ML20035A716

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Rev 1 to JAF-CALC-NBS-00223, 02DPT-116A,B -117A,B -118A,B -119A,B Main Steam High Flow Pcis
ML20035A716
Person / Time
Site: FitzPatrick 
Issue date: 11/17/1992
From: Granitto F, Petrenko A, Stranovsky G
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20035A711 List:
References
[[::JAF-CALC-NBS|JAF-CALC-NBS]], JAF-CALC-NBS-00, JAF-CALC-NBS-00223R1, JAF-CALC-NBS-223R1, NUDOCS 9303290194
Download: ML20035A716 (20)
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Text

.. _.

I CALC. NO. JAF-CALC-NBS-00223 REU.

1 IP3 l l JAF l X l NOD / TASK NO.

{

QA CATEGORY:

I PRELIMINARY:

FINAL:

X l

l PROJECT / TASK:

Setnoint Calculations to extend oneratine evele SYSTEM NO./NAME: 002 / Nuclear Boiler (ADS)

TITLE:

02DPT-116A.B: -117A.B: -118A.B: -119A.B Main Steam Hi Flow PCIS NAME SIGNATURE DATE

,/

/

DESIGN ENG.:

/

r PREPARER:

F. Granitto h=d8M

////7/92 l

I I. Stranovsky (6? W.

////7/ 92.

j CHECKER:

G VERI?IER: NO G.

Stranovsky 61 M er'//i/ 9 2_

APPROVED:

A. Petrenko Mf

'N//7/f1-a PROBLEM /0BJECTIVE/ METHOD Calculate Instrument Setpoint considering hardware drift and uncertainties for extension of the operating cycle from 18 to 24 months and power uprate.

i This calculation has been prepared in accordance with the Methodology outlined in ISA s.67-04 and IES-3.

gygpgg pg$ ges DESIGN BASIS / ASSUMPTIONS hb5

.. ~ b7 I

-i e,u-.

r 1.

HELB in the Reactor Building, No Accident in the Dryisells'_

=

cm.n

- ~... -

2.

IDCA or HELB in the Drywell, No Accident in the Reactor' Building;S. LOC:

l

SUMMARY

/ CONCLUSION The present setpoint is 5 106 psid. The calculated setpoint has been determined to I

i be 5 110.26 psid and s 112.86 for power uprate. Therefore setpoint change is not required.

1 I

J REFERENCES Vendor Manuals, Drawings, Tech. Specs., ISP's, operatfra; Procedures, EQ reports.

See Section 3.0 of the subject calculation for specific information.

AFFECTED SYSTEMS / COMPONENTS / DOCUMENTS hhh Q

Nuclear Boiler (ADS)/02DPT-116A, B; -117A, B; -118A, B; -119A, B.

NQy ] g ;gg j

h 930317 (L, y s w

P 05000333 i-w m m n a PDR i

I IVOIDED OR l

IVOIDS OR g

l SUPERSEDED BY:

lX l SUPERSEDES:

Rev. O (CALC. NO.)

(Calf. NO.)

FORM DCM 2, 4.1 (JAN.1991)

Page 1 of 5

f a

IP3 l l

/

JAF ld INDEPENDENT DESIGN VERIFICATION CONTROL SHEET VERIFICATION OF:

JAF-CALC-NBS-00223 Document Title / Number

SUBJECT:

Mainsteam Hich Flow PCIS MOD / TASK NUMBER (If Applicable):

QA CATECORY:

I 9

OTHER DISCIPLINE REVIEW: ELEC MECH C/F I&C (SPECIFY)

Check l

l l

l l

l ly l l

l as required METHOD USED *:

84 DR VERIFIER'S NAME:

8 ST444/SVf4'V VERIFIER *S-INITIALS /DATE:

8[ # //? /91

/[

Date:

YMS E APPROVED BY:

A.

