOLWD_
B
- ACTUATION RESET #1-1 I N/A B
_- ACTUATION UNITS #1-1 I ~
N/A B More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel l
i 1
q44 u ,w,c m e - e ., e: - .-~ -- --
TIMDO34 H COMPONENT / ASSOC. . RAKE [ h. 04/18/96 17:10 Help Data Print Roadmap Exit
-Facility = PSL --Unit -01 System = 21_ Comp. Type - ID Sub-Type - Gl__
Component = PDIS-21-7B Associate = SWITCM UTC:
Name : PRESSURE DIFFERENTIAL INDICATING SWITCH FOR TCW HX 1B STRAINER maza ssan= = - - -- --
c Paranneter Name Type Value UOM C1s Data By
_ ACTION #1-1 I INCREASING N/A B 03/19/95 MEDOLWD_
_ FUNCTION #1-1 I HI A N/A B 03/19/95 MEDOLWD_ l
_ PROCESS SETPT #1-1_ I 2.5 N/A B 03/19/95 MEDOLWD_ l
_ PROCESS RESET #1-1__,I N/A B i
_ PROCESS UNITS #1-1__ I PSID N/A B 03/19/95 MEDOLWD_
_ ACTUATION SETPT #1-1 I N/A B
_ ACTUATION RESET #1-1 I N/A B
_ ACTUATION UNITS #1-1 I N/A B More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel mea umye orr e a -es wo: re? oc, et e
TIMD034 COMPONENT / ASSOC :.RAMEF-.
Help Data Print Roadmap 04/18/96 17:1C Exit Fccility -=- PSL Unit = 01-System =71_ Compr-Type"= ID Sub-Type i=~Gl__
Component = FIS-21-9A, Associata= SWITCH UTC:
Nama : FLOW INDICATOR SWITCH FOR ICW CCW HX 1A OUTLET
_ _ . . . _ _ . . . . _..r- -----ar-- - =a -- . - = --- -
am---. --- ..
O Parameter Name Type value UOM C1s Date By
_ ACTION #1-1 I DECREASING N/A B 03/19/95 MED0 LWD, FUNCTION #1-1 I LO A N/A B 03/19/95 MED0 LWD _
[ PROCESS SETPT #1-1_ I 4395 N/A B 09/26/94 MEDOLWD_
_ PROCESS RESET #1-1__ I 7500 N/A B 09/26/94 MEDOLWD_
_ PROCESS UNITS #1-1__ I GPM N/A B 09/26/94 MEDCLWD_
_, ACTUATION SETPT #1-1 I 16.9 N/A B 09/26/94 MED0 LWD _,
_ ACTUATION RESET #1-1 I 49.2 N/A B 09/26/94 MED0 LWD _
_, ACTUATION UNITS #1-1 I IN WD N/A B 09/26/94 MEDOLWD,
~ -
~
More: -
F9 TO VIEW LOCATION OR UTC HISTJkY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd. F8= Fwd F12= Cancel 4
,,37.; u c.- . e ; -. - , - , -- -- t
0 'Ol 'J dy lait latioly M
TIMD034 COMPONENT / ASSOC.,D..l : ; ., ."., . ..RAME . ~ ' -
04/18/96 17:11 Help Data Print Roadmap Exit Facility = P51, Unit =-01 System = -21_ Comp. Type - ID Sub-Type _= Gl__
C;mponent= FIS-21-9B Associata= SWITCH UTC:
Name : FLOW INDICATOR SWITCH FOR ICW CCW HX 1B OUTLET
===m-_ _ .. . . _ _ . __ ---- ______ ___
um -- __
O Parameter Naas Type Value UOM C1s Date By
_ ACTION #1-1 I DECREASING N/A B 03/19/95 MEDOLWD_
FUNCTION #1-1 I LO A N/A B 03/19/95 MEDOLWD_
PROCESS SETPT #1-1__ I 4395 N/A B 09/28/94 MEDOLWD_
N/A B 09/28/94 MEDOLWD_
_ PROCESS RESET #1-1__ I 7500 N/A B 09/28/94 MEDOLWD_
_ PROCESS UNITS #1-1__ I GPM N/A B 09/28/94 MEDOLWD_
, _ ACTUATION SETPT #1-1 I 16.9 N/A B 09/28/94 MEDOLWD_
_ ACTUATION RESET #1-1 I 49.2 '
N/A B 09/28/94 MEDOLWD,
_ ACTUATION UNITS #1-1 I IN WD i _
- ~
~
~
More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel
~~ ***J <t'3E ONnf 93d "ad Wd6i:50 96, 8I MdO
t- S w :14:1:37' TIMD034 COMPONENT / AS80C...t :;:s . w.:~d :.d y
.RAME. L' O4/18/96 17:04 Help Data Print Roadmap Exit Pacility-- -PsL%it = 02 system = 21_ -Comp. Type - ID sub-Type e G1; Component = PDIS-21-25-1A1 Associate = SWITCH UTC:
Name
- PRESS g33333333333333---__m DIFF INDIC m_
SWITCM FOR SEAL -- ..
WAT C SUPPLY STRAINER
...-_____6.-,.
SS-21-3Al~ ---
0 Parameter Name Type value UOM C1s Date By
_ ACTION #1-1 I INCREASING N/A B 03/19/95 NEDOLWD_
, . , WMCTION #1-1_ I HI A N/A B 03/19/95 MEDOLWD_
_ PROCESS SEIPT #1-1_ I 3 N/A B 03/19/95 MEDOLWD_
_ PROCESS TdtSET #1-1_,I N/A B
_ PROCESS UNITS #1-1__ I PSID N/A B 03/19/95 MEDOLWD_
_ ACTUATION SETPT #1-1 I N/A B
_ ACTUATION RESET #1-1 I N/A B
_ ACTUATION UNITS #1-1 I N/A B
~ ~ -
More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd FE=Pvd F12= Cancel i
wTay**a fcc ^L e
- t*J *?- C*.*n 2: 2* M JLJ
TIMD034 COMPONENT / ASSOCb.d..Idf ..N ..!RAME!Eh.'3 04/18/96 17:04
, Help Data Print Roadmap Exit F'oility = PSL Unit = 02 System.= 21_ _ Comp. Type = ID Sub-Type = Gl__,
Claponent= PDIS-21-25-1A2 Associata= SWITCH UTC:
Name : PRESS DIFF INDIC SWITCH FOR SEAL WATER SUPPLY STRAINER SS-21-3A2
-__ ---- __.ar. _ _ __.=-2 - -
.sssaismuz O Parameter Name Type value UOM C1s Date By
_ ACTION #1-1 I INCREASING N/A B 03/19/95 MEDOLWD_
FUNCTION #1-1 I HI A N/A B 03/19/95 MED0 LWD.,
[ PROCESS SETPT #1-1_ I.3 N/A B 03/19/95 MED0 LWD,
_ PROCESS RESET #1-1__ I N/A B
_ PROCESS UNITS #1-1 I PSID N/A B 03/19/95 MED0 LWD,
_ ACTUATION SETPT #1-1 I N/A B ACTUATION RESET #1-1 I N/A B N/A B
[ ACTUATION UNITS #1-1 I ,
~ ~
~
More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt FS= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel l
6 h
.- .- - . . . - . - . - _ _ _ ..~ ~ _ -.
e TIMD034 CqMPONENT/ASSOCbhl 5NRAME Holp IIA ' 5 04/18/96 17:05 Data Print Roadmap Exit FGcility_= PSL CCaponent= PDIS-21-25-1B1_ Unit = 02.__Systen.=_21______ comp._ Type =-ID Sub-Type --G1; Name : Associata= SWITCH _ UTC:
PRESS DIFF INDIC SWITCH FOR SEAL WATER SUPPLY STRAINER'SS-21-3B 0 Parameter Name Type value m azurzzmunzzm=22_-- ~___
UOM C1s Date By
_ ACTION #1-1 I INCREASING
_ FUNCTION #1-1 I HI A N/A B 03/19/95 MEDOLWD_
_ PROCESS SETPT #1-1 _,,I 3 N/A _ B 03/19/95 MED0 LWD _
PROCESS RESET #1-1 I N/A B 03/19/95 MEDOLWD_
_, PROCESS UNITS #1-1__ I PSID N/A B
~ ACTUATION SETPT #1-1 I N/A_ B 03/19/95 MEDOLWD_
_ ACTUATION RESET #1-1 I N/A B N/A B
_ ACTUATION UNITS #1-1 I ___ N/A B More: -
F9 TO VIEW LOCATION OR UTC HISTORY. '
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkvd F8= Fwd
]
F12= Cancel 2
l l
1 1
l
- g ;.g .rw
- e myrw et -c; we'.c6 cc t' VA
1 0 ': 'd azi J,paA!a:a2 TIMD034 COMPONENT / AS SOC.9,.71 .; : . J.], . .y.RAME.
- 04/18/96 17:05
. Help Data Print Roadmap Exit Comp. Type = ID Sub-Type = G1 3
F0cility =-PSL-4 nit = ~ 02 System _=_21_
Component = PDIS-21-25-1B2 Associata= SWITCH UTC:
Name : PRESS DIFF INDIC SWITCH FOR SEAL WATER SUPPLY mo esem emem m am m _ _ _ _
STRAINER SS-21-3B2_
_ - e= =en
- g. . .
o Parameter Name Type value UOM C1s Data By
_ ACTION #1-1 I INCREASING N/A B 03/19/95 MEDOLWD_
I HI A N/A B 03/19/95 MEDOLWD,
_ FUNCTION #1-1
_ PROCESS SETPT #1-1__ I 3 N/A B 03/19/95 MEDOLWD_
N/A B
, _ PROCESS RESFr #1-1_ I B 03/19/95 MEDOLWD, i
_ PROCESS UNITS #1-1__ I PSID N/A N/A B
_ ACTUATION SETPT #1-1 I B ACTUATION RESET #1-1 I __ N/A N/A B
_ ACTUATION UNITS #1-1 I j _ _
~
~ ~
~
More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel 1
l i
I H~tOS ONnf 'J3d '.Sd WeGI:50 o6, 8I bdJ
'~' < ' ' "
l
?';fv i:1*
TIMDO34 f COMPONENT / AS S OC_3'1"_'_:;:1 . .':
. .'RAME. _. _ l i a : 1 : i-'1 Help Data Print Roadmap 04/18/96 17:07
, Exit !
Facility =- PSL-Unit = 02 System---21_ - Comp. Type - ID Sub-Type = c1 ;
Crmponent= PDIS-21-6A Associata= SWITCH UTC:
N=e :
PRESSURE DIFFERENTIAL INDICATING SWITCH FOR CCW HX 2A STRAINER
_ _ _ - - _ _ _ _ - = - - -
o Parameter Name Type value UOM C1s Date By
_ ACTION #1-1 I INCREASING N/A B 03/19/95 MED0 LWD _
_ FUNCTION #1-1 I HI A N/A l B 03/19/95 MEDOLWD_
_ PROCESS SETPT #1-1__ I 2 N/A B 03/19/95 MEDOLWD_
PROCESS RESET #1-1 I N/A B
[ PROCESS UNITS #1-1[ I PSID N/A B 03/19/95 MEDOLWD_
_ ACTUATION SETPT #1-1 I N/A B
_ ACTUATION RESET #1-1 I N/A B
- ACTUATION UNITS #1-1 I N/A B
~
~
~
More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel l
l l
77fe:.a WNyc ^6r e ew ew w97 c' ec c' u
.I u.. . . , 4 .... . .....
l j TIMDO34 COMPONENT / ASSOC
I'
' .RAMEI. :_7 'I 04/18/96 17:08 i Help Data Print Roadmap Exit i Facility = PSL -- Unit = System =-21_ Comp. Type = ID Sub-Type = Gl__ l Component = PDIS-21-6B Associate = SWITCH UTC:
N*.ma : PRESSURE DIFFERENTIAL INDICATING SWITCH FOR CCW HX 2B STRAINER
_w-.____. ___.,_____
--__--_________,,am.
_ _ =--- __
o Parameter afame Type Value UOM C1s Date By
_ ACTION #1-1 I INCREASING N/A B 03/19/95 MEDOLWD_
_ FUNCTION #1-1_ I HI A N/A B 03/19/95 MEDOLWD_ l
_ PROCESS SETPT #1-1__ I 2 N/A B 03/19/95 MED0 LWD _
l
_ PROCESS RESET #1-1_ I N/A B
_ PROCESS UNITS #1-1__ I PSID_ N/A B 03/19/95 MED0 LWD,
_ ACTUATION SETPT #1-1 I N/A B
_ ACTUATION RESET #1-1 I N/A B
_ ACTUATION UNITS #1-1 I N/A B
~ ~ ~
More: -
- Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8=Pwd F12= Cancel i
)
4 5
l f f.k *h e Y l
w amt' l0All387*
TIMDO34 COMPONENT /AZSOC"f M :: ': :dv.'.RAME . ..;. ' 04/10/96 17:08
. Help Data Print Roadmap Exit Facility = -PSL - Unit = 02_ System _=_21_ Comp._ Type..=.ID Sub-Type _=.Gl__
Ccponent= PDIS-21-7A Associate = SWITCH UTC:
. N1re : PRESSURE DIFFERENTIAL INDICATING SWITCH FOR TCW HX 2A STRAINER
-__ mumm m .________ --
4 o Parameter Name Type value UOM Cls Date By
_ ACTION #1-1 I INCREASING N/A_ B 03/19/95 MEDOLWD_
_ FUNCTION #1-1 I HI A N/A B 03/19/95 MEDOLWD_
_ PROCESS SETPT #1-1_ I 2 N/A B 03/19/95 MED0 LWD _
PROCESS RESET #1-1 ~ I N/A B
~_ PROCESS UNITS #1-1 _ I PSID N/A B 03/19/95 MEDOLWD_
_ ACTUATION SETPT #1-1 I N/A B ACTUATION RESET #1-1 I N/A B
[ ACTUATION UNITS #1-1 I N/A B
~ ~
~
More: -
F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd FS= fwd F12= Cancel i
i i
1 I
i i
i 4
3
. ., ,e . . ; ure2c Ount 92d 'Sd WdO2:52 E 8T ado
- - - - _ _ -_--~_
. ': t '; $v i:!' 09.s:1:iv COMPONENT / assoc..f.8 3/ ] ::. ; . .~ 4 . .h E . . 7 ~
~
04/18/96 17:09 F7CO34 Print Roadmap Exit Help Data System = 21, Comp. Type = ID Sub-Type = Gl__
Facility
- PSL -Unit = O2 Associate = SWITCH UTC:
Component: = PDIS-21-7BPRESSURE DIFFERENTIAL INDICATING SWITCH FOR TCW HX 28 STRAIN ~
Name -
By
- ==sassuammar
__=
UOM cis Data Type value o Parameter Name N/A B 03/19/9S MEDOLWD_
ACTION #1-1 __I INCREASING N/A B 03/19/95 MEDOLWD_
I HI A B 03/19/95 MEDOLWD_
FUNCTION #1-1 N/A N/A B
_ PROCESS SETPT #1-1__II 2 B 03/19/95 MEDOLWD_
~
PROCESS RESET #1-1 ~ N/A
_ PROCESS UNITS #1-1__ I PSID N/A B __
N/A B
_ ACTUATION SETPT #1-1 I B ACTUATION RESET #1-1 I _N/A
[ ACTUATION UNITS #1-1 I _
~ -
~ More:
~
F9 TO VIEW LOCATION OR UTC HISTORY. F7=Bkwd F8-Pwd F12= Cancel Fl= Help F4= Prompt F5= Search F6= Refresh l
c e n o r : m ,s u m a n. m se
- vc: -
XJ8 BTt' :tA'9:lv j TIMD034 COMPONENT / ASSOC' / : - ':i ;dy.RAME
.~' -
04/18/96 17:11 l . Help Data Print Roadmap Exit Facility = PSL-- Unit = 02 System = 21_- Comp. Type = ID Sub-Type-= Gl__
Cccponent= FIS-21-9A Associate = SWITCH UTC:
Ncte : FLOW INDICATOR SWITCH FOR ICW CCW HX 2A OUTLET
.__ ------=====___==_____= - = = = = = = - - - - - - - - _ _ - _ _ - =_ _ . _ _ --
0 Parameter Nalne Type Value DOM C1s Date By
_ ACTION #1-1 I DECREASING N/A B 03/19/95 MEDOLWD_
_ FUNCTION #1-1 I LO A N/A B 03/19/95 MEDOLWD_
_ PROCESS SETPT #1-1__ I 7500 N/A B 03/19/95 MEDOLWD_
~ PROCESS RESET #1-1 I N/A B PROCESS UNITS #1-1] I GPM N/A B 03/19/95 MED0 LWD _
~
ACTUATION SETPT #1-1 I N/A B ACTUATION RESET #1-1 I N/A B
[ ACTUATION UNITS #1-1 I N/A B I _ _ _
~ ~ ~
. More: -
)
i F9 TO VIEW LOCATION OR UTC HISTORY.
Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd F8= Fwd F12= Cancel 1
i
- . . , - - ww7e m19r e?9 '9d 14dT? :93 96, 9! MdB
. - _ -. . . _ _ . _ .-- __ ._ _ =
, TIMD034 CONPONENT/ASSOCENI f I . .YRAME'..$. 04/18/96 17:11 Help Data Print Roadmap - Exit FOcility = PSL Unit = 02- System = 21_ Comp. Type - ID Sub-Type = Gl__
Component = FIS-21-9B ~ ~~~ Associate = SWITCH UTC:
N me : FLOW INDICATOR SWITCH FOR ICW CCW HX 2B OUTLET l
_ =====___=____=== =====_==_______ _______ _ _____===
o Parameter Name Type value UOM Cls Date By
~ ACTION #1-1 I DECREASING N/A B 03/19/95 MEDOLWD_
- FUNCTIOM #1-1 I LO A N/A B 03/19/95 MEDOLWD_
i PROCESS SETFT #1-1 I 7500 N/A B 03/19/95 MEDOLWD_
_ PROCESS RESET #1-1__ I N/A B
_ PROCESS UNITS #1-1_,I GPM N/A B 03/19/95 MED0 LWD _
_ ACTUATION SETPT #1-1 I N/A B
~
ACTUATION RESET #1-1 I N/A B ACTUATION UNITS #1-1 I N/A B W W "
8 M m W
~ ~ ~
More: -
i l F9 TO VIEW LOCATION OR UTC HISTORY.
i Fl= Help F4= Prompt F5= Search F6= Refresh F7=Bkwd FS= Fwd F12= Cancel 1
8 d
4 k
4
+,,,3; e 39 Omr 03d 7 d Wd!2:SO 96, 9I Bdd
T ,
The Steam Generating Tham a me m u. em w. ca,,,,,,
l a ,
..3
. .. c . , or , , , . . . . ., , r a i . .i.
I
- s. ,m . .i . -,
. . :;.v l i
l October 14, 1996 'r 96-SGTF-027 I Mr. Richard Sipos Project Manager Florida Power & Light Company -
SGR/PSL -
P. O. Box 128 Ft. Pierce, Florida 34954
Subject:
SGR Monthly Progress Report - September, 1996
Dear Mr. Sipos:
Enclosed is the September, 1996 Steam Generator Monthly Progress Report.
If you have any questions or comments, please contact me at (561) 468-4331.
Sincerely, I [4 $6 .
Martin D. C pkauskas President MDC: rap Enclosure cc: W.A. Fox - E&S we File 11-1 w/
[ 1
///.
J/ /
l J
l 1
J
r1 .
i l
t I
TABLE OF CONTENTS l
I
_ I. MANAGEMENT
SUMMARY
II. ORGANIZATION III. SCHEDULE STATUS '
Pre-Outage Overview Milestones Pre-Outage Schedules SGT PCM/DP/WP Status IV. SEPTEMBER ACTION ITEMS LIST V. PIIOTOGRAPliS I
l I
i l
1
. l
, The SGT: .11K/DE,ts l
a b l l
' i ST. LUCIE PLANT - UNIT 1 STEAM GENERATOR REPLACEMENT PROJECT MONTHLY P~ROGRESS REPORT SEPTEMBER 1996 This document was prepared specitically for the CONFIDENTIAL use of the SGT of N1orrison Knudsen and Duke Engineering & Services management and should be treated as such.
SECTION I
. MANAGEMENT
SUMMARY
A. OVERVIEW OF PRO.IECT !
l e
4
1 NTEAM GENEllATOlt itEl'l.ACEMENT The M;T: M K/l)E&S
\T. l.It 'll: /*l..lNT - IWIT I Al(DNTill.Y PROGRILW REPORT l 1
l MANAGEMENT SITMMARY l l
A. Proicci Overview l i
The St. Lucie Steam Generator Replacement Project is being perfonned for Florida Power & Light by l 1
~
l the Steam Generating Team (SGT), a limited 50/50 partnership between Morrison Knndsen (MK) and l I
Duke Engineering & Services (DE&S). MK is providing overall project and construction management.
DE&S is providing design engineering and licensing support. Framatome Technologies (FTI). now a l l
subcontractor is providing technical services for steam generator reactor coolant pipe mensarements, decontamination. RCS pipe machining / cutting and narrow groove pipe welding. )
l l
5 The project is located on Hutchinson Island. south of Ft. Pierce Florida. The brief scope of services ,
1 I
being provided to FPL by the SGT is engineering, procurement, and construction services for the ;
l replacement of 2 Combustion Engineering steam generators with 2 BWI steam generators fabricated m Canada.
This is the lith monthly progress report issued for the Phase 2 or the SGR implementation phase of j the pro.ieet and covers the period liom August 26,1996 through September 29. 1996. l'hase 2 has i
been defined as the period from the beginning of November 1995 through project completion or the end of December loo? The scope of Phase 2 i3 procurement of implementation materials, construction i
worklorce mobihzation. erection of outage facihties. receis e and prepare the new steam generators for mstallation. mockup trainmg. and the actual team generator replacement.
i l
4
. . - . - . . . - . . - = . . ~ we - _ . - .
SECTION I
~
NIANAGEMENT
SUMMARY
- 11. 31A.JOR ACCOMPLISIIMENTS l
h
_ _ _ _ _ . _ ~ _ _ . _ . . . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ .
l l
, NTEAM GENERATOR HEPLACEMENT The SGT: M K/DE& S ST.1 tir1C PLANT . IINIT I .stDNTilLY PROGREW REPORT MANAGEMENT
SUMMARY
l i
H. Maior Accomplishments l
Major Accomplishments for current period include:
Process FPL/BWI controlled documents as they are received.
The QC services contract change has been negotiated with FPL (verbal approval).
Construction Work Package Status: (89 Total identified. 4 New)
Internal Review by Team: 89 FPL Review / Comment: 89 FPL Approved: 87 On Hold: 1 (Painting)-
(See Status Report)
Overall, CWP effort'is approximately 98% complete.
FpL will not build the OSGSF, OSG's to be shipped off site (verbal).
^
Mammoet performing detailed engineering, fabrication & procurement to support October 20.1997.
Transco is proceeding to support October 20. 1997 outage. SGT & Transco are discussing insulation installation options. Negotiations to begin January 1997 for installation of insulation.
Special Processes teutting, machining & welding) out for quotation.
SGRP Project Review Meeting held 4/23/96.
Engineering / Licensing Contmued interfacmg with Mammoet to review design informanon and resolve comments. Review mg Mammoet shop drawings.
13ecan plannine engineering / licensing activities and resources necessar,s to support the SGRO rescheduled from begmning m early 1998 to October 1907 Conducted general project aeovities te c. project management. document control).
. NTEAM GENEltATOR REl'I.ACEMENT The SGT: MK/DE&S VT IITIE l't. 8 %T 1%IT I A10NTill.Y PROGRl;ss REPORT
~~ - --- -
MANAGEMENT
SUMMARY
B. Maior Accomplishments - Cont'd Work planned for October includes:
Management / Pre-Construction -
FPL to amend contract to incorporate QC services.
SGT to prepare. review and issue " FRAG" net schedules for pre-outage activitiet 1 Project Review meetine with FPl. !
Deploy Ollice Engineer to the SGT Site Office to suppon pre-outage activities.
Review Transco installaiion option, negotiations to proceed January 1997.
1 l
a SGT to mobilize Project Control Engineer to site to suppon pre-outage planning ~
j activities.
Engineering / Licensing Plan engineering / licensing activities and required resources to suppon the SGRO rescheduled from beginning in early 1998 to October 1997.
Deploy Design Engineer to SGT Site Office to suppon planning for the October 1997 SGRO.
Continue interface with Mammoet as necessary.
Condnct general project activities ie.g. project management. document control).
1 Continue to resiew and approse mtert' aces for BWI RSG tirawines as they are
- ecen ed.
1 l
l J
l 1
SECTION I MANAGEMENT
SUMMARY
1 C. ITEMS OF CbNCERN !
l 1
_ _-.___ __. _ - ..___ __ _ _.._ _ _ _._. _ . _ m __ _ .
i l
. STEAM GENERATOR REPLACEMENT The .NGT: MK/DE&S l
}*
ST. Li'CIE h.wT . LINIT I AIONTHLY PROGRESS REPORT I
\
! MANAGEMENT
SUMMARY
l l
l 1 i
!- C. Critical items of Concerns i
- - - The Steam Generator Replacement Outaae date needs to be defined. - The present target date is October 20.1997. This has changed from Feb. 3.1998, O
t l
,w. . . ,,m -r .,.___n.,
SECTION I MANAGEMENT
SUMMARY
D. SUBCONTRACTOR
SUMMARY
i i
t 5 II A Al i el Ni it A !e sH l(I l'1 As 'l All N I liie N(il'. .htK/t tlix s
\1 1 I I Il /*l t N I 1%Il i AltlN11tl i' l'MIHo*RI %.V RI l*tlHl' MANAGEMENT
SUMMARY
J ,
D. Subcontractor Summarv I
SUBCONTRACTOR SERVICE / MATERIAL STATUS
)' Davenport Mammoet Steam Generator Detail Engineering Rigging / Transport for rigging evolution proceeding Transco Products, Steam Generator Preparation of l u c. Insulation engineering documentation to
- support release for fabrication LAW Engineering OSGSF Soil Boring Completed
- Contract closed Special Processes 4
Request for Proposal issued to i
subcontractors t
4 0
s a
e i
s
-' - ~ ~ ~ -
. e SECTION II ORGANI7ATION 1
A. PHASE 2 ORGA NIZATION CHARTS 1
4
f . .
9 i
ST. LUCIE STEAM GENERATOR REPLACEMENT PHASE 2 ORGANIZATION
~~
FPE 5GRP PROJECT MANAGER Richard Sipos_
~! ~ i3usiness 2_ Projeci~~~ Project Quality l l Manager Director -----------
Manager (Acting) !
! Sharon Williams Marty Cepkauskas Andy Walcutt !
Group Welding Engineer i
Alan Artayet j
~ ~ ~ ~ ~ ~
l l j Design Quality ENGINEERING TECHNOLOGY CONSTRUCTION Manager (DE&S) i l l Mark Sanger Design Process Technology Site Project i Engineering / licensing Project Manager Manager l Manager Max Bingham
- Bill Fox __
i l
l i
6
ST. LUCIE STEAM GENERATOR REPLACEMENT PHASE 2 ORGANIZATION SITE PROJECT MANAGER Max Bingha_m_
_ _1 . . . . _ . . _
.______.I__ . - - . - - ... l _ ___ _ _. _ _ - {.
CONSTRUCTION . PROJECT CONTROLS CONSTRUCTION ENGINEERING MANAGER l MANAGER I I Stbve Mager l Glen Bickel _ . _. Rob Pommerening !
i ;
- m. --e-ww e=
~
^~ ~555tGN ~ ^5iT5 D55 IGA OFFIC5 FIELD $NGINEERING ENGINEERING / LICENSING ENGINEER ENGINEER i ;
, MANAGER Hyde Griffith Dale Vest Bob Herod i
[ _. . Bill Fox _
i 4
3
- ST. LUCIE STEAM GENERATOR REPLACEMENT ENGINEERING & LICENSING PHASE 2 ORGANIZATION DESIGN ~5M5iNE5 RING /LIC5NSING MANAGER Bill Fox ,
. PROJECT QUALITY DESIGN QUALITY PROJECT MANAGER MANAGER - - - - - - - -
ENGINEER Mark Sanger Mike Anthony Andy Walcutt (Acting [ .
SIT 5 ENGINE 5R Hyde Griffith TECHNICAL . _ _ __ _
SUPPORT Randy _Ab_ernethy i _
l LEAD LEAD L5AD LEAD l si_ECTillC^L i ,
SUPPORT CIVIL / STRUCTURAL PIPING /SR MECHANICAL LICENSING'
' Dan Grundman Rick Parler Stan McDowell Larry Davis i Mark Ceralch I
l l
l I
l ST. LUCIE STEAM GENERATOR REPLACEMENT PROCESS TECHNOLOGY PHASE 2 ORGANIZATION
- PFiOdE5S TECANdLOdY l PROJECT MANAGER
..___ . _ L _ __ . l_ _
I SPECIAL PROCESS _ ALARA PERFORMANCE /STARTUP TESTING MANAGER MANAGER ENGINEERING MANAGER ,
j i , _ . _ _ .
- 1 _ _ _1 _ . I MEASUREMENTS MACHINING WELDING ENGINEERING DECONTAMINATION >
MANAGER !
' MANAGER MANAGER '
MANAGER I f !
^
e i
l -
- 4. _ . . ,._-, . _ , . . ..- --
- - - - - - - - ~ - - - - -
-* *~*"
m,e 1
SECTION III SCIIEDULE STATUS A. PRE-OUTAGE SCHEDULES l
I 1
1
,__ _ . _ ._. .. _ __-_. _. - ~..__......_ _ _ _. _ _.__- . . _ . . _ _ . . . . . . _ . . .- _
l .
1 STEAM Gl'NEl(ATOl{ l(El't,ACEMI'NT NT. l.IlflE Pl.,4NT - !! NIT I The SGT: MK/DE&S 410NTillt' PROGRESS REPORT l
I l
i SCIIEDULE STATUS t
i B. Pre-Outane Schedules l The Pre-Outage schedule included has been divided into 5 major categories of work, Engineering, Licensing, Procurement FPL Responsibility, and Pre-Outage Construction.
! .. Pre-Outage construction activities include facility erection, craft training, receive and prepare the new Steam Generators.
I l
l
- r r
n l
{.
- y. y-
01 Lu vlL t-f ttVU l/AOC UuttW!t tf8 ,
KEY MILESTONES 1L92 1993 1994 1995 1996 1991 i egy j {}s{ j, 2nd i 3rd [ em t st j 2r'd l 3rd j 4:n 1 st l Jd _ l_ 3rd _ j sth 1st l 2nd l 3*d j 4th 1 st l 2nd l bi l an.
4 Cordract Award ;
' l
+ Begin Prepare Project Procedures / Work Packages i .
l
' + Begin Ucensing Report l l l e Spring 1993 Outage / Data Collection Complete i !
+ Begin Engineering Design Packages I
i eissued SASE / SGRR Revision 0 i
e Fall 1994 Outage / Verification Complete
- Engineering Packages Complete
! ! I j e Work Packages Complete i l
e FRG Reuew of PCi t1 Complete l l l e Phase 1 Complete I l i
!, + Begin Revision OA/QC Scope !
l l I' I ii + Mobilize SGT fnitial
'I j i I
+ Begin Reconciliation
.l i4 ;
Complete Revision OA/OC Scope + l
,; , j
+ Unioad New SG's!
i Begin CAB Erection +
l Begin Outside Gantry Footngs +
.' l Mobilize SGT Final +
! I i Begin SGR Outage +
1 f
~0T LUCIE SGRP -
SGRO- 10/97 R09 96
- . .. :" w n .." "-.. ... uorrison xnuesu
. .> PRE -
0VTAG E <-- -_
i tetet ettei esist effet teint i i
es 37 57 17 97 I i' . i iJil I iillil lillil Ill:si 12: 0tA t2:09A 12:e9A I2:eOA i2:00A Tl rfe now i:li!
- itin PHASE 2 EN 3RG tilt
-~
.! s het.iii !;i) 1:riitti si ); ii il 144 II:ll!!! il IsF
~
Z~- ~~1
!il:1 til ilil 1:illlititCl it it'll !I I!! 11111!!! 11.IIF. 18 A i.!_!:_ !!I it ! :i'! i:lI;li! -
il !! il Il ill 11111ll1 l} Iif 4!f t. __.__1
.Pi
!!: if ii::t:ilith:1 il si if il til littlill Il tiF 1151 L -
i
'll! ini 3 !s:i:3i tilli'.n i: iill !! si !i il lli 11!]I1!! 11 lif il A
'-~ ~--
. !:t if i ::l:111111:1 li il if il ill liitilli Il fit Hit E~ ~Z Z I
- !!! . ::l:1.i disti fi.9iG i.it :i !! li il fit il it:!! il fiF 4tf I '~'~-~7
- ::s'. I't: I r8C 41 6 il !!! 15 ll'!1 fl i!F iif I !
- t
... Ili . ~ :!I li !di . ii il i:1 II.11l!! il liF I4!f I iti:i .il:I 8::::vi a:i ~ fi :l i:1 11.!!:1111 i:i I::1 !
l li.: I; ii :i:. !
~:1~ i:::! .il!! it! Ei:-: .i il fi it it ill itill!!i 11 It! !!! ,
. . . I: :is!!I liff;tlii FC; , * :1 ii il lit lis!!!!! 11 ItF lif , _ _ _ _ _ - - I
- ! i I: :it!!I tiil'itil FCi ::t
. it ':1 if Il llA 11114ll1 Il (IP I!g i i
i f '
- !: ill tii:'ll !P: .:i :i !i il !!! firil!!T !! iii lif !
I
__ _ . 8:1.'!ii!:4 _ _ _ _ . _ _ _ __ ,
- 11! * :ll!:li PHASE 2 LI CENSING j .
j l
i It iii.i I::.I:n . ii it ill il llili il ::f i;! 1 .
i
- illii;;l 1:s ii !! .;;t:1 .i i .: it ; ii il ill li'll'?! Il lif lit i Tiii - ::t:llin'l:1 !! ?: ii il 114 ilillili il !!i !!d 1
'!!i . : :n.*,j: . :! ; i; :l i:1 !!'t! 11113:7 !: A
- I!! : IIII;il i I
PHASE 2 MA LIM 0 E T !
i a ::.:. i:il.i: i,; iO :! : . : ?: .!: is it i; ni: r;- .s - - - - - -
i eth:ii a:: ::::. :iithi ini: ;il: 1:! : ii 11 i:5 !I'It li i! iti '111 FJ J .. _ . .n i n ,
ist :? ii.
~ i:: ::: .. ?!Illtii ini3; -ii I:! i !i 11 i!4 Iltitill il lif ' 17it s rc/s ~'~ s z--'- _
1 f
I L E G E ** D % 8 r, .- . e .. e .
.._1.ei.....
A .us .... . Soried e, C; e , ..
sime . c i : e . .
C .in peege.se g A rs . .
1
.R09.96 10/97
.... . ....... ST. LUCIE SGRP -
SGRO. uorrison xnvesen
.. e..~. ~.. "..... .. ...
00TAGE g .. :: :: ~ - "
..> PRE - <--
.1,.. ,,,,,
.1 ,
,, ., .1 I .I
,2:..A ,2:..A ,2.O.A Ill:ll i
tillTI 12:..A 12:eeA i il !!!tillittl ' li!!il Ti h now e i
freij i - Itil . (: : s.tl PHASE 2 - AfA lf MOE T - Conff ived t.
I
, it!!i illit:lli tii il li il il fit lf!tlili 11 lif 111 l _ _. --
lif I-~~--~~ l8 e Ill!!! lillf*llt fi 14:11 !! 11 Ill Ill1Ull Il liF E'
~'
1
!illia liiti* lit Ill IWil 14't1 !! 11 Ill tilli!!! Il lif . l!i_ i C3 it!l 9:11111 IEi1 iill 1007 I; !! Il !! Il lit ilfil!!! li til ' !!s .
Ilit I:n liit '1 Ifiles liI;stFgrg]1;;tig; ;;.1151 il lit IIllilli il IIP , 54 _. f ti !
- 1!48 Iti[;1tf9Ililiilll] lies:El iltil 17 il lin 11111:!! Il lif !i i I
- lii! lill riiin i;8tirii !!!iil 11 it ii il ill llill'!! Il lif !!!
illi, !
f--
li!i: Ifit lis; istiit IJ !!Il 1111 Et il fit l!lilill El lif lit I
- li!I illig!II If itt i:ll;I!ni ii 11 la !i il lli 1i1111!! 11 !!! !!!
ilil till:ii! t
' irli[ l - li::54flIII PHASE 2 - P FI O C U FI E M E N T I
. : i; ii::-i 5.!:iiNisi silii sti it ii il ist lililit!i 1111F it i
.; :n; : 01 stis irr; ,it;iititi:s 1*i 11 il ti it ill 11:71t!i Il lif lit I- :
ittist
[
~ ~ ~
I
'Il!!i Ill III ti!! I Blit! - I;! 11 1 !i ll lli II'll II Il !!E lit r
- ilt:s! Ii l
'tii Itti i litat fanlitt Er:!' il 11 ii it ill it'll!!! il i!F !! t g
i:1it::ss i I
i!ai; llllfil lilliCi is Ilill;lII il il li il ill il.ll'il Il lii i d i
11!.181! I ~ ~ ' ~~
I I
- sii Illilitil ilill!ie:1 if !! si il fit il !! II il iii IMi !
Tilli:: ! i l---
il il li it ill li 1811 il liF it!I if *I F Ittii it Ill! Uil Hit _
}
- :f! i8i i inhelt J i (Cll li: :! !! 17 if !!4 !! Il 1111 i:F !!!!
ill:l! I '
- st: fi*:i:i it!t:'M illi Idi !! l! !! il 114 lifII !i il III lil l
r anii;! '
l ~~
~~~ 4 4 eg es 4 e ee e L f f. E N D '
O .rie a.e Sorfed by Cr e. ,
& .sete.. ... t mulm. c 4 e e e e . An**: [
- tra. i n ........ L
.,_A . - . - - - --
__.m _._m _ _ _ _ __.._.....___m __..._____.m _.________m.. _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ________2 ______ __._._ __
, c
SGR0: 10/97- R09 96 I::::n..!*':U:......... Morrison Knudsen .:
- -.. " . . :: ::" " ~
_ -> PRE -
0UTAGE <-- _
t IOf91 01101 94f01 9T701 a19701 l 98 97 97 97 17 >
ll Ill:iliffti - 15Illi tillil III:!I 12:004 12:60A' 12:00A
'~
12:09A 12'O9A f T. f now j
- -ail l ~::sitini intre.n PHASE 2 - PROC UREnlEN T - C antinued
-~~
iiii li::tii il Cetlit fi,C1 Us!i si !! 11 it til !:ll II It i(I ill rT ~'~1 It!! il%III $181C1 !XII !! il !! 11 lil 191111711 !!F l!i f i -.-.E- _I Iliti fl%til 985911 illifist ilill li 11 !! Il fit liitt '!I il lip 111 t- J .
E ~2 Z - "1 I
!it!! llll13!If $F33t flitli il ti'll il lit lillfill il II; Ill
,I ill! iltilli(A*ffil (Illini it it !! il Ill 11111 !! 11 IIF 411 T~~~~! !
III::lilCICI ill; ;I;;fil El Citii I!ifii il ~1 ti il til litil li Il liF !!i 't illi li::Ililitil43 ill li li 11 Il lit fliti:1111 !!F 1[I t .
til: fi::Lii il! l HiF I!I:tifi! it it !! 11 ill ll!11'll il li; Its $
sis 1:si :3 5. ; ni.tsil:t I: :l ;! !! !! I:8 II;;i !! ij ;;; 11 3 i i
ill: l 1111 !!II tillini l;:l# (Ulf Il !! il ill ll!ilell 11 i(F 1: A t ,
it;l Illi ill!:ll i!I !allii i;5ti
- il li il ill 11lll 11 Il lif if A i i
ill: !!I: ice 1:61 i !li ?! !! li il til ll:ll !! Il t!i If ,
A
, Ilii !El; fi((l I311; !! !! 11 il lit fil11fil Il !!F If A ,
A I
- s:s I:illl!i fi;liiItatO n!
!! !! !i il !!I It!!!!!i 11 E!F 11
- i fisil lii .
Ill 1:11111115 FPL ACTIViTI ES t I
li:1 liti:18 illii fi?F iii [.i33i I:! !! if Il ! 1 Ilfli !i il Ili I!! ITE E "E a l i
(111111111:t ' ;
ii t illiiilliti (dilli (iiii .li 8:! ii il ti ill II,!! !i il !!i it j tl ti li !!i 5f8;I ilt 1* En:ET I:! iniit i: !! 1; ii !i iil li ti li il i:T iii ~ a j fissit ;
~~
. ill il fi #II! -? lilii't! :t ; % ii i:1 it !! li !! i:i lif
[
Illt li !il .
l
- i:i ilt::lli 11:7131:ifi liitil it ti !! it ill 11i18'5111 sif_, if A l In:lllit !
iiil itiltlit litti illa lii!:ll it 1! II il fit 1111411 il fit i A }
._ __- . ti6tii ,. _ ,_ j tecemo se. ......- ,
I I J.pe. ..e a . mss.. ... Soefed 2, C2 . . . . . ;
ame.e....... . ...
. m .. ........
~. _ _ _ - . . _ _ _ _ _. _ ) - _ _ . _ . -
f i
SGR0: 10/97 R09 96 s......
. 1.aso....
..s..- M0TTI$0n-Kned$tn
,,;...... . s. ..
0UTAGE
.n
- ... . . e ... ., PRE - <-- :
.,,... i.,., ;
i.,., .,,,, .., , ,
12:8.A 12:.0A II !!!(IIIII(1 111111 [Ilill I!l:tl 12:00A 12:90A 12:.8A T! s$t now l
'iit e:htat i ::st,ssant FPL ACTIVITI ES - Continue s 1
- li! I:t:Al iit Iliiinit li:i 11 :! !! il til itilt til 11 i:P II A
- ie
- it!i! sigiig Tiii iaf;il;II lit !8Fil 5:i' it i! li ii !!A 14,i1:11 Il IIF it &
. iiCiti!! iitt!I
!! !! ?! it ill il.II'll il lif it A
!i!! Iit 10 Fi:IIII li 141 ;
6:itil'llCI ti ! i li;ie8t 11 i!-il !! ill i5!!! !! I! ill ts A ,
'i!! Fit li Fi:Illi li til 5:?.il:815:e ki !.5 liiiit t t i i illi li iill!I l lifi;Ii 1 e iis si il li it fit lill!'ll 11 inf tit ti d ;
- 11; *:l::".1 til li8:lli!! iie:It it il Si il ill 16111!!! Il I!F '
I itse i e [in 8:s j'liiill!it i ii il li !I ill II'll l! il !:i !!!
[
li:::tl ]
A I! :l li II iii 18 liell il !!i
- ia: II; 13 ii:ll't 1111: !a' 11 4:iitill:t ;iiii "
A ,
. !!:: [*.Elintli.:n i lifi:iii if I! i: li il ill liiti II il lif li Ili i A l iii ::t:2:i i.uf .1:7 gitti!aiti . :: !! II (14 11 is:ti il i:F 11
.i ili'll
- II 11 !! 11 !!I it?ll.'!! !! !!F A!
titi i: 1; ii:11ji iii 11 It' 11
~ ~ n:iiitill:t11: !!;I u i ill 13 I!ildili 5 ~3 II :s 11 !! itt II.!! 17 !! i:P' EI '
l IlitiiJi I 15::.11 f
til 1111:itil II:lllll HEW SG STORA GE FACILITY i
f' l is;: . i:i:1 tie i i Tit: 51::8.! . i? i! 04 il 1: !! i+ :!i lit I it::t.it liI:;511f i
t!! II liiit:! 18:11111 OLD SG STORA GE FAC1LITY ,
ari :.: i 1:i:ii.a ti ii, i:i it tiits la i; 11 u i 3 is c, ,
i
" 'il I 5h 9-i a.
7 ee....e so .., ,, n ....
Ape w :
j M eta pr.ge.es t i . _ - - - - -
. . . . _ . _ . ~ . . _ _ _ ~ . _
U
. . . _ _ _.-_.-m .:. __ _ _ - _ .
- _ . _ _ _.. . _ _ . . - ._ . - . . . _ . ~ _ _ . _ _ .- . -. . _ . _ _ . , . _ . _ _ _ _ _ . . . - . _ _ . _ . . , . _ . _ . _ _
. . , . a -c._. ...m. . . y .-.~_-_..._m_>m.m..__. . - -m m _ . . _ . .. , . ~ . _ - - .. . . >#..4..___m.. m..
,E s"e .i ,
,- 2
- ts -
e a
! c w - e" ' . _
e o .
-c .*
- O .e n ,
, -- e .ce _
~
e .t
- ,. , t i _. g t
o -
3 '. L *
- +,
. - - 4 .
~
i L 4 d
ea e
.e . . . -
e s ew .
e e ..
r C -
! 4 t O ,
w
- . - t .
.J I I
[, O -
- e. .
r
' o. g C e oj
%- C
.cr e ~ .
e ,
a 4
e r* . V t-O 1' l
-. W .
o O!
ei I
v== C .e e e. e. s I
e . -
l .** $ l O
!C H Q Q a.
c.
' I- '
n l WD ,, 5 =
. e .: l, -
o e o e.
o e .
e e g
' 1 8 H cr I
Q Lj,) in C C
- ~
O z LA.J * ,
.a
' ""** O G.
Q'It O 8 t .
j .
- ,. l'. . .... ..
... ._..t . ._.
.. . . . .. . .. i.,
. - -, ~ , _. ~
l i
f- . 3 i
.i i e . .
.... i .a.
.. . . . .s w
.u, ....
w p ,,
.. e.,
. ... e .
.. ... l . . . . .. .. .. . . .. .
. ~== . .. - . .
.. .. ._ .~.. _. ._.
. ~.- j-
.~.
~ "* ~ - - . . 1.", .
r ** ** ~. .
?.*
_ _ ._. . . _.= .
._ "i. .'.. ._~.~.
~ *** -~
~ '
.s
.e. r
)
4
. .. .. . .. m. .,e. .
. . .. =. . . . . .
.o.r
. t
. . ~ .
i .,a.. w .. ... .. . .. ... ... .
.. ;. . ... ~... .. ~. ! ,.. . . a. . _
~ . _ . ~...t . . .
.. . t., m.
r
,. e. - , .
u - . , . . .
=
.) : .*.. ..
n_ . .. .,. . . ..
t .._
e s . .e
~... *a..
'.* r.;
T " n _ ..
. m.
.g.
1.* . .n *~
tal **
- e. .e e, m
...e.
6 .. . -
- =- .
.e.ea
. . == ..
u
= .=e
- n s-
= ..
.=..
n es .
.a .,,,.o... -
.r. ,c. i
=
...r. M .=.
- a.
I . .,
.2 1."; -** " ."., =- "
."7".w ** +
e..
- 2. - -
e..._. -. ... ., _ . .
...e se .. ..
m
._. ,u. .. ,. .
E. a. u. ..
.. _ ...... .a..
.a ..- .- .
. .m ...
.. .sos g-
...i..
. . .. . . . .. .. .. ... .a.. .
9..
. .. Lw
.~ i go 4
. i.
i.. ..
. ...-. .' .l i
4 s
, - . . , . . . ._ . ..-.. . .~~.--.~.u..~~-> . - . ~ . n. a . . . - m..~-----a ~~-.n,.n--.u_. s- - a ._ u + a 2.. .-.
I l '
t i
' 4 i }
- 1 ee m
f ts a ::n ar I M
- t
- o.
- e e 4 e c - .
l
- i o . ~ :
g - S .c.*. .e g f i
t +
i
- s. 4 h & a .
o , . t M . s I
.' I L 4 ,
I 44 ou
.e
- e. s. ew ,
o a .. r t
I 4
(L* r l.
cr. ,
I m . =. i.
j ;
O e oa t
- , y g =
e e.e . .
j e L s i i.
N V '
1-p
. m
%W I o .
.a 1 w C -
me
- e
[
. m. ..
- 4 l. tz l Ew ,
' O Q e,
- s j
- I C b c ,
- C .~. r, 4 0 e j {
g -
. . o , ,
. . % ; Y E
s' O '..'
. . z o
50 . ,
. . . m ,
~
Q o e*= >
CL e * = Q tz l !
w -
l I C m 1.o o CW 'O Z
us w
@E .
i l Q I = 1En , l w i 3
w a
.X:
c a
'D l i-
- a. i
- A j' a. to j ;
O e 1
4 3
C 4 I
.~..
J '".".I.
+
Sf i* ) 4
""' = e. I* l t':
- 2. t
- i. .
i p ,
t
' M *:" .; .
a ai l
+
- . *~ C "
g.
- =
~
.K.
~ .~- I
. eu. er . l
... em..
~
.e. . i
.. .. t
- i 1
j
- . 5 t : u i ;
.. e :
e '
ee**
e.e
.. * . *. e. e :
.- g; .x ;;;i 3 ..;g .. .... I l a
-'..d.
. e. l
- 8. ........*
. 2." . ., .
.a . . o
.e. ..
. e = 2.
= ;
n.
4:.7.,.r g g m ji g E =. i g-:F.
-t!M +
l- u...
.=,: : :r. s
- .~ .
4
.:,: x, : .. =. a .
.i .. ..
i: ..-.
. . . . .= -
. ... , ,a,, ,
..... . - - i:: i
. jo . i
"':'*".! m 'd E :. :::: E- .
)
I"
- . .... =
es*s * -
- =.tc I: l t .. .. c. . r -
i o.,- ,,n , - -,,, - , , .-
e ,
l SGT PCM/DP/WP STATUS Type # Description
^^
Related WP's FRG j Approval '
PC/M 151-193 SG 1 A Replacement Modification 2560A,2540A,3020A, 03/22/96 3061 A. 3081 A PC/M 152 193 SG 1B Replacement Modification 2560B,25408,30208, 03/22/96 30618,3081B PC/M 153-193 SG 1 A Manway Platform Moo. 1523A 3523A,1560A, 02/01/96 '
3560A PC/M 154-193 SG 18 Manway Platform Mod. 15238,3523B,1560B, 02/01/96 r
3560B PC/M 155-193 SG 1 A Blowdown Mod. 1521A,3521A 04/05/96 PC/M 156-193 SG 18 Blowdown Mod. 15218,35218 04/05/96 PC/M 157 193 SG 1 A insulation Modification
^ 1540A.3540A 04/05/96 PC/M 158-193 SG 1B insulation Modificaiton 1540B.35408 04/05/96 PC/M 159 193 OSG Storage Facility 2080 PC/M 194 193 SG 1 A Main Steam Ruoture 2551A.3551A 01/29/96 Restraints ,
PC/M 195-193 SG1B Main Steam Rupture 2551B,35518 01/29/96 !
,, Restraints '
PC/M 206 193 Safety injection Line Ruoture Res. 1536 l 01/29/96 >
PC/M 207 193 Surge line rupture restraints 1535.3535 01/29/96 PC/M l 70-194 SG 1 A Supports l2520A.3050A i 02/01/96 PC/M 71-194 SG 18 Supports 2520B '3050B 02/01/96 )
PC/M 11 195 RCS Pipe Elbow Replacements 3061CA,3061CB PC/M 40-195 Main Steam Trestle TG Suoport 1030 {
01/31/96 SGRR Steam Generator Replacement Rep l 08/07/95 SGER Steam Generator Eauivalency Reo 08/21/95 DP 2.6 Containment Access Building 2050,4050 DP 3.1.1 Containment Jib Conduit 1510.3510 DP 3.1.2 SDC MOV 3652 Motor Conduit 1510,3510 DP 3.1.3 FCV-25 7 & FCV-25 8 Conduit 1510.3510 DP 3.1.5 Steel Const. Hatch Lighting 1510,3510 Conduit OP 3.1.6 Cont. Va. Relief Valve Horst 1510,3510 Conduit DP 3.2.1 RCP 1 A1 and 1 A2 DP instrument 1522A,3522A i Lines I DP l 3.2.2 Shield Building Ventilation Duct i 1520,3520 i i 3.2.3
} DP RCP 181 and 1B2 DP Instrument l 15228. 35228 Lines I DP i 3.2.5 i CVCS RCP Seal iniection Line i1522A.3522A a
! DP i 3.2.6 i Shutdown Cooling MOV V3652 i15228.3522B I
' DP i I 3.2.7 l Instrument Air Pioing in Annulus !1522.3522 I l DP 3.2.9 Service Air Quick Disconnect 1522,3522 Pioing
' DP 1
~
3.2.10 i HVA Cont. Ventilation Duct Risers l 1520,3520 1 1 i DP ! 3.3.1 l Platform on SG 1 A West WMI i1530.3530 i I j
DP i 3.3.2 1 Platform on SG 18 West Wall i 1530. 3530 l '
i I DP 3.3.3 I Cons. Hatch Platform inside Cont. I 1530. 3530 i i I DP i 3.3 4 1 Tool Room Area i1530,3530 i
' DP l 3.3.5 I Annutus Structures i 1530.3530
- l 4.1.1 Shield Building Concrete Const. 1551,3551 l DP j j Hatch i '
i DP i 4.1.2 l Cont. Vessel Construction Hatch 6 1550,3550 i. i 1
! DP i 44 I Reactor Cavity Deckino i 1060.5060 i i DP F '1 Steam Ger.erator Of fload 3010A.3010B DP , 5.1.2 l Steam Generator Transport l2570A,25708,3030A, <
I l !
l30308.4501.3040A.30408l I I DP : 2 ~emnorary Gantrv 'TGi 1031.5031 l CP 5.3 ,
Temocrary Lif tinq Device 1032.5032 i DP i 54 i Hatch Transfer System i1032.5032 1
I i i DP i 6.1.1 i RCS Hot Lee Piping 1 A Cavity !2530A.3051A l 1 Page1 I
9 a SGT PCM/DP/WP STATUS Type # Description Related WP's FRG
.._._.~-~ - - ~~
rd~
DP 6.1 3 RSC Hot Leo Piping 1B Cavity 25308.30518 1 DP 6.2.1 SG 1 A Main Steam Piping Temp. 2550A,3070A S/R )
DP 6.2.2 SG 18 Main Steam Piping Temp. 25508,3070B S/R DP 6.3.1 Feedwater Piping Temp. S/Rs 2550A,3070A SG1A DP 6.3.2 Feedwater Piping Temp. S/Rs 25508,30700 j SG1B '
DP 6.5.1 SG1 A Primary DP fnstrument Lines 1522A,3522A DP 6.5.2 SG1B Primary'DP instrument lines 1R
~m 22 P. 3'5 2 28 DP 6.6.3 SG1 A Second. Water Level inst. 150,4 A, 3522 A Lines DP 6.6.5 SG1B Second. Water Level inst. 1522B,3522B Lines DP 7.3 Containment Ventilation i1020,5020 DP 7.6 Temporary Electrical Power i 1050.5050
~
WP 1020 installation of Temp HVAC I I WP 1030 install Steam Trestle Strue. Steel i I WP l l 1031 Erection of temporary TG and HTS I i l WP ! 1032 Erect TLD inside Containment i I WP l 1050 Install Temporary Power i l WP 1060 Install Reactor Cavity Deckinq l WP 1070 Construction Service Air Installation WP l 1510 Electrical Interference Removal I WP 1520 Removal of Perm. HVAC in Containment WP 1521A Remove Blowdown - OSG 1 A 04/05/96 WP 15218 Remove Blowdown OSG1B 04/05/96 WP l 1522 Small Bore Pipe Rem. In the l l l Annulus l I WP i 1522A l Remove Small bore SG1 A i l 03/22/96 WP I 15228 I Remove Small bore - SG1 B t 03/22/96 l WP l 1523A Remove RCS Piping - SG1 A 02/29/96 1 Platforms l WP l 15238 Leakoff tubing rem. . SG1B O2/29/96 l I Platforms WP 4 1530 i Remove Structural Steel I
, WP 1535 l Surge Lme Rupture Restraint 02/29/96 l
{ l Removal I
! WP 1536 i SI Ruoture Restraint Mod. - SG1 B i j O2/29/96 l WP 1 1540A l Remove insulation SG1 A i I 04/05/96 i WP i 15408 I Remove insulation SG1B i i 04/05/96 j WP l 1550 l Construction Hatch Steel Cap.
I I Rem. .
"J P '
1551 Remove Concrete Hatch i i
! WP l 1560A 6 Remove Steel Platf orms - SG1 A I O2/29/96 WP t 15608 i Remove Steel Platforms - SG1 B 6 i 02/29/96 WP 2050 i C AB install i I l WP '
2080 i Construction of OSG Storace Fic.1 I WP 1 2520A I Aemove Supports - SG1 A I O2/29/96 WP i 2520B I Remove Supports - SG1B .
I O2/29/96 WP 1 2530A i install RCS Restraints - SG1 A i I WP 25308 I 'nstall RCS Restraints - SG1 B '
WP i 2540A ' RC Pipe Cuts SG 1 A 03/22/96 i i WP ! 25408 i RC Pipe Cuts SG 1B i i 03/22/96 WP i 2550A I Remove Temn. Sec. Restr. . SG1 A I i
's P 25508 i Remove Temp. Sec. Restr. SG1 B !
! WP i 2551A 1 y
Remove MSSR SGI A i 02/29/96
, WP i 25518 I Remove MSSR . SG1B O2/29/96 Page 2
S SGT PCM/DP/WP STATUS Type- -# - Description Related WP's FRG Approval WP 2560A MS and F/W Pipe Cuts SG1 A WP 03/22/96 25608 MS and F/W Apo Cuts - SG1B WP 03/22/96 2570A Remove / Transport OSG 1 A WP 03/22/96 2570B Remove / Transports OSG 1B WP 03/22/96 3010A Offload SG 1 A WP 3010B Offload SG 1B WP 3020A Prepare and Stage SG 1 A WP 03/22/96 30208 Prepare and Stage SG 18 WP 03/22/96 3030A Transport RSG 1 A WP 3030B Transports RSG 1B I
WP 3040A Install RSG SG1 A 03/22/96 WP 30408 Install RSG - SG1 B 03/22/96 WP 3050A Install Supports - SG1 A 02/29/96 WP 3050B install Supports - SG1 B O2/29/96 WP 3051A Remove RCS Restraints SG1 A '
WP 3051B Remove RCS Restraints SG1B WP 3061A RC Pipe installation - SG1 A 03/22/96 WP 3061B RC Pioe installation SG1B 03/22/96 {
WP 3061CA RC Pipe Elbows SG - 1 A WP 3061CB RC Pipe Elbows SG 1B WP 3070A install Temo Seendary rest - SG1 A WP 3070B install Temp Secndary rest - SG1B WP 3081J. Install MS/MF SG1 A 03/22/96 WP 3081ts install MS/MF SG1B 03/22/96 WP 3510 install Electrical WP 3520 Install Perm. HVAC in cont, and i' ann. I WP 3521A install Blowdown - SG1 A I 04/05/0? j WP 35218 Install Blowdown SG1B l 04/05/96 '
WP 3522 install Small Bore in Annulus i WP 3522A install Small Bore SG1 A i 1 03/22/96 WP 3522B Install Small Bore - SG1 B l l 03/22/96 i WP l 3523A Install SG1 A RC Piping-SG A Plat. I I O2/29/96 j WP 35238 Install Leakoff Tubing V3651 & l V3652 i l 02/29/96 j I i WP I 3530 install Structural Steel i i WP i 3535 Install Pir Surge line RR - SG1 B l I 02/29/96 WP 3540A Install Insulation SG1 A I I 04/05/96 WP 35408 install Insulation SG1 B i i 04/05/96 3P 3550- I Const. Hatch Steel Cao install I WP I 3551A I install MSSR SG1 A i O?/29/96 I WP l 3551B i install MSSR SG1B i 02/29/96 WP l 3560A l SG 1 A Manway Platform install. I O2/29/96 WP i 3560B I SG1B Manway Platform Install. '
02/29/96 WP 4050 Containment Access Building Removal WP > 4501 i Safetv Load Test I i WP , 5020 Removal of Temp. HVAC in Cont.
Building WP I 5031 l Demob TG and HTS i I WP i 5032 i Demob TLD I I WP i 5050 1 Aemove Temocrary Power j
'/ P 5060 Aemove Cavity Deconn
{ WP l 5070 Const. Breathing / Service Air l !
I Removal I
- / P 6521 P aintinq j
Page 3
.-- . w
i SECTION IV
~ l
- ACTION ITEMS LIST - SEPTEMBER i l
i f i '
Page t of 6 St. LuCie Steam Genertator Replacement -Team Action List 13-Oct-96 Item No. Activity DATE
/ Type / Reference tio ACTION BY NEEDED BY Comments ' Listed Promised Scheduled Closed 95100 Procurement Plan MK St. Lucie FPL St. Lucie MK Bill of Materials to be purchased - 5/13/95 1/30/96 1/30/97 Cep auskas Sipos Permanent plant matenal f.11 G 2/1/95 (Old item 314) l 95 104 S(liedule Activities MK Cleveland FPL St. Lucie Revised schedule with 2-3-98 stait date - 4/14/95 7/31/96 9/30/96 l Sager Cowdrey development continuing - SGT Letter 96-MF-010 and 96-SGTF-012 4 f.11 G 414! Weefly T.leeting l l
t I
95127 Shy. ping Configuration BW1 CANADA MK St. Lucie RSG final shipping configuration . 7/26/95 9/30/96 Young Cepkauskas tiO 95 f.1F 093 95 131 S6H Rescheduled MK St. Lucie FPL St. Lucie 1) Payment schedule revision 2) Outage to 9/13/95 11/30/95 9/30/96 10/30/96 Cepkauskas Sipos 10/20/97 reference Ltr 9S-SGTF-026 i 11 1%I SGRP 95-297 i
Page a of 6 ,
St. L,ucie Steam Genertator Replacement -Team Action List 13-Oct-96 Item Nb. Activity DATE ITypf IReference No ACTION BY NEEDED BY Comments Listed Promised Scheduled Closed '96-001 Bid for Ouality Control Services SGT FPL St. Lucie FPL to issue Change Order to SGT 6/10/96 6/12/96 9/30 m Sipos Contract - verbal approval Cepkauskas LTl 6-4-96 Letter No Number 1
96-00 Temp Gantry Crane (Outside SGT FPL St Lucie Analyze changing the mode restriction from 8/20/96 2/28 97 RCB) Pommerening Sipos M-5 to M-1 LTl PSL SGRP-96-085 96-00) SG1 A & 1B MS Rupture SGT FPL St. Lucie Determin0 which actrvities can be started 8/20/96 2/2" 7 I Restraint - Sieel Sipos prior to M-0. Redefine mode restrictions Pommerening l
accordingly. Break activity into more detail j LTI! PSL. SGRP-96-085 to determine which activities' can be worked in paratlett 96-004 SGI A MS Rupture Restraint - SGT FPL St. Lucie Move M 0 to M-5 P'20/96 2/23:'87 Jib Crane Removal & Pommerening Srpos LTI- PSL-SGRP-96-085 1
. . . _ _ _ _ . . . _ _ - . - _ . . _ _ . _ _ _ - _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . _ . _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . __.__..__m_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ _ .
? '
Page 3 of 6 St. Lucie Steam Genertator Replacement -Team Action List 13-Oct-96 Item No. Activity DATE :
1 Type 1 Reference No . ArilON BY NEEDED BY Comments Listed Promised scheduled' Closed 96 005 Jib Crane Conduit and Cable SGT FPL St. Lucie - Move from M-0 to M-5 8!20/96 2/28!97 l Pommerening Sipes t i! PSI SGRP DG 085 ,
96 oil 6 Srb A&B Platforms at 73' SGT FPL St. Lucie Move removal and Replacement from M 0 8/20/96 2/28/97 Eleution Pommerening Sipos to M-5 t il PSI SGRP-96 085 96 607 Ait tiimmoet lleavy Equip (TG. SGT FPL St. Lucie Review schedule activities upon completion 8/20/96 2/28/97 Skot Trans. It D & Mobile Pommerening Sipos of DP's for possible schedule reductions and or logic changes 1.11 PSI SGRP 96 085 96 008 Ed@ Current Tests of S/G A&B FPL St. Lucie SGT FPL is not performimg tests - completed - 8/2d/96 2/28/97 2/28/97 9/30!97 in Veitical Position Cepkauskas verbal Gross ,
1.11 PSI SGRP-96 085 l
i L
k i ' i :
a i
St. Lucie Steam Genertator Replacement -Team Action List P@ M 6
- 13-Oct-96 Item No. Activity DATE
- IType I Reference tio ACTION BY NEEDED BY Comments Listed Promised Sclieduled Closed 96 009 Surge Line Rupture Restraint SGT FPL St. Lucie Move from M-0 to M-5 8/20/96 2/28/97 RIR Pommerening Sipos I il P ,L-SGRP 96 085 !
96 010 Surge Line Rupture Restraint SGT FPL St. Lucie Analyze for possible elimination of this 8/20/96 2/28/97 Replacement Sipos equipment via Leak Before Break Analysis ;
Pommenening a 11 l':it SGRP 96 085 i
96 011 RGB Laydown Areas - Storage FPL St. Lucie SGT Identify the storage locations of equipment 8/20/96 2/28/97 included on MK's " Storage Areas for RCG" of Permanent Plant Equipment f.ictaughlin Cepkauskas list t il Pdt SGRP 96 085 96 012 Siti 1B f.tanway Platfo m - SGT FPL St. Lucie Modify package to show capping leak off 8/20/96 2/28/97.
Remove, Modify & Reptace Sipos line from V-3652. The leak off line from V-Pommerening 3651 was capped by Mech Main in 1995 t il 1851 -SGRP 96 085 Outage Move platform reinstattation from M-0 to M-5.
l i
I
r St. Lucie Steam Gencrtator Replacement - Team Action List Page 5 of 6 l13-Oct-96 Item No. Activity DATE i f t ype i Reference No ACTION BY NEEDED BY Comments Listed Promised Scheduled Closed 96 013 SIG 1 A Manway Platform - SGT FPL St. Lucie The current schedule logic shows 8/20/96 2/28/97 Remove. Modify & Replace Pommerening Sipos reinstallation of the RCS instrument lines prior to reinstallation of p!atform Change I il Pbl SGRP 96 085 logic to show a finish-to finish relationship. i t
90 017 Construction Hatch SGT FPL St. Lucie Determine documentation requirements for 8/2d/96 2/28/97 Pommerening Sipos danging the weld process from double to single bevel.
l t Il PSL SGRP-96-085 l
90 (119 licavy Litt Lquiprnent Schedule SGT FPL St. Lucie Analyze to identify any conflicts there may 8/20/96 2/28/97 Pommerening Sipos be in the use of the Polar Crane. Mobile Crane, etc.
t Il Pbt -SGRP 96-085 96 020 S. hedule Codes SGT FPL St. Lucie Present plan for coding activities to indicate 8/20/96 2/28/97 Pommerening Sipos Plant System, Work Packages, EP/DP, Area, WBS. Mode, etc t 11 Pbl SGRP 96 085
Page 6 of 6 St. Lucie Steam Genertator Replacement -Team Action List ;e 13-Oct-96 l'em No. Activity DATE I 1 Type I Reference No- ACTION BY NEEDED BY Comments Listed Promised Schedule'd Closed 96 021 1IVAC Containment Vent Duct SGT F'PL St. Lucie Move removat and replacement from M-0 to 8/20/96 2/28/97 l Hisers Pommerening Sipos M-5 I 11 l'SL-SGRP-96-085 E
b b
t i
i i l
i i
L
1 t l l
l 4
SECTION V PHOTOGRAPHS i
1 i
o, .
+ .
. STEAM GENERATOR REPLACEMENT The SGT: MK/DE&S ST. LUCIE PL4NT - UNIT I MONTHLY PROGRESS REPORT PHOTOGRAPHS A. - Proiect Photogranhs There are no new photos in%)uded for this month's report.
'9 s i
I i
i e
1
.c e r -- - - - - --
-'?-
Vi
- _ _ _SGRP/SGT_ STATUS SEETING FORMAT i
b.a I. Onenine Remarks - R. Sinos II. Point Beach Uodate - M. Ceokauskas 567 F< - . > i Mo c&
b
! /rs o#~s \ .
IILSfsT Reoort
- 1. Project Manager comments
- 2. Pre-outage milestones achieved since last report
- 3. Progress report on upcoming milestones'
- 4. SGT schedule status ,
- Pre-outage l j - Outage
- 5. What is needed from SG7P )
i IV. SGRP Reoort )
- 1. Project Manager comments (A, e Ps =-2. Pre-outage milestones achieved since last report
- 3. Progress report on upcoming milestones
, (4. Overall schedule status .
- 5. V5iat is needed from SGT l
l V. Ooen Discussion ~
l
- 1. Review of Action Item Tracking System items not previously discussed
! 2. Other issues not previously discussed VI. Review of Action Items From This Meetinz VII. Schedule Next Proiect Review Meeting 6
w \
tHUMAN I )_ -OLO yPERFORMANCE EXECUTIVE SUNNARY l 9ENHANCENENT l
, SYSiEM -
( /
- 1. Nuclear Unit 2. Report Date 3. Report 4. Evaluator Plant Unit Time Month Day Year Number Name St. Lucie 2 1915 02 01 95 95-02 Locke l
- 5. Event Description n! l The instrument and Control (l&C) department in conjunction with the Operations and TecF Staff departrnent were performing troubleshooting activities on the letdown system. An i 1&C specialist lifted the leads on the transducer to perform tests on it. After completing ;
these tests, the specialist re-connected the leads to the transducer. Later, when the I i control room operator attemoted to have the valve take control of letdown, it was ,
discovered that the leads had been re-connected incorrectly. i l
2 y i
i
- 6. Human Performance Problems Item Description of inappropnate Action Repeat Consequences 1 Leads landed incorrectly Yes Insufficient letdown j
!l
_ Jl l
- 7. Etuipment Failure (s) or Condition (s) Affecting Human Performance I
Descripbon of Equipmert Problem Repeat Consequences None N/A N/A i
/
,/
. page 1
l t s
[k 8 Evert Nanative (Ci.udg; cal Description) p . . _ _ _ _ . . . _ . -_ _
- The letdown system for Unit 2 had been experiencing unstable operations. In an attemp to determine the root cause of this problem, troubleshooting activities were commenced.
On Tuesday, January 31,1995, Letter Of instruction LOl-T-89 was generated to provide detailed instruction for the troubleshooting activities on the system. The focus of the troubleshooting activities was to be on valves LCV- 2110P and LCV-21100.
i Operation of these valves is selected from a common hand control switch in the control j
room. The switch allows"P", "Q" or "BOTI-f' to be selected for operation.
1 A tailboard meeting was held involving the Operations crew, the I&C crew and representatives from Tech Staff. LCV 21100 was placed out of service in preparation fo i
testing. An I&C supervisor and a specialist went to the Reactor Auxiliary Building (RAB) l with the Nuclear Watch Engineer (NWE) and a Senior Nuclear Plant Operator (SNPO).
i The l&C spec lifted the positive and negative leads on E/P-21100 and taped them to l prevent the leads from coming in contact with the case. A static flow scan instrument j was connected to the E/P and valve diagnostic tests were performed. The flow scan 1
instrurnent was disconnected and a 50 ohm resistor was connected in series withi the
! positive lead on E/P-2110P. Another piece of test equipment was connected to the E/P and a stroke test was successfully performed. The test equipment was disconnected from the E/P, and the two leads were re-connected to E/P-21100. At this time, LCV-
!. 21100 was to be placed back in service with monitoring equipment connected to it to record characteristics with various charging pump and pressure control valve i arrang6TE-nts. The control room was notified that the valve could be retumed to service ,
i The Reactor Control Operator transferred control from LCV-2110P to LCV-21100. LCV-21100 failed to open as required and charging was secured. After some investigation by i the I&C personnel, it was discovered that the positive and negative leads on the E/P i
had been re-connected incorrectly. At this point, the testing was secured.
I t
! l l
- a.'
! 9. Surnnary of Factors that influenced Htanan Perfomunce
! Behavioral Analysis - How it happened for each inappropriate action '
i l j Unawareness -The l&C spec who re-connected the leads to E/P-21100 did not i
i i I
realize that the leads had been connected to the wrong terminals. .
1 q
i i
pageZ 3
, 10. Summary of Causes Causal Analysis - Why it happened for each. inappropriate action _ - -
Work Practices - Error Detection Practices - Self checking not applied to ensure intended action is conect -The l&C spec re-connecting the leads did not apply the self checking process when the leads were re-connected to the terrninals. The leads had wire markers designating (+) and (-) on the leads and (+) and (-) was etched into the case of the E/P above the teminals. These markings would have provided positive identification if they had been checked.
Work Practices - Error Detection Practices . Independent Verification not perfsnad anr=ctly -The LOI called for an Independent Verification after the leads were re-connected to the E/P. The I&C supervisor assisting in the troubleshooting activities signed off the IV after observing the I&C spec re-connect the leads. The supervisor i
thought that the " level of IV' needed for this job was less than that required for control room work or work on sensitive or safety systems. Independent Verification should be a .
truly independent look at the task or step performed, and should have the same level ofh detail applied for all plont systems. p WHtten Communication - Method of Presentation -Inappewiate emphasis of step or information - Step 4.2.24 of the LOI states, " Remove the Transmation, reconnect the
- positive and negative leads to E/P 21100 and connect up the valve position recorder fot the test." Two spaces are provided after this step; the first for a sign-off by the performer and the second is for I.V. (independent verification) that the step was performed. The ;
I&C supervisor stated that when he signed off the IV he interpreted it to be that the leads had been re-connected and that the valve was available to be placed back in service. In retrospect, he says that for the valve to be placed back in service, the leads [
would have to be correctly connected, j
i
- 11. Evaluator Comments Explanation of repeat problems, exceptionally good perfomnance noted, etc.
I None. ,
pageS !
S 1
1 11 %== tion (doctanents, logs; references, interviews, etc.) ._. _.
2-LOI-T-89 " Diagnostic Testing of Letdown Level Control System" '
t Unit 2 Reactor Control Opuator Chronological Log Interviews with various plant personnel
- 13. PKW Conective Actions 1
- 1. Procedures or LOls whicn require independent verification should be specific in the l step (s) to be taken and v. hat the independent verification means. In th should have directed the spec to land the positive lead on the positive terminal, etc. Thid format would ensure that the intent of the independent verification is clear.
- 2. This event should be incarporated in In-House Event Training for all Maintenance i
disciplines. Independent Verification should be the focus of the lesson; definition of IV, what management's expectation of IV !s, how IVs are to be performed, etc. (STAR l'
- 950342) l 3
- 3. A plant procedure e citled " Independent Verification" has been written to ensure ;
independent Verification by all plant personnel is consistent. A generic review of plant I procedures will be performed to identify, and change all definitions of IV to one consistent definition. (STAP #950341) i
- 4. Maintenance Management will assess the knowledge and interpretation of (
independent Verification and Self Checking by maintenance personnel After this
. I; assessment has been ca.ncieted, Maintenance Management and Training will develop l:
and provide training as necessary to ensure the level of knowledge and application of the Independent Verification process is consistent with Plant Management's expectations. (STAR #950242) l 1
Submrtted: - ///l)R$ 4 HPES Coordinator ' Date Rev.
page4
l ___ _ ____ __.__._. ____.
To: Distribution Subj: PSL POLICY 105 REVIEW; OPERATIONS OF UNIT 1 ON ONE MAIN TRANSFORMER WITH ITS ASSOCIATED COOLING EQUIPMENT
- 1. On 4 Sep 1996 a Policy 105 team was assembled to review the power operation of Unit 1 on the single 1 A Main Transformer with its associated cooling equipment. The team was comprised of the following members and disciplines:
J. A. West System Engineering (SRO) Team Leader R. Raidiris System Engineering _
W. Busch Design Engineering .
B. Czachor Operations Support (SRO)
S. Patterson Operations Support (SRO)
B. Griner Electrical Maintenance Technical B. Enfinger Operations Support
- 2. The following documents were reviewed in support of the subject evolution: 1
-. Engineenng Evaluation JPN-SPSL-96-0399, Evaluation of Temporary Operating . _ _ _ _
Configuration with IB Main Transformer Out of Service
. Temporary System Alteration to disable equipment servicing the IB Main Transformer while operating on the 1 A Main Transformer
. Procedure Change Request to NOP l-0030124,Rev 5, " Turbine Startup Zero to Full Load"
- 3. The engineering evaluation was reviewed for technical content in support of operation of the unit on a single main transformer. The follow observations were made:
- Based on a review of the engineering evaluation against the Unit 1 FUSAR it was the recommendation that the 50.59 screening be expanded to include a full 50.59 evaluation.
Responsibility: Design Engineering
. The transformer load curve developed by design engineering required a verification and approval by Transmission and Distribution to ensure that the assumptions used in the development of the curve were conservative and correct.
, Responsibility: Transmission and Distribution, Design Engineering interface
. The operating restriction of" the average temperature of the cooling air for any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period shall not exceed 30 degrees C." Was judged to be to restrictive. It was requested the this operational limit be reviewed by Transmission and Distribution.
Responsibility: Transmission and Distribution, Design Engineering interface
/
I
~ .~ Tuisole operation on the~1XMain Transformer, it was requested that Operations td:e readmgs on all available data provided by installed instrumentation on this transformer.
l This data will be taken by use of the data loggers. I Responsibility: Operations Support in concurrence with Operations l
A precaution to the load operating curve was recommended which is similar to " The main generator shall not be operated above 200 MW with the startup transformers in service".
The load operatmg curve "x" should be modi 6ed to include a zero point to ensure there l
are no human factors concerns throughout the generator loading sequence for the Operators. l Responsibility: Design Engineering, Operations Support The engineering evaluation should be modified to include an explanation of the load operating curve.
Responsibility: Design Enginecting Numerous questions arose surrounding the operations of the isophase cooling system:
- 1. If the isophase cooling system were to be blanked off on the IB main transformer what would be the effect on the flow to the 1 A main transformer? Will the setpoint for the flow l
switch require a change? Can it be changed with the isophase cooling system in l operation? Are the any heating effects that we should be concerned with on the B I isophase side of the cooling?
- 2. Why can't the isophase cooling system be operated in a normal configuration since the isophase box will no be removed? Is it necessary to insulate the bus link ends? If they must be insulated with the system in service how will this be accomplished to prevent a possible failure of the isophase cooling system if the insulation should come loose? Can you have a valid dispatchers clearance ifyou can not verify the air gap on the links visually?
Responsibility. Design and System Engineering A letter is requested from Protection and Control Management which states that a thorough review of the intended operation has been conducted and that the proper relaying has been disabled and there will be no effect on the l A transformer operation.
Responsibility: Protection and Control, System Engineering interface d I
The fire d.eluge system supervisor control will be added to the Temporary System Alteration.
. 1
}
The engineering evaluation requires that the oil systera cross-tie valves be closed and I locked. It is recommended that it require the valves to be closed and a danger tag be l placed on the valves to prevent operation. I I
I
- f. .
s
~ ~ ~~4. The'Tenigiorary System Alterati5n was reviewed for technical content in support ofoperation' of the unit on a single main transformer. The follow observations were made:
- Specific information on where to break the IB Main Transformer deluge line for capping is required. A PWO to perform this work is also required.
Responsibility: System Engineering, Maintenance Planmng
- Specific information on where to lifi leads and install the jumper to disable the IB Main Transformer deluge line is required A PWO to perform this work is also required.
.. Responsibility: System Engmeering, Maintenance Planning
- Provide the details necessary to perform the'IB main transformer relay work via Relay Work Order and capture the associated components on Figure 1 of the TSA procedure for documentation of the abnormal configuration.
Responsibility: System Engineering / Protection and Control
- 5. The Procedure Change Request to NOP l-0030124 was reviewed during the scope of the _.
engineering evaluation review. Observations were captured during that review and documented above. The following additional observation was made: __._. .
A_h.
- Backfeed through the main transformers was not addressed and the associated procedures which launch this task have not been changed. It was requested that this be reviewed again.
Responsibility: Operations Support i
. It is requested that Licensing perform a review to ensure that we do not have any licensing I commitments which require the capability of backfeeding through the main transformers to be available.
Responsibility: Licensing dem.~
l s.
l b
l 1
l ERT i 1
2B Steam Generator Level Anomaly '
Problem Statement:
l At appronimately 5:00ar 11/14/96 cperatcrs noticed a spike ir 2B Steam Generatcr Level to appro:nmately 695 (4i high:. ,
After transient returned to normal Steam Genera:Or le'rel was i observed to ramp up uncontrolled at a 3-4i/hr rate. Manual control was taken on the feed water control syster. The system is now stable under operator manual control.
Immediate Actions:
- 1. While in Auto mode Steam Generator setpoint was ck aged to 631. The ramp rate was observed to level off ior a time period and then continue the ramp increase as I before. -
2 FCV-9021 was visually inspected and SNOOP tested for air leakage and normal operation. Results indicate no air leaks and good valve operation.
l 3. Non intrusive data was taken on the feedwater regulation controller inputs and power supplies. Results indicate inputs look normal and the power supplies are within acceptable tolerances. AC ripple has increased since the l
last test but remains within tolerance.
Coupleted Actions:
l
- 1. Collect non-intrusive data to further assess condition
~
while in manual. !
! I/C-PWO to be planned by 1:00pm I/C OPS & SCE - tailboard 1:30pm ERT team - Collect Data and review results 2:30pm l~ 2 Analyze Daca and make recommendation on further more intrusive tccting or component replacement.
l l 3. Identified and located spare parts available for repairs.
Conclusions:
- - _ Data indicates that automatic feedwater controller has failed l and requires replacement. As a prudent measure the power supplies should also be changed while the controller is replaced. Additional low risk testing in automatic mode at power could help confirm the mode of failure.
t 4
g =
/ .j-
/-
/ -
~ -
s \
$ l 1
l Short term test Plan: )
'.. ER: Team - f.na__:e tes: setup and preceaures f : ne:: _ :
phase of testinc with the system in auts. l Due 0800 11/15 l
- 2. Ops /ERT Team - monitcr system in Automatic Mode. j 0900-1200 11/15 1
- 3. ERT Team - review data from system in automatic mode and make final recommendations for repairs.
Due 1500 11/15 l l
l 1
Repair Plan: l
- 1. I&C Maintenance - prepare spare controller, 24 volt &
45 volt power supplies for service.
Due 1600 11/15
- 3. ERT team - Finalize spare parts requirements Due 1200 11/15
- 3. Work controls - set time / schedule for downpower to replace controller, power supplies and verify valve operation.
Due 1500 11/15
- 4. Conduct downpower to replace controller, power supplies and verify proper valve operation.
1:to k DEGR AD E.D G R ID F Lo ta CNT Fw PAG E E :
( TEsit uC1
\ _
tJ PM FN to o %
WdaA x ( Giot.
3.o 'b V _
\m ~
- _ _ - . - Enm em _ _ _ _ _ . - .
I to (~ iy \d _
G 'd_a
a =
/
Assignments:
y_ _,
_.7 _ .
- 2. Dave Steward - Create time line and CCl eC: data
.. ,, , - ~ - _
.y._
A __ m n ,, : ",;.'
s.
.m _ _- __.-.n_.n ..
s
_ _i.e, _ . _ .
n, y_v._e.-
n
. - .. , + , _ _ _ _
- . a,nalysis team r.eview ckt design f or ne:: ster
- 6. I&C - bench test replacement components i . p O
.. L, e,.,.s.o .
_ _ Qe , , Ve N, e. O C O n t C ., ., o 2 - ). / e a.,.,.c-As sem i uq C. b 6 Cob'c
~
b4 4
0
-_ ~ ~ ~ ~ - - .
b
A
[ i . i F ~~
J
_ g gg g g __.___
l 1. The resulte of your review and investigation of the noted
< problem including identification af prnhahle root cause(s) .
- My review of the noted overtime guideline adherence problem i indicates several problems which need resolution. My
! investigation also concludes that violations are more apt to occur when the workforce is scheduled on extended hours, or people with unique talents are needed to perform work at the site. Finally, my investigation indicates that contractors, maintenance personnel and key technical people are most likely to ,
approach guideline limits.
Problem -
The bi-weekly timesheet does not progranmatically identify which overtime hours are turnover time and which hours '
are work time. It is left up to the worker to annotate the form for this identification.
Problem -
No standardized mechanism exists for contract administrators to nonitor the overtime worked by contractors.
Problem -
The amount of turnover time is inconsistent among departments and that workers and lower level supervisors are determining for themselves how much turnover time is acceptable.
Problem -
Some workers / supervisors may be falsifying timesheets with respect to when overtime hours are worked, in an effort to avoid detection of any guideline violation.
Problem The timesheet format does not contain information about the six calendar days prior to the beginning of the say period, which precludes any identification of an early week violation of the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 6. days guideline.
Problem -
Cross checking of timesheet data is not being performed at any organizational level.
Note -
If the Nuclear Division adopts a "no pay for exempt overtime" policy, the timesheet, as it is currently configured, will lose its usefulness as a tool in identifying guideline violators This is evidenced by the current inability to accuratelh determine the ccmplaince of management personnel with the guidelines.
The probable root causes of these noted problems are threefold:
Root cause - Timesheets are not formatted to clearly identify turnover hours and unpaid hours which must be accounted for in determining overtime guideline compliance. They were not designed to accomplish this task.
. Root cause - Management expectations for compliance with guidelines and with documenting hours worked are not sufficiently robust to preclude violations.
Root cause - There is no efficient mechanism in'31 ace for management to routinely verify compliance with the overtime reautrements.
Root cause - No efficient means exists for supervisors or managers to crosscheck data entered on timesheets. )
[
- Q
- 2: Review-depart 2nental self-Resessment activities to identify why this problem was not self-identified. Why did the worker level or l supervision not find thie pmblem?
Departmental self assessment activities consist of reviewing bi-weekly time sheets for approval. Some managers and department heads specifically review the time sheets for overtime guideline conpliance, but many do not. The lack of timesheet clarity
- .egarding turnover time and unpaid hours worked (which still must count against the guidelines) precludes an efficient mlf-assessment.
- 3. A determination of the generic impact of the problem i.e.
whether the pmblem extends to other areas, systems, drawings, procedures, etc., or whether it is isolated to those examples cited in the audit report.
The overtime guideline problems are widespread across FPL personnel, and contractors alike. The results of the QA sample do not bound the population of personnel who may be in violation of the overtime guidelines. The corrective actions will assume that all departments and contractors are equally susceptible to this problem.
- 4. Actions taken or planned to correct the problems identified and to prevent recurrence of the deficiency. Corrective actions should address any self-assessment /self identification weaknesses found in (2) above.
- 1. Inmediate (interim) corrective actions:
- a. Mtter from Site VP emphasizing Nuclear Policy comoliance and better defining limits on turnover time.
- b. Perform a mantal, monthly surveillance of a sampling of plant personnel and contractor timesheets versus gatelogs.
- c. Determine discipline for any individuals found to have deliberately manipulated their timesheet in an effort to avoid detection of guidelinn violation.
- 2. Progranmatic (long term) corrective actions:
- a. Time Sheet Improvements
- Alter form to requi.re documentation of all overtime hours worked, regardless of pay status
- Alter form to require documentation of previous six days overtime status (prior to current pay, period)
- Alter form to clearly delineate turnover time
- Alter form to add a statement for the submitter's signature that reads "I have not exceeded NP 306 overtime guidelines."
- Alter form to add a statement for the accrover's signature that reads "I have reviewed th'e surmittal for compliance with NP 306 overtime guidelines."
l l
4 -
1 1
-b. Revise QI--6-1-to requiz.e uvuL1. actor submittal of- hours ~ ~
l worked to contract administrator on a biweekly. interval. I 1
'c. Irrprove the reporting capability of the Security access cotoputer program to generate a routine report that examines the hours on site for obvious NP 306 exceedences.
1
- 5. Date when above corrective acciaa(s) was or will be achieved. 1 Corrective action la. - 8/ 96 l Corrective action 1b. - 8/ 96 Corrective action 1c. - 8/ 96 Corrective action 2a. - 9/ 96 Corrective action 2b. - 10 /96 Corrective action 2c. - 10 1/96 l
- 6. Individual (s) responsible for each corrective action.
la. - C. Burton (Services) PMAI ,
ib. - C. Burton (Services) PMAI )
Ic. - Joe Marchese PMAI '
2a. - R. Heroux (Resource Control) PMAI 2b. - R. Heroux (Resource Control) PMAI 2c. - u. Patel (I&C) PMAI
1 I
- SGRP/SGT STATUS MEETING FORMAT __ .__ _ .
, 1 i !
1 4 I. Ooenine Remarks - R. Siods II. Point Beach Uodate - M. Cepkauskas < ,.- , ,
" ~*
III. SGT Reoort f
- 1. Project Manager comments -
- 2. Pre-outage milestones achieved since last report
! 3. Progress report on upcoming milestones
- 4. SGT schedule status
- Pre-outage
- Outage
- 1. Project Manager comments
- -, < i f . 2Pre-outage milestones achieved since last report
- 3. Progress report on upcoming milestones ;
( 4. Overall schedule status 1
- 5. What is needed from SGT V. Ooen Discussion
- 1. Review of Action item Tracking System items not previously discussed
- 2. Other issues not previourly discussed VI. Review of Action Items From This Meetine VII. Schedule Next Project Review Meeting a
a 6
/
/ /
/ /
/
STEAM GENERATOR REPLACEMENTPROJECT PROGRESS REPORT MAY - JUNE 1996
,l \
g i 1
e Nuct 8" 1 d
( g,
) d I Nrtle
' (O'SGFW40047-CVR-R1)
j..
!. l TABLE OF CONTENTS l
i s
l The Steam Generating Team (SGT) i
! B&W Canada Steam Generator Fabrication i
Engineering
! l l Quality i l 1
Attachments:
}
SGRP Budget Status - Capital Dollars l SGRP Budget Status - O&M Dollars l l Pre-Outage Bar Chart for SGT l l Engineering / Design Pkg. Development Status Graphs
- Construction Work Pkg. Development Status Graphs
! Steam Generator Fabrication Status Schematic Photographs
- l i '
i l-t
1 ST. LUCIE UNIT 1 SGRP HIGHLIGHTS REPORT MAY - JUNE 1996 THE STEAM GENERATING TEAM (SGT. Ltd)
SGT has completed 95% of the PC/M engineering and work packages, and haS contracted for long lead material aS Shown in the table below. ,
1 1
Major work will re utr.e January 1997 when SGT mobilize $. At that time, all engineering and licensing q documents will be reconciled for implementation.
4 I
SGT, LTD SUBCONTRACTOR SUNSiARY l m ...
- ,; . _. __ _ . _ . . ;__.._._;. ..__._._._- I St'BCONTRACTOR SERVICE /hiATERIAL STATUS I Davenport Mammoet Steam Generator Rigsmg and Transporting Engmeerms Development 2 Transco Products. Inc Steam Generator Insulauon Engmeenng Development 3 LAW Engmeerms. OSO Storage Facahty Soil Bonns Completed l
l l
B&W CANADA STEAM GENERATOR FABRICATION The new Steam generators are planned to arrive on Site June 1,1997.
The table below ShowS that five of the Six new contract milestones have been completed ahead of
=chedule. All other B&W activities are alSo proceeding on Schedule. i l
B&W MILESTONE STATUS 1
- . :,: :== m - : .----- : -- - - - - -= =.= . - . - j M/S S/G MHETONE STATUS TARGET ACTUAL NO. NO. DESCRIPTION COMPLETE COMPLETE I si Foal Weld Repar - Weld s4 (Stay Cylinder to Pnmary 2/1/95 12/24<94 l Headh 2 #2 Weld tD Seal Pass - Weld s4 (Stay Cylmder to Pnmary 2/195 1l'1894 Head).
3 st Compteuon of Pninary Head ic Tubesheet to Shell Assembly 5'9'95 21:19 5 Welds through MT repass of Support Base to Shell Weld 4 82 Completion of Pnmary Head to Tubesheet to Shell Assembly 7!5/95 41495 Welds through MT repars of Support Base to Shell Weld 5 Both Completion or Tube to Tubesheet Seal Weidmg 6/11/96 2 6/96 6 Both Final Dehvery of 5/O's at PSL 6,l'97 7
. .t.
l 4
ST. LUCIE UNIT 1 SGRP HIGHLIGHTS REPORT MAY - JUNE 1996 B&W CANADA STEAM GENERATOR FABRICATION (continued) l Maior Accomplishmeng l
Cambridge, Ontario - Heat Exchangers .I l
l Both Lower Assemblies '
Complete and loaded on rail cars for transport to Toronto for barge loading.
Mt. Vernon, Indiana - Steam Drums
~
First Unit Steam Drum 4
Complete - waiting for heat exchanger to arrive from Canada. l Second Unit Steam Drum l
Completed all PWHT NDE. l Completed installation of sec. manway covers and linkages. {'
Welding of internals in progress.
Internals Complete - All five separator modules are assembled for both units.
ENGINEERING Outare Preparation Commitments have been made to return the three FPL engineers to the project on July 1,1996. These resources are needed to complete the remaining engineering issues and prepare for a potential early SGRO in October 1997.
SGT and Mammoet Engineering will mobilize J .nuary 1997 to complete the project.
A draft project engineering erganization chart for the outage has been developed.
B&W Engineerine Engineering reports are being worked for completion in 1996. FPL resources will be available to review these documer ts in 1996.
-2
e ST. LUCIE UNIT 1 SGRP HIGHLIGHTS REPORT MAY - JUNE 1996 ENGINEERING (continued)
SGT Eneineerine l
SGT has completed the engineering with the exception of the heavy rigging Design Packages which are expected to commence in January 1997. All the packages completed to date have been approved by j FRG. j Early Outare Impact evaluations were done on the early outage scenario versus the current contract outage of February 1998. The results showed that the Contractor and the steam generators can support installation as early as June 1997.
Steam Generator Disposal Two vendors are bidding on the disposal of the Unit I steam generators. Bids are expected on August 1,1996. FPL will determine if the near term disposal is cost effective compared to long term storage.
OUALITY Surveillance continued at Cambridge and Mt. Vernon manufacturing facilities. Both I'SG heat exchanger sections completed manufacturing and were transported by rail from the Cambridge shops to the Port .
of Toronto. This transport and the subsequent loading on to the barge was successful.
)
Archive weldment and material samples were receipt inspected and found acceptable.
l Radiographic Hims for the heat exchanger sections were shipped to PSL. These Elms were inventoried l
and inspected. All were found acceptable and are in the PSL record vault. i Distribution:
T.F. Plunkett l J. A. Stall W.H. Bohlke L.W. Bladow J.M. Brady K.R. Craig C.L. Burton D.J. Denver J. Marchese C.D. Marple K. A. McKenna J.C. Scarola C.H. Wood
-b
- i !
ST. LUCIE UNIT 1 i SGRP BUDGETSTA TUS- CAPITAL DOLLARS 1
- JUNE 1996 a
l 7,500 i '
l l !
7,000 1
4 5
6.500 I L-- -lMoNTHLY BUDGET i MONTHLY ACTUAL o 6.000 - "
C = CUM DUDGET # T IO'#
---O- CUM. ACTU AL o e 5.500 - -
4 ,
l 3
- p m
5,000 f,------ -- --- - - - - - - - - -
s.
g s
4,500 p'- 13.500 A, i m
) 4.000 l ' u 5
a l
, a s E g 3,500 j o, 3
a
. m i g
O l a m 3.000 p m
, .-i i
@ 8.500 e
< i o 1 2500 L p"- -
)
E 2.000 I
i o
e '_ m' ;
S g )
l 1
l 4 1 l
, 1,sou1 - ,,o* -- - -.I 1 l
1
."O 1 3.500 l i.000l ,o _ __ _.J l l _._ o' u, _, / _ _
Ly _ _
0+
,E ILI+ 3 e M E R y _E:
,5 4
9 a
t a 8 3
I w s 4 s < m o = a ;
500 1 -1 .500 (5000) I CURR MONTH YR-TO-DATE TOTAL-TO DATE YR-END FCST BUDGET $627 $5,162 $66,403 $18,881 l ACTUAL /FCST $753 $2,027 $61,546 $16.405 VARIANCE $127 ($3,134) ($4.857) ($2,476)
Significant contributors to the Year..To-Date budget underrun:
- SGT payment schedule was changed due to the reschedu!ing of the SGRO fro 9/97 to 2/98. ($2,121K)
- Deferred payment for blowdown line analysis done by SGT. ($100K)
- Deferred QA/OC contractor support. (5357K)
- Negotiated ehmination of BWI scope change for barge transportation of new S/G's (236K)
I F '.USERSICOWDREPRE TMD5-v ART AT'36'i RV, Onnt L;,is 721?C KJC
u ST. LUCIE UNIT 1 SGRP BUDGETSTA TUS- O& M DOLLARS JUNE 1996 2
1 80 - ,000 t
! i iMONTHLY BUDGET I MONTHLY ACTUAL , '
= C " CUM BUDGET g
j --O---CUM. ACTUAL e 00 I #
o
?y 60 i' 7 g
5 i
i o So g i i*$2 d a w '
g - - -
2 l
- 3 !
3, i m l
o j , 300 d
- u. l 4f 0 j O #
I o
m I #
1 u
O '
- 1 O j 30 - --- - #y---- -
e m
-j Q l
E :
? 200 5
+ s 8
m , l z d,n#1-10 J -- - - --
0 8 8 8 8 8 8
! 0 8 8 8 8 8 8 i g 4 s i
- s'
, w s < 3 ,s ? e 8 s 4 i < m = 6 I
- ($000)
CURR MONTH YR-TO-DATE TOTAL-TO-DATE YR END FCST BUDGET $43 S277 $1,381 $550 ACTUALIFCST $13 $89 $981 S550 VARIANCE ($29) ($188) ($400) 50 Significant contributors to the Year-To-Date budget underrun:
- Project support efforts are below the level estimated for the 1996 budget due pnmarily to the hold placed on the OSG Storage Facility (Mausoleum) and the elimination of the Main Steam Trestle PCM from the 1996 outage scope. The Mau"8eum will remain on hold until the OSG on-site storage vs. disposal alternative is decided upon. The Main Steam Trestle PCM has been deferred until the SGRO.
r uccasc:owoncocram.#r<cwx nw rw om m an
m . .. . . .
...... ....... ST. LUCIE SGRP - SGRO: 2/98 Morrison Knudsen
- n. ~'...
- ";;;
- :,
.,, : y:: .. .. ...
nn .
--> PAE - 0 U T A G E <--
n .
09/01 04/01 07/03 10/01 01/05 04/01 e 07/01 10/01 97 97 97 98 98 9 96 So 97 12 00 A 12: 00 A 12 00A 92 00A 12- 00A I 13 3 DIP [!N [DE UNil EW 12 00A 12:004 12 OO A 9 M 91E Sol PHE- Olli LGE PG 2 -IM PifASE 2 - ENGRG ird CDIRIE !Elt!ttllE NAtM N RA ll/IT5 81 W W = =
theell . . . . .. . .
!)4 titrlIII RTE 16 8 luml4 ftAIN RIl4 12/2W 118F e i DPs TE) 4CKill/W9tl IMICI R M B2AIN 98 IIA 11/351l} W e ~ ~~
= i
- =
11B RClllClilm E DES 11AWIt RA 10/2551IlW IN EQtWit ,
in Efliefna!! ngG3N5 - 11/tsN N ma t#W 31W e 1 >
EM ' "~ " ' ' ' "
7175 [G 9PP51ll419 it $14 14/ttN 18 N4 11/11511 IIP It ~ 'n " ' " ' "' '
r a f1lt IP ECxitItila MM N W4 M57 tillP MB ' '
FEF MMi9mlIE PEumN 95/12N N 84 96/21/110 W W =
s i
il!I (EMIRIrG B METE 15/1W NIN 8254lE Htr IEI SMEI '
TE9 MFtE/10pil/IPMWE F5 MN tt104 I?/2W 118F W '
ElDIE RIURN5 . .
TIP (M RIDHEWI 9PPBf MN N N4 11/3/3 Illt 54 ,.. . . . . . ... . .
MM NIn 11/3N HIr B i '
~ "
F112 0 4 mEIIPMME5I9 RIM ' "
.. '. = =
1114 F RCKill4119 E/20N N 184 H/21N N 904 918 '.
=
1116 e Etilu/IPMetE5 IIA IPs 81/2tN N 84 11A151 BIIP IS ... . . . . .=.. ..... . .. . . .. .
te o
TD [ Emit 15 SDE SIE 11/IIM st sa 11/215 Hte ESIIINI8 ........... ............. . . .
MG 2 -llEEIE PHASE 2 - LICENSIFC tit E5fi;n 84515 EDERI 84/15N N BA 15/3 N 81le N
___m Cxitiatiz -
in a utwittitia ata M W ui 12/357 H er se .,
ire 9 M tP06ft -If EE 1143N N NA II/23/B IIIe IN ,
stoneture.
LEDENO t I-en an a Sor'ted by C3. C2 pc.,
A .wsteetone Ap r= w *
- 3 ,
2 l
a w -
..; - -
- a c . .
eJ -
m 4 .
- - . . e t = : : . . * : e o o S . .
- c u
c ;8-o N :
a er e I c , -
c !
o . .
0, l
.M .
.
- a ..
t L
o 8 a .> !
o %
e s l 2 g8$
- n - -
- : : - t a .c j
il; il , .
- n. ..'
- l4 I . '4 o E I" ::
- N .
e ~m - .
- iu . . :
a g 8 . .
Nn N oa j l , ,
l . ... .
V - o CD R .
(7) uj oan k. w - - - .
N : . .
- q - -
(1) O . ..: : : : * *
- b . .
N e
u ,
.cr g g . .
- s : . .
- l y - -
C O 3~N oe- ..,
. : . ei o
CH e g '
- x LD o w -
- :- i : : : .
o wa 4 g *
- u - .
g g i
a :-
e.
~
O I s tu c- . . .
t o g N. t,o a. .
o
-c - D 1 l
{
l O! .
c e m Ui - - -
O U 4 b w . . .
CD E sg 8 rn . .
E ~eN :
z n
p.i oe- t w w H A a ,
(J l D '
R 8 g B E
- 3 m 5 -
8 E M5 i N E R M 8 M 8 8 J i k k k k E k k k k k k' k fs k k k k k R k
= = = = = - = = = ='= = = = = = = =
p a a a a Pa g E E E E a E m
E e
~' a -
= a C D E E E E E E m a
G c e s = s e s =
= s = ii: = = = d = u.~s '
i E E E E E E E E E E E E E E E E E E
- m z a m z s am e u zz El'E a s s e s m z e E es -
sa ama a E- e m -s -
a a ig g i i g s_
3 5_ m_ s. c. $ E_i i s_ s._ s_
e e l e e . .
- S , - o g e
- 5 * - c-m g - -w- E' = E - e
.I
- .E e e n o. .o. s t
u
- * ~e _
W I#. E b h d a W * *
$ s' y N C5+
se $$ " E =
.E
- 5 B g ag i- 2 : a 5 s m w g w .
r E. E. . = 1.". :.
.....
- E -Eh 8 5 't E O'. h B m G =g se:
=
EIL i s' 4 $.1. . . .
E- ea , a 3 9 m m g m ta g
D $ N 5 n E 8 *
=
a h '8
- . f h. a h'
- a. ~
=s w- a m
as
=r _. --
e gg =a
- - = u. =_ a
- - f,
- ;;.,, e
...c.. g :-
$ g = f*
48 C S Nt C*
$' . O
=
g g g@ g C e $. @ = $ W: ~
uC1
= = = = s e s i .I.7.A o E -
R ~ ~ - ~ ~ .
w....
~ . - - -.. .-
ST. LUCIE SGAP - SGAO: 2/98 Morrison Knudsen
--> PRE - 0 U T A G E <--
37 - ..":::::~ " *" .
07/05 10/01 09/01 04/01 07/01 to/ot og/ot o4/o t gg e
g 97 97 97 ge 96 36 97 t?.00A 92 00A 12 OOA l?. 00A 12 OOA I (Tanit Eles 12 OO A 92 OO A t?.00A D EDIPflu EBalt Y3 R UlifG -lentsatt SCR PRE-OUT4GE - Con !inued PG 2. NEMitni . tant vet PHASE 2 - PROCUREM?NT - Con tinued S .. . 0..... ..... .. .. ..
led Mt f EMef it$1!E MIsli 12AIN N II4 12AW I19EP .. . . . .
C 3 Fr4 9stputti E MIiMMut il 12/EN Mitt 91/1613 IIIIP El Sli! MWEi . .. .. .
e . .. .. . ..
. .A. A.
12/lW Niet 12/12N t10lr . .. .
14 5 fil II SIP EDIl lEP ... .
it'I Ill il 9fP Fillt tilRiflE 12/22N N m I?/lW11W W IMP . .... ......... .......... .
r1 Kilf11115 FPL ACTIVITIES r
12/5N ItIll 14/22N.tllIP W 1
'I' 114? FR Itf!!B t IPPIIDIE aA Fi "
$4/14N Nilt 14/115 811F W 71 lRII MYlE 3 Bf .. . . . . ... ...
Fra RA ps/Iri (E ltVIIII 84/ZIN N N IIAW119F El aRutM E "A E iR II Pef 1E le Inf $4/EN ItIIe li/E N tilet cirnria Esa mim . . . .. .
W
.d..
48 6 4tene 41116 1 ktess Irse 11AIN NIIe IE/EN IIIF It (turd NI3 ' =
??M IR I87'ef1E E N 5ffilE MAIN NIBA II/3NillIP B "E'
Rm TO 5i "
flaw NIIt IIDIN 911# E 1210 fR It ESI3til SHI . ..
siminn u sin . . . . . . . ..
..A..
12 4 IPL 19 Pef!E 519 Dif 12NN It st 12AIN 119F 5
.J.... . . .
miinfla re 5N . . ..
.d...
12 6 fpt II pitflE El E Ilf IIN!B StIli llAl/W llIF E 91gnatueee LE OfP.O pc . p .
Q .pl.nned Sorted Dy C3. CP A . usa.. ton.
ame-creeerni A rn e w -
ST. LUCIE SGAP - SGAO: 2/98
- "'... :";", ; ,.. .. ... Norrison Knudsen nn - .. n'::'- - "
--> PAE O U T A G E <--
04/03 I I')7/Ot 10/01 0:/01 04/0t 107/0s 10/03 08/03 e ga ge g 96 s 97 97 97 g7
$? 00& 17 00A IF 00A I? OOA SP OOA f C E331 Pile N!! UME EM t ?. 00 A 12 00A t ?. 00 A 53 M ETE - Cetsonet SoR P M-OUiAGE - Con t inoted ts % 5!se Igittlf NEW SG ST ) RAGE FAC iLITY IN C3 ael IECI III SA 11W STWK 84/3N It 54 IWN 911F iEttlif. IF 18 05EI ' '
N bE"I' ki ii'IIY" "'
El 5 515E fKillif db "kG' S'T 88t5 Ole 55 lirtesim If IPL - RN5 It114 81/1/5 IlIIP W d 9ert er 9tp . ... ... .... . .. .. .. . .
i saa 57 9E 9911!45 8 sit MTB5 It m fl4W IlIIP M P4rA .... . .. . . ... ... . .
443 [ECT 55 STRIE TEltllf - IIMM ItIK 35415131F M ' s EI3P8 M IE ... ......... .... . .
Pl!311NE PLANT ISL AND O 1401 aseitimal fitts wiles I4At 5 It114 lanW 11stP 19 . . . . . . .. 3..... . . . . . . .. . . .... .. .
CE MP 1W WIIII 5 94/lW ItIII 84/MN Iltr 9 . .. ... .. .... . .. . .... 0..... . .. . . . . .. . . ... . ... ,
C3 IIC Eit SIP EIRL WIL 64!3N It 34 854 W 11 W 18 BWUl!CES t [85GENIS . . . . .. . .... .. .
o [
CQ MPat SM R9h814 El 41 154W It104 954 W 91IF 3 I
9 17 I5 . . .d . . . l' 1291 4e 5 flu EithfB5 EllWEl f5hlN N 804 15/19N I?II4 I8 M . .. .
S O 431 C.060/5 fait Es 5fts 95/UN N III 35fMN 11 IIP EERif55 , ,,, ,,, , , , , , , ,, , ,
' =
4IM Setup WEIGtE E W F E44N N 94 II/MNlisF S ha ,, ,, ,,, , , , , , ,,, ,,,, , , ,, ,
' =
a7E 151att !!F fi[CI NES IIAW ItIIA IWN 819F B Ol!!Sif .. . .
8!M M cl'IE 9FFBI II/IIN It 106 01/21/3Iltr B .. ... . .. . ... . .. . .. ... . . . .= . . .. ... . .
a?e Dall IEini4 - h Arts itAW 9t III I?/NEiltr WI . . . . .. . .. .. .. .... .. ...=..... .. . .... ... .
CD C't [ECT flRE ETE 1 M 11AW It 114 11/21N IIIF IS i
tF5 stan tur..
L E GENO ta -en aa.e Sor'ted Dy C3. C2 e,. . a .
A .usn..t. .
a.m._,-... .i & re e. w =
.s w e - ,
C :*
- 48 : : *l c . .
1m - : : -
- : : : e 3 o . .
. e c
x >3u c
3 e
c : . . . .
- o O *
- . . . . C m . . : : : : -
o a
L -
e c o 8 - - - - - -
..a .>
j D N !
~
- n n;O e o o8 .
.m
-l l Il. L a A "
- :: Q::;:; U ;bJ o 3 . .
e ~,u-
- i: -
- : i g g : : . .
N N EW . .
i oe- .
t .
- i. -
V -
- g c) er. . .
CD LtJ o, no-N . . . . ...
nj w .
- t t . . . ..
- t 0 N
.. < a 8 m n u
O 3*N ea- 5 .E 3 9 -.
C C
y O
o o : : : x ma O O . .
- .- c
- i i -
- i . : e O R I W o t -
l t e8-N.
- e. z.
t e
l "'J . . .
E o D .
0 W < i w WG g g :t
, a k N e d : : ' '
w _o $ - e 2 - -
H A M . . . i .
y - -
= 1
, . . . . E . E . . E E I . . . . . . . . . . . .
G H i i i s i l i- i i l i i
~ w = =
- . a = a .- ~ _
5 E E E E E E E E E E E
- a a u m a s z u m u n s
. 5 E E E E E E E E E E E 5 E
=
E
=
E
E E E EE E a u m a a
'2 E a m c-
- m S
- = W - , :
- E E E " -s u
. .s .s .
- 1 s em B 5- a a
.i~h a m 3 -
e w . ,. e, ' " *'
] = a ;
- E is a; =
- 33. & '
. E - ] E=
- . nm
- g- w - -
g s ==
e
--oe
. U. E g
5 5 N w Es 5= E s I- E E 5 5 s E 8j "ITT B 5 -g
- . 3 8 e -
a y y ga lu _
i s sa m a t e= -p ri g -n w g-
- s. .;. !. . . .
y
=
.s !}l9 e
f a ea 2 % @ h h
i Sl'. LUCLE UNITNO.1 STEAM GENERA TOR REPLA CEMENT PROJECT j
ENGINEEldNG/ DESIGN PA CKA GE del'ELOPAIENT STA TUS JUNE 1996 4
j EP/DP REVISION O ISSUED FOR FPL REVIEW n 56 20 l -
60 f
10 CUMULAllVE PLANNED
- b6 . ** *s l CUMULATIVE ACTUAL = 56 ,
i 16 ,
50 7
i
- 14 '
- g l $ 12 ; 7 40 o g / , , E i
a 10 ,
um /.'
,,,, l 30 gs 9
& B j
! 5 4 . D i s 6h Q20g I
I 4{ A
=
}
2'
[
+ 10
, O -
-- E !
.O 9/93 11/93 1/04 3/94 5/94 7/94 9/94 11/94 1/95 3/95 5/95 7.'95 i
?
EP/DP REVISION O APPROVED BY FPL SGR TEAM n 56 20 -
60 I ....... .
18 +l--CUMULAllVE PLANNED = 56 ,.' . -l 16 CUMULATIVE ACTUAL = SS 4 50
$12 f M T
' 40hs ad .* I NOTE: THE ONE HEMAINING HEV O APPROVAL IS $
I10 l , - ,...'
FOR THE OSG STO. FACitlTY WHICH IS ON 30 C 9
68 i
HOLD. i 5 l 3 '
I ~
20bU 6,
i -
{
43 _ _
l j -
T 10 p __ _ ._._..- _ . . - - _
OA "-
O h i g-7-n khk m hkbe
,o ~ m kkkk e c ; y-n k m , o e
. k~e e 9
- k kk g-n m ,e e LEGE ND PL ANNID ACTUAL CURRENT MONTH L. ._ . !
CUMut A fiVf * * ***
F:' USERS BCOWDRf T.WDIC W thG ttC1 ENG LIC1,XLW het Date FIS 90 W JC
i f
ST LUCLE UNITNO.1 STEAM GENERA TOR REPLA CEMENT PROJECT CONSTRUCTION H'ORK PA CKAGE DEWLOPMENTSTA TUS JUNE 1996 ll 1
i CWP'S ISSUED TO FPL FOR APPROVAL i
4 n =89 4
25 ; 300 l i !
CUMULATIVE PLANNED = 89 20 CUMULATIVE ACTUAL = 89 ~ 80 3
' l T 70 15 $
.* l oo 5 a
o .
ti 50 5o 10 ,- 40
. 1 20 5 _ "._. 20 I
- O -
en -- - - . - E. r- E . --- 4 --+ E i' o d '94 6/5:4 8/04 10'94 12/94 2/95 4/95 6/95 8/95 10/95 12/95 2/96 k
i l
1 l CWP'S APPROVED BY FPL SGRP TEAM a
n= 89
, 25 -
4 I
j CUMULATIVE PLANNED = 89 l100
.....-........ . . 4 90 i CUMULATIVE ACTUAL = 87 l l
\ '* T~ :;f \"
J l NOTE: THE TWO REMAINING CWP's ARE THE , j 70
$ OSG STO. FACILITY (ON HOLD) AND PAINTING ," I w
i, 15 -~ INSIDE THE RCB.
- 60 2-
. 1 10 ' , ,
40 j l k
10 ,
o i 0 k '. 4 -
_. E !
o E5EEIEEEI.$$$$$$$E$$$6$$$$@E v e c N m m o ; N - N m v c c N m e o - N - N m e e e LE GE ND PL ANNED ACTUAL CURRENT MONTH L _ _,___J M CUM UL ATivE Ff USERS BCOWDREYINDIC WK CWP1 CWP1.RLW Print Does 7'18 96 WJC
c ; , I i [ I' ,iL e .
E
- T E
I P _
N O S mWC E Lt
- S P. 4 T D Yv _
D E E t .
C 4 E E 01N C(
FI T D E E. 4C uD TI OC DL )OEN MM E
E DL E . GC L A
E L I
T E
D L
iD EILE NED YYAA T
t U Ht T E E
t E P B L
P E E
D T -e - C WDPD TSST R
F L E N.
O W L D
f F S U O D M T E
W Nm H OC vF C S EML fF OO E
" T S N D L O L AS L tiA D L E ')l CW T A VO C
E D E M I N C E C
L P L HG L tE TT E O C M D E
Z L O C
N A N N E .D M
E H Do M EM .D T l?WGR DD NA Pt D
M O E L Z O E f tO N DE O
I E'_T L E
C C S.
hi AD S rN F T A
%D OS'B NGD FT DD M O
D E
D T L C Y E
-W _
N.
N O i A T9T AL F T
A L
2ti 2F W S T
C E
S S u Cf t E
>t D A E
TNDA EF eA L
ETt W%
C
% L T S E C E C A L L 0M L R E H E O
E t
L P I Y T t R T E F O FN L*
T A 1 O
L E O 3T TNe PS TO mt T D O L
TMMS DT D
P UAETEA I
" W A M P L A. i C t TLA %' S FC H P -
CT T )
AR T E *1 F E F 3 SC t
N N S N N r% EO Y B L HT. OE E O T8 S M N M R M fu I
N I OT O L E T T D' . DALC HP H S O A L C H O ES E P
~
E N
I C S - ACER R R KR Cm A S L
0 I F
T P
L A D L
H T
D A D HC 1 ND EfL I
O R
E P E N
E P C"h T EZ L
E T ALT Zi ME M A
A A T
O L
E W L
E A 8E T JE H OWW C 9 I HO Su F
F'T eC P EMJ[v ;S I Na TL TuN 1 E U L 1 S C P M I E W F' WM 'e l TW S LA C N I TC I T NN Oi IIAC RA PB R
F R
- E -
\
- M . '
1 1
l ,
. E T h
-E g E T
gE _
S S
.r ~ E U
. a }
L T
r P _
A M [
T S I - . ' .
g E g O C gE N
I I O
O. A T hh g.
- N gta =E NC 9 $tl l
- Rs
- 4 e t
tl ] j Qq{ t d
kg wh A
hg TI I R 69
,Q y yckkgho NB 9 UAF I E E IR N CO U UT LA J
- R rE TE N t
i SN M. .
O N E .
- P *O N T D DE Y1 E D . C E O ED E F .
N CC E
D T D E LE D W D. L P D I T D OD OE L VY G
L E IL E L E T A L E t Ht L Da M F N E. D I
4A T E P U L .
T E O WDPE TT E N E E B F E DE MD SS W Nw W WH C E
S Y %
AS L OC E L T P R O
- D V SDO L O0 E M A MO C
T E
L P
D E
S E
L W
O O
N A
O C L E
C C
E L
P U HS L
L MG Du L
4S.
iA BM D
L E
E l.
LECW ZWG E
T1 3D T
E A O C T M D 2 7
C D N .
N O
W E D D NL EN
.D W 2 OSMB N R A EE 1D PL M
E E T t
D O T O M E OE I
L C AD W T A D NGE -lL O D C m T
2E EL 0 Su C f A 4DTA TtT A S EE C T C L W I E
LT H. E 2PL T. O H rC i Tl D V Y !
S E C E C A A L L. O T 9 F ERi A. E WW Y
E O *D DN O 1 T ~ L ;
NM t
R Y S
L E. t E A E H.
I I F O
S N
LLP AM A
T O t
C TMc*E DT R
~ Y A M t P W L
P E
Pt I TO S EC E
1 C T
E E
S M N M E
R M G N S SC N N OT S N L. E N . - rW mE ODCA HP 4'v C
" N P O A O D O I L
A IG CH O N!.BP P A C M C N C M D I T
i : E : fU f O R W SF. Tu S HS2 E T E H
R f
N GN U C A C E F. F F P KM C L AS E
" L D H D A D H R ND I
O E E E S ALE A A
EPL2O 0 F P T L T L C E 1 R W) N F CM rM si E El E '
ME M A A O :L W A T 9LE 9 a s P eO E T S 1
1 S C E
P 9
M B W F'. 'W M N L TW H
S OM LA O
C N +TCC N.CC U T T uN T L
NNWE Jv N I
RA PB I
R I f II P
R.
l
\
J W
1 1
g 1 ,
E a E gB T \ . T S .
E f i L e r
- P e 1 e
M m.
g O
- v
[ m C gB e
e g
a-F e
M x g, m u
- s h q, ' kg a
9 fe5 E t3 I 4 en tgw
- y w k n 4 n e
,O , qck k}D8 e
u e
s
- - . - . = - .
- l. i FLORIDA POWER & LIGHT 222-7698 l
l l
\ . g. e -
_g l
- ~)'
l f
, i:
}, .
!?
k i
s I
9.T Q -
7p I .
l' ~
\
i N' . -
^"
A ~
' - _ _ ll q%
i ,\ .
l 1
i i
LAYOUT FOR DRILLING BASE SUPPORT - S/G 1 A May 1996 i
i i
u_ _ __
t l
- . 1 i l l l l.
l l
FLORIDA POWER & LIGHT l 222-7698 II .. _ -
j 4
l . 1 A I s.s -+
. s b
4 f Y
- _ g
[ j'
, / '
4 ll
~
I i
) 7..r7 ,?
7 4, . : ';
~
! lU '
l f%f$YAjdEJEAi ~
~
- T i .l.
,f ,f L
i ,
i <
l i
i 1
DRlLLING OF BASE SUPPORT - S/G 1 A 1
May 1996
m4,.A4.t.aeme. S m a ah . e m.m. hme.w.,.g.E he m h Jm4. M w;n r. mammM A m > As h,a mem aw- . m a.h a.p'w.w e m m mm.ms m su.Am rA--' e mwam sq.aS.m u AM ,L.,a.
. B 4
FLORIDA POWER & LIGHT
- 222-7698 l
l I
, I. I
~
... ese j
$ . :; q 7. .=r , , , ,
8i.- j, i I. ,
' Y 'nl .} 5 * ; .
M - -
m N
~~
.s ,
? g -
l y , ..
i j ,
~
,. =
gp ,
(.I , ,
7.M l *% ~ ,'..
~
~
Q. '4*
- ~ ~. .
u
- . . . . . l 1
I
,f i
SADDLES FOR HEAT EXCHANGER l MAY 1996 i
i l . .-- . _.. . . . .. . . _ _ . _
,i i ,
i i
i 1
l FLORIDA POWER & LIGHT I
222-7698 I
l
%. a ; -
.tN * '
4fg , -
g g. '. , ,
d E< 6,)/_
f) M I
l y .
e o 5 6
l s
W.
e - . f ..
y i
( ',
s _
- l. , ..
l , e
,g~ r \ .
,s %- .
7 ' s y- .
f' .W"J I i -
_ 'f j s- - ,,
- ,~_'*' i, --- f
- 'g
_' 2-
,.g 4 y ',agr'. W . s , .. .fTv-y - - --
.,k,4 c.<?, . ,,$ g,..: . -.
.A ' .';; ' b, 3;$, ,g .; - .' w .,,,- >
-Lgn_ n% , , .
a s u .i.:.n.re,r<... -
- - . : M;.nw ALW c
,\ w.w 3. %::....
g,n ~;_
m.' ,
~,.
-w n. . .. . v. ...
m s
_.y..'
. . n. n-. . . -
Ap, :.__..4_. ,.a, ,n - - . -v t.,<.
t' . .*- '
- w g' ( A ak'
'2 .* $
A '
l l
l l
t i
1 1
1 PRIMARY MANWAY MANIPULATOR i MAY 1996 4
-, ,_. - _ . _ . , _ _ . . _ . . . , _ _ . _ . ,,e .,
1 1
1 i
j FLORIDA POWER & LIGHT
, 222-7698 I
a l
l l
1 .
. y -
- p. '; i p p '
I '1
- ll ,s \
n
, ,1 ,
\
- j, glh' 's..
==
3a i
)
- .. m ammw I, fu- 4.-
l ;%f 'W~^
NT E,7 -$_
~'
~
e a dh
- '(\}.-j ', NN '
~
g.
}lg,,' - .
ff &- . ~'
m.
I . ,
, x. .
+/ , .
/
l
'hu -
. ,_$ w.. #,II1 1 .
- 4. ,,
I i ,g.i.s .- = . . g g, as .1 - ammerm*;x. * .------* -
.,w -
i t
i i
t i
1 i4 I ECT - S/G 1B
{
MAY 1996
=_ .a i
1 \
L. _- ,_ - _ , _ . . - . - . - _ . , . , - . .- 1
2 ,
! 1
!- l
! 1 i
i I
i l
FLORIDA POWER & LIGHT l
i 222-7698 '
! l 1
i i l l
l t
I l
1 i
i i
l f
i l
F/W HEADER & GOOSENECK - S/G 1 A MT. VERNON, IN D.
MAY 1996
l 1
< l l
I i
! 1 1
i FLORIDA POWER & LIGHT 222-7698 L
l i
P l
i l
i l
l t
t '
I , .. .
I T.?: _ p n +m n ' '
- ,;, - < j' - ,
.,4 v: [E,_, ,e- ' ^*J
. g
' . - v'q. .v' v f,' Lk. :c .g r. v.. c, ,;',, ,'r
- '.5- / ,, _
,.,,s. -~y4
,... +y . s'
,n t
. f. *-
'y.* 'gx* >, x' '
,y, t ,y.;y.. '
l ~
' n' :._ . _f ks' .
I I
- 1.. d.
'. '.1./ --
_ . _ _ _ t' . . _ .
l - . . ,
l } \
c
' .- . 4 l -
.. a. l l \ .
- .t ; . .
1 f
%, -e c-- g ;
- - . g[.u . .
t .. i. .
Wj%k j F2-ttl
. !;g . .
..- e
.., po. ',,-
i .(. '
+ .
I 'h g, .
l I
l
~
l i
1, i
i l
i INSIDE STEAM DRUM - S/G 1 A i MT. VERNON, IND.
5 1 MAY 1996 "
- l. -- . . - ._ .. .--- _ - - - .- ... . _ . -- -- . - -
A < m m a -. m..a we .4w d us eu aae .a.w.e a te Aw .e4mae.4-- 4. a, w a4 % a= 44 m. -a-m4*m-,n.
- w s 4- m a m m-- ---e.s.--4u-au.-mu%-se-m.=e.---+es--ame4----wmas l
I FLORIDA POWER & LIGHT I 222-7698
- I i
i t
I i
k 7-.
p.. .,,
( ,, ,
.w. : , , .
..,a, . .
/j lI 8 b
- S'M ~af:4' i
' ~
i b'kh6 .t : [,k., . . . . 'I f k.%
- , ; . - = : . 4. 1 ;. . k" N? W -
- )' }.u R
.n : luj. l f j. n.; {'j.<,_, , c
.. e. t.y 9
, .Y a'K, s,. . , '
W.- j ,..44 /
e
- -/
,., ,.4.<=
^y's
- 2
, y ~. , ,
)
Vf: k 3 -'s ..
{ I .. g, ,,. ;-_ y- '
, q f. / -
l 3: --
g -
x
-s
.9 ',)
/ /'4 Y
l' _ Q,,
j ' 0. g
'3.
? \
/
4 7 '
- f'*. .~
i
~. 4 . ,
c // +- .b l : "L,
_.:.f = KL:.~.7C g'y ~p la % .,*(' ,
.p' ,[
sum. ,[ M.l; / rc.-
i , -.
i e
f j INSIDE STEAM DRUM - S/G 1 A l MT. VERNON, IND.
j MAY 1996
4 ..
I i .
i i
1 l
l' FLORIDA POWER & LIGHT l
- 222-7698
\
1 l
1 .
I 1
l l l l 1
i
! l
, I 4
l s
- c gapseese *v pseen s*=* p- em. q,
-* =ggstv.* , >sP*"t ?. **
gy *M l __ , ,4 , - . - - , ,g
!; ','.* ' . ** L, 4 ..','y j M M 4)';if ,V'*h <r ^( * * *
. e- Y. i4 M. *-M../. P/ M!-TMed 2
- .:Q' QQ'* d *'yl,r.[3*
t Mp( . .
-gr -
f, 9]{',-Q,, ,,,
. 7. ,
- d;*%, = , , ;,?t'.';k,';WkW lYy *,y,&,{t:[,l.fy% 1. Al h h'i i:27. sf : . %=
- . 3; @...$ u s. <
c w.g;,4.+,
..,j' y>.
v u* n. ;,,, :.; .' . . ., .3,s?=f,tc.Q,,,
- ,g , , ,, a .y4.; 4, c,g; . :. , - - .
- g. :; * -;-;
. .-<e - >n.,,,. Jr ., ...a.;. , ; y S ':- ,*,* m , .r,. , ..r.
..',e.,,,
.+-
7* -
, ,,.,yA *' e / . .'y ;-.'t. , ! ,
. g <,y f -',,,,
,J7 -
- V. . a;*.
, ,(,4z:.
_*i *
',, .. . % . * * , ?
i i ,,
. - , .~, .
.h t : 4' l s -
. '+ - ,.4 g
e .
l i
4,t g _). i l
g gag i
a 3
~ ~-
~
1 % a i
4 1 _..n.,'*.
)>
I ,
q
~~
kI t..
4,.',
.' '# ^ '
/ 3 -. , .,, , , _
l i
i F
t 6
i i
l I
}
TRANSALTA RAll CAR
[
MAY 1996 i
.1 l
1
i
- I i
{'
B l FLORIDA POWER & LIGHT 222-7698 l
I i
1 l
1 i
t.
_' .~ _.-
g .
. 16 i ..
s.
?
s '
...... ~.
X4 n
. .~.
-Ns i
i b
i LOADING OF S/G 1 A ON RAILCAR 3
May 1996 i
i a
! l i*:
i 1*
FLORIDA POWER & LIGHT 222-7698 l
l
= -
a 4 I o
! Of.
. . . s.. . . ,r;, , . .;
$ )1 ' . ?i ..t ,*,
,. .. 'l> 7 , .44 n
8 e. .
g
. ep..
1 8 1 7p.
< y , .' '.. . .y+/..
l g' " s
{E. _
s k . :: -
... \
.6 a
g 1 . <:
" Ast f , . - {$.h '
2 .
< ? , ,.g * %
l .
+;:s
! ?
l . ~.
l l
l
_t ' . . .
l l
1 1
l LOADING OF S/G 1 A ON RAILCAR May 1996 2 .- -
i l'
l l
l FLORIDA POWER & LIGHT 222-7698 l
! l l
l
- 6. A f< , - [,'
~
- [
l b b - (T
[T fNI t]
I
' N,44
- b.
l l
! r
// '
(: s
- 1
~
f' 4
I y.
1
_ _...q g y ^ -
1 j
1 1 ,
i j RAll TRANSPORT OF S/G 1 A l Cambridge to Toronto l
June 1996 j
t i
i va 1
- FLORIDA POWER & LIGHT l
4 222-7698 4
d i
i i
l l
, ..m. %
3 . g*
. *W
. - r.:
T* g e x-f ', 4. 'a .i{ ,: $4; ( ..* ,- ,
, ' ' jff' [y ,
/# .' ,
f-_ D'; ,4 ' f5 $ $ .Eff YN .
p.~ y .
o g . . .%m, g -
'. 3 ?%$ ' '{ fh. . . 4,kk.;.
, *~ ,l Q j '
e' -'
% Y 4 g h, a. :- i~.4 e. W
< 34 f -#
l .
, i q f, -
- . ms -
15 s -- . _
f ur .
'p (,S '
g-G"? j ..' ,i * ', I. a 1 y(
- j. ~
ll j .,i 4g -
ll
~
l .. .
4 kb ~
$ 2 . 3 7 ..
% ( ~- _
j.l4.g_. 1" l. ,..' _
- --3 . _ '
sm
- . ~ ~ . . - . . _ --
- .
t M-. . ,. t _" .
j i
i i
i 1,
]
i
- ! RAll TRANSPORT OF S/G 1 A Cambridge to Toronto i June 1996
b' I
FLORIDA POWER & LIGHT 222-7698 1
l I
I 1
is i
i l
l l
I l
l l
RAll TRANSPORT OF S/G 1 A Cambridge to Toronto
, June 1996 I
- , , - , . - - - - - , - - - - - - - - , - - - - - - - - - - , - - - - - - - , , - - - - - - - - - - - - - - ------,,----,,----------,-,---,n --,- - - - --, - .-- - - - - - - ----
i4 -
O STEAM _G.ENERATOR __ _
l REPLACEMENT PROJECT l SEPTEMBER REPORT i
i I
b.
l I
i
--J, ~~~ m . _ _ _ _ _ ,
l ,g.3,
- .n -
j Offloading in Mt. Vernon Report Contents:
Project Pre-Outage Milestone Schedule Page 1 Executive Summary Page 1 B&W(S/G Construction) Status Page 2 SGT (Installation Contractor) Status Page 2 Engineering Status Page 2 Quality Assurance /C,ontrol Status Page 3 Plant Construction Status Page 3 Operations / Support Status Page 4 Health Physics Status Page 4 Project Controls Status Page 5 O&M Budget Performance Page 6
)
Capital Budget Performance Page 7 ,4 1
/
4 emoc?t.
s7LucOetone k -
maca a.,a .
i SF gy,4NOV_DEC,..LAN_ ,FEB , MAR, APR_ .MAY_.
.r JuL '#UO ~ SC -,0CTINO '
lOENTIFY SGRO CRITICAL PATH 30SEP98 APPROW SGRO CRITICAL PA
_.4' _ [ ;
170 ctg 8 AMENO SGR CONTRACT 01NCMG 01NOV f' COMF1RM UCENSING DOC's 130ECet .
jyC IDENTIFY PLANT OLTTAGE SCOPE 130EC06 1YO AWARD OSC DISPOSAL CONTRACT 310ECes 3yC l COMPLETE RELOCAT NORTH 31JAN07 I'hAN DEVELOP LAYDOWN PLAN 01PE897 0 ES CONDUCT 2nf PARTY REA04NE 01 7 0 ES DEVELOP HP PLAN 0$FE807 05PE8 y)
SELECT CPECl 15FE897 RECONCILE EP/DP/WP 21FEB97 2 EB l' j
DEVELOP HP PLAN 01 MAR 97 ' 0 l
, l DEVELOP CRANE PLAN 14 MAR 97 $ Id "
COMPLETE INITIAL MOBILIZATION OF 31gARg7 31 MAR '
SGT (MK / DESf) V DETERMINE UNIT 2 OUTAGE IMPACT 01APR97 01 APR l 1
ICENTIFY NON SGRP PROJECT 01APR97 INTERFERENCES I I CyR i
RESOLVE NON SGRP PROJECT 30MAyg7 30MAY INTERFERENCES Y !.
RECEIVE NEW SCs 02JUN97 f' 02 START CRAFT MOBILIZATION 01JUL97 Op APPROVE ALL WORK DOCUMENTS 20AUG97 20A VERIFY PARTS, PAPER 20Apog7 20^
STMtT CRANE OUTSIDE CONSTRUCTION 20AUG97 2 START SCRO 200CT97
_ Tf j Executive Summary Considerable progress has been made in areas of project staffing and identification of schedule needs, An inillal meeting was held formally with the Plant Staff to inform them of project status, Nuclear Olvision decisions were made on severalimportant issues.
- Immediate disposal of the original S/Gs was approved.
- The QAlQC scope of the replacement project has been awarded to the implementation contractor.
- Approval was gained for an independent assessment of our licensing basis.
Our implementation contractor has begun the replacement of SIGs at the Point Beach Plant, and we are watching closely to gauge their readiness, their skills, and their ability to ir,tegrate lessons learned into the St Lucle project. '
Wo are dissapointed with the lack of aggrossivo scheduto improvement on Si. Lucle's outage sinco the contract was awarded, and with the real time participation in our outage managr .nt mootings. I have discussed both of these issues with Marty Cepkauskas, Presiden of SGT, and received assurances of expedient action by SGT.
My staff and I have determined that the existing contract needs renegotiation to bring terms, incentives, and scope up to date with current FPL performance standards. This effort is currently underway with support from the plant contracts organization. Our goal I is a contract amendment that more clearly defines our expectations for world class performance, while ensuring that FPL receives fair value for every dollar spent.
, Dick Sipos - Project Manager Docio 1 ;
o -
B & W Status:
1 Closure seam welding of the first replacement steam generator is in progress.
The facility in Mount Vernon is working 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day, 7 days / week on welding to i ensure the 6/1/97 delivery date to the site is met. I 1
Accomplishments: l
- The primary head mockup and archive samples were shipped to the site. '
Hardspets: J
- B&W has used some of their float. FPL is monitoring progress weekly to assure delivery schedule is met.
. m m m ... m .. m . m m .. m .. m m m m ... m m m m . m ...... m m .
SGT Status:
The Point Beach SG replacement outage began 10/5/96. A vast majority of the SGT project team which will perform the St. Lucie implementation is gaining invaluabla experience during this replacement.
l Accomplishments:
- A Construction Manager (Steve Mager) has been assigned full time to the PSL site.
- A commitment was made to provide a full time DES engineering person and a scheduler.
Hard spots:
- Mgmt Rep needed at PSL Unit 1 outage meetings.
- Aggressive schedule reduction expected.
m .. m . m m ......********** ..
- m ... *******...***... ....*.. **..*******
Engineering Status:
The focus of the Engineering Group is on the fabrication of the RSGs at Mount Vernon, Indiana, and various project support efforts such as technical review cf disposal bids and water depth surveys of Big Mud Creek.
Accomplishments:
- A contract for a third party review of the completed 50.59 evaluation was issued.
- A survey of Big Mud Creek depth confirmed that no dredging will be required to accommodate the barge carrying the replacement SGs.
- Technical bids for SG disposal were evaluated.
Hard spots:
- None at this time. -
Ron Gross o,nn n
4 Quality Assurance / Control Status:
QA/QC activities continue to focus primarily on the manufacture of the replacement steam generators. This focus requires routine visits to the manufacturing facility, as the shop is now working 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day, 7 days / week.
Overall progress continues to be good. The transfer of QC responsibilities from FPL to the implementation contractor has resulted in the Project Quality Plan needing revision. This revision is underway, with completion scheduled for November,1996. Quality records are now being received from B&W.
i Accomplishments: *
- Replacement S/G material archive samples have arrived at PSL. These samples have been receipt inspected and stored in the North Warehouse.
- Received QA records such as RT films, tubing CMTRs, and tubing PSI data.
These records are in the vault.
- All history docket information for the steam generators has been reviewed and is up to date.
- Point Beach was visited during their preparation phase for replacement.
Hard spots:
- FME during manufacture of the RSGs continues to he an area of concern.
u.u.u.
M #" Rick Weis Plant Construction Status:
The Construction Group acquired Fred Gigele from Maintenance. Activities center around gaining familiarity with the PCMs, Design Packages, Work Packages and project schedules. An observation trip to Point Beach to observe contractor controls and performance is underway at the time of this report. '
Accomplishments:
- Supported Outage Management with initial laydown area needs inside containment.
- Canvassed Plant department heads to identify projects that would impact polar crane, station air, service water, temporary power, or laydown areas that would represent a threat to SGR success.
Hardspots: ;
- MK does not have a proven track record with FPL to ascertain their ability j
'to deliver a quality work product within cost and schedule constraints. '
- PrelimineJy review of MK/DESI documents (PCMs, work packages) and the implemeniation schedule indicates that more work is required to ensure no problems are encountered in the completed work turnover process.
- MK does not yet have a Level 2 design schedule prepared for the heavy rigging contractor, Mammoet. The lack of this design schedule could impact our ability to effect an early start to Steam Generator Replacement.
- Although it is agreed that removal of the pressurizer missile shield from containment is needed, there is no owner for the missile shield once it is l removed from containment.
c.e2//w Fred Gigele Pann3 l
Operations / Support Status:
John Tepley has been assigned to manage the SGRP's Operations / Support group. This group's recent focus has been on the development of an action item tracking system for the SGRP. A support technician has been added to administer the input and output of the tracking system, as well as microfilm SGRP records in the QC vault. Action has been initiated to gain approval by the Plant of the post maintenance testing associated with the SGRP.
Accomplishments: j
- Action item tracking System developed and implemented.
- Departmental training guideline developed for SGRP personnel.
- Testing for SGRP work has been identified.
- A matrix of all SGRP documents has been developed.
Hard spots:
- The impact of QI 7-PR/PSL-1 on the SGRP has not been determined. Action has been initiated to review this Ol.
- Engineering Packages and Design Packages contain mode restrictions which appear to be overly conservative. A review is underway to identify areas for relaxation which will improve the schedule.
/
John Tepley u u u = u ,,,,,,,,,, u u u = = = = u u u ,, ,,,,,
= . a u u n,,,,,,,,~,,,,u Health Physics Status:
Development of the Radiation Protection Plan was initiated. A prcblem with the SG replacement Manrem Goal was identified. The original target was niet at 370 Manrem based on previous changeouts. More recent SG changeouts tell us that we can accomplish our task with a budget of approximately 200 Manrem.
Manhour estimates for each activity are needed from MK before a final, legitimate target can be set.
Accomplishments:
- Developed outline of Health Physics responsibilities / activities / concerns regarding the project.
Hard spots:
- HP issues with original steam generator disposal
- Coatings
- Filling SIG with other radwaste
- Removal of water from inside SIG
- RCS Pipe End Decon (cost ver sus Manrem saving)
- Manrem estimates and incentives
- Radwaste minimization initiatives Ken Payne Y Pace 4
Project Controls Status:
Level 2 schedule development is underway for each project discipline. Daily interface meetings with Plant outage management are held to review progress l on the Unit 1 refueling outage schedule. All existing pre-outage schedules are being converted from Primavera to a Schedule Publisher format to be consistent with Plant software.
Accomplishments:
- The project cashflow (as been adjusted to accommodate a projected 10/20/96 start date.
- MK has been formally notified of our intent to replace the S/Gs in fall of 1997.
- Level 1 schedule for pre-outage work has been developed.
Hardspots: I'
- Decision on original SIG disposal requires contract amendment and i
submittal of additional budget item ($12 million)
- Contract amendment needed to acknowledge incorporation of QA/QC scope with MK, North Service Building use for workforce, and to tie deliverables to payments more closely.
- Need input from MK on selection of subcontractors and parts delivery dates.
- Need to establish a project readiness date.
- A more aggressive critical path schedule for MK activities is needed. This will occur in early October.
Chris Burton C#8 Page 5
l i
~
SEPTEMBER 1996 80,000 -
600,000 j llElHIM BUDGET - MONTH ,o 550,000 1 =
' ACTUAL - MONTH "
- * - BUDGET - CUM ,a 500,000
, ""C-- ACTUAL - CUM ,
e l
60,000 ,' 450,000
, 400,000 h ," -
350,000 .h 40,000 ' - - -
i 300,000 l N b l e 250,000 o 200,000 l l 20,000 -
150,000 0-
! $ h $ h h E $ h h h h h i
,s e = a s s
' e e u a e a 2 < 2 ' < " O 2 0 (5000) l f CURR MONTH l YR TO.DATE TOTAL-TO-DATE L YR END FCST BUDGET $57 $422 $1,526 5550 '
ACTIFCST $3 $105 $997 $550 ACT/FCST VAR ($54) ($317) ($528) $0 1
Year-To-Date Variance ($316,695) t' Significant contributors to tb.!s vonance:
d
- Project support efforts are below the level estimated for the 1996 budget due i partially to the elimination of the CmG Storage Facility (Mausoleum) and the deferral of the Main Steam Tretta PCM until the replacement outage, i
1 w uos.=ar= = =-m w Page 6
'd
I
- ST. LUCIE UNIT NO.1
- SGRP BUDGET STATUS - CAPITAL DOLLARS SEPTEMBER 1996 7,500,000 22,500,000 7,000,000 l
20,500,000 6,500,000 MBUDGET MONTH 9 6,000,000 18,500,000
= ACTUAL MONTH '
1
-*Y 8UDGET CUM ,'
5,500,000
+ ACTUAL CUM -
16,500,000 5,000,000 '
14,500,000 o
j 4,500,000 1 6
- I ,
12,500,000 I j 4,000,000 ,
e j
- 3,500.000 - - - - - -
o' - 10,500,000 j E
h '
4
$ 3,000,000 N -
8,500,000 3
g
, 2,500,000 p' 4 2,000,000 2 -
,e 1,500,000 , d' -
- 4,500,000 g
e 2 1,000,000 *' -*- -
e o - - P g 3
I a - >
( o g o
-500,000 -t ,500,000 t
($000)
CURR MONTH YR.TO DATE TOTAL TO-DATE YR-END FCST BUDGET $718 $11.068 $72,309 $18,881 A_CTIFCST $81 $4,252 $63,771 $10,160 a ACT/FCST VAR ($637) (56,817) (58,539) (58,721)
Year-To-Date Variance ($6,815,815)
Significant contributors to this vanance:
- SGT- Revised payment schedute to reflect the SGRO schedule change. 51 071.200)
- SGT - Deferred Blowdown Une analysis. ,sioo coo)
- BW1 Delayed corrpletion of First Steam Generator Closing Seam weld. 52.436 ees)
- BW1 Negotiated the elimination of extra costs related to Barge Transportation. (5252,750)
- QA/QC Deferred contrador support due partia!!y to eliminating the OSG-SF and defemng the Main Steam Trestle Mod. activity until the replacement outage. rs47s 277)
TOTAL explained vanances.
(se.saa.eet) w wootsecoo rwirpoa remancarosame nw Page 7
' ~
4
{ ,
4
!>~
j - - --
REPLACEMENT PROJECT OCTOBER REPORT i
i i
l l
J. l
~
i
.s_=
il Report Contents:
- Project Pre-Outage Milestone Schedule Page 1 l Executive Summary Page 1 1 Organization Chart Page 2 l B&W (SIG Fabrication) Status Page 3 SGT (Installation Contractor) Status Page 3
! Engineering Status Page 3
} Quality Assurance / Control Status Page 4 i Plant Construction Status Page 4 i Project Controls Status Page5 Health Physics Status
{
j O&M Budget Performance Page 5 <[/
Page 6 ( g4 j Capital Budget Performance Page 7 / )
i I,
A
, -- . . - . . - . . ~ - . - - - . - .-- - . - - _ _ . . _ _ . - . - - - - - -=
88'C* si Lue:2esGAP ,
J TIPLfY
- PKE CUT AOf AAL E s t(wt S UPDAT1S W
loENTIFY SGRO CRITICAL PATH 0toCT96 sF[
APPROVE sGRo CRITICAL PATH BY 23oCT96 T MGMT.
AMEND sGR CONTRACT 01DEC96 EC IDENTIFY PLANT OUTAGE SCOPE 13DEC96 Ih AWARD osG Disposal CONTRACT 31DEC96 ,
COMPLETE RELOCATION TO NORTH 31JAN97 SERVICE BLDG. Y DEVELOP LAYDoWN PLAN 01FEBC7 EB SELECT SPECIAL PROCESSES 1$FEB97 CONTRACTOR I DEFINE scope To RECONCILE 21FE897 EP/DP/WP 24EB I
CONDUCT 3rd PARTY READINESS 01 MAR 97 OM REVIEW Y ,
DEVELOP HP PLAN 01 MAR 97 0 j I#
DEVELOP CRANE PLAN 14 MAR 97 .
j COMPLETE INITLAL MoBluZATioH oF 31 MAR 97 sGT (MK / oEst)
DETERMINE UNIT 2 OUTAGE IMPACT 01APR97 OM I y j IDENTIFY NoN sGRP PROJECT 01APR97 INTERFERENCES RESOLVE NoN sGRP PROJECT 30MAY97 I INTERFERENCES RECEIVE NEW s/G s 02JUN97 02)UN i v i START CRAFT MoBtLt2ATioN 01JUL97 APPROVE ALL work DOCUMENTS 20AUG97 #
v VERIFY PARTS. PAPER & PLANNING 20AUG97 20A W COMPLETED vI l i
START CRANE ouTsIDE CONSTRUCTION 20AUG97 #
v START sGRo 20oCT97 yT Exocutivo Summary The SGRP pro-outago preparation reached a milostono in October: the outage start dato is loss than 12 months away. As the countdown to October 20,1997 has begun, the SGRP Team has increased it's efforts to micro-plan the Unit 1 project. To ensuro success, a self-assessment of the project team (organization, mantoading, skilllovo!) is in progress.
Our stratogy is fundamental: build on the in-house project and industry experience with Industry exporlonce from outsido (Point Beach, Salom, North Anna, etc.). A series of roadiness reviews are planned which includo FPL Internal,implomontation Contractor, and Third Party. With tho vast data that is availablo,it is anticipated that information systems applications will play a significant role in the SGRP's success.
As SGT (the Contractor) completos SG changoout work at Point Beach, a focus to ,
prepare their facilities (officos, computers, phonos) for a sharp personnel ramp up is underway. Nino SGT people are expected in Occomber. The number willincrease to more than 30 in January. The FPL SGRP complomo will be at 20 poople in Januar .
John Toploy - Project Managor Page1
SGRP * '
ORGANIZATION CHART J
l i.
SITE VCE PRESIDENT JA STALL ;
+
l SGRP Sm MANAGER OutuTY M AN AGER
- L W. BL ADOW y,= >
PROXCT TECHNICIAN G.LABHART I i i 6 T :.
n
- C :
O N i i t
RADuisON PROTECTION PROECT ENGNEERING FTIOKCT CONTROLS CONSTRUCTION g LEAD MANAGER MANAGER. LEAD g, gggg K. PAYNE R.C. GROSS C BURTON F.G OELE I
[
l L
COST /BLOGET LEAD Owt/sTmuCTLRAL N g -. QA/OC E. BfJREM TM) g gg g PLANT INTERFACE L. MCLAU9eLIN MECHNUCL EAR M. M ACLEOD WORK PACKAGES L. LOSTOCCO SCHEDLLERS TtNDNNER YLF. OROSS. LEAD mT)
_ D.MOSAPO M. MAISANO I
LICEN94G
- TBD -
I i SLPPORT TECMetCtAN M. BRYAN ICS t
MIRA P84
l_
Contractor Status: ,
l B&W: _. _
!' - Closure seam welding continues on the second unit while radiography is performed on the first unit's weld, e
- Decision made to ship both replacement SGs on a single barge to PSL.
SGT:
- The Point Beach SG replacement outage is in progress. The polar crane has been modified and load tested in preparation for steam generator lifts. l
- The original steam gpnerators have been cut from the reactor coolant system with no resulting movement of the RCS piping.
- A 36 day critical path schedule has been provided to PSL.
- .eeeeee !
Engineering Status: l l
Outage Preparation:
The project has accelerated mobilization to begin in 1996 due to the new outage start date of 10/20/97. Integrated Plant /SGRP outage meetings, scoping, and l scheduling are taking place. '
l B&W Engineering: (fabrication contractor)
Engineering reports are being worked for completion in 1996. FPL has reviewed and commented on these documents. FPL will issue the final record Certified Design Specification by December 1996. i 1
SGT Engineering: (implementation contractor) l The scope of reconciliation of engineering and licensing documents is in '
progress. The production effort will begin in 1997. An engineer from DES is now on site full time.
l Disposal:
The decision was made to dispose of the old steam generators. Two vendors bid on the off-site disposal. Contracts is completing the commercial evaluation. ,
Contract award is due in early November. !
10 CFR 50.59 Review:
A draft report from the third party review of the completed 50.59 evaluation was received on 10/18/96. An internal review of the report is underway.
Hard Spots:
- Awaiting final barge / shipping configuration from B&W.
- Need full time engineering support for the disposal project and the 50.59 reconciliation.
- Complete the planned staffing of the SGRP engineering area.
- Settle outstanding contract issues with B&W.
s Page 3
e Project Controls Status:
- Discussions were held wit'h the Operations Manager and subordinates to define 1 expectations for Mode related activities. This discussion resulted in a number of l proposed changes to the work packages and engineering documents that will !
benefit the project schedu format the work packages,le. Additional to facilitate discussions case of NPS approval focused during on how tc best '
implementation. The videotape which overviews the replacement was provided to the Ops Manager for review by the Operations Department. 1 i
Accomplishments: i,
- A copy of the North Anna Plant / contractor interface document was reviewed and will forrn the basis for our interface document with SGT.
- A preliminary review of construction work packages for recommended revision to accommodate the Operations Department needs is 90% !
complete.
1 Hard spots:
- Procedure detailing the PSL Plant /SGT interface needs to be written.
- Additional procedures which define previously unencountered RCS conditions need to be' identified to the Plant procedures group. (Example:
complete draining of the reacivr coolant system)
Health Physics Status:
Development of the Radiation Protection Plan is on-going. Revision 0 of the HP staffing plan for the outage has been developed and is under review by Plant Health Physics supervision. Observations at Point Beach and Salem are underway to evaluate benefits of pipe end decon.
Hard spots:
- Completion of the HP readiness review requires input from SGT and the associated due date has been pushed back to March 1,1997.
- Need to make recommendation to Site Management regarding a street clothes clean RCB. SGT input is needed.
-Individual tasks / outage manrem estimates require major effort by SGT.
This will be an immediate priority following Point Beach completion.
- Access to RCA and containment plans need to be finalized for SGT to permit planning for dosimetry and other HP controls.
Ken Payne 7D Page 5
{ ,
ST LUCIE UNIT NO.1 ;
}i 1
SGRP BUDGET STATUS - O&M DOLLARS l l OCTOBER 1996 i
i i 80.000 600.000 MBUDGET MONTH o + 550,000 i
i ACTUAL MONTH ,'
- '* - BUDGET . CUM l o' l
--O-- ACTUAL CUM #
~
o 60,000
,' 450.000 l
- 400.000
_ ,'o
' l
- 350,000 7
I 4 40.000 - - - - -- - - - - -
- 300,000 i ,
250.000 i
- 200.000 20.000 4 -
-f - - --- -
-- 150.000 l
.4 + + 100.000 50.000 j 0- -
-0 l
5 4
a i
i g
j 2
i a
E a
i s
E s
($000)
CURR MONTH YR-TO-DATE TOTAL TO DATE YR END FCST I BUDGET $43 $464 $1,568 $550 ACTIFCST S1 $106 5998 $200 ACT/FCST VAR ($42) ($358) (5570) ($350) t
] Explanation of Year-To-Date budget underrun: ($000)
- . Project support efforts are below the levet estimated for the 1996 budget due j partially to eliminating the OSG Storage FacilttyJMausoleum) and 1
defernng the Main Steam Trestle PCM until the replacement ou' age (5358) j TOTAL explained variances
($358)
- .e_,._._,,,__....
j Page 6
ST. LUCIE UNIT NO.1 j -
SGRP BUDGET STATUS - CAPITAL DOLLARS OCTOBER 1996 l
. . . - . . _ _ - . - - _ . - - . . . _ . - - . . - - -- - - - l 1
7,500,000 22,500,000 7,000,000 20,500,000 t
6,500,000 i l
THE BUDGET OVERRUN IN OCTOBER WAS THE RESULT 18,500,000 6,000,000 OF A DELAY BY BWIIN COMPLETING THE CLOSING '
SEAM WELD OF T(IE FIRST STEAM GENERATOR. THE 8 PAYMENT FOR TylS MILESTONE WAS BUDGETED IN #
5,500,000 AUGUST AND ACCRUED IN OCTOBER.
16,500,000 5,000,000 i
x ,-
,] -
+ 14,500,000 I l
4,500,000 ' l
/- -
I
} 4,000,000 g -
12,500,000 _
M BUDGET MONTH ---
.E l 5 t r iACTUAL MONTH l
f 3,500,000 + .
o . BUDGET CUM o s - , ,000 _
+ ACTUAL CUM -
3,000,000 - - ' - - - -
, o o
2,500,000 , -
- 6,500,000 I 2,000,000 r - '
o' 1,500,000 -.--
- 7 ,c'- - - - - - -
4,500,000 1,000,000 --
7 J -
7 2,500,000 500,000 r - M - -
t -
l T 500,000 u
0}k ! 2 5 k $ k E E $ 5 E k
-500,000 - - -
1,500,000
($000)
CURR MONTH YR-TO-D AT E TOTAL-TO-DATE YR-END FCST BUDGET $1,220 $12,288 573,529 $18,881 ACT/FCST S3,088 S7,340 $66,859 $10,000 ACTIFCST VAR S1,868 ($4.948) (56,670) (58,881)
Sigt'ificant contributors to the Year-To-Date budget underrun: ($000)
SGT - Rev' sed payment schedule to reflect the SGRO schedule change ($3,598)
Deferred Blowoown Une ana!ysis
($100)
BWI - Negotated the eliminabon of extra costs related to Barge Transportaton (S253)
C A/OC Reduced contractor support due partally to eliminatng the OSG-SF and cer ernna the Main Steam Tresne PCM unti the replacement outage ($520)
TOTAL erotained variances (54,471)
. # wstasecownatwicponrummoresio nw en o. sin 2m
1 i
STEAM GENERATOR i REPLACEMENT PROJECT ;
j NOVEMBER REPORT :
- I l <
i I 5 J, :
76 . / i y- > </ '
1 e @ '
[ ] '
R
/ :
,~
~ % 1 se
% L-. - . . .
l
_ ~ -.
- h l
k# y 1 --
w 4
- Report Contents:
Project Pre-Outage Milestone Schedule Page 1 Executive Summary Page 1 Engineering Status Page 2 B&W (SIG Fabrication) Status Page 3 l
j SGT (Installation Contractor) Status Page 3
- Plant Construction Status Page 3 l Quality Assurance / Control Status Page 4 i Project Controls Status Page 4 4 Health Physics Status Page 5
- Action item Tracking System Status Page 6 O&M Budget Performance Page 7
)
Capital Budget Performance Page 8 i
SIG Disposal Fragnet Page 9 i
- 50.59 Review Fragnet Page 9 j Facility Relocation Fragnet Page10 {
SGRP Documentation Fragnet Page 10
e
. 030EC96 ST LUCIE i SGRP LEVEL 1
- J TEPLEY PRE OUTAGE SCHEDULE FOR 10 97 SGRO
.SF T. OV
'010CT96 T~g -~~
toENTW SGRO CR171 CAL PATH
~ ~ ~DEC_ AN.FEB. MAR,APR;MAY.,
~" ~
.. J L Au SE P ,0C .NOV APPROVALSGRO CRITICAL PATH BY SENIOR 230CT96 MANAGEMENT AMENO SGR CONTRACT 010EC96 y-IDENTIFY PLANT OUTAGE SCOPE 130EC96 j 9 ISSUE OSG OISPOSAL CONTRACT 310EC96 j 31DEC COMPLETE RELOCATE SGT TO NORTH ISSUES 3g;4Ngy N.M FACluTY OBTAIN MGMT. APPROVAL OP LAYDOWN FOR
< SGRP i 01FE897 l 'f, '
SELECT SPECIAL PROCESSES CONTRACTOR 15FE897 i sf,EB , ;
DEFINE SCOPE TO RECONCILE EP/DP/WP EB97 Y-IMPLEMENT THIRD PARTY SGRP READINESS REVIEW 01 MAR 97! l
' DEVELOP HP PLAN 01 MAR 97 DEVELOP CRANE PLAN 14 MAR 97 NR COMPLETE INIT1AL MO81U2ATION OF SGT (UK / 3,ggggy 31 MAR CESO
.lOENTIFY NON SGRP PROJECT gigppgy , OM' INTERFERENCES
, DETERMINE UNIT 2 OUTAGE IMPACT 01APR97 ; U #.#"
RECEIVE NEW S/Gs AT SITE 08MAve7 ! 08M,AY RESOLVE NON SGRP PROJECT 3ny3ygy 3N INTERFERENCES i START CRAFT MOBlu2ATION 01JUL97 01,JpL
' ! VERIFY PARTS PAPER & PLANNING 20AUG97 ] !
l 20AUO l l,
f COMPLETEo q i ,
, i "i I ALL DOCUMENTATION APPROVED BY FRG 20AUG97 1 3 20*fG l START CRANE OUTSIDE CONSTRUCTION 20AUG97 20A
, j j
! ;8EGIN SGRO 200CY97 i l 2MCT2,MCT:
Executive Summary Fabrication of the replacement steam generators continues in an excellent fashion. The final closure welds are complete and post weld heat treatment is in progress. The shipment of the steam generators has been advanced to April 21,1997. (The contract ship date is June 1,1997) The replacement steam generators are expected to arrive i onsite on May 10,1997. .
The decision to dispose of the OSGs has moved from decon and cut up, to burial. The 4 main reason was due to the increased risks to FPL beyond February 1998 on a new process to dispose of OSGs. As the contractor was seeking a shared risk approach, the decision was made in support of the direct burial cption.
SGRP guidelines to conduct readiness reviews were developed. A series of readiness reviews will be conducted throughout the preplanning phase, of which the first is an internal readiness review, scheduled for December,1996.
An ALARA study was conducted which determined the effectiveness of the pipe-end f decon. It was estimated that more than 100 man rem can be saved by performing pipe-end decon. Work continues with our main contractor, SGT, to integrate into the plant. !
h Contract negotiations have begun with SGT to develop an incentive contract based on performance and realistic, aggressive criteria. The current scheme which represents a 370 man rem ALARA budget and 47 day critical path windwrdoes not reflect reality. e MMO
-9 /%C
- John Tepley - Project Manager l
l Page 1 I
i
i .
{
Engineering Status:
l 4
B&W Engineering:-(Fabrication contractor) -
Engineering reports are being completed by B&W FPL is in the review process. !
FPL has issued the final record Certified Design Specification. !
4 i i Mount Vernon Shops: (B&W Facilities) !
The Upper and Lower sections of both replacement steam generators have been i j joined. The final closure welds are complete, and the first generator has i i completed heat treating. The,second generator will complete heat treating in l December.
i SIG Delivery:
Shipping of both replacement steam generators on a single barge is scheduled
- for April 21,1997, with arrival on Site May 10,1997.
2 SGT Engineering: (Implementation contractor) 3 Schedules are under development for the production effort needed to reconcile j engineering and licensing documents which will begin in 1997. An engineer from Duke Engineering Services (DES) is now on Site full time.
{ Disposal:
- The decision was made to dispose of the old steam generators. Two vendors bid on the off-site disposal. The technical and commercial bid evaluations are i
complete. Contract negotiation is in progress with the evaluated bidder, and I award is anticipated in late December or early January. (See attached FRAGNET l in this report) i l 10 CFR 50.59 Review:
FPL contracted with NUS as the third party reviewer of the completed SGRP 2
50.59 evaluation. Their draft report was received and additional work was identified by NUS to meet current NRC interpretations. The revised text and rationale was discussed with NUS and others. The revised 50.59 is expected to comply with NRC interpretations, and a PLA will not be required. The final NUS
- l report is due in early December. (See attached FRAGNETin this report) l l Accomplishments
- - Final barge / shipping configuration received from B&W.
SGRP work scope conveyed to Fuels, Reactor Eng, l&C Eng, and
. Mechanical Eng.
i
! Hard Spots:
j Obtain a full time project engineer for the SIG Dispoa project.
- Action: Tepley(AITS#69 - Due 1/15/97) j -
Obtain and mobilize remaining authorized engineering staff- these will j
^
be contractors.
Action: Tepley (AITS #69 - Due 1/15/97) i' LD Ron Gross 3 Page 2
-e+= m-m y-en r-mW i+--w,, ,-
---Tr - -----g ,r- -,
- - - v--- -
yw
Contractor Status:
~ ~
B&W:
~'Clo's ure' seam welding is complete and' radiography " sat" on both St. Lucie units.
- Hydrostatic test of secondary side of new S/Gs due in December for first unit and January for the second. ,
SGT:
-The SGT critical path portion of the Point Beach outage was performed in 25 days. Welding of the feed / steam lines' remains.
- Ramp up of SGT persorinel at St. Lucie is underway. One planner / scheduler and one resident engineer are now on board. l Plant Construction Status:
Construction activities during November centered on reviewing Work Packag'es and assisting Maintenance on Polar Crane readiness issues, final planning for SGRP facilities move to the Plant North side, purchase requisitions, and the upgrade to Substation 10.
Accomplishments:
- Provided the PR for a factory rep to review the polar crane maintenance history and provide recommendations, spare parts, and service for the Unit 1 SGRO.
- Negotiated agreement and schedule with Maintenance to exchange facilities. Maintenance moves south, SGRP moves north. (A/TS # 112 due 12/15/96, and AITS # 115 due 1/15/97) See attached FRA GNETin this report.
- Performed observation of SGT's SG transport and rigging capabilities at Point Beach.
- Obtained valid requirements for electric driven air compressors from Protection Services to support the " Clean Air Act" requirements. SGT will consider electric compressors for their scope of work. (A/TS#172-Complete)
Hardspots:
- Planning is underway with Power Delivery, Electrical Maintenance and Projects to finalize a design for needed improvements to Substation 10.
Options will be presented to management during the December 11,1996 Unit 1 Outage Meeting. Action: Gigele (AITS#149 - Overdue) e Page 3
[.
2 '
Quality Assurance / Control Status:
l l Steam' generator fabrication continued, with the completion of two major 4
milestones. Both closing seams are now through the heat treat cycle. No
- probl3ms were encountered during this stress relieving, and this completes the
, pressure boundary welding. The next major operation is the secondary side j hydrostatic test. A series of meetings was held with SGT QA Management, and a f
! plan was formalized to complete a review of the SGT Quality Execution Procedures (QEPs). This activity is now a Level 1. These documents form the .c basis 'or how SGT will conduct business at St. Lucie. 9 4 ,,
- Hard spots
- Clarification of which SGT documents must receive FRG review is needed.
! A recommendation from SGRP will be provided for St. Lucie Mgmt review l by 1131197. AITS # 209 - Due 1/31/97.
1 - PSI UT results from B&W were shown to the JPNICSI UT department. The
- j Level Ill rejected the documentation because it did not meet his 1
expectations for level of objective evidence. B&W states that the reports meet the Code. Resolution is expected by 2/14/97. AITS#210- Due !
2/14/9 7.
Rick Weis N i
Project Controls Status:
i i
Meetings with Operations Dept. and Work Control have resulted in an approach i for the contractor work packages that will not cross system boundaries or l modes in a single work package. With this Operations Dept. approved i approach, we can now proceed with SGT to reconcile the work packages a final
- time. PWO generation for work packages and associated testing is in progress in
- anticipation of the 12/13/96 Plant Pre-Outage Milestone.
3 Accomplishments:
4
- A draft of the Plant / contractor interface document has been written and is
, under review.
l
- The SGRP Department training and indoctrination program was approved and implemented.
- An SGRP guideline has been written to address how readiness reviews will j be conducted for the Steam Generator changeout.
i l Hardspots:
! - A well defined ramp up and ramp down for SGRP, SGT, and associated j craft must be developed and provided to the Plant by 2/1/97.
Action: Cowdrey (AITS #154 - Due 12/31/96)
- Incorporate lessons learned by SGT at Point Beach in an effort to further reduce the SGR critical path. (Point Beach effort was accomplished in 25 days) Action: B. Gross (AITS #175- Due 1/31/97) k Chris Burton cXc ,
Page 4
-- , _.n,
i Health Physics Status:
Activity in November centered on the decision regarding RCS pipe end decon.
---Discussions with other utilities and comparisons to St. Lucie <, i e accomplishe~d.~ ~
Internal discussions were conducted to identify the Outage Hr organizational split between the SGR work and the remainder of outage work.
These decisions will support the further development of the overall HP Plan for the replacement outagc. (i.evel 1 Project 101 supported by AITS # 131,132,133, 134,135,136,211, & 212 - Due 3/1/97)
)
I Accomplishments:
) - Completed pipe end dg, con evaluation. Recommendation to perform decon 3
at PSL accepted by management. Expected ManRem savings: >100
- Defined the list of HP in'strumentation necessary for SGRP.
l - Held initial discussions with Plant HP organization on rad waste plans and j budget. More discussions will determine if the budget accurately reficcts l'
expected rad waste handling expenses.
(AITS#135, Due -2/15/96)
J Hard spots:
]"
4
- Need final resolution of how HP shift management will be performed during i the entire Unit i refueling outage. Although the SGR HP technicians and the balance of outage HP technicians will be separate groups, we must
! resolve whether there will be split supervision or a single on shift j supervisor. SGRP project manager will resolve with HP Supervisor.
Kenny Payne '
t a
i f
j c
i j Page 5 1
1 ACTION ITEM TRACKING l
s pi al
!i a Deve oaec 10/96 SGRP ACTION ITEM DATABASE :
I Items M
= VllS/SGRP Join': 250 -
Total items li en':Ure ,,oe,eeeee
- i 200 -
im $m
= Trac <s SG !P, SGT, items sim .
- Open e Anc B&W Actions 'So -
@ Items Closed H m 206 Items Tracked in ,00
~~
$y First Two Vlontas -
lh 50 i, -
@ m Wor < Control
- 's Consicerino c Similar a o September October iNovember di
? System Month ,
sww u:y :m .
ee -em jg cm g
-_______ -___ ____ _ _ - _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _l
. 1 ST. LUCIE UNIT NO.1 '
O SGRP BUDGET STATUS - O&M DOLLARS i
NOVEMBER 1996
~
600.000 i 80,000 -
I
,o 550,000 MBUDGET MONTH e
r i ACTUAL - MONTH ,
- o - BUDGET - CUM ,o 500,000 e
--O-- ACTUAL - CUM ,
,' 450,000 60,000
- 400,000 350.000 f
_}
I2 I
- -- -- - 300,000 40,000 - - -
5 5 --
250,000 C ,
' 200,000
- - 150,000 20,000 -
100,000 i
- 50.000 1
--O 0
i : : : : : : : : :
s a i e s i k ,e 1 i s o s a 8
I E w 5 4 s < m =
l l !
l (5000)
CURR MONTH l YR-TO-DATE TOTAL TO-DATE YR END FCST j 543 i 5507 51.611 5550
! BUDGET l ACT/FCST 57 5113 51.005 5160 ,
(536) (5394) (5606) (5390) l 1 ACTIFCST VAR 1
i Explanation of Year-To-Date budget underrun: ($000) l Proiect sucpert effens are cetow tne :evet estimated for tre 1996 bucget due ,
O art: ally to enminabng the OSG Storage Facihty (Mausoieums and
- efemng tee Main Steam Tres';e PCM untilt*e reofacement cutage (f394)
TOTAL exclained vanances i ($394)
I
- ,4.<a
. ouu...cowo ren - .4-7 l
ST. LUCIE UNIT NO.1 SGRP BUDGET STATUS - CAPITAL DOLLARS NOVEMBER 1996
', 7,5 00,000 --- --
_ _ _ _ _ . . . - 22.500.000 7,000.000 _ _ .
20,500,000 6,500,000 --
o e 18,500,000 f 6,000,000 ,
i -
o i 5,500,000 ' -- 16,500.000 i
- i o
5,000,000 - - r- -
, , 14.500.000 4,500,000 '
p I '
3 4,000,000 c
m BUOGET . MONTH --
,o' -
12,500,000 }
i=
, j i i ACTUAL . MONTH ,o g i ; 3.500,000 - o - BUDGET - CUM o" 10.500.000 g I 5
= - O- ACTUAL CUM -
- S 3,000,000 j C ,
2
, 8,500,000 g 2,500,000 p' -
- 6,500,000 2,000,000 ,' --
l ,o
$ 1,500.000 ,e' -
g - 4,500,000
- ,e-1.000.000 - - - '*" - - --- - - - -
a 2.500.000 500.000 r- - ~ - -
0 - - - -
I 5 9 9 1 % s 1 E & U ? 8 U
500,000
"_ __ E.. l_ _ l-. 2 4
- Z 1.500.000
, (5000)
CURR MONTH YR.TO-DATE TOTAL TO-DATE YR-END FCST BUDGET S1.078 513.366 574.607 S18.881 ACT/FCST $484 57.824 567.343 58.570 ACT/FCST VAR ($594) ($5.542) (57.264) (510.311)
Significant contnbutors to the Year-To-Date budget underrun: (5000)
SGT - Revised payment senedule to reflect the SGRO senecuie enange (54.158)
. Deferred Blowoown Line anaivsis ($100)
BWt - Negot:sted the enminat on of extra costs refated to Barge Transconation (SM 3)
QA/CC . Recuced centractor suppen due cart:ady to enminating tne CSG-SF and eternno the Main Steam Trestre PCM until the reeracemer.t eutage <$534)
TOTAL exclained vanances I ($5.04 5)
,,. ouw.scowone ue m mivin'^~" "* ' ' ' ' ' ' " "
Page 8
f .
. ' escscas ~~
se ava, son,
,e an , % * ,
oso estantAt Lt VEL 2 Scut oult
- e._ , ._ w ,,e,, 4, me m . . ,
-sposff 0*Dicomme ogy 9 RE8iD l l,sen COMMERCIAL j OSGDISPOSAL f I" *
, ,,e 840 u2- .mczas++oevue -*I r m - p- } #f.
- PN
~7"M- : j I ,t ao RECEIVE CSG DISPOSAL SIOS o noctes l
3" ' PERFORM COMMERCIAL H
' EVALUATION teocres v2soctas teoc.reoc7 me NEGOTIATE / AWARD f acci ~si c I !
ICONTRACT 48 mocTes atDEcas I'
, j l f
ENGINEERING EVALUATION & '
f
- a %YSiS SY CourR. = lM aas' !2maaer '
I i
ei am 27heAA l . ! '
i %
- i i '
, l sto ,ENGWEERING REVIEW BY FPL '
{
en t?me? I tonener i EVALUATE i MODIFY SpePPtNG . iN ti' at amtsasr aarse anhana SADDLES amenmer I w
se2 INCORPORATE PPL COhdhdB4(73 93 8APRBr .Jenf437 ses !007 REVIEW OF SUBMITTAL too mAPas7 naps? "
sao EQUIPMENT FABRICATION Fo asklumer maaper f
CLEAR AREA & PROVIDE TEMP.
l 522 i SERVICES i oioctonoct t
' "0C"' ' C"'
f pr j
{ ,
$as MOBILIZE AT SITE j REMOVE A S/G FROM ao 'asocvsr mver ,
} f 1** f
- CONTAWMENT SY SGT o ignowr i }
f fl
, a nonow
- REMOVE 8 S/G FROM
{
g
. { j l o ahow? i (
2cmov
^
{'88 I, CONTAINMENT BY SGT i PREP A & B S/G's FOR
,3''"O* "D' C 20how ltof C 2coi eDASPOSAL a
8
, 2010 IgAngg I LOAD & SECURE A S/G TO '
s isotCs7 NEct? !
wl*
isoac z20ec l lf
'I j ,
gi ,
M88 . TRANSPORT A S/G TO
, 1
, ! .I 2aotter vtamam DISPOSAL SITE se .230sc iamm i ,
3"' PREP LOAO & SECURE 8 S/G l ,
TO SARGE r temmu 2rme temmaram l l
TRANSPORT S S/G 70 l a
me . DISPOSAL SITE 18 at. Amu wtaas ! I 4
lmansarseg,g l l
.J i
oescas ,,g,,,,,,,
-- .h.o . ,v . ..v . _ , ,c o. ,,,,,, ,,,, c., ,,v ;
0""' 19ee gegy l C ir
,DEC I p gSgpr- f M FE8 _ uAR . APR AUTHORIZATION SY FPL Ip i ! ! ;
e t 1' , . .
PRE AWARO DISCUSSION . FPL , ,
jjf ffjll ,
i l! l l
SSUE CONTRACT . FPL h l1 REVIEW AND # REP DRAFT . NUS i !
. i l' , ,,
ISSUE DRAFT REPORT. NUS I !
j !
l REVIEW # COMMENT SY FPL ,,'
0 ,
, f l! ,!
VENDOR MEETING i , , , { , ij
- SSUE MEETING COMMENTS TO NUS I l .
ISSUE FINAL DRAFT REPORT . NUS , I f ffl j ;
f OEVELOP PLAN FOR IDENT:FIED CONCERNS .FPL l ' ;j +
f !
REVIEW STRATEGIES WITH NUS 5 i , f l ECi
);
I LEGAL REVIEW OF FINAL CRAFT FPL 1, j
. ISSUE FINAL REPORT. NUS i. ,
j PRESENT STRATEGtES / PLAN TO ST. LUC 1E FPL f i 110EC 1 ' i
, ; j MGMTi vi ' i , ;
' SELECT IMPLEMENTING STRATEGIES i j .
,see pian A . O belown 4 1IDEC*> l l l'
"'MPLEMENTATION PLAN CPTIONS " ;
PLAN A . CUAUTATIVE JUSTiFIC ATION BASED ON a EAISTiNG ANALy$13 i PLAN A . OEVELOP QUALITATIVE REVtSIONS 1 HDEC i um PLAN A REVfSE EVALUATION s M 21FE8 PLAN A REVIEW 4 CCMMENT REVISED h 24FE807uAR i EVALUATION d =====
PLAN A .dSSUE REVISED SAsE I - <
' ! f , 'I I' 4l , I ' hamar # ,t !
Page 9
- . - _- _ . = ~ _ . . - . - -
i i 9 -
4
, ] F GGtt l' '; GAP HI~t OCA flON PL AN i
UlHAll filt C9ti HEV 1 ,
NOVf MfwR T iW crusu H .. 7
~ ~ JANUANY
'NORTN SE' R ~VeCE BUILDhG' SECONO LEVE' L ,
C2 t
De i I 1
_ .. _, DEMOBILIZE D 13 OFFICES FOR SGRP WITIAL MOVE 1 09 t3 I l ' !
t l ~~~"t !
--REPLACE CARPETS IN AREA OF VP OFFICE & HAuWAY f 07 07 I i
- I t'
H SGRP INITLAL MOVE TO NS8 2ND FLOOR OFFICES '
a j y MIS CQaruTER i TELEPHONE SCRVICES l 1 1 to 20 FINAL SGM 880VE ' '
l i l
l 1 .
i !-
l- i l <
t s l ,
i !
I
- j 31
- SGRP FINAL MOVE COMPLETED * -
4 4
- j
- i 80AT HOUSE UFFICES & WORK AREA i *
] l
" 13 i i i DEMOSILIZE BOAT HOUSE OFFICE FOR SGT PERSONNEL I i
C3 -* ~
a SGT PERSONNFL INITIAL MOVE TO BOAT HOUSE 3 c
1 1 I i !
,. I s l I J
l l
~
- . .. . . . st W
- esoaces at Luca some i.
l tantavomum sonP 00ctmaanrarion tavet 2 acasouts vraars eicaces new i i 1998 o 1997
, OCT NOV DEC JAN APR MAY JUN JUL FEB AMAR _1MPR 27MAY AUG _ SEP_OCT_.)
, ; UNIT 2 OUTAGE - ;
l 1 180CT ' 31DEC I l ' I ! ' l PERFORM Men Q REVIEW OF EJUSTING PCMs (ConA0 wepon Mgmt)r 6
'. ItOCT 01NOV j CETERMINE PWO & WP BREAKDOWN 1 t OdNovo8MOV '
p TRANSMIT TO SGT WP BREAKDOWN REQUIREMENTS i i ,
2 01Nov ve0EC i _ ORK31NATE PWO WORK REQUESTS FOR ALL WORK PACKAGESI i
130EC I I
- 3 y ALL UNIT 1 OUTAGE PWO WORK REQUESTS ORIGINATED (PLANT MILESTONE) 31NOV 31JAN j i
- DEVELOP CONTRACTOR INTERFACE DOCUMENT 31JAN I ' !
a I !
a 1 <- REVALIDATE PREVIOUSLY APPROVED DOCUMENTATION '
j
=
! 01aAN '
j , SGT RECONCILE DOCUMENTS , 18JUN .l i
1&JUN I Au DOCUMENTAflON FROZEN e,-
1RJUN j0SJUL i PERFORM uin Q REVIEW (Contgwauon ugmt.)
4 01J ALL WORM ORDERS PLANNING COMPLETE (PLANT MILESTONE) e,,UL
- 0JULieJUL.
1st GROUP FRG APPROVAL ( SGRR, SGER )
3 17JUL 21JUL k
2nd GROUP FRG APPROVAL (NEAVy LOAD DPs ) ,=,
24JUL 30JUL i 3ro GROUP FRG APPROVAL ( PCMs I a j 31JULO6AUG eth GROUP FRG APPROVAL ( PCMs I a 07AUG 13AUG 5th GROUP FRG APPROVAL ( PCMs 3 -
7CAUG ;
ALL DOCUMENTATION APPROVED SY FPL *-
I 700Cr START SGRO -
- . - - - - - .Page 10 i
I
I s
- W
- ST. LUCIE UNIT 2 PLANT AUX CONTROL BOARD ANNUNCIATOR LA & LB 6 AND 12 FLOW DIAGRAM REVIEW Annunciators LA & LB Annunciators are safety related. The subject windows 6 and 12 refer to Atmospheric Steam Dump Valves.
The window engraving refers to "ISOL", which means the aormal isolate switch is in the " Isolate" position. In isolate the valves position is controlled from the Hot Shutdown Centrol Panel (HSCP). The " OVERLOAD /CLOSE" engraving refers to a thermal overload actuation and closure of the valve.
The annunciator symbol (diamond with an "A") is not shown on the flow diagram for the subject wind 5ws (2998-G-079 sheet 1) . The flow diagram usually represents alarms directly associated with instrumentation (PS, FIA, etc). The flow diagram stan lard STD-D-3.15 does not require items not essential to the process to be shown (STD-D-3.15 page 8). ,
h>[+T
. - /F ,
I N & % ,Q)T J 5:.~ D / h..Q M4 & .L f ?
' ;:z ,( b W
. ')!N{-E.Ssl\d ?:')GC" < %'!~$ j 1
b h
, STANDARD STD-D-3.15
^
Rev. 1 NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Dm 08/94 FLOW DIAGRAMS Page 1 of 32 e
et Emefle digt Umflh a .
?
Mew o.e -
v_
ormrd l h$
~
g\V(bf Revision 1 Q !
I i
i j
i 5
l E
b
STANDARD STD- .i.15
-- ..- - - - - . ~ . - - - . . - . _ - - _ _ - -
3 NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS Page 2 of 32 TABLE OF CONTENTS PAGE 1.0 APPROVAL . . . . . . . . . . . . . . . . . . . . . . . 5 2.0 SCOPE . . . . . . . . . . . . . . . . . . . . . . . . 5 3.0 PURPOSE .
. . . . . . . . . . . . . . . . . . . . . 5 4.0 RESPONSIDILITIES . . . . . . . . . . . . . . . . . . . 6
5.0 BACKGROUND
. . . . . . . . . . . . . . . . . . . . . . 6 6.0 DRAWING CONTENT . . . . . . . . . . . . . . . . . . . 7 6.1 HIERARCHY OF DRAWING RELAT'ONSHIP 7 6.2 CONTEXT . . . . . . . . 7 6.3 STIPULATIONS . . .
8 6.4 LIMITATIONS .
8 6.5 FLOW DIAGRAM CONTENT . B
-.6 rQtP.
- P.u..r..".T '" .--rNT. 7 7 7 . "u n' T. T .v^ N 1 0
.-../ : r .m.v - , - - , . - -
c . . .- w ,.
.. . . n.
. .e . r..
. . r 4 . . .r .on
- - .. .;.w w ; --..e...
. 7. . m 7 ; - . . . .
... .-....4 ..e.
., , .0 - .DC ^
-w.. S.T
- ". Y. . n - .P r 0 .. r^"-
. 4 m ., . .O.*/. .r .* . -
. .i
,- . a. .^ ,.. ..r.s . .
.e ~;;-*4 s.-..*
. s ta.4- t. r. .. e. c t O. r.
.. . r .e. . ~. ~. . n.--..r e v..
j y
a a ;;*
..cywp
. . . - a
-n. . -;nJw... q p ., .- '.
1
.-ta. -. . ;
. ..r.e. . 7 ..-...e-; ;, ; . n....p*gr
. - - - - . . . . . 'As t
- .. ,.. , , , - c , - . . .
O.. . . . . , , , , - ,j n , - - . .
. .% V I., w-v .e..... ". O n. w . f....J . . w - .~ O
.s 7.O DRAWING FORMAT . . . . . . . . . . . . . . . . . . . . 15 n
- ; 3..... . ;,....
. g i
3 i i
}.
'w
. - . . . ...J -. .
... l O
E l h
v4 E .
l
.I 1
l 1
~
STANDARD STD-D-3.15 O. . _.
NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 FLOW DIAGRAMS
__. Rev. 1_ ._ _ _ . _
Date 08/94 Page 3 of 32 TABLE OF CONTENTS PAGE 7.3 TITLE BLOCK DETAIL . . . . . . . . . . . . . . . 16 7.4 DRAWING REVISION BLOCK DETAIL . . . . . . . 16 7.5 GENERAL / SPECIFIC NOTES . . . . . . . 16
( A@ .
7.6 REFERENCES
.. . . . . . 17 7.7 DRAWING NUMBERING FOR FLOW y 17 v D) 8.0 COMPUTER AIDED DESIGN & DRAFT ' . . . . . . . 18
,m %. j 8.1 RECOMMENDED LAYOUT
,m- v 4 19
. \ . . . . . . .
e 8.2 LAYER CCINENTION ,^. L . .c. .v 19 l
8.3 ATTRIBUTES [. '
-' . O, V
. . . . . . . . . . 20 8.3.1 VAWE A IB S 1 21
. ~.,
). . . . .
8.3.2 3QtHMN ;&~"/4CESSORY AT~RIBUTES 22
,e.
- 8. 3. 3/. INSTRUMENTAT.KsN ATTRIBUTES
\ v) .
22
. \DjONTINUATIONFLAGS 23 3 .e... :- :w. ~h,
- . nar. ._.y
- u r v.n. . .
r =.
......-...=O--
- . -s M . . . . .c r.) . .r .=.~rs rw=--o *A.44rJ .
,e
. u .J 8.5 TEXT STYLES . . . 25
-.C
- r. . e .- ew.u.e
.....w .
.S vc
~; -
.s.I.c .. p . .* ev .s tv.er .O v. y n n.-b/
a
- e
. D O a . . .. . .- n 5,* . . 7 T. - 3 0.g..v M t' a) e
. O a m . ...... , . .-,e,-c. *-
$ 0, . e. . L O 3 n w
. 0 0 0 6'T. 10 4D 2
a.. .. .. .o . . . . . v. . e .s. . . . . . c.v .", & 2.C v" .#.0,.0. v^ .._.~ r ,c
. . ,', 7
'E, 3
i
~
N E
3
I STANDARD STD-D-3.15 ;
._ . . . _ .' ~ ~ ~
- - ~ -
Rev. 1 !
NUCLEAR ENGINEERING DEPARTMENT i ST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94 FLOW DIAGRAMS 1 Page 4 of 32 l 4 TABLE OF CONTENTS PAGE
- ~
8.7.4 EQUIPMENT & ACCESSORIES . . 27 8.7.5 CODE BOUNDARY FLAGS 28 8.7.6 LINE NUMBERS .
28 8.7.7 CONTINUATION FLAGS 29 9.0 SYMBOLOGY . . . . . . . . . . . . . . . . . . . . 30 1
(
10.0 VALVE TRACKING SYSTEM . . . . . . . . . . . . . . . . 31 4
11.0 REFERENCES
. . . . . . . . . . . . . . . . . . . . . . 31 12.0 RELATED DRAWINGS / DOCUMENTS . . . . . . . . . . . . . . 31 4
O 1 k
- d j =
5
?
C e.
E 3
STANDARD STD-D-3.15
~ -- -~ -~
Rev. 1
' NUCLEAR ~ ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1& 2 _ Date 08 / 94 FLOW DIAGRAMS Page 5 of 32 1
1.0 APPROVAL Approved by: !
Manager, C ,f ' tion Management Approved by: I PSL PEGP/iroject Manager Prepared by:
C165D Coordinator
\<VA 2.0 SCOPE mm A.
s .. .3 This standard applies to shall be generated wi lkkagrams. Flow Diagrams
~
e se-n.f Co utar Aided Design and Drafting (CADD) for ie #R D.%t Units 1 and 2.
7 'of Flow Diagrams, the format It specifies the da d
( for their prese at , a .th r content by examples of what l should and shou h not % @ pented.
NS lT 6 l
This standwidqh not\b!/y to " vendor flow diagrams
- unless redrawn by tdrida Powbc 4 L ght . '/en dor f1ow c3agrams are defined a \;)obe drawings supplied by an equipment vendor in ,
tv a written specification unntained within, or respon referenc@ M by,.a purchase order, and which depict the process flow of,feand the instrumentation requ red :: Operate and monitor the equipment being suppl:.ed by :ne /endor.
3.0 PORPOSE The purpose f this standard s :: pr:c;de P.e ser w:th guidelines for the prepara::cn and or ma:ntenan:e cf the St.
'ucie Flant F 10 ',. : :. 5 ; r ams wh.:n .: . f:e d ::ns stency cf appearance and prcm::e : cmp:ehens:On f p an; system operation. Ito drawing revisions wi 1 be in;;;ated solely as a result of this standard.
sie h
3 t
)
- l E
3 .
I
l
. i I
STANDARD STD-D-3.15 i Rev. 1 NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS ,
Page 6 of 32 !
i i
4.0 . RESPONSIBILITIES l
The Manager of Project Engineering (PEG) is accountable for l ensuring that this standard is implemented by all individuals l preparing and/or maintaining flow diagrams.
The Manager, Configuration Management :s accountable for the training and self-assessment of conformance to this standard by the Plant Engineering Group (PEG)
The CADD Coordinator :s responsible for the upkeep and maintenance of the Flow M agram Menu program.
5.0 BACKGROUND
To better . understand the Flow Diagrams, certain historical details should be noted and their implications understood.
The Reactor Coolant, Chemical and Volume Control, Safety Injection, Spent Fuel Pool, Sampling, and Waste Management Systems, together with selected components of the Main Steam and Feedwater Systems are collectively known as the Nuclear Steam Supply System !NSSS), and were originally designed l and/or supplied by Combustien Engineering (CE)
Most Balance of Plant (BOP) systems and components were within the EB7SCO (the Architect-Engineer or "A/E") scope of design and sup..ly . These systems include, but are not limited to the Main S eam, Condensate, Feedwater, Heater Drains and Vents, C;rculat:.ng and :ntake :coling Water, Component Cocling Water and Contair. men: Sp ral Systems.
CE supplied certain ccmponents in the Ma:r Steam and Feedwater Systems and ESASCC 2:re ::mponents :r the NSSS side.
Therefore, certain CE style. valve numcers appear en the BOP side and likewise ESASCC style val /e nurters on the NSSS s:.de.
- is therefore important to close'.y cbserve the type Of name or number used as an a: d to determine the compcnent 's crigin, past hi s t o ry , and its significance to system cperation. In a
t ceneral,
- the ecmponen: .urt e - - "e Flow magram should confcrm 10 the component ag ;r the field and the equipment f data base 'Eass?Or:
1 0
s i-O
=
E 5
i 1
- 1 STANDARD STD-D-3.15 {
- -~~ ~
Rev. 1
~ ~-
NUCLEAR-~ ENGINEERING DEPARTMENT ~
~
ST. LUCIE PLANT _ UNITS 1 & 2 Date 0 8/ 94 FLOW DIAGRAMS Page 7 of 32 6.0 DRAWING CONTENT 6.1 HIRRARCHY OF DRAWING RELATIONSHIP Flow Diagrams contain design basis information for 1 -
mechanical systems in the power pla ey also depict l the lor. tion of instrumentation. Fo h e systems which are assv;iated with the steam to n te to f eedwater i cycle, the Flow Diagrams are am ca ions of the Heat i Balance Drawings. For other sy the Flow Diagram j may be an expanded version the @vfonceptual document. l Other documents serve the purpose for other l disciplines. The Main ne L' Wiring Diagram is an example. All other drawi essentially derived from them, or provide a detail to amplify the
.n information shown. t 's t refore imperative that information critic 1 -
ation of the plant be illustrated on t h I
{ 6.2 CONTEXT Other mechs al (and . discipline) drawings use the Flow Cia %Ws tpI4 ' asis and authority fcr the design e
and c'g Nexpres ) thereon. Once the Flow Diagrams havereeerigenerate %2e their draft form, other documents foll (.The General Arrangement Crawings can be made qc . the layout of equipment. A ?: ping Line List is veilbped 6@(g'ihons, dc to required wall :hickness , material specify size, design and operating requirements , nuclear saf ety :_ ass, and seismic category for design Of the piping. A '/alve and Specialty List provides information relating to valves, strainers, !
restriction orifices, and other appurtenances required to assure correct system function (Note that these " Lists' have since been integra:ed int: Fass?crt) '.Jsing these ,
the Piping Plans are drawn to show the routing of piping from :ne piece :f equipmen :c another. ?: ping
- scretrics, scme .mes ir :cmcination with spool sheets, are used :: detala :he piping and s =plify installation.
Eacn f these icwer _evel documents in turn provide in f o rma tion as feedback to the Flow C;agrams. For
} example, the iscmetri: is the document upon which the
! need for high point vents and low point drains becomes i apparent. This informaticr. 12 used 10 modify and j ccmplete the flow diagram, _ine, */ a i ce and specialty 7 _is s, and ?;;;n; plans.
I f.,
T.,
E B
e
STANDARD STD-D-3.15
~ ' ~
Rev. 1 NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1& 2 Date 08/94 FLOW DIAGRAMS Page 8 of 32 6.3 STIPULATIONS l
The St. Lucie Plant Flow Diagrams are process flow diagrams. Miscellaneous items such as pipe stubs, flanges, unions, etc, are<not essential to the process and are not required. These details are shown on other mechanical drawings.
Main process lines (when so depicted) are indicative of the main flow paths as criginally conceived and designed.
These flow paths do not necessarily coincide with current operational practice or procedure.
Operating positions of valves are dependent upon plant l
, parameters or conditions, i.e., plant mode. Valve positions are normally shown as if at power, i.e., Mode
- 1. Obvious exceptions are those systems whi:h do not function at power, or are not mode dependent, e.g., ;
Secondary Side Wet Layup and Demineralized Water, which '
are shown in their functional positions.
6.4 LIMITATIONS The limitation cf individual drawings is determined by the functional boundaries of major operating systems.
Major systems which cannot be shown :n their entirety shall be logically divided for p'resentation on multiple sheets. Minor systems or subsystems may be grouped on
" Miscellaneous Systems" drawings. Operat:.ng systems are
_isted and enumerated cn the System Cod:.ng 'ndex and FassPer: f:r 5 . :_ucie 'Jn :s ' and 1 respe::;/e.y 6.5 FLOW DIAGRAM CONTENT The f cilcwing paragraphs summarize the general centent of the Flow Ciagrams. Each item :.s descr:hed :n detal; in secti:ns 6.6 through 7.7 respect cely Equiprant :.nc luding , but not limited to, the reactor, a steam generatcrs, steam turbine, rendenser, pumps, heat i exchangers, tanks, f;1:ers, strainers, icn excnangers, E etc. Ea:P ciere Of equ;; ment cha.. bs ;n:cuely 5 identif;acle D'y ':~enz.ature i n d 'c r ".u ~.r e r 3
5.
E 3
s ___ . . , _ _ . _ . -
- - - - - - - - - ~ - ^ ~~'
i l
1 STANDARD STD-D-3.15
~ ' - -~
Rev. 1 NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/ 94 FLOW DIAGRAMS 1 h Page 9 of 32 l 6.5 FLOW DIAGRAM CONTENT (Continued)
Piping (including tubing) used to convey process fluid between pieces of equipment. All new process piping installed shall be identified with unique line numbers. l i
. l Valves used to isolate equipme .strumentation, control or regulate flow ./> c _ssure, relieve overpressure, or prevent backfl Q
- Each valve shall be identhe4 y a unique number as noted in Section 6.8. W Valve closure and - k. y godes shall be shown as I detailedinSectick6. . \\
Instrumentation
\
it c:0mbitor and/or regulate process conditi c rument shall be identified by a number i 'c ' ng th strument loop with which it is associat j
- Instrunebtion,sb uld be limited to the root or sendi. p ts.hrurt. (E a '.evel transmitter) and its prems '-c9nt ro'l'.s d , ice .e.g. a level control valve),
or (he visual Td audible indication for process moti(!;,pving (e.g. a level indicating controller with an i Simplified electrical or pneumatic l d,9npbncia siynals tor )
connect the devices and demonstrate loop '
'rm a t i o n s hip s . Further details such as instrument isolaticn valves, ven; and dra:.r valves on instrument '
tubing, five /alve manifcids, 5 :. gnal c ondi t :.cners ,
square roo: extractors, :.nt e g r a t o rs , etc are shown on jl the Instrument Installation Detai;s and the Control Wiring Diagrams and are unnecessary cn the Flow Diagrams.
I System zents, drains and pressure tes: :cnnections as i requ:. red e: her f or prc:ess :r "yiresta .: testing. For ,
add :icnal informati:r, see Se:::cn 6.10. !
- Hea or steam tracing for pr
- cess temperature
- maintenan
- 9.
i Piping and equipment ;nsulat :n is not shewn er the Flow j Diagrams.
2 5
b_
E 3
m
STANDARD STD-D-3.15 NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAG"AMS Pege 10 of 32 6.5 FLOW DIAGRAM CONTENT (Continued)
The physical order of connections shall be observed when l constructing the Flow Diagram. Vent lines should point up, drain lines point down.
Seismic category and quality group break points. See Section 6.11 for more information.
l 1
Connection interface points with vendor supplied I equipment.
Continuation references flags o other drawings. l Continuation ref erences on Air Supply lines to primitiae instruments and valves. l l
Record of revision. .
See section 7.4 :or cetails of i presentation. \
General notes. See section 7.5 for details of presentation.
Reference drawings. See section 7.6 for details of presentation.
6.6 EQUIPMENT IDENTIFICATION Equipment names and numbers are logically assigned by ,
unit and process function. . hen naming equipment or l assigning unique line, valve Or instrument nurters, due '
consideraticn should r'e given to the affect on plant
-o.,..,.,
y . , . . . , . . . . , . . .g.
.=...t.,.. =.. ....
a ..=
. .-..--a.. ., ..,e .
- orresponding ncmenclature and nurters fer botn 'ni t 1 )
and Unit 2. However, variations do exist. l Equipment is named f or its f un::::n A singular .tiece of m4 aa
..=..,c --.= g. .2. - .
.3.,,..c.....
.+.e. , . . . - ,,
. .e name en the Flcw Ciagrams. Therefore the unit must he n.
y +-. . c e..=a wgg., ,. a..a
- . c . .n , . . ,g ...
.a e -.-;
. = , ..e....=.
Examples: Deborating Ion Exchanger a
Condensate Storage Tank
.. s
. on.. .. ...... y =. n. a. .e .; .= .g..,
. .y .. a .... .=.:..,.. . . - .;~,..,,... . , a . . = . . , , , , ,
A .v p. 5* .***.
, v A.a .na.*, e. *+ -
.s.e**w** ..e....e. e..- .e--..o p y . .e. 4
. v. 1 ..e .*
gy 6 *' 3 * - . . .e. -
{ A c. .c . ,~ .e. . . .v : u:44 43
.- ..g n.e~...;..~..~ .z... -. .. .v g
- 2
...a. y A.-
E E
4 e
2 E
3
l 1
\
l STANDARD STD-D-3.15 4
~ ~~ ~~
Rev. 1
. NUCLEAR ~ ENGINEERING DEPARTMENT ~
_ ST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94 FLOW DIAGRAMS h Page 11 of 32 6.6 EQUIPMENT IDENTIFICATION (Continued) piece of equipment is added for flexible redundancy, the I spare is usually designated "C."
Examples: Purification Ion Exchange & 1B Condensers 1A & 1B Intake Cooling Water s 1B & 1C
, i 1 Multiple, train dependant equipm f orming equivalent l functions are given unit n mber, rain letter, and a l numeric identifier. ;
Examples: Circulating Wa s 1A1, 1A2, 1B1, 1B2 i
Condenser W , ye 1A1, 1A2, 1B1, 1B2 Certain equipment 's g with the train letter after the numeri n.4 l
l Example: e ater ters SA & 5B
( o 6.7 PIPING LIH15hDENTUi'J ~
,Q>
"3 ,
~ Ine.n. user's shan bp.l assigned and maintained by JPN (or se sigpee,)). The :.orw-of ling./, numbers is e$lphred below.
V )*, #flI"'C # # #
Lig- nu:riers are 7 -Posed
-> -.". a T- i meismic Category the ?.cman numeral
- ' 4 "=-28gs
' \a-i
~
"I" is used as a N" ukl01 ^wBER line si:e srs7tw Asentv prefix), , es, :ne - u st S;;r sys tem abbrev 13::,cn, "
SCd an ind1V1fuS1 nurrber unique ::
that _ine :. n that rigure FD. 02 system. For in example see Figu:
FD.01.
I i
i i
i b
N e.
E 5
m
I 1
1 i
i 1
STANDARD STD-D-3.15 3 - - ---
NUCLEAR ENGINEERING DEPARTMENT l ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 p.g. 12 of 32 l 6.8 VALVE AND SPECIALTY IDENTIFICATION Unique valve numbers shall be assigned and maintained in Passport. The standard forTn of valve numbers is explained below. -
i Valves are numbered with a prefix, system number, and operational number, written as a continuous string. .
Examples: V08141 V 08 141 1 V392031 V 39 2031 1V09238 V 09 2380 Unit designation I Prefix
- System numcer*
Operaticnal number *
- Passport identification fields ,
i The valve prefix "V" is most often used (indicates gate, !
globe, or check valve) but may be any letter or l combinat.cn as shown in Passport.
The next one or two digits indicate the process system !
number. Refer to the System Coding Index for the l appropriate system number. 1 The fc110 wing three or four digits indicating the n e v. a * . ^ . . a .'".. "
m
~C . %. p ..e. -~. t., a. .e. , .e.
.~... e - "... w .~ua
--..".a.
-- .r= .' ". a ....at
, s t e m. . .
.. .. - . . k.. p y ..a; ne ^ ^ Q s'. no
- a. . . a. .n .e...'~
y, ,,
. e ..
pr, e. y e.
n 2 1. .;
- . .-. .-w 'n~.= aA .e. . %. z.
. -' . 2. 2.. 2. ....v : .e
~; "
. . i. . ,^-.W4 A m , e. '
- ..C3.
v . .
- m. . h .a.
p .e . 7.s...'.e..,
. 3
. .c.m; w *s '.=\
- o
" .v 3 w ., p. ,s.,3 . w. .a r. .= ,. a. ..e. .
.e ,., p .., . c ,. -e .as-2 .' . . .w. o. . , .+w rs ;
.e. s s .a. = .., a.
number as part of .he valve nur-ber. The exception to
-..k. .' s .e . .a. . a. . e .r. * -
. . ..=.'.a..="
.ee.a . #.-.. . ^ , ..a " ..- . .e..b. w. v^.. *..". e Other u n :. t s drawings. r cr
- example, if unit valve a vvs en o. c . a . s w
.e. . . e ...e
.o
- . ....e4. . . . . a -.r
- = ,*. ,. .e. ,, e ,
.w,
.. c... ...a. Av..
2'.s.
4,
- h
&O a
.G.. h e .1 e 4 * *. '
. n G. _; R. . si p
g 2p.. . .e n..... ..'.=. .c wc : ... . n .n . A mz .e. a .r
== a y*
- 4 21..g
..e. . 1.,..
7 .....~k.,.:.,.v.
.+ . . .s.3 .' .'
..ew .u p
,; e .m . . . . .W. g. . .. e. . t ~.
. ..b. e .y .e.
.. . b. 4
- 4. .
y A.. . ..
...e m ; . .e..
. - . . . 4 p...v
.. g>v.gD
- l . .c .c .
e.4 : :
.AAg .. ..e..y.. .k . . . ; e
.e
. .;. *. ,. .'. ~. .."
. . . , , , .. .e.. A. . w..z. ; .r R aa i .n- -. . e. A- e s
J
. . - .z .e .
n
..v..
~n f
k h
Sh 94 E
3
%_ _ . , _ - . , . - - - - - - - * * - = - - -"
STANDARD STD-D-3.15
- ~~ -~
Rev. 1 NUCLEAT ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FPL e e 13 > n 6.9 SPECIALTY VALVES AND EQUIPMENT
~
Certain specialty valves and equipment (strainers, etc) are numbered with a prefix, a system number, and a one or two digit unique specialty number, separate with
" hyphens.". -
Example: HCV-14-2A HCVl
- MY- p[
, Prefix
- System number * .
s
(
Unique specialty number
- Redundant equipment lett *---Ng y Passport identifica Y ds When more than one a .. lty of a given type was purchased and th 'q s ial' number did not have a redundant equi ,,
t ded, a three or four digit unique number s ded. this case the original two i digit uniqu er 4 a d as the generic number.
\
Process cog 1 vah numbered to correlate with the a s soc:.a t = r'rgsif loop. Though, coordination with the Equips , a in\@ ort is required for numbering, the falve." number,s wil> r.,e similar to specialty valves.
^ \wi Exsbqt M special circumstances, valve numcers will not be assigned to valves associated with instrumentation-bey,ond the piping root talve.
6.10 VENT, DRAIN AND PRESSURE TEST CONNECTIONS Illustration of vent, drain and pressure test connections on the Flcw Diagrams ncrmal'y t e rm:.na t e s at the 'ast valve. Caps, blind f'.ances, r guick :cnnect ::uplings are .:: regu; red, cu: .a . ce sh:wn f:r further detail.
Ali /ent, drain and pressure temperature PX or TX) test g
Connection /alves s h a l . l'e s n:Wr i n ~. n e Cicsed Posi:lon on Flow Clagrams.
S 1
=
4 3
C 0.
E 5
m
STANDARD STD-D-3.15
. _ _ . - . . - ~ ~
Rn. 1-~
NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS 1
Page 14 of 32 i
i 6.11 SEISMIC CATEGORY I AND NUCLEAR SAFETY RELATED PIPING Piping A,
which is Seismic Category I and/or Quality Group B, C, D shall be so noted.
Seismic ca t ego.7 and Quality Group classification is assigned to each line in the Piping Line List in accordance with the function of that line.
l The method of indicating Seismic Category I is the Roman nume letters "A", "B",
ra l " I " . The Quality Group class is indicated by the "C", or "D" respectively referring to ASME code Classes 1, ^ , 3 and ncn-nuclear saf ety related.
All are enclosed within a square as shown on the Flow Diagram - Legend of Symbols.
Piping which is seismically supported' solely to prevent damage to other critical equipment is not designated Seismic Category I nor is it spec: ally noted on the Flow Diagram.
Seismic and safety class breaks are made at normally closed er fail closed (cr to safe position) valves or components. Although the absolute point of a class break
- .s at the valve seat, the valve Or component is always associated safety class.
in its entirety with the line of higher The seismic and safety class breaks for trim piping (system /ents, drains, pressure test points, et:; are considered to Occur at the end of the last barrier
.crma113 :losed talve, :ap, :r b ' '. n d flange, shown On .
the F1:w ::agra. and ~.ay r. : te ; r. d; : s t e d . : f ,0 :Sp cr blind lange is shCWL, One .s '0;
. requ ree to ee :n place.
If, however, One ;s shown :n the Flow Diagram.
then :: :s to be considered a res;;n Baseline, and the class break Occurs at the tap, Or blind flange, ,unless C;herWise ir.d1Cated.
6.12 VALVE CLOSURE AND LOCKING MODES R /alves shall be sh wn Oper 4 r :1: Sed as requ. red f;r "g norma OEera 1Cr
. 3 */ e s ei n l C." are
.= . o.
. T.O. r** a l . V
- nrCttle
.e...,e
.. . m .e
.e
,%..,._... .- ..2..-=e..-
. s
...=e ..,.
.2 .
$y ..
.e.
. . p. .e e o e% . . e.- z- y :.ae
= . 2. .~ e. ,;;, v.. . . v. e .c e : ..a g .e. 4 A e
...e
. -.e ..
. -- ... . . s .s .-.r.. ....e . .
~. .". C u h . . e . E. $. e U. e I '.$I. C I 1 C 7 ~3.
$ 31 17 3 r. - E. C [I.a O r 959r gen!) : O r. d i ". i C 3 .
E i.
h 5
E 3
.m. - - . . .
T I
STANDARD STD-D-3.15
- ~ ~ ~ ~ ~ ~~' -
Rev. 1
~ - ~~~
NUCLEAF ENGINEERING DEPARTMENT ~
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 PLOW DIAGRAMS Page 15 of 32 6.12 VALVE CLOSURE AND LOCKING MODES (Continued)
An example of this is the Safety Injection System which is shown aligned for emergency core cooling in the event of reactor coolant system depressurization, but does not experience flow during normal power o - tion. Symbology s h a 1 1 differentiate ^
t h e V
, g gg difference between' locks physically located the valve and on y A\/
$?
M ~
mgmg wr those in the (}'m <
control room. aasra tocAD COSD See figure S "NN A00v FD.02 for an a FC lLC/Cl example. M i t #,;A-462 ) 7[
Valves sha V2187 I
be as indic 1
d hJ (9 open' w trA locke d )d whent . ~ as a (Q) .. s Pigute FD.02 D e \A i c, n B$ h e ,' glocks are necessary for nuclear or personnel da f dct/ . Valves locked administratively for equipment seqcrity and Other similar purpcses are not to be addressed on the Flow Clagrams.
l 7.O DRAWING FORMAT !
7.1 DRAWING LAYOUT Equipment shall be arranged er the Fl w Diagram in a manner which emu _a:es physi:al _aycu as much as is pra :::al. e;her so arranged, the drawing shall be cr ented sucr :ha: ':c r t 'r _s a: :ne ::p cr :: the left of
- the drawing. If a physical .aycut is not prac : cal,
{ equipment shall 'c e arranged such :na: ilow begins at ;
I equipment in the upper left corner cf the drawing, i cnt nu;ng from left :: righ:, r if a : rcuit us flow, j :n a Cl:ckWise dire :: r.
7-1 E
3 u.
I STANDARD STD-D-3.15 l 1
gew. y l
NUCLEAR ENGINEERING DEPARTMENT l ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 l l
FLOW DIAGRAMS l Page 16 of 32 1
1 7.2 DRAWING SIZE Drawing size shall be in accordance with the l Administrative Procedure, General Drawing Procedure JPN- l AP 4.8 as applicable to Flow Diagrams. l St. Lucie Plant Flow Diagrams shall be of uniform size, l 30" x 42", commonly known as "G" size, which is denoted '
by the letter "G" in the drawing number. See attachment "A" for an example of Flow diagram format. l Example: 8770-G-081 D70 2 - vel I I t Drawing number pref:.x l
Letter size of drawing ,
Sequential drawing number l 7.3 TITLE BLOCK DETAIL Title block detail shall be in accordance with the Administrative Procedure, General Drawing Procedure JPN-AP 4. e as applicable to Flow Diagrams . The two or three line :::le shal. state :he drawing type ( :. . e . FLOW D!AGRAM) and the applicable system.
Example: FLOW DIAGRAM HEATER DRAIN & VENT SYSTEM 7.4 DRAWING REVISION BLOCK DETAIL Revision block detail shall be in accordance with the Administrative Prc:edure, General :rawing Fr:cedure JPN-AP 4.6 as applicable :: Flcw :agrams . See attacnment "A" f or 10ca::.cn Of rev .sicn bic:k :n F;;w : .agrar f:rmat.
1 1
7.5 GENERAL / SPECIFIC NOTES r
l fj General Specifi: .0:e5 shall ce in a;;;rdance x;;h the E Adminis t rat ive Prc:edure , General Drawin: Frocedure JPN-I AP 4.E as app 11:able :: Flow : agrar.s ' _res a t : ?. :hmen t i ' A '- f:r _::st:.:r :f .::ss :r F 12., :;5;rar f:rra:
a
~e I
C' I
e n
E 5
STANDARD STD-D-3.15 4
-- ~' ~~
Rev. 1
~ NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1& 2 Date 08/94 _
FLOW DIAGRAMS Page 17 of 32 REFERENCES 7.6 References shall be in accordance with the Administrative Procedure, General Drawing Procedure JPN-AP 4.8 as applicable to Flow Diagrams. See attachment "A" for location of references on Flow Diag ormat.
7.7 DRAWING NUMBERING FOR FLOW DIA All drawing numbers shall be ssi y
d in accordance with FPL Administrative Proce e JPN-AP-4.6, Nuclear Engineering Department D awin' umbering Procedure for St. Lucie Units 1 & 2.
St. Lucie Unit 1 Flow la O v' ams
,1 N numbe re d " 8 7 7 0 -G . . . " .
St. Lucie Unit 2 D. rpms ar umbered " 2 9 9 8 -G . . . " .
All NSSS Flow 'a s ha een grouped into the " . . . . -
G-078" ser' I a ig sheet number assigned k correlates ot sys m mber of the operating system, e.g., th mica M ume Control System, System 2,
.s :.n thg . t ( ep ser:es, ano the Waste Management, S y s t nAe,m - 6 ' i s in\ whdI I" Sheet 160" series. (The sheet numcer is the la% v three digits of the original CE drawihq,.r.umbe r , and has been retained for continuity.)
Q y' yst Flow Diagrams have been assigned drawing BbP nuhb Q'ers "em. .-G-079" and above. "nlike the " .-G-078" seFEes, these drawing nurters .n no way carrelate to the system number. However, the systems have been grouped into sheets of a drawing nurter. For example, all steam systems (Main, Extraction, and Auxiliary Steam and Air Evacuation Systems) are shown on multiple sheets of drawing number "G-07 9 " , and the Feedwa:er and :ndensate Systems are shown on the "0-;8:" series.
Steam Generator Slowdown Trea: men: Fact.;;y 53BTF) Flow Diagrams are numbered "3509-G .. "
, and consistent with other SCP systems, the drawin; number d:es no: 0;rrelate
- _' to tne system.
O z
7 I
i.
E 5
s
STD-D-3.15 i
. _ _ ..____ STANDARD R ev. 3 - - - ----- -
NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1& 2 0'"
08/94 l PaEn, FLOW DIAGRAMS Page i g of 32 8.0 COMPUTER AIDED DRAFTING l Nuclear Engineering has developed a customized AutoCAD based i Flow Diagram Program for St. Lucie Units 1 & 2. The program I contains symbols identifying various components / equipment as (
an integral part of the process flow system line work, notes, '
tables, etc. as defined in this standard.
Input consists of placement and manipulation of symbols, line work and text for use in AutoC.C. Output consists of a Flow i Diagram drawing and sorted, printable component report of attached attributes.
St. Lucie's unit 1 & 2 flow diagrams have been drawn using Computer A:.ded Design & Draf ting (C.C D) to ensure consistency and standard symbology. New flow diagrams and revisions to '
exi s t. ing f1cw diagrams shall be completed using the AutoCAD based Flow Ciagram program. NO MANUAL drawings cr revisions' of Flow diagrams shall be accepted.
M M M M CONTA!NWENT 90VNORY J4R *0if (COLOR. BLUE) maamme a summe a summes a mamam SUILO:N; OJiiiNE JyER *a:f (COLOR. uACENTA)
WAIN PROCESS LINE JTR '# (00 LOR. OREEN)
SECONDARY FROCESS LINE LAER 'S' (COLOR CYAN) lNS'RUMENT L:NE >4R " ' (COLOR YELLCW)
E.E: R: a 5::w .:sE >sa :r (00;0R. E;)
^ ^
. 1 , 1 RAD!ATION SIGML LAYER 'S' (COLOR. CYAN)
- Di TRACED > i; (00 LOR E a0*)
, , , . (#AT ~RACINC FUN 07:0W)
- 97 'RA0E0 s iR ~~~ '0OLOR SL.0*;
+ + + +
(-EA' ':AO:N: as00sE:)
- =
- AD:..AW '.2:NO 2
.AER (00LCR YE L;*)
,, .,- a' '
- NELMATIC S
- 0W LAIR ( 0 LOR ELLO*)
.t!
j ------- - -- ---_ ._.
D"AUS* CR OR SCREEN 34R D* (00aR uA;ENu) fT 5 Figure FD.03 f
E 3
m
l STANDARD STD-D-3.15 ;
\
- ~ ~ ~
Rw. 1 I NUCLEAR TIGINEERING DEPARTMENT
~ ~ ~ ~ '-~
l ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS I Page 19 of 32 l
8.1 RECOMMENDED LAYOUT Place major equipment in their appropriate location first. Draw pipe, according to the flow hierarchy (main, secondary, instrument etc. ) connecting the equipment . See FD.03 Q
figure for -
complete list of )
g' 3, i, line hierarchy for ve l flow diagrams. . ,/),
. ss
'\V 608 l Avoid crossing one line with another, i where possible. 1/8' GAP
% (__
When lines have to g\ i p
cross one another, follow the flow .j Ig ,
hierarchy determination for A~
Q N which line M D Q l break. The 1' t bc broken 11 M i have a 1/ ga n each si f ti1% s _
I us unbroken . 'e S#~ Ng r, ficur m f
~
4 f 'ck..
de A e N%
Figure FD.04 p b'.
8.2 LAYEkiCONVENTION All drawings shall contain the layer convention setup in this standard. All entities inserted into the drawings using the Flow diagram program correctly will be placed on the appropriate layer.
There are twc exceptions :: the above statement : t ext not contained n a symbol attribute and miscellaneous equipment. All free ferr text snal_ be pu: cn the layer "0" zerc) Miscel.aneous equ;pment w;__ ce manually drawn cn the layer "E" : Equipment) ~f a tag number is supplied, the user will insert the block containing the
- attribute information for equipment. The block is i located at " 2 4 - E " e n t he T.enu t a b le f or the Ficw Diagram I Program. Figure FD-05 lists all the standard menu i program layers tha: shall be :entained ;r ea:P file.
t.
O I
k b_
m 7.
E B
s STANDARD STD-D-3.15 NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS MMP ' MCol.oR: DESCRINTIOW ""YENTrrES"SHOWNUN R?NAMEi .
. . w- .c.. 'byg
, O White Zero All non. intelligent components and text.
BD Magenta Building Outline All Building Outlines.
CB Blue Containment Containment Boundary Boundary outline.
E Cyan Equipment All equipment EA Magenta Hidden Line Exhaust Air or Screens.
GRID White Coordinates Drawing Coor. Grid 1 Yellow Instrument All Instr., tubing, signals, instr.
valves and instr. text.
ID Red Instr. Dotted Electrical signal line work P Green Prirnary Main flow piping and valves HEV White Revision Revision clouds S Cyan Secondary Secondary flow piping and valves.
NSR White Sticker Nuclear Safety Related T White Tags Valve and equipment tag numbers V f White Vellum Flow Diagram format.
Figure FD-05 8.3 ATTRIBUTES All valves, equipment, instruments , certain accessories, the fi w diagram format and continuation flags have attributes a ~ ached. After each is inserted in;0 the drawing, the user will be
.rrompted :: enter the appr:gr:Ste informaticn n -
4 ce:::cris 8.3.1 through 8.3.5 . s: -he attributes j 20r va ves. equipmen:,
- nstrumen 3, f;0W diacram -
---.~=- .. .....:....
g
- . . - __agg [ g s p g - ; ; ,. g , .,
- :3
. - ,2 - -.. _; _
f
- * * - * *e Av -e e ' e5 ,[ [g,j ;"f "a sF~CO s, see crawing 2,;9-3-;~3 Shgg ,;;;
t 8
4 STANDARD STD-D-3.15 Rev. 1 NUCLEAR ~ ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94 i
FLOW DIAGRAMS ,
% Peg. 21 of 32 j 8.3.1 VALVE ATTRIBUTES When valves are inserted, prompts must be answered to complete attribute processing.
See figure FD.06 for a complete list of valve attributes.
/) .
ATTRIBUTE PROMPT
^
hV EXAMPLE Tag Number NQisg V09235 Locked Mode h le LC or LO NV/
Failed ModeQ N / V4ibie FC -
Seismic k )then I Ge[kbgx. HidMn 212A
, tdgTk Hidden VL E
(
k h Grofh) \N //
Hidden A. B. C or D NNValve CB>rd.v' Hidden C3
\ t
^m' ,, \
\,Y,; }
. Figure Fd.06 C' The only valve attributes with defaults are lp\,)
t ^,
Component type and Sub-type fields. The i
Component type shall always be the code 4
value "VL." The Sub-type code value shall be set for the type of valve that is being inserted into the drawing. For example, a Ball valve will have the /alue "A" and a Check valve will have the value "C." Pefer to Passport for a ::mplete 'is: of Sub-type
- ce :a.ues.
There are two c;;ua:::ns wnen the 5;.b-type
- ode /alue shal. :hange f:r valves. The first ;s when adding a valve accessory or
, . operator to a Cate /alve. -n this situation t
there shall be no 'calue for the Sub-type.
i The second situation :s wnen adding a l Solenoid Operator :: ar; calve type. The
!, S ub - :v. . e cal e 2n51.
. 5..;5v.s r'e "SV."
I I
d t
E 3
m
5 .
l STANDARD STD-D-3.15 3 - -- -
NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 cate 08/94 :
FLOW DIAGRAMS '
Page 22 of 32 8.3.2 EQUTPMENT & ACCESSORY ATTRIBUTES When equipment or accessory blocks are inserted, prompts must be answered to
- j complete attribute processing. See figure l FD.07 for a complete list of equipment '
attributes.
l ATTRIBUTE DISPLAY EXAMPLE PROMPT Description line 1 Visible Condenser Description line 2 Visible 2A Tag Number Hidden CNDSR 2A Seismic Hidden I .
1 Quality Group Hidden A. B, C or D Figute FD.07 8.3.3 INSTRUMENTATION ATTRIBUTES Xhen instrument blocks are inserted, prcmpts must ce answered tc complete attribute processing. All attributes are visible. See figure FD.08 for a ::mplete _tst of
- nstrument attr:butes.
ATTRIBUTE PROMPT EXAMPLE Panel or Rack Number 202B Function Tl System Number 09 Identification Number SA2 g Switch Position PB j-Temporary Flow Element T 3
h Fi7ure Fr.09
+
I L
2 E
5
a STANDARD STD-D-3.15
' Rev, 1
- ' ' ~ ~
~ NUCLEAR ENGINEERING DEPARTMENT
- ~~~ -
ST. LUCIE PLANT UNITS 1& 2 Date 08/94 FLOW DIAGRAMS Page 23 of 32 8.3.3 INSTRUMENTATION ATTRIBUTES (Continued)
When inserting instrumentation, hyphe's n shall be removed from the three fields within the symbol that makeup the channel number. If the suffix is to long for the third field, it ma rtially placed on the second fiel S number). In this situation pl . h hen between the system and suffix n' See figure FD.09' for examples.
COeTCT Y lhCO@TCT JAGIRWENT T TAC PJ 4 PX FX-09 09 09-2 09-8 A.M 8 P. 3 9 PR 1rR g ,g ,g bg (i i
9 9 d
'9 d
'9
/ \\
(
v i 1 r% 1 r% 1 r5 k j j k@ j k@ j k@
~ .s ' ^ _s n
p \p; sVj
~J Figure FD.09 i
O ,% '
BW 4 CONTINUATIONS FLAGS
- , (, -.
When prompts Continuat;0n must ce lags answerec 5re to inserted, complete
{j attribute proces sing. See figure FD.10 for examples. :nstrument Air Continuation flags shall not have the System number attribute. ,
1 ATTRIBUTE PROMPT EXAMPLE Desenptsn Cont.
To or From Dwg No 2998 G-080 SH 2A System No. RC j
j Dwg Coordinates (E-7) l 1
Figure FD.10
)
~n C -
e.
STANDARD STD-D-3.15 3
NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS 32 h Page 24 of 8.3.5 FLOW DIAGRAM FORMAT ATTRIBUTES When Flow Diagram formats are inserted, prompts shall be answered to complete attribute processing.
,. . I
" ATTRIBUTE EXAMPLE - _
Dwg No. 2998-G-080 SheetNo. 2A Revision 0 FPL Florida Power & Light Company Plant St. Lucie Plant installation-Unit 1983-890 MWe Extension - Und 2 Title 1 Flow Diagram Title 2 Feedwater & condensate Tale 3 System Scale None Date 1/12/94 Discipline Mech Drafter (Name of Drafter)
Checker (Name of Checker)
Respon Eng Org Plant Engineenng Group NSR1 Nuclear (Nuclear Safety Related Box)
NSR2 Safety Related (Nuclear Safety Related Box)
Cadd File No USM00001 (Assigned by FPL)
Upper Dwg No 2998 G 080 (Upper left corner of Dwg)
Upper Sheet No Sheet 2 (Upper Left corner of Dwg)
(z F1gure Fd.1:
h i
-s o
i l
STANDARD STD-D-3.15 !
c,
~~ ~ ' - -
Rev. 1 ,
' NUCLEAR ~ ENGINEERING DEPARTMENT !
ST. LUCIE PIANT UNITS 1 & 2 Date 08/94 l FLOW DIAGRAMS I Page 25 ot 32 8.4 ATTRIBUTE REPORTING -
I l
Provisions have been made for the extraction of the 1 attribute data to the system data report file for hard i capy printing of customized reports. l To create a customized report, ed t "Reptemp.txt" using any of the attributes li d sections 8.3.1 through 8.3.4. Then run the L t ne " Report" from the AutoCAD command line. The (.TXT file) can be loaded into either dBase E . For additional information on extracting at 'E e information, refer to the AutoCAD Reference Manu
! 8.5 TEXT STYLE The default te 's .a . d andard" (Font name, Flow.shx). Text i . inches, with a width f actor of 0.8 inches k Use the te st "L e (f ont name, Large.shx) for all cri etail Titles and Containment Equipmenq, Soundary -desc &.p/p;4c o n Text height is .125 inches, with a wid@fdcitor ofs w }5 inches.
z All v / shall be typed in Upper Case. The only e#Mhgt h will be abbreviations that are normally shown ' i ih )qwer case. For example, the word Hydrogen Ion '
Ocg entrator is abbreviated as "pH."
Text should be placed herinentally on the drawing. Text that is placed vertically, shall be rotated 90 degrees with the text facing to the left of the drawing. For example, all valves placed on vertical lines will have the talve number and modes rotated 90 degrees automatically by the Lisp routine. With the exception of the valve numbers and modes, rc:ating text vertically should be avoided.
The Ficw Clagram fcrmat has a mix ure of tne text styles
" Roman 5" and "RomanD." The forma: shall not be exploded i, :: change r alter the f:rmat.
z I
s 7
b
~
E 5
m
STANDARD STD-D-3.15 3
NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS Page 26 of 32 8.6 REVISIONS Flow Diagrams are maintained in as-built condition, therefore, revisions will be required based on various change documents. -
All revisions shall be back circled using the "Rcloud.lsp" routine. The LISP routine will prompt the.
user to sketch a line counter clock wise around the revised portion of the drawing. The routine will then draw arcs on the layer "Rev" in place of the sketch line.
8.7 INSERTION OF SYMBOLS All symbols shall be inserted into the drawing by means of the Flow Diagram programs"s menu tablet . Most symbols are inserted using the LISP routine "FFIN.lsp." The FPIN.lsp is programmed to insert the symbol on the correct layer. Those symbols that are inserted into the drawing using AutoCAD's " Insert" command have the layer preset.
Layer Convention.
For additional information see section 8.2, 8.7.1 GRID AND SNAP All Flow Diagram CADD files shall have the Grid set to 0.;25 n:hes and the Snap set to 0.0625 :nches. All f les shall be drawn and rev sed w :h the G::d and Snap se: :n l
l 8.7.2 VALVES & ACCESSORIES All valves shall be inserted en either a
- ........ . se:Ondary r nstrur.en _ r. c . The "FPIN.lsp" r o u t :.n e .:.. place the talve on -he
- rre:: .ayer and c
'reak the _ r. e , nce inserted.
l
[ The 1_s; rout.ne w ._ reduce ne 21:e af the l
}z /alve a::Ord:r.; :D :nr . .ne ar.c ayer tha: the j ca _ te .2 _nsert r a _ ces sre r; aced :r !
i F r : r.a r . ._r.es a: 1 . '. ' , S e r :r.d a ry _ _ r. e s =~ ^ i 3
I
,,, i 1 !
i i
f l 7.
E B
?*
STANDARD STD-D-3.15 t
- - ~~ ~~
~
R ev. 1 NUCLEAR ~ ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94
% { page 2 7 of 32 8.7.2 VALVES & ACCESSORIES (Continued) reduction of 75% and Instrument lines (beyond the root valve) at a reduction of 50%.
Valves may show two diff types of mode, Locked or Failed. E s a separate attribute field and 1 t around the valve. Valves that s locked closed or open at the contr om shall be shown with a box drawn roun he attribute and a
"/C" after the abb i on " LO " o r " LC . " See figure FD.02 f an ample, The "FPIN. P q 1 e shall set the correct rotation f val as. The rotation shall be dete i y -
rotation of the line picke O O
, Al al ad essories have their origin i p set 4 e enter of the valve symbol.
\. 1 ve a es ries and operators have their m in pein t to the center of all valve c *)
Ir gMotor a W Solenoid Operators shall be shown 1
.\ // with a circle leading to the valve.
The
_4." circle shall have either an "M" or "S" to ,
designate motor or solenoid operator. See j
_. figure FD.02 for examp]e. i 8.7.3 _If TRUMENTATION & ACCESSORIES All layer instruments and accessories are set to the
":" after being :nser:ed :nto the drawing. Ir.st rumer.:s wi n brea k the .:.ne they are being atta:ned ::. T ". e Orig;r point of all instrumen:s Sr.: accessories _s set to the renter Of ne .nstrument symbcl e, . I
~
t g 8.7.4 EQUIFMENT & ACCESSORIES e
1 All equipment :s set ;; the _ayer "E" after reing i r.s e r : O in!- . r.e Or 3w; r.; .
5 E
i E
5 1
~
l
-)
STANDARD STD-D-3.15 {
3 - - - - - -
NUCLEAR ENGINEERING DEPARTMENT l ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 i FLOW DIAGRAMS h Page 28 of 32 8.7.4 EQUIPMENT & ACCESSORIES (Continued) j The origin point shall differ for each piece.
of equipment. Only certain pieces of equipment break the line that they are placed on.
For those symbols that do no break the line they are placed on, use the AutoCAD command
" Break."
Certain pieces of equipment may need to be scaled after being inserted into the drawing.
For this reason, attribute information has not been attached to all the equipment symbols. Equipment that requires a description or tag number after being scaled l shall have the appropriate bl'ock inserted f rom the Tag section of the menu tablet. See l attachment *B" for example of menu tablet.
All equipment accessories are placed on the layer "0" once inserted into the drawing. All origin points are set to the center of the symbols. All symbols will break the line that l
they are placed On, except for those symbols '
that are normally placed at the end of a line.
8.7.5 CODE BOUNDARY FLAGS All Code Soundary Flags are placed on the
.ayer ":" after reing inserted nte the dr5 Wing. T".e Cri?;T 901n: .s set 2.1 inches frCm the hCttCm of the sym.Ocl.
When PCssible the CCde EOundary Flags should be placed on the top of the valve symools, leaving the valve tag number : entered under the valve symbcl.
8.7.6 LINE NUMBERS ft A '. . .
- ne numcers are placed :n the layer "0"
- :: f : 9 r rein; ; T. s E r ' 9 5 _.-*.1 *"9 :1 f..i n g .
e -
T ",. e oe a o e a w e Y w e .*
- 6 4 t
I E
3
)'
STANDARD STD-D-3.15
- ~ ~ ~- ~ ~
Rn. 1 NUCLEAR ~ ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1 & 2 Dat, 08/94 FLOW DIAGRAMS Page 29 of 32 8.7.6 LINE NUMBERS (Continued)
All line numbers shall be placed on a line.
Line numbers shall not have leaders pointing to the line they represent. The LISP routine is set to break the line each end of the symbol. If the line n not placed on a line the LISP routin i omb.
8.7.7 CONTINUATION FLAG NV Y/
Continuations from p e drawing to another shall have con 6hq uanon flags at the beginning and end of -ene 'ne, f or each drawing. The continuati ~7 gs mai have a description line and syste contin o .
aQco the location of the inuation flags shall have i d sheet nt.mber and drawing coo n of drawing the pipe continues
' ?p% C'h p-m
.~ .~, '*
W '
<L 10 Miawxt Air twx r- ) *f cwilarlw nAc I
\ (2775-N85 SH.2A2 l ,, ,
_.. Nf E/P} l F, ; 9021 ,
j i\
')
- e
! E770-G-085 Sw.2 57' I I 4
t Tsw M!haEWT AIR 4Arinc COVTio11M /2A: l
'70 LCV-11-;ES (2998-C-081 SH.1 (G16) {
p WFM
/ C%71UTIM /2AC
- -12[ ,
-]N.
~ .
l 2935-:-250 E' .20' i
/ ' 5) i j
! 'v/ i j l FEEDWATER PJVP 28
- L z
5 Fi;;r.:re FD.1:
5 1 E l 5 >;
5
~ 1 b
1
1 1
STANDARD STD-D-3.15 l Rev. 1- .
NUCLEAR ENGINEERING DEPARTMENT l ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS l Page 3 0 of 32 l 8.7.7 CONTINUATION FLAGS (Continued) l l
Continuation flags for Instrument Air continuations shall have two separate flags that show the continuation to and from the drawing "g-085." Continuation flags that continue to the Instrument Air drawing from another drawing shall only have the Instrument Air drawing and sheet number and drawing grid coordinates. Flags that are on the Instrument Air drawing a'n d continue to another drawing shall have a description, drawing and sheet number and drawing grid coordinates.
Pumps that have necming f1ow from another system shall have a continuation showing the system, drawing and sheet number and drawing coordinates. See figure FD.12 f or examples of all continuation flags.
9.O SYMBOLOGY l
, Flow diagrams shall depict equipment, ;;;;ng, valves, 1
instruments, etc by the use of standard symbology in t
accordance with the Flow Diagram - Legend of Symbols, drawing 2998-G-076 Shee 100. l l
< 1 In addition :: the Legend of Symcc.s, :ne Au:cCA: based menu l program's tablet nenu >;:.11 :cn t a ir- S._ syr2clogy used for drawing and revising the It. Lacte un : . i : f':w c:agrams.
) .efer :c at:achmen: "5" fcr ar examp.e :f m=nu tablet.
s i
The symbol legend wi.1 cnly be shown en drewing 2996-G-078 Sheet. 100. Syrbols that ure used repeatedly wi.. " ave an
. i AutoCAD block created w:.th ne apprcpriate at:ributes. The CADD Coc"* -=*' #~ ""~'=a- r 7--ca
- ="=~
-=er- ='"'e
-=
for the maintenance :f ex.s. ng Ficw ::agrar syrrc'.s and the creat.cn cf .=w syrr; .
Syric.s are .c: :: be exploded for
'i;ering their appearanze cr Cha"g ng a: r:bu:G nicrma :cn by cesigners or drafters.
o k
e 2
t l
e 5
4 2.
e E
.B _ _ . , ._n . _ _ . - - . . . . _ - - - ~ - - "
9 STANDARD STD-D-3.15 Rev. 1 NUCLEAR-ENGINEERING DEPARTMENT-
~ ~ ~-
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 FLOW DIAGRAMS Page 31 of 32 10.0 VALVE COORDINATE SYSTEM All valves shall be tracked by the coordinate system on the drawing. This information will be up loaded to Passport for referencing.
11.0 REFERENCES
A N '/
(h,'2 V The following documents are referen't , /Merein and contain information necessary to the pre atioo'of Flow Diagrams.
8770-A-001 SystemCodinggndeI.-@' L-1) ss A 2998-A-001 System Cod:.nrIndG.' kPSL-2 )
8770-B-053 Valve OpAr (
- e. L l D. t r Index (PSL-1) 2998-B-057A (PSL-2)
~
8770-G-078 Valve F iagY
%\ xich^(humberIndex s
s egend of Symbols l ;
eet ( 00 ) PSL-1) l
% ;s - ' ._
2393-G-378 NM Czaghm - Legend of Symbols
,m h.,
,-s Sheet 100 (FSL-::
.c. ..
\.d)s l 12.O RELAT M RAWYNGS/ DOCUMENTS i i
Changes N de to Flow h agrams T.a y affect the following drawings / documents wh. h T.ust be reviewed and evaluated for
- .mpa c t .
System Coding Index
'laive C; era: 10 na l ' u-t e r : n de:-
General Arrangemen: Tra...n :
F:.ging :rawings g Large Ecre F ping Isometr;;5 Small Ecre Piping :sometr; s i
j .
Instru.ent :nt:a..i ::r :sta: s s
8 2
E 5
i I
STANDARD STD-D-3.15 3.
NUCLEAR ENGINEERING DEPARTMENT ST. LUCIE PLANT UNITS 1& 2 Date 08/94 FLOW DIAGRAMS i
12.0 RELATED DRAWINGS / DOCUMENTS (Continued) l l
- Control Wiring Diagrams '
Safe Shutdown Analysis
~
+ Essential Equipment List
. Equipment Data Base (Passport)
Updated Final' Safety Analysis Report Plant Techn cal Specificaticns j . Plant Operating Precedures FPL Nuclear Division Configuration Management Manual
)
e .
i i
3 k
e E
3 m _ _
-_ -- . - ~ - - - - . . - - . - - - . .
, 9 P.
i !
e-A I
205 W a ei t e anagemen t and Chenical and Volume Control System
)
2De Fnsin cred bafet. Feat.7as Systems The heating ventilatit. control board ( P/( E ) and plant auxiliary boards are f free standing ve-ti:,C. 'a n a r d.s with contrn; sw i t c h e e, , indiccting and record-
.ng display in:::i umer a : ion on the front <! tne boards. For a discussion l of plant heatt: ventilatinu and air coaditioning systems see Section 9.4, !
2 The Plant Auxilier) 0 ;rol heard in one ranti section of heating-Venti-i lating and Planc Au;;il ' aries Control Bocro. On the safety sections of the board (SA and Sh reet;.a), two salc ty-re: utec redundant annunciator LA and )
LB and atmospherac steeri dump controls are located. Tne atmospheric steam dump controls at o duplicated here an a t ackup to the controls located on RTG ;
board 202 cud ".' Hot 25ut down pane l . The tafety section is separated from j the non-sa fety - c t s : sf the plant uexiitary control board in accordance with Regulatorv Gntre 1.75 (b1) (refer ta FSAk Tabic 7.5-1).
The hot shurdcwn ?'nel is a free standic wnt; cal board .it. cesaroi switches sad indicati;g .iisplay instrumentation on the f ront of the board.
For a discussion of en ergency shutdown f rom out side the control room see Subr etion 7.4.1.5.
The display instrurnent , switches and indicating lights are functionally grouped on the boards and identified with nameplates for each component.
The safety related display instrumentation located on each of the above mentioned boards are listed in Table 7.5-1, b) Annunciators The annunciator vindows are located on the upper vertical portion of the RTGB and ifVCB and are functionally grouped and f orm non-safety display nits.
The annunciator ,sindows on each board are associated with the systems havi., instrumentation and/or controls on that same board.
The annunciator initiating circuits, generated by the Class IE devicee are connected to the annunciator logic through isolation. de-vices.
Safety related ununciator window display units are provided on the plant auxiliary board with 16 windows for channel SA and 16 windows for channel SB. Table 7.5-3 lis,ts the safety related windows. -
e.. Audible alarms, together with visual displays, alert the operator of departures from normal operating conditions, such as trips, by-passes, overrid is of-WaTety signals or ment faults. The arrangem Je L-af .ununcigtor windows is s own n igure li ted in FW, M V M Wd W{e gable <.7-1. ' *
- t* s 7.5.1. Bypass en? Inoperab e Status Indication s,,
Bypass and inoperabir iatus indication for EFF and ESF support systems are located on the ?O6 MTCB. The bypass and inoperable status system is _-
7.5-5 -
I
. - - . . - ~. . _ . _- . . - . - - .- _.
i
- i
% I TABLE 7.5-3
[ J\FETY RELATED ANWUNCIATOP WINDOWS Windo'w 1
No. Actuatinc Device j LA-1 Intake Structure Water Level - Low LS-21-5A LA-2 Safeguard Pump Room B Sump Hi-Hi Level LS-06-41 LA-3 Diesel oil Storage Tank 2A Low Level LS-17-10A 4 -- LA-4 Lube Water Supply Strainers High Differential PDIS-21-25-1A1 Pressure 1A2
. LA-5 Spare '
[ LA-6 Atmos Stm Dump I sol Valves MV-08-15, (74,33)1621 I MV-08-17 Motor Overload Valves closed (74,33)1623 LA-7 Condensate Storage Tank Low - Low Level LIS-12-11 j LA-8 Safeguard Pump Raom A Sump Hi/Hi-Hi Level -LS-05-1A j s
LA-9 Diesel Oil Day 'Ienks 2A1, 2A2,. Low - Low Level LS-17-552A/553A
- LA-10 Component Cooling Water Surge Tank -J.S-14-1A 4
Compartment F Low Level ;
, LA-11 Spare l
] LA-12 Atmos Stm Dump' Valves MV-08-18A/IBB (74)1623,SS-1626-3 !
! Hotor Overload CS isolate (74)1628,55-1628-3 1 l LA-13 Condensate Stora,e Tank Low Level LIS-12-11 l l LA-14 Fuel Pool High/L:w Level, High Temp LS-4420,TIA-4420 LA-15 Containment Pres. Transmitter I-SE-07-5A,-5C,-5E d
Sensing Line A Isolation 1 LA-16 Spare
$ l l
-- LB-1 Intake Structure Water Level - Low LS-21-5B j LB-2 Safeguard Pump R.som A Sump Hi-Hi Level LS-06-40
! LB-3 Diesel Oil Stora;e Tank 2B Low Level LS-17-10B l y LB-4 Lube Water Supply Strainers High Differential PDIS-21-25-1B1, j Pressure 182 j LB-5 Spare i LB-6 Atmos Stm Dump Irol Valves MV-08-14, (74,33)1622 MV-08-16 Mote. Overload Valves closed (74,33)1624 l LB-7 Condensate Storage Tank Low - Low Level LS-12-8 l LB-8 Safeguard Pump P.oom B Sump Hi/Hi-Hi Level , M -1B .s
? LB-9 Diesel Oil Day Tanks 2B1, 2B2, Low - Low Level LS-17-552B/553B ~> q l LB-10 Component Coolin" Water Surge Tank M2 16-15,L5-10-5 '
, Compartment B Le; Level, High Level i LB-11 Spare LB-12 Atmos Stm Dump valves MV-Op-19A/19B (74)1625,SS-1625-3 ..
] Motor overload CS Isolate (74)1627,SS-1627-3 i LB-13 Condensate storage Tank Low Level LIs-12-115 l LB-14 Fuel Pool High/ Law Level, High Temp LS-4421,TIA-4421
! LB-15 Containment PresJ Transmitter I-SE-07-5B,-SD,-5F
, Sensing Line B I,olation LB-16 , Spare 3
4 4
N \ N Y\ -
h (, Q k! Q\i ff \ .
f -
i 7.5-38 pnendment No. 7 (4/92)
I f\
N\l\ Y Y Y ( \ ( )
.- - - - - .. - -_=_. - _ . - . - . - _. _ _ _ _ - - _ _ . - -. - - _- _ _ .
~
COMPLETE PCMs FOR ICW
- l l
pcm unit bcm_supplemeni _ ._ _
pcm_ title , __ __
76117 01 00 SNUBBERS FOR BARTON D/P INSTRUMENTS ON ICW SYSTEMSTRAINERS . _
77229 01 . 00 REPLACEMENT OF VENTS AND DRAINS ON ICW HEADERS WORKED ON AN ~
77232 01 00 ICW PUMP IND LUBE WATER MdDiFIC TidU I3EI 5-7 ' ~ ~
77321 01 00 00 INS A13. FITTINGS ON ICW PUMP PRESSURE G UGES SPARE ICW PUMP REPAIRS
[ l I
l 78339 01 78414 01 00 REPAIR ICW DRAINS, VENTS AND INSTRUMENTATION PIPING RUNS REA _ _
ICW FLOW ORIFICE "B" TRAIN BFI 5-6 '
78415 01 00 ~ ~
78433 01 00 ICW SER INER BODY MATERIAL CHANGE BFI 5-7 79523 01 00 ADD CURBlN AT ICW PUMPS, CST DOORWAYS AND SEAL CST PIPE TUNN 79534 01 00 BACKFLUSH LINE (ICW/CCW) STRAINER REA-SLN-56 79552 01 00 __
ICW/TCW PIPING REPAIR BFI 5-8 _ _ f 79573 01 00 ICW NON-ESSENTIAL HEADER VACUUM BREAKERS l
79615 01 00 ICW LUBE WATER - PHASE Il-VI REA-SLN-19 BFI 5-7 80069 01 00 _ _ _
ICW PRESSURE TAPS BFI 5-8 __ _
80083 01 00 FLOW MEASUREMENT OF OBCW-ICW BFI 5-8 _ __y _ l 80128 01 00 ICW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8
_ _ _ l 80128 01 02 lCW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8 80128 01 03 ICW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8 80128 01 01 ICW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8 81051 01 00 ADDITIONAL OF VACUUM BREAKERS BASED ON ICW FLOW BALANCE TEST _ _ .
81104 01 00 REPLACEMENT OF DRAINS IN ICW SYSTEM REA-SLN-153BFI 5-6 81104 01 02 REPLACEMENT OF DRAINS IN ICW SYSTEM REA-SLN-153BFI 5-6 i 81104 01 01 REPLACUMEbT OF DRAINS IN ICW SYSTEM REA-SLU-153BFI 5-6 f 82065 01 00 ICW LW RESTRAINT MODIFICATIONS REA-SLN-19 BFI 5-7 82122 01 00 ICW PUMP SHAFT MATERIAL CHANGE REA-SLN-464 ~~
82122 01 01 ICW P5P 5 HAFT MATERIAL CHANGE REA-SLN-46[
~~ ~
83001 01 00 I REPAIR CdBUTTERFLY VALVE 51-SU-2i2I1 BFI 5-9 Page 1 A
i 83001 01 01 REPAIR ICW BUTTERFLY VALVE #I-SB-21211 BFI 5-9 .
83272 - 01 00 ICW PUMP LUBE WATER STRAINER REA-SLN-530 83305 02 . 00 ICW PUMP MISSILU SHlELD REINFORCEMUNT REA-SLN-618 BFI 127- __
83343 02 00 ICW PUMP BEARING MATERIAL CHANGE REA-SLN-608 BFI 5-12 833d8 W 00 ICW PUMP IMPELLER MATERIAL CHANGE REA-SLN-608 BFI 5-14 i 83374 .,1 00 APPENDIX R ICW PUMPS CURBS REA-SLN-105 BFI 54-10 _ _
8338' 01 00 ICW/TCW STRAINER REPLACEMENT REA-SLN-660 _
83385 01 01 ICW/TCW STRAINER REPLACEMENT REA-SLij-660 _
l 84031 02 00 ICW PUMP MISSILE SHIELD LADDERS REA-SLN-618 BF1126-13 BF _
84178 02 01 ICW PIPE ACCESS MODIFICATION REA-SLN-84_77 BR 5-9 84178 02 00 ICW PIPE ACCESS MODIRCATION REA-SLN-84-77 BFI 5-9 '
84223 02 00 ICW PUMP INTERNAL COATING REA-SLN-608 l !
84223 02 01 ICW PUMP INTERNAL COATING REA-SLN-608 l
84229 02 00 2A ICW PUMP DISCHARGE SPOOL PIECE REA-SLN-85-135 BFI 5-9 i I
84231 02 00 __
ICW PUMP 2C WIRING MODlf lCATION 85008 01 00 _
ICW SYSTEM ORIFICES UPGRADE s ; !
85009 02 00 _
ICW SYSTEM ORIFlCES 85017 01 01 ICW PUMP LUBE WATER STRAlNER REPLACEMENT _ _ .
85017 01 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT 85017 01 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT 85017 01 02 ICW PUMP LUBE WATER STRAINER REPLACEMENT 85017 01 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT _ _ _
85017 01 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT 85017 01 02 ICW PUMP LUBE WATER STRAINER REPLACEMENT _
l 85017 01 02 ICW PUMP LUBE WATER STRAINER REPLACEMENT 85017 01 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT ~
l 85018 02 02 ICW PUMP LUB5 WATER STRAINEFi REPLACEMEN ~
85018 02 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT ,
Page 2 b
. _ _ _ __ _. . _ _ _ _ _ _ _ ____.._____._-.___..____._m_._
. COMPLETE PCMs FOR ICW -
I-85018 02 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT 85018 02 00 ICW PU PIUBE WATER STRAINER RUPLAChMENT 85018 02 ~ 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT
~
85018 02 02 ICW PU i.UBE WATER STRAINER REPLACEMENT 85018 02 00 IUW PUMPIUBE WATER STRAINER REPLACEMENT ,
85018 02 01 ICW PUME LUBE WATER STRAINO3 REPLACEMENT 85018 02 02 IUW PUM5 LUBE WATER STRAINER REPLACEMENT ~
85082 01 00 PROTECTIVE COATINGS FOR INTEiiNAL ICW PUMPUOLkMNS
~ ~-
85085 02 02 ICW PtjMP EXPANSION JOINT REPLACEMENT 85085 02 01 ICW PUMP EXPANSION JOINh REPLACEMENT _
85085 02 00 ICW PUMP EXPANSION JOINT REPLACEMENT _
j 85089 01 01 ICW ISOLATION VALVE REPLACEMENT HEA-SLN-663/85-135 85089 01 00 ICW ISOLATION VALVE REPLACEMENT REA-SLN-663/85-135 .
85166 01 00 ICW RESTRAINT MODIFICATION REA-SLN-663 85184 01 00 ICW PIPING INSPECTION PROCEDURE 85185 01 GO PSL-1 ICW DISCHARGE PIPE ZING ANODES REA-SLN-85-187 ~ ~ ~
85204 01 00 ICW BACKUPIUBEEATER BACKFLOW PREVENTOR REPLACEMENT _ _
86047 02 00 MISCELLANEOUS ICW MODIFICATIONS_ _.
86124 02 00 ICW LUBEWATER FLOWRATOR MODIFICATION _ j 86146 01 00 ICW MISCELLANEOUS SYSTEM MODIFICATIONS _
86148 01 00 ICW BUTTERFLY VALVEREPLACEMENT , ,
87043 02 00 ICW PUMIESELF LUBRICATIUN MUUlFICATION l 'f 87043 02 01 ICW PUMP SELF LUBRICATION MODIFICATION 87083 02 00 MISbELLANEOUS ICW SYSTEM MOblhlCATibNS 87134 01 00 ICW LUBE WATER STRAINER REPLACEMENT l-SS-21-12 ICW LUBE WATER PIPE RESTRAINTS MODIFICATIONS [
88015 01 00 ,
88016 01 00 ICW PUMP MISSILE BARRIER MODIFICATIONS
~
88048 02 OU DWG & INST LIST dURR. FOR GEN PROT RELAX FOR ICWUMP i
f Page 3 i
c -
f COMPLETE PCMs FOR ICW 88055 01 00 ICW & CW PUMP PACKING REPLACMENT DEEP l
88056 02 00 ICW & CW PUMP PACKING REPLACEMENT DEEP ,
88071 02 00 ICW LUBE WATER PRESSURE INDICATING SWITCH. DEEP. I 88122 01 00 ICW PRESSURE INDICATOR UPGRIDE 88123 02 00 ICW PRESSURE INDICATOR UPGRADE 88178 01 00 ICW LUBE WATER FLANGE REPLACEMENT NCR 6652-2163M 88228 02 00 ICW '2B' PUMP DISCHARGE ISOLATION VALVE REPLACEMENT 88247 02 00 ICW PUMP COUPLING, SPLIT RING ASSEMBLY _
88271 02 00 ICW LUBE WATER STRAINER l-SS-21-3A1 COVER REPAIR 88311 02 00 ICW SYSTEM PRESSURE TRANSMITTER PT-21-8A SPOOL PIECE 88315 02 00 ICW FLOW DIAGRAM DRAWING DISCREPANCIES _
89010 02 00 ICW STRAINER UE PRESSURE SWITCH REMOVAL 89035 02 00 ICW PIPING AND RESTRAINTS TO FIS 21-9B _ _ _
89035 02 00 ICW PIPING AND RESTRAINTS TO FIS 21-9B .
89035 02 01 ICW PIPING AND RESTRAINTS TO FIS 21-9B 89035 02 01 ICW PIPING AND RESTRAINTS TO FIS 21-9B y 89048 02 00 2B ICW PUMP COLUN SEIMIC RESTRAINTS 89052 02 00 ICW-CHECK VALVE 21-V21208 FLAPPER PLATE H1NGE REPAIR 89127 01 00 REPLACEMENT 4" ICW BUTTERFLY VALVE (1-SB-21188) 89249 01 01 REPLACEMENT OF ICW/CW STRAINER MESH _ _
89249 01 00 REPLACEMENT OF ICW/CW STRAINEF1 MESH 89252 01 00 ICW LUBE WATER STRAINER CABLE REPLACEMENT 89260 02 00 lCW SYSTEM ISOLATION VALVE RELINING 89380 01 00 ICW,CCW, SMALL BALL VALVES WITH CONTROMATICS j 89382 01 00 ICW STRAINER BACKWASH ARM MATERIAL CHANGE 89383 02 00 ICW LUBE WATER COUPLING INSTALLATION (NCR 2-303) 90041 01 00 REPLACEMENT OF ICW BALL VALVES l
90041 01 01 REPLACEMENT OF ICW BALL VALVES Page 4
COMPLETE PCMs FOR ICW -
l 90041 01 02 _
REPLACEMENT OF ICW BALL VALVES _ _
90041 01 00 REPLACEMENT OF ICW BALL VALVES
. 01 90041 01 REPLACEMENT OF ICW BALL VALVES 90041 01 02 RUPI.ACEMENT OF ICW BAL[ VALVES 90044 01 , 00 [ ~RbMOVAL OF ICW VALVE SH-21374 f' 90051 01 00 CHANGE IN MATERIAL FOR ICW CHECK VALVE 90060 01 00 ICW PUMP 1C DISCHARGE ISOLATION VALVE REPLACEMENT _
REPAIR OF VERTICAL CONDUlTS AT INTAKE, CCW, AND ICW '
90129 02 00 i 90129 02 01 REPAIR OF VERTICAL CONDUlTS AT INTAKE, CCW, AND ICW _
90129 02 00 REPA@ OF VERTICAL CONDUlTS AT lNTAKE, CCW, AND ICW _
j 90129 02 01 REPAIR OF VERTICAL CONDUlTS AT INTAKE, CCW, AND ICW 90133 02 09 _
ICW PUMP BUILDING ROOF HANDRAILS ,
t 90141 02 00 ICW LUBEWATER COUPLING INSTALLATlON .
j 90157 02 00 RPELACEMENT OF TI-21-12 A& B ICW 90178 02 00 ICW PUMPS 2B & 2C SELF LUBRICAilNG MODIFICATION 90178 02 01 ICW PUMPS 2B & 2C SELF LUBRICATlNG MODIFICATIONS _ _
90178 02 02 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION _ _ _ , i 90178 02 00 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION l
90178 02 01 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION__ _
90178 02 02 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION 90178 02 00 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFlCATION _ __
90178 02- 01 ICW PUMPS 28 8. 2C SELF LUBRICATING MODIFICATION __ _
j 90178 02 02 ICW PUMPS 28 & 2C SELF LUBRICATING MODIFICATION 90213 02 00 CW & ICW PUMP PACKING REPLACEMENT l 90227 01 00 MONEL 400 MATERIAL AS SUBSTITUTE IN CW/lCW PIPE SYS.
90241 01 00 CW AND ICW PUMP PACKING REPLACEMENT i 90273 02 00 MONEL 400 MATERIAL SUBSTITUTE FOR ICW/CW PIPING SYSTEM -
90280 01' 00 ALTERNATE ICW & CCW PUMP DISCHARGE CHECK VALVES .
I !
Page 5 !
0
COMPLETE PCMs FOR ICW .
l 90284 01 00 ICW LW-42 RESTRAINT REPLACEMENT .
90325 02 00 USE OF TITE-SEAL GASKET SEALING COMPOUND IN ICW APPLICATICT43 __ ,
90327 02 . 00 2A ICW MOTOR LOWER END SHIELD REPAIR _ _
90327 02 01 2A ICW MOTOR LOWER END SHIELD REPAIR 90327 02 02 2 h MUTOR LOWER END SHIELD REPAIR i 90327 02 00 2A ICW MOTOR LOWER END SHIELD REPAIR 90327 02 01 2A ICW MOTOR LOWER END SHIELD REPAIR 90327 02- 02 2A ICW MOTOR LOWER END SHIELD REPAIR !
90327 02 00 2A ICW MOTOR LOWER END SHIELD REPAIR _
90327 02 01 2A ICW MOTOR LOWER END SHIELD REPAIR _
90327 02 02 2A ICW MOTOR LOWER END SHIELD REPAIR _
j 90355 02 00 ICW PUMP MOTOR LEAD TERMINAL LUGS I 90426 G1 00 HARD CAFID EVALUATION M&S 008-56996-7(ICW STRAINER) f 91030 01 00 ICW STRAINER SUPPORT REPAlR 91030 01 01 ICW STRAINER SUPPORT REPAIR _
91030 01 00 ICW STRAINER SUPPORT REPAIR 91030 01 01 ICW STRAINER SUPPORT REPAIR l
91078 01 00 ICW PUMP COLUMN PROTECTIVE COATING 91177 02 00 ICW & CCW VALVE TAG DISCREPANCIES .
91238 01 00 ICW F5 UMP DISCHARGE CHEbi[ VALVE [
91285 01 00 ICW PUMP MOTOR STATOR MATERlALS UPGRADE __