ML20216D117
| ML20216D117 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/28/1998 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20013F498 | List: |
| References | |
| NUDOCS 9803160279 | |
| Download: ML20216D117 (33) | |
Text
(
l EXHIBIT G l PRAIRIE ISLAND NUCLEAR GENERATING STATION License Amendment Request dated March 6,1998 l
l l
Westinghouse Letter NSP-98-0120 Rev 2 February 1998
" Prairie Island Units 1 and 2 COMS Setpoint Analysis" NON-PROPRIETARY VERSION l
l l
l I
1 9803160279 990306 PDR ADOCK 05000282
[ P PDR I
Westinghouse Non-Proprietary Class 3 PRAIRIE ISLAND UNITS 1 AND 2 I COMS SETPOINT ANALYSIS (FINAL, REV. 2) -
WESTINGHOUSE ELECTRIC COMPANY P O. Box 35 Pittsburgh, Pennsylvania 15230 C1998 Westinghouse Electne Company All Rights Reserved
( ,
Westinghouse Non-Propnotiry Class 3 PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS (FINAL REV. 2)
- 1. INTRODUCTION.. .
.1
- 2. DISCUSSION . .. . ..-.. . . .1
- 3. RESULTS .. .
.3
- 4. CONCLUSIONS. .. . .. ,
. . . . . . . .. . . . .4 TABLE A - MASS INJECTION TRANSIENT RESULTS . .. . .5 TABLE B - HEAT INJECTION TRANSIENT RESULTS.. .. . . .5 TABLE C - PEAK RCS PRESSURE AND MARGINS. . .. . . . . .. .. . .. . .6 TABLE D -- PRAIRIE ISLAND UNIT 1 (NSP) STEADY STATE HEATUP/COOLDOWN CURVE D ATA WITH ADJUSTMENTS. . . . . .. . . .. .7 FIGURE 1.. . .. . . .. .
.9 FIGURE 2.. . .
.10 FIGURE 3.. . . .. . .. . .. . . . . .11 ATTACHMENT A - TABULATION OF COMS INPUT ASSUMPTIONS . . . .. . a12 ATTACHMENT B - COMS INSTRUMENT UNCERTAINTY CALCULATIONS . . . .1#
Pagei
1
\
Westinghouse Non-Propnetity Class 3 PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS (FINAL, REV. 2)
{
1
- 1. INTRODUCTION Westinghouse was requested by Northern States Power Company to perform analyses of the Mass injecton (MI) and Heat injection (HI) events and to evaluate the Cold Overpressure Mitigaton (COMS) ;
setpoint for Prairie Island, Units 1 and 2.
I Both Prairie Island units have a single Power Operated Relief Valve (PORV) setpoint of 500 psig. It is desired that this setpoint be maintained in order to minimize changes to plant operating procedures. As such, Westinghouse has determined the allowable number of charging / safety injection pumps which can i be operable when COMS is enabled. Results of the mass injection analyses indicate that the current PORV setpoint of 500 psig will continue to protect the revised Appendix G Limits (35 EFPY) for both Unds 1 and 2, with up to three charging pumps in operation for the full range of pressureMemperature conditions when COMS is enabled. The current setpoint can be maintained with a Safety injection pump and a maximum of three positive displacement charging pumps in operation for an P.OS temperature greater than or equal to 200*F when the COMS is operable. Furthermore, the Appendix G limits are shown to be protected during the heat injection transients over the full range of RCS temperatures in which COMS is enabled up to an RCS temperature of 310*F.
- 2. DISCUSSION At relatively low temperatures (less than approximately 350*F) two potential overpressurization transients to the Reactor Coolant System (RCS) have been defined as the design basis for COMS. Each of these transients assumes that the RCS is in a water-solid condition and that the Residual Heat Removal System (RHRS) is isolated from the RCS.
The first transient is a heat injection scenario in which a reactor coolant pump in a single loop is started when the RCS temperature is as much as 50*F lower than the steam generator secondary side temperature. This results in a sudden secondary to primary heat transfer and rapid increase in primary system pressure.
The second design basis transient is a mass injection event, caused by the failure of the normal charging controls to the full flow condtion (or inadvertent startup of a safety injection pump) with simultaneous isolation of the RHRS and letdown. The influx of flow into the relatively inelastic, water solid RCS also results in a sudden increase in primary system pressure.
The LOFTRAN code was used to model both the heat injection and mass injection events.
Based on current Westinghouse methodology as outlined in WCAP 14040, Rev. 2, and input from Northern {
States Power Company, the following major assumptions are relevant to the mass injection and heat
! injecton analyses (these assumptions are presented in tabular format as Attachment A):
- 1. The mass injecton event is relatively insensitive to injtial RCS temperature, but is limiting at lower RCS temperatures. An initial RCS temperature of 68*F is assumed for the mass injection event. The heat injecton event is very sensstrve to RCS temperature and a sensitivity study is performed for initial RCS temperatures between 70*F and 310*F (secondary steam generator temperatures between 120*F and l Page1
Westinghouse Non-Propri:tiry Class 3 i PRAIRIE ISt.AND UNITS 1 AND 2 i
COMS SETPOINT ANALYSIS (FINAL, REV. 2) 360'F). The heat injection event is more limiting (resulting in higher system pressures and overshoots) i at higherinitial RCS temperatures.
- 2. The mammum flow delivered by one positive displacement charging pump is 60.5 gpm (flow for two pumps equals 121 gpm). The maximum flow delivered by three charging pumps is 181.5 gpm. The flow delivered by one safety injection pump is 835 gpm at an RCS pressure of 500 psig.
- 3. In order to preserve the single failure enteria established by IEEE-279, failure of one PORV is assumed.
One Copes Volcan Pressurizer PORV (design Cv=50) is available to mitigate the transients. Flow is linear with valve travel. A stroke open/close time of 3/3 seconds is assumed.
- 4. The setpoint of 500 psig must protect the 35 EFPY Appendix G limits for both unts. Since overpressure events are most likely to occur when the vessel is at isothermal conditions, the steady state Appendix G limits are used for the design of COMS. This is consistent wth WCAP-14040, Rev. 2, which has been endorsed by the NRC.
- 5. ASME Code Case N-514, which permits a 10% relaxation of the Appendix G limits below the COMS enable temperature, is applied in this evaluation of the setpoint. Note that the Code Case has not been genencally approved by the NRC as part of the WCAP 14040 methodology and therefore requires plant specific approval. The code case further permis a COMS enable temperature corresponding to a reactor vessel metal temperature of 200*F, or less than RTuor+50*F, whichever is greater. RT~or is the highest adjusted reference temperature for weld and base metal in the beltline region at a distance one-fourth of the vessel section thickness from the vessel inside surface, as determined by Regulatory, Guide 1.99. Revisbn 2. The minimum acceptable enable temperatures have been defined by Westinghouse as 225'F and 205'F for Units 1 and 2, respectively.
1
- 6. The evaluation conservatively accounts for plant specific pressure uncertainties. The channel statistical i allowance for the wde range pressure transmitter is 57 psi. (See Attachment B for more detail on l instrument uncertainty calculations). Note, the wide range cold leg temperature instrument uncertainty of 28'F, was not applied in the analysis, as the NSP COMS is not temperature actuated. Additionally, )
heat transport effects, which account for a 50 F temperature difference between the reactor vessel and l the wide range temperature transmiter, was not applied for the same reason. Northem States Power Company will procedurally account for temperature uncertainty, where applicable.
- 7. The evaluation of the setpoint accounts for the pressure difference (Delta P) between the wide range pressure transmater and the reactor vessel mid-plane. With one Reactor Coolant Pump in operation, this pressure difference is 31.1 psi; wth two reactor coolant pumps in operation, this pressure drrference is 61.1 psi. The pressure difference is based 0% steam generator tube plugging (conservative), a flud temperature of 68'F and the wide range pressure transmitter located 6.7 feet below the centerline of the hot leg pipe.
- 8. The RCS is assumed to be enclosed by a non-yielding, inelastic boundary, wth the pressurizer water solid and at the same temperature as the reactor coolant. This mammizes the pressure overshoots dunng the design basis transients.
- 9. The mass injection event is conservatively analyzed with 15% Steam Generator Tube Plugging. The heat injection event is conservatively analyzed with 0% Steam Generator Tube Plugging.
( 10 The parameters consdered in the analysis are consistent with those identified in WCAP 14040 Secton 3.2.1.
Page 2
Wutinghouse Non-Propri;tiry Class 3 PRAIRIE ISLAND UNITS 1 AND 2 j
COMS SETPOINT ANALYSIS (FINAL, REV. 2)
- 3. RESULTS Results of the mass injection analyses are summanzed in Table A. Pressure extremes are tabulated for mass injection rates between 60.5 gpm and 1016.5 gpm. These rates correspond to vanous combinations of charging and Si pump flowrates. The minimum rate of 60.5 gpm corresponds to 1 positive displacement charging pump, and the mammum rate of 1016.5 gpm corresponds to 1 safety injection pump and 3 posarve dsplacement charging pumps. Intermediate flows of 181.5 gpm and 835 gpm correspond to operation of 3 positive placement charging pumps or 1 Si pump, respectively.
Wah the em:eption of the final three cases, all mass injection analyses were performed for an initial RCS temperature of 68 F. The final three cases were performed for an initial RCS temperature of 200*F in order to confirm that the Safety injection pump and Safety !njection Pump plus 2 or 3 charging pump configurations are acceptable at RCS temperatures as low as 200*F.
Results of the heat injection analyses are summarized in Table B. While the minimum COMS enable temperature has been calculated to be 225'F for Una 1 and 205'F for Unit 2, the current enable temperature for Prairie Island Unds 1 and 2 is 310*F. As such, the heat injection transient was analyzed for the inadvertent startup of one reactor coolant pump between RCS temperatures of 70*F and 310'F (steam generatcr temperatures between 120*F and 360*F).
Table C summanzes results of the setpoint evaluation and available operating margins for the single PORV setpoint of 500 psig. A descrption of each entry in the Table is provided below. Note that Table D provides-a detaile:I tabulation of the heatup and cooldown curves and adjustments:
- a. A companson of 35 EFPY steady state heatup and cooldown curves from Units 1 and 2 indicates that the Una 1 curves are limiting. The limds applicable to temperatures assumed for the mass injection and heat injection analyses are shown in Column A of Table C.
- b. In Column B of Table C, the limds have been adjusted for the minimum of the 800 psig piping limit or ASME Code Case N-514 which permas a 10% rela >ation of the !imits below the COMS enable temperature. Figure 1 illustrates the steady state limit, wth and without the Code Case, superposed wah the PORV piping limit. At temperatures of approximately 145 'F and above, the !
pping lima is bounding. Note that the PORV piping limit in COMS design is based on an analysis of j water hammer effects on relief valve piping for certain classes of rapidly opening relief valves (i.e., Garret valves) during water solid conditions. As other PORVs, such as Copes Volcan valves I used at Prairie Island, have relatively slow opening and closing times, water hammer effects are greatly reduced or effectively eliminated when compared to the Garret type valves. Note, the PORVs at Prairies Island have a stroke time of 3 seconds. The practice of taking conservative results of the Garrett analysis and applying them to all COMS setpoint evaluations is consistent wdh Westinghouse methodology.
- c. Adjustment for the delta-P are shown in Columns C and D of Table C, for one or two reactor coolant pumps in operation. These values, along wah Figures 2 and 3, represent the mammum allowable RCS pressure dunng the mass injection or heat injection events.
- d. Columns F and G of Table C indicate the operating margin to the adjusted limits, both wdh 1 and 2 reactor coolant pumps in operation.
l l
Page 3
l Westinghouse Non-Proprietary Class 3
{
- PRAIRIE ISLAND UNITS 1 AND 2 l COMS SETPOINT ANALYSIS (FINAL, REV. 2) !
l l I
- 4. CONCLUSIONS
{
l Results of the analyses indicate that the current setpoint of 500 psig is acceptable for both Prairie Island Units, for the following plant configurations:
- 1. The analyses performed for the mass injection event support the current setpoint of 500 psig for operation of a mannum of 3 charging pumps below an RCS temperature of 200*F. At l RCS temperatures greater than or equal to 200*F, a single safety injection pump plus 3 positive displacement charging pumps is acceptable.
l l 2. Adequate margin to the Appendix G limits is also available over the range of temperatures analyzed @ 310*F) for the heat injection transient. 1
- 3. Results are applicable for both 1 and 2 reactor coolant pumps in operation over the range of temperatures when COMS is enabled.
l l
l l
} Page 4
0 T 6 J 0000 EO /
0 7728 _
RO 1 61 31 UHi )
873 3 SSs 1 35 5 690 S )
)
s S Rp 222 6 533 T s E E( 0 S ie RD L e 5 -
t n PN U in t 3 2264 T ia 661 8
/
L U S ia 0 0 61 31 U tr E t r
e 3 S ce
- R c E n ME T nU 0 R U U UgR) 2375 N 0 9973 3 T n t
MI Sis 8643 41 0 467 E n t
3
/ 1 1 90 s N en NSp 2224 444 I e 0 61 22 l
s2 ADS E I
r u
I E(
MR S N um 5
2 P r CNI S S r A t R ns t
yA r
Y N sn T 0
5 a1 L A I EO T I o 2 9 28 t
eS A) R o R / 7 9 90 i
rT N2 pI A . V T N S O)
U Hi 26 45 1 36 N N O F .
0 0 5 7 22
- _
S RSs 1
2 oN N F. (p 1 23 046 I T 0 -
PrU NR TE E E 2 222 5 O 0 I
RV C 1 0 e n DIO L ,
T 86 P O E 3 0 2 2 2 00 g oN P A C = J o a 5 4 91
/ 4 NAL T N E a E N t 0 22 P z F 5 eS sI SF EI J n R I
T 0 1 u ( N e K U )g 1 264 36 oES I T ASi ESs 1 235 1
046 A 7 0 hRM I
gI S =
s P E (p 5557 775 E = 5 nA O S c a R H sc 1
/
3 3 73 2 81 t
is R C A T P - T a 0 0
5 2 22 eP M t n
)) B t. 1 W - e Ss / 2 20 37 2 45 2.0 1 o I Sm 1 836 6 31 E in o 0 A p t e WI
((
b 465 8 1 2 1
1 1
1 34 1 1 L
B e t p 2 1
6 6 173 8 E s A s
/
0 1
5 1 22 L g N 7 T g B
A is p
O I
) ) is T F ) _
T 00 C F
'
- p F -
8 0 5 0 (*
6=02
- 5. 0 55 5 E JTE )m 0 566 0 -
(
nap 1 3 2 351 5
( G .
.o t .
I R (e s61 8 8 c 1 =89 s
c 0 S st soso S a a 1 T eo sh S T T
/
S rhe s
( r r .
A (
C PsPe r M R xe avinnd .
T MOMU _.
s
) P 5 g G C 87 974 52 31 1 80 31 nn i)
( R 21 2- 953 24 72833 1 21 1 1 ia r gi t
s 2 r
e ap .
pM ( t i
O )
P 5 im F C 8738 974 S2 31 1 80 l
( R 5431 953 E7 02833 221 1 1 g -
1 in ip e
r p
k u )g ) ig S asiE 1 264 1 36 6329920 s Pess
) 1 235 046 1 2471 67 N 4 I 1 er (p ( 5557 777 5555666 p G 5 P 0
- 0 R
A N 8 e -
e e h M sa l t r
D C ba "* s o N e we P 6666 000 8060000 e 3 )
s A do l oru D
(
CR 8888 3333 000 000 0540000 461 0000 s
a s2 As s l .
5555 888 5578888 CP ADS E C e 2 l
CNI S R d mr uP dl ea t yA Y U n oe r
a1 A)
L S a imS CD t S P xC ed eS E at a R )g ) P nT N2 C 6666 000 8 0 6.0 0 0 0 hn g a pI A V. R e M isC 8888 000 0540000 t
- R oN NR PrU TE P D (
p(
1 6666 5555 000 888 7940000 5578888 nt iyin y
6 S s e
n DIO ,
C e lpta g L e" oN P pr a TA 7777 0.0 0 91 00.000 NA R i t
)de B a e P o s r c N 6666 000 8300000 eS L sI SF EI K ina t
(
C Ca 5555 6666 000 888 5800000 6688888 eU n A r t E ce
(
uES f
oI ae it r hRM gl P n U
t i
msu oAR O - t ei m h s C en GrPe t
t s C aL .
S G )g )
t eP 77 x W E L u m yixiA s 7777 9999 1 1 1 000 000 91 7 925 00 1 0 05 66 33 ir do r d d P( 5555 567 22 nf B s t a
e en(
1 1 1 1 1
> > es A I n t Sp p pt pn T ha Aem _
A dt
(
w ) esu t
mpm
) sl
- )
)
p g jaud
- )
t n m )mmp g5 t F d e p pg) n* ahd 66 e( e vFg g E- 8 5. 1 5. m p F)m51 0 9 0 ve Er u hw t
it n60218g 0 pg (g (1 2 nt a f om io S(= 6 (1 1 5 = 5i ng ore0 000000 i mL t
cCg g(g8 3 S3gn r i i
t c p7 050501 e
jRa i n(n n C(ha8ag r om 1 1 2233 uG -
nTg rgir igS RI TSCh inTe l
mx i
sAh aar t
ha1 t 12C indi in s h A +3 t
aS me a CC 1 2 C
i+ HR eC ep M 3 Si hp 1 S TA '
1
}
Westinghouse Proprietary C! ass 2C PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS (FINAL. REV. 2)
.a.c TABLE D - PR AIRIE ISLAND UNIT 1 (NSP) STEADY STATE HEATUP/COOLDOWN CURVE DATA WITH ADJUSTMENTS I
l l
l l l
I Page 7
L-Westinghouse Proprietary Class 2C
, PRAIRIE ISLAND UNITS 1 AND 2
- COMS SETPOINT ANALYSIS (FINAL, REV. 2) l
- d.C TABLE D - PRAIRIE ISLAND UNIT 1 (NSP) STEADY STATE HEATUP/COOLDOWN CURVE DATA WITH ADJUSTM i
l l
i 1
e I
1 I
f i
Page 8
l l
Westinghouse Non-Proprietary Class 3 PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS (FINAL REV.2)
FIGURE 1 Steady State HU/CD Curveswithout Margins (with and without Code Case N 514) 2400 4 1900 1
~
y ;
1400 1- ---------- - -.--xx- -- - --
A 400 60 110 160 210 260 310 Temperature (Oeg.F) -
Code Case 4514 Steady State HU/CD -..-. PORV Piprq Lmt i
Code Case Applicable up to 200*F (Note: PORV piping limit of 800 psig limiting at Tacs>145'F) l l
1 l
Page 9
I-Westinghouse Non-Proprietary Class 3 l PRAIRIE ISLAND UNITS 1 AND 2 l COMS SETPOINT ANALYSIS l (FINAL, REV. 2) l FIGURE 2 Maximum Allowable Pressure (Mass injoction Event) 900 -
800
, sY f700 !
- i. .
3 .._ .
[
I E /
500 400 60 110 160 210 260 310 Temperature (Dog.F)
)
i l 4 l
i Page 10
)
Westinghouse Non-Proprietary Class 3 PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS (FINAL, REV. 2) l FIGURE 3 Maximum Allowable Pressure i (Head injection Event) 900 800 700 /
i i 8 f
i a /
500 l l
400 60 110 160 210 260 310 ,
Temperature (Dog.F) 2 RCPs 1 RCP Page 11 l
Westinghouse Non-Proprietary Class 3 PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS
, (FINAL REV. 2) l ATTACHMENT A - TABULATION OF COMS INPUT ASSUMPTIONS Mass Iniection Event:
Initial RCS Temperature: 68'F Mass injection Rate:
1 Possive Displacement Charging pump 60.5 gpm 2 Positive Displacement Charging pumps 121.0 gpm 3 Posdive Displacement Charging pumps 160.0 gpm High head Safety injection pump 835 gpm @ RCS pressure of 500 psig Steam Generator Tube Plugging: 15%
PORV stroke open/close time: 3 seconds open / 3 seconds close -
Valve Cv: 50 Pressure Uncertainty: 57 psi Delta P between Vessel and Wide-Range Pressure Transmrtter:
(based on a fluid temperature of 68'F and wide-range pressure transmitter elevation of 6.7 feet below the hot leg centerline) 1 Reactor Coolant Pump 61.1 psi 2 Reactor Coolant Pumps 31.1 psi l
f l
Page 12
r i^
i Westinghouse Non Proprietary Class 3 PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS (FINAL, REV. 2)
ATTACHMENT A - CONT'D TABULATION OF COMS INPUT ASSUMPTIONS Heat Iniection Event:
Initial RCS Temperature 70 'F 310 'F Initial Steam Generator Temperature 120'F-360*F (SG temperature 50*F higher than RCS temperature)
Steam Generator Tube Plugging: 0%
PORV stroke open/close time: 3 seconds open / 3 seconds close Valve Cv: 50 -
Pressure Uncertainty: 57 psi Delta P between Vessel and Wide-Range Pressure Transmitter-(based on a fluid temperature of 68'F and wide-range pressure transmdter elevation of 6.7 feet below the hot leg centerline) 1 Reactor Coolant Pump 61.1 psi 2 Reactor Coolant Pumps 31.1 psi Page 13
Westinghouse Non Proprietary Class 3 PRAIRIE ISLAND UNITS 1 AND 2 COMS SETPOINT ANALYSIS (FINAL REV. 2) l ATTACHMENT B - COMS INSTRUMENT UNCERTAINTY CALCULATIONS a
Page 14
Table of Contents t
Title Page
..................................................................................................................1page l
Table of C on ten ts . . . . . .... .. . . .. ... ..... ... . ..... .. ... .. .. . .. . ... .. .. . .. ... . . .. . . . . . . . .. . ... .... . . . . . . .. .. . . . . .. . . ..
Ex ecu tive S u mm a ry . . . . . .. . . .. .. . . . . . ...... .. . . . . . . . . .. . . . . .. . . . . . .. .. . .. .. ....... .. . .... ... .. ... .. . .... . .. .. .
Appendix A Temperature Uncertainty Calculation ................ ..... ................................ 5 pages index of input Variables .... ......................... ... .......... ............... .... .. . . ... ...... (5 of 5) l Appendix B Pressure Uncertainty Calculation ...... ....................................... .............. 3 pages Inde x of input Variables ................ ......................... ........ .................... ........ (3 of 3)
Appendix C Block Diagram of Overpressure Protection System ............................. ... 2 pages Appendix D index of Docum ents R eviewed................................................................... 1 page l
i I l 1
}
l l
l oM033rmprop doc:142'698 i
Prairie Island Units 1 & 2 L
COMS Instrumentation Channel Statistical Allowance j Executive Summary To support the COMS work for Prairie Island Units 1 & 2 the uncertainties for the temperature and pressure input to COMS were calculated. Summaries of those calculations appear in Appendix A for the temperature and Appendix B for pressure uncertainty.
Prairie Island specific procedures were reviewed along with documentation on file at Westinghouse. The Block Diagrams for the Overpressure Protection system are included in Appendix C. An index of the information reviewed is attached as Appendix D.
In summary, the RCS Loop A wide range pressure transmitter uncertainty was calculated to be
[ ]***. There is no specific reason for the large uncertainty other than the 3000 psig instrument span.
Temperature uncertainty was calculated to be ( ]**'. This value includes a [
]*" allowance for streaming. This value is based on [
]*". Previously this value was based on an instrument span of 700*F with an allowance of [ ]*". For these calculations the
[ ]*" is adjusted for the 650'F span at Prairie Island. Some research was conducted in an attempt to reduce the [ ]*". A review of the RTD spacing, RHR and RCS piping layouts, and the expected operating conditions where the COMS would be required provided no justification for establishing a new value. The [ ]*"is used in this calculation.
The remaining uncertainty appears large due in part to the method of calibration,i.e., modules are individually calibrated, no string calibration.
Although the majority of the documents reviewed and utilized for these calculations were Unit 1, the analyses are applicable to both units based on the assumption that Unit 1 information is representative of Unit 2 configuration and hardware.
i l
ovo33nonpmo ooc:1b-2/sse Page 1 of 1
! ' Appendix A i
l l
t O WO33 doc;1>2/5/98
1 RCS Wide R nge Tempercture untertainty callulations for Prairie Island COMS (OPPS)(analog racks)
Description:
These calculations are to determine the COMS temperature uncertainties. Only one loop is used, i.e., no average is credited for multiple loops. Hot leg RTDs are not used and therefore not included.
Calculations are performed in the wide range temperature span. Rack ,
terms are included to account for Wide Range RTD, R/E, E/E, E/l and bistable for actuation.
Instrument span.
Ton. = 700 - 50 *F Temperature span in Degrees F reference SE-lCAT(96)-304 SP 1224 Rev.16 page 26.
Ton, = 650 *F Process Measurement Accuracy Uncertainties (AT)
~
+ 4,C RTD uncertainties
+ a,e l
l l
o wo33 doc:16M9e Page 1 of 5
l* R/E uncertainties Foxboro 2A1 P2V.
l -
+4.C i
j i
I i
l omooc:1&2/54e Page 2 of 5
Cclibr: tion of tha wide rcnge E/E Foxboro 2AO val j Reference SP12241TM-450BB,0.05 VDC on 0 to 10 VDC span 1
+a.c l The M&TE allowance for the bounding worst case equipment per Prairie Island comments is l
ualized .
+a.c I
Wide range E/l calibration module Foxboro 694AC-OAW6 Reference SP1224 ITM 409,0.2 ma on 10 to 50 ma span
.a.c Output or bistable, again is independently calibrated and the m&te is applicable only to the input as the bistable change of state is a go or no go status with little uncertainty about the result.
Note all settings have the same tolerance.
+4.C
~
Cable IR term to reflect effects of adverse containment temperature.
+a.c l
1 j
i l
l I
l I
l l
o9033 occ:ttr2/s/9s Page 3 of 5
I-Cciculated Temperature Uncertainty The overall temperature CSA is based on no string calibration, and includes only one term for rack temperature effects and rack drift.
.a.c
~
I i
i l
l l
l l l I
l l
oM033 doc:1b-2 M MI Page 4 of 5
. Temperature index cf input V riables Ton.= 650*F Variable for the effective span of the RTDs.
.a.c Variable for the allowance of streaming due to inadequate mixing of different water temperatures Variable for the accuracy of the maintenance and test equipment used for calibrating the RTDs.
Variable for the allowance of the accuracy of the RTDs without periodic cross calibration Variable for the allowance of RTD drift.
Variable for input rack maintenance and test equipment accuracy.
Variable for output rack maintenance and test equipment accuracy.
Variable for the combination of the rack maintenance and test equipment.
Variable for the combination of the rack maintenance and test equipment for the RE module.
Variable for the calibration tolerance of the RE module.
Variable for the combination of the rack maintenance and test equipment for the EE module. -
Variable for the calibration tolerance of the EE module.
Variable for the combination of the rack maintenance and test equipment for the El module.
Variable for the calibration tolerance of the El module.
Variable for the combination of the rack maintenance and test equipment for the Bistable.
Variable for the calibration tolerance of the Bistable.
Variable for the process rack temperature effects.
Variable for the process rack drift effects.
Variab!e for the process rack drift effect for the RE module.
Variable for the process rack drift effect for the EE module.
Variable for the process rack drift effect for the El module.
Variable for the process rack drift effect for the Bistable module.
Variable for the effects of adverse environment.
Variable for the channel statistical allowance.
l l
! o9033 occ:m 2/sse Page 5 of 5
. Appendix B l
l l
0:WC33nonprop. doc:1b-L'5/98
RCS Wide Rrnge Pre cure in:trument Uncertainty C:l:ulatinn3 f r Prairie Island COMS (OPPS)(Analog Process Racks)
Introduction. This document contains uncertainty alculations for Pressurizer Pressure COMS input.
Definition of inputs and Assumptions The span of the RCS Loop A Wide Range Pressure Transmitter per Reference SE-ICAT(96)-304 (Note this document is an intemal Westinghouse letter transmitting inputs to Safety Systems Operations in order to perform this analysis:
PP_USPAN = 3000 psig PP_LSPAN = 0 psig PP_ SPAN = PP_USPAN - PP_LSPAN Instrumentation Uncartainties (all values are in percent span)
Process Measurement Accuracy (% span) ,
( )...e Primary Element Accuracy (% span)
( )...e
~
Transmitter uncertainty terms Rosemount data sheet 2514 Model 1154GP9RC.
Sensor calibration accuracy (% span) per input summary confirmed with calibration procedure sheet. __ _ ...e Sensor reference accuracy (% span) per specification.
g )....
! Per SE-ICAT(96)-304 summary 3 psi M&TE. Prairie Island utilizes 0.0824% for internal calculations, for conservatism Westinghouse will utilize 0.1%.
_ __ +a.c 1
l __ __
Sensor pressure effect (% span) N/A for pressure transrnitters.
( )...e Sensor temperature effect (% span) reduced for 50 degree F i.e. 70 to 120 degree F expected range. It is noted that Prairie Island utilizes 30 degree F for internal calculations, however for conservatism Westinghouse will maintain 50 degree F for this calculation.
+a.c ovo33 cocs2s9s Page 1 of 3
Sensor dnft (% span) for the calibration interval per Rosemount specifications, MAN 4514,1992.
[ )...c Harsh environment allowance (temperature & radiation) (% span) g j...e Transmitter Bias
[ )...e Process Rack uncertainty terms based on SE ICAT(96)-304.
Rack Calibration Accuracy (% span )
~ ~
+8.C Rack M&TE (DVM), per SE ICAT(96)-304, however Prairie Island has commented that internally a smaller value of 0.0144% span is used. Westinghouse will retain the more conservative value as initially provided.
~ ~
- se.c Rack Temperature Effect (% span) Westinghouse utilizes one temperature effect for a bounding value when performing process rack temperature effects for Foxboro equipment.
This term accounts for temperature related changes due to calibrating process racks with the doors open and operation with doors closed. Dependent on the cabinets the temperature may either increase or decrease therefore, it is deemed prudent by Westinghouse to include this effect.
[ )+..e Rack Drift allowance (% span) Westinghouse has historically utilized a 1.0% instrument span to bound this effect. Based on instrument drift analyses for other plants, Westinghouse is currently evaluating the magnitude which more reasonably reflects the instrumentation I capability. Prairie Island has commented on the magnitude of this allowance and identified that intemally Prairie Island utilizes 0.6% for this value'. This will bound the information being evaluated by Westinghouse and therefore is acceptable to utilize.
g j....
l oMass doc:m.2nves Page 2 of 3
1 l
l l
1 Instrumentation Uncerta:nty Caisulationa Calculation of the channel CSA assuming no trending or reconciliation of "As Left", to 'As Found" values. 3
+a.C 1
W!de Range Pressure Transmitter Summary of Variables PP_USPAN = 3000 psig Variable for wide range pressure upper instrument span.
PP_LSPAN = 0 psig Variable for wide range pressure lower instrument span.
PP_ SPAN = 3000.000 psi Variable for wide range pressure instrument span.
+4C Variable for wide range pressure process measurement allowance.. ;
Variable for wide range pressure primary element allowance.
Variable for wide range pressure maintenance and test equipment allowance associated with the transmitter.
Variable for wide range pressure transmitter drift.
Variable for wide range pressure transmitter calibration tolerance.
Variable for wide range pressure transmitter reference accuracy.
Variable for wide range pressure static pressure effect.
Variable for wide range pressure transmitter temperature effect. l Variable for wide range pressure maintenance and test equipment allowance associated with the process racks.
Variable for wide range pressure process rack drift allowance.
Variable for wide range pressure process rack temperature effects.
Variable for wide range pressure process rack calibration tolerance.
Variable for wide range pressure channel biases.
Variable for wide range pressure channel environmental allowance.
_ _ Variable for wide range pressure channel statistical allowance.
ovo33 doc:m2rssa Page 3 of 3
F f
Appendix C l
r f
l i
f i l
i 8;% doc:1D-2/5/98
opsm enwutam mm W M Northcrn States PowcrCompany
_ a um w,ua, vowetw s4s m l%,- ,,
a we wa a n- % , n.. , _.
< 77- w zo 1
P Q-4 t o er i
- 7 pc., . 4 2.s ft -
yy
{ltr*+,' 8+1 el 4; ; $.I 1
jl-i i I v/ rc qog I l PMWi$
e,i 6
"g $I Tl(( . 1._ 3tO*F i Edl v Mt 8 6
h PR-no U
D
- *** W ~ # ""' * ~ ' ' " * ' ' ' h "'J*~r l O -
, = sisrae w r d sJora - execer en '. ^r I
w
l0 Appendix D 4
Index of Documents Reviewed
- 1. Westinghouse drawings 7524-H sheets 19, NSP and drawings 9392-NRP sheets 1-6, RTD location drawings.
- 2. Westinghouse letter SE ICAT(96)-304, input for Prairie Island Instruriient Uncertainty Calculations for Cold Overpressure Mitigation System.
- 3. Northem States Power General Computation Sheet, Over Pressure Protection System Block Diagram.
- 5. RDF RTD P/N 21205 description report.
- 6. Rosemount Product Data Sheet 2514, specifications for Model 1154 Alphaline Nuclear Pressure Transmitters.
- 7. Prairie Island surveillance procedures, " Event Monitoring Instrument Calibration" SP1224, Revision 16. .
- 8. Prairie Island surveillance procedures, " Overpressure Protection System Calibration" SP1199, Revision 18.
- 9. Prairie Island surveillance procedures, " Analog Protection System Calibration" SP1002A,
- 3. w . Revision 20.
I i
i i
oMo33nonprop. doc;142W98 Page 1 of 1