Petrenko REMARKS / SCOPE OF VERIFICATION:

1 i

i f

i i

6 l

l I

I Cr Methods of verification: Design Review (DR), Alternatt Calculations (AC),

Qualification Test (QT)

Foran DCM 4, 4,1 (MAR. -1989)

Page-2 of 5

,.~.

f 4

DESIGN VERIFICATION CHECKLIST l

i DESIGN REVIEU METHOD i

i f

VERIFICATION OF:

JAF-CALC-NBS-00223 i

Document / Title / Number

]

SUBJECT:

Main Steam Hirh Flow PCIS MOD / TASK NO.: (If Applicable)

I i

DISCIPLINE REVIEW

-OTHER ELEC MECH C/S

.I&C (SPECIFY)

Check as Required l

l l

l

.l l

lX l l

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Yes/No/Not Avnlicable 1.

Vere the inputs correctly selected and incorporated

/No/NA into the design?

i 2.

Are assumptions necessary to perform the design

'o/NA activity adequately described and reasonable:

Where necessary, are the assumptions identified j

for. subsequent reverifications when the detailed design activities are completed?

}

- T 3.

Are the-appropriate quality and quality assurance Yes No/NA requirements specified? e.g.,

safety classification.

l 4.

Are the applicable codes, standards and regulatory Yes Jo/NA requirements including issue and addenda properly

~'

identified and are their requirements for design. net?

S.

Have applicable construction and operating experience Yes/No been considered?

i

-s 6.

Have the design interface requirements been satisfied?

Yes io/NA l

i 7.

Was an appropriate design method used?

Yes io/NA'

]

8.

Is the output reasonable compared'to inputs?

Ye /No/NA 9.-

Are the specified parts, equipment and processes suitable' Yes/No NA l

for the required application?

t

.j l

1

' Form DCM 4, 4.2-(Page 1 of 3), (MAIL 1989)-

Page 3 of 5

l

(

4 DESIGN VERIFICATION CHECKLIST DESIGN REVIEW METHOD

+

4

,-i Yes/No/Not Annlicable I

10.

Are the specified materials compatible with each Yes/Noh other and the design environmental conditions to which the materials will-be exposed?

11.

Have adequate maintenance features and requirements Yes/Noh been satisfied?

12.

Are accessibility and other design provisions Yes/No adequate for performance of needed maintenance and repair?

13.

Has adequate accessibility been provided to perform Yes/No the in-service inspection expected to be required

~

during the plant life?-

t 14.

Has the design properly considered radiation exposure Yes/Noh a

to the public and plant personnel? (AIARA/ cobalt j

reduction) i 15.

Arc the acceptance criteria incorporated in the design Yes'No/NA-documents sufficient to allow verification that design j

requirements have satisfactorily accomplished?

16.

Have adequate pre-operational and subsequent periodic o/NA test requirements been appropriately specified?

f 17.

Are adequate handling, storage, cleaning and shipping Yes/No requirements specified?

j i

18.

Are adequate identification requirements specified?

'e s o/NA i

specified?

19.

Are the conclusions drawn in the Safety Evaluation fully Yes/No f

supported by adequate discussion in the test or Safety Evaluation itself?

20.

Are necessary procedural changes specified and are JNo/NA

  • esponsibilities for such changes clearly delineated?

l 21.

Are requirements for record preparation, review, approval, Yes.No/NA-retention, etc., adequately specified?

q 1

22.

Have supplemental reviews by other engineering-y No/NA

'I disciplines (seismic, electrical, etc.) been performed

(

on the integrated design package?

i i

l I

Form DCM 4, 4.2 (Page 2 of 3), (MAR. 1989)

Page 4 of 5:

l

s.

DESIGN VERIFICATION CHECKLIST DESIGN REVIEW METHOD 3

r Yes/No/Not Applicable 23.

Have the' drawings, sketches, calculations etc., included Yes o/NA-in the integrated design package been reviewed?.

24.

References used as part of the design review which are not listed as part of the design calculation / analysis.

l

  1. [/kY2 DESIGN VERIFIER:

Signature /Date l

SE Title i

I i

i i

1 t

I 4

i t

i I

i Form DCM14, 4.2 (Page 3 of 3).-(MAR. 1989)

Page 5_of.5-

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CALCUIATION SHEET Mod /Proj.No.

JAF-CALC-NBS-00223 Set lA Pg. 1 of 8 Subj/ Title 02DPT-ll6A,B-ll7A,B-ll8A,B-119A,B MS HI FLOW PCIS QA Class 1 Prep /Date: _11/16/9f Rev/Date gg gp g Rev. 1 Ap/Dt 1.0 PURPOSE Calculate instrument setpoints considering hardware drift and uncertainties for extension of the operating cycle from 18 to 24 months and power uprate.

This calculation is being prepared in accordance with the methodology outlined in ISA S.67-04 and IES-3 2.0 ASSUMPTIONS 2.1 Temperature and radiation levels in the relay room for the ATTS cabinets is assumed to be normal during the HELB in the reactor building or LOCA in the drywell.

Control room and' relay room have the same_ ventilation (air condition) system and do not contain any high energy lines as defined in the Standard Review Plan.

EQ radiation cales show mild rad. environment in these areas for all postulated accidents.

I 2.2 Final values of calculations will be rounded off to achieve a consistent calculation degree of accuracy.

I 2.3 No margin will be applied, since the methodology used in f

reference 3.12 is inherently conservative.

2.4 HELB or LOCA does not occur simultaneously with seismic event.

{

2.5 This Calculation assumes the following scenarios:

i a)

HELB in the Reactor building, no accident in the drywell.

l b)

LOCA or HELB in the drywell, no accident in the Reactor

[

building, i

!4 2.6 It is assumed that this calculation ( for loop 02DPT-116C ) is applicable to loops 02DPT-116D, - ll7C & D, - 118C 6 D, - 119C &

D because the transmitters are located'on the same rack and the loops are identical, j

2.7. Reference 3.11 shows the worst case error for Insulation Resistance Effect (IRE) for the maximum lenghts of various.

instrumentation cable types with various transmitters at JAF i

under the most severe accident-conditions. The maximum error _due to degradation of instrument cable insulation resistance is 0.5%

_ i.

of the span which occurs at the low end of the span.

Since most

[

setpoints are at the extreme low end of the span, a representative IRE is considered to be 75% of the magnitude of the maximum uncertainty. -Thus,. IRE - 3/4 x 0.5% x span.

f 8

f a

CA14U1ATION SHEET.

I i

i Mod /Proj.No.

JAF-CALC-NBS-00223 Set 1A Pg. 2 of 8 l

Subj/ Title 02DPT-116A,B-117A,B 118A,B-119A,B MS MI FLOW PCIS QA Class I Prep /Date: 11/16/92h Rev/Date CS uh7/d Rev. 1 Ap/Dt A

p t

2.8 Master Trip Units Rosemount Model 510DU and 710DU are interchangable. Uncertainty characteristics are the same for both units.

{

2.9 In accordance with reference 3,16 ve assume the worst case Process Element uncertainty for the flow element.to be 5% of.

the full span.

l

3.0 REFERENCES

[

3.1 JAFNPP Technical Specification Tables 3.2-1 Amend No. 122 Pg.

f 64, 4.2-1 Amend No. 136 Pg. 78.

3.2 JAFNPP Operating Procedure Section 1 Rev. 26.

3.3 Rosemount Model 1153 Series B Pressure Transmitters manual.

Publication no. 4302.

i 3.4 Rosemount Model 510 DU Trip /' Calibration System Operating l

Manual 4247-1.

j 3.4.1 Rosemount Model 710 Du Trip / Calibration System Operating f

Manual 4471-1.

3.5 JAFNPP EQ Document: Environmental Parameters After Postulated-LOCA and HELB Accidents Rev. 2, 4/17/90.

I 3.6 Rosemount letter dated October 4 1990 from T. J. Layer to G. Stranovsky specifying drift point based on testing.

l t

3.7 ISA S67.04 Part 2 Draft 7, " Methodologies For Determination of i

Setpoints For Nuclear Safety -- Related Instrumentations."

.t 3.8 ISP - 100A Rev. 13, 100B Rev. 12, 100C Rev. 12, 100D Rev. 17; l

I

-101A Rev. 2, 101B Rev. 3, 101C Rev. 2, 101D Rev. 3;

-202 Rev. 4.

3.9 JAFNPP ATS setpoint determination, dated 3/11/1985. EJS-09-85

'l from E. J. Schmidt to G. V. Dain - GE.

')

l 3.10 Drawings: 1.60-32 Rev. C,

-38 Rev. C, -43 Rev. C; LP-02-38 Rev. 4, -40 Rev. 4; FE.4AU Rev. 3;.OP-1-1 Rev. 11; FM-29A Rev.

22; SE-9ACK Rev. 2, -9ACW Rev. 2; LP-06-1 thru 4 Rev. 3; 7.71-4 Rev. A,

-5 Rev. A; FP-27A Rev.14 -27B Rev. 11, 7.71-42 Rev.A 7.71-42A, GE-528-51393.

3.11-General analysis of cable circuitry performance at JAFNPP, Ecotech, Inc., latest issue date 17 July 1987 ETR 2062.1, Rev.1.

i

_I

l

o CALCUl,. TION SHEET Mod /Proj.No.

JAF-CALC-NBS-00223 Set lA Pg. 3 of 8' y

i Subj/ Title 02DPT-ll6A,B-ll7A,B-ll8A,B-119A,B MS. HI FLOW PCIS QA Class I Prep /Date: ll/16/92h Rev/Dateggn/f7/97 Rev. 1 Ap/Dt,

g i

3.12 NYPA IES-3 rev.0 Instrument Loop Accuracy Calculation.

3.13 Master Equipment List MEL dated 4/24/91.

3.14 JAFNPP I&C dept., Instrument Setpoint Log.

l 3.15 JAFNPP Document,' JAF-RPT-MULT-00206: Consideration of Temperature - Induced Uncertainties in Automatic Actuation Setpoint, dated 3/4/91.

3.16 Telecon between F. Granitto and R. Sang of Permutit Co on 4-24-91 3.17 I&C handbook by Liptak, section 2.2.3 "on Venturi tubes, Flow nozzles and Flow tubes".

3.18 Test Equipment Maintenance Procedure TEM-09 for the analog 1

Trip System Readout Assembly.

(

3.19 Telephone discussion between J. Lazarus - NYPA and T. Layer -

Rosemount dated 5/1/91.

3.20 ASME MFC-3M-1985 - Measurement of Fluid Flow in PipesLUsing Orfice, Nozzle and Venturi.

3.21 Telephone conversation between G. Stranovsky NYPA and.Ed i

Schmidt GE dated 6/26/91.

l 3.22 GE-NE-187-40-1191 Dated Nov.1991 Final Uprated Plant Conditions.

3.23 CE-NE-187-50-1191, NSSS Instrument Setpoint Evaluation.

t 3.24 JAF-CALC-NBI-00192, Hi Pressure Scram.

[

4.0 FUNCTIONAL DESCRIPTION Transmitter 02DPT-116A is part of an instrument loop which initiates a primary containment isolation which is' the closure of MSIVs to prevent core damage and excessive release of radioactivity to the environment due to main steam line high steam flow (<l40% of rated l

flow).

n p

CALCULATION SHEET a

Mod /Proj.No.

JAF-CALC-NBS-00223 Set lA Pg. 4 of 8 j

Subj/ Title 02DPT-116A,B-ll7A,B-118A,B-119A,B MS HI FLOW PCIS QA Class.1 Prep /Date: 11/16/92h Rev/Date g,c n/p/gg Rev. l' Ap/Dt g

?

5.0 BLOCK DIAGRAM i

Venturi Flow Element Transmitter rack 25-56 Relay room ATTS cabinet I

02FE-114A 2DPT-116A 510DU 2MTU-116A Uncertainty Allowances To Address (1) Process Measurement Effect f

(2) Equipment Uncertainties-(3) Calibration Uncertainties (4) Other Uncertainties 6.0 DETERMINE UNCERTAINTY EQUATIONS CU - 1 ( PM2 + PE2 + ey2 + '2

+ IRE 2 + PS2 ) 1/2 -B

.i 2

2 + TE2 + RE2 + SE2 + HE2,Sp2 MTE )1 p + DR e-+

2 In accordance with Ref. 3.7 the following applies:

i PM Effects are not applicable to this configuration / application IRE: Based on Ref.3.11 and assumption 2.7, IRE - 0.5% x 3/4 x span B-0 There are no known bias or dependent uncertainty based on review of Reference 3.3.

7.0 DETERMINE UNCERTAINTY DATA 7.1 In accordance with assumption 2.5, consider normal conditions in the drywell and HE13 in the reactor building.

a) Determine uncertainty associated with Flow Element -

02FE-ll4A, Permutit Model TG Venturi type.

j PE - Primary. element uncertainty PE - 15%.of full span (ref.3.16, and assumption 2.9)

PE - 10.05 x 116.8 psid PE - 15.84 psid 4-

.4 CALCUIATION SHEET i

4 Mod /Proj.No.

JAF-CALC-NBS-00223 Set 1A Pg. 5 of 8 f

I Subj/ Title 02DPT-116A.B-117A,B-118A,B-119A,B MS HI FLOW PCIS QA Class I Prep /Date: 11/16/92h Rev/Date g g tp7/477 Rev. 1 Ap/Dt g

j b) Calculate uncertainty associated with e - transmitter -

Rosemount 1153DB7RC.

.i RA - Reference accuracy i

RA - 0.25% of calibrated span (ref. 3.3) - 0.0025 x 150

[

RA - 0.375 psid j

DR - Drift DR - 0.2% of URL fo 18 months. (ref. 3.6) F l

DR-1[(0.002x300)g+(0.002x300x12/18)gr3] months:

)

DR - 10.72psid TE - Temperature effect.

These components are required for Main Steam Line Break only.

i d g re e po t

no r qu d to function during a HELB accident.

RE - Radiation Effect In accordance with Ref.3.3, RE - i4.0% of 'URL 7

accuracy during and after testing to 2.2 x 10 rads.

i Ref.3.5ghowsmax.accidentradiationinthisareatobe 1.45 x 10 rads.

Since this is negligible compared to the tested level, this term is assumed to be 0.

SE - Seismic Effect SE - Ref. 3.3 shows SE - 10.5% of URL - 10.005 x 300 - il.5 psid.

Comparing the TE and SE, account for worst case SE.

Set TE - 0 i

HE - Humidity Effect - 0 (ref 3.3)

SP - Static pressure effect I

SP - Ref. 3.3 shows static pressure effect to be i0.5% of the URL l

per 1000 psi for code 7.

Normal operating pressure of 1005 psi.

L SP - 10.005 x 300 x 1005/1000 - 1.51 psid i

MTE - Measurement and test equipment effect. Use US Gauge with accuracy of 0.5% of span. (Use 0 - 150 psid span)

MTE - 10.005 x 150 - 10.75 psid t

Use fluke, range 0-20 V DC, accuracy 0.05% of reading +2 i

digits. Using 0 - 5 VDC, MTE-negligible.

Total MTE - 10.75 psid

't PS - Power Supply Effect PS - Ref. 3.3 - i0.01% span per volt variation. For 24VDC assume +

f 2.5V.

[

PS - 12.5 x 0.0001 x 150 - 0.038 psid (negligible).

IRE

-Insulation resistance effect j

Since considering Seismic effect (SE > [TE + IRE]), set IRE -0.

CALCULATION SHEET Mod /Proj.No.

JAF-CALC-NBS-00223 Set lA Pg. 6 of 8 i

Subj/ Title 02DPT-116A,B-117A,B-ll8A,B-119A,B MS HI FLOW PCIS QA Class I Prep /Date: 11/16/92 Rev/Date gg g /f7[9y Rev. 1 Ap/Dt p

I et - +(RA2 + DR2+S 2 + SP 2+MTE}1/2 2+

2 et - (0.3752 + 0.72 + 1.5 1.51 + 0.75 )l/2 2

ei - 12.40 psid 7

c) e2 - Trip Unit

-DR - Drift, Trip Unit Per Ref. 3.4 f

Rosemount 510 DU shows accuracy _- 1 13% of calculated span for 6 0

months. DR - i0.0013 x 150 - 0.195 psid.

Digital trip unit is utilized therefore RA - 0.'

(ref. 3.4)

TE, HE, RE - 0 (ass.2.1) i SP - N/A SE - 0, (Exceeds seismic response spectra, operates up to 11g's) i i

t MTE - Use Rosemount Digital Readout Assembly. Accuracy

.0625%

}

of the span (16 mA) - negligible, ref. 3.18.

t e2 - 10.195 psid 7.2 In accordance with ass. 2.5, considering LOCA or HELB in the drywell and normal conditions in the reactor building.

Calculations for this scenario are not pursued any further since these conditions do not affect the steam flow.

i 8.0 CALCU1 ATE CHANNEL UNCERTAINTY.

I e

For case 7.1 (normal conditions in the drywell, IDCA in RB):

CU - 1(5.842 + 2.402 + 0.1952 + 0.563 )l/2 - 6.34'psid.

-f 2

t 9.0 OBTAIN ANALYTICAL LIMIT'(AL)

Existing Conditions.

i OurALis-{echSpeclimit5140%ofratedFlow.Ratedflowis 2.618 x 10 lb/hr.'(Ref.instrumegtdatasheet234A9301RK) l 140% of rated flow is 3.665 x 10 lb/hr. From the steam curve 528-51393 this flow corresponds to 269 feet of water. Multiplied r

by.4335 it corresponds to 116.6 psid.

I

i I

CALCUIATION SHEET Mod /Proj.No.

JAF-CALC-NBS-00223 Set 1A Pg. 7 of 8 l

1 Subj / Title 02DPI-116A,B-117A,B-118A,B-119A,B MS HI FLOW PCIS QA Class.I' l

Prep /Date: 11/16/92% Rev/Dateggg/n/g Rev. 1 Ap/Dt g i

s For Power Uprate.

l 6

Rated flow is 2.618 x 10 lb/hr.

This corresponds to 127.24 ft H O dif (from steam flow curve 528-51393).

This corresponds to

[

2 55.1 psid.

Pow. Uprate will increase the steam flow by 4.8%.

Thgsincrease l

corresponds to 2.618 x 10 lb/hr x 4.8% - 2.7436 x 10 lb/hr.

l Ref. 3.22 and 3.23.

OurALisTgch. Spec. limit $140gofthepoweruprateflow.

l 2.7436 x 10 x 140% - 3.841 x 10 lb/hr.

10.0 DETERMINE SETPOINT (TS) l For the existing conditions.

TS - AL - (CU + margin) - 116.6 - ( 6.34 ) - 110.26 psid.

l I

For the power uprate.

Due to increased pressure of 35 psia, the operating pressure will

'l increase to 1055 psia (1040 psig).

To be conservative we examine the setpoint near the power uprated 1

Hi pressure trip, calculated to be 5 1062.47 psig or 5 1077 psia.

(ref.3.24) Using the pressure correction curve dwg.7.71-42A,'we i

re-drawed the steam flow diagram 525-51393. Dottedlinerepresgnts the corrected steam flow diagram for 1077 psia. The 3.841 x 10 lb/hr flow corresponds to approx. 275 feet of' water, multiplied by l

.4335 is 119.2 psid. (Steam-flow and pressure correction diagrams l

are attached) r f

TS - AL - (CU + margin) - 119.2 - 6.34 - 112.86 psid.

a I.I r

CAIEUIATION SHEET l

7 Mod /Proj.No.

JAF-CALC-NBS-00223 Set lA Pg. 8 of 8 Subj/ Title 02DPT-116A,B-117A,B-118A,B-119A,B MS HI FLOW PCIS QA Class.I' Prep /Date: 11/16/92 Rev/Dateggg/p/g Rev. 1 Ap/Dt J gj, f

f 1.0

SUMMARY

j Our present setpoint is $106 psid.

f r

Calculation determined the setpoint to be $ 110.26 psid for the j

~

existing condition, and 5 112.86 psid for the power uprate.

No Trip setpoint change is required.

Existing conditions Power Uprate l

(1015 psia)

(1077 psia) i Rated flow 55.1 psid 56.3 psid l

Tech. Spec. 116.6 psid 119.2 psid (140% RF)

Calc. setp. 110.26 psid 112.86 psid Actual setp. 106 psid 106 psid

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MNewYorkPower W Authority TsSo-1 Figure 1 JAMES A. TITZPATRICK NUCLEAR P0k'ER PLANT DOCUMENTATION OF TELEPHONE DISCUSSION DATE: (o[,2(o.'4/

TIME:

J's.n w MODIFICATION NO.:

SUBJECT:

[/ca,w [/cw-. (g[_f o 1 4J

/0# p.s f/,

REFERENCES:

3/)NMds

//4 u -k M N v

f CM rz < '

s NAME ORGANIZATION PARTICIPANTS:

6' [/ra. m v c/c >-

A,/ PPA t=ct Ec h m a d W _

G'. e SLHMARY OF DISCUSSION: 6?.C.-

//A*

cb x-w/ /wro-4ow /AL' e.ul&o I

+e/4cM'##EL%w ow CE diu.-m uj A C O

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af 4Ad }W== //d A4/d, PVo we est,

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Ok.

U

/

/

AGREEMENTS / COMMITMENTS:

J 6/d 9/

Prepared by:

u Date:

Title:

(re+. O [ N J u-f v

i Reviewer Date:

1

Title:

j Distribution:(other than participants) i i

O b M PbWer

& Authefty NUCLEAR GENERATION DEPARTMENT - WITE PLAINS SEleING NWEER:

914-681-6536 CONFIRMATION:

9I4-681-6I76 h

DATE

/

/

T0:, O S[NM/DT

-CE 408 - 9.2 5~ - 43 44 FRON:

SE02 GE'

.C7R A AlD Y.[$V PHONE:

$l4~ [El~ SSEO Q

NWEER OF PAGES BEING SENT, INCLUDING C0VER SHEET:

O FULL Flog (/40V, elRATED Flot6): 3A65NC ll'A A 'I NES$hGE:

g u t c4 x (. 4sas) = nc. <r psi;t.

bred floo =.2. arx e it,,xe cJ u2 24 (/ s o df-c u 7. a x (. 9 s as') = ss.1 pid.

How dd gw gd/Orpcid g 3 mod Ae ~,wy o ~cwy.

1 GENERALh ELECTRIC

~

~

234A9301RK

[4 r.'

intt

  • *" * *-r o 25 s-t 24 INSTRUMENT CATA SHEET 234A9301 RK c c s.as, 25 = = =
  • 24

'rast wact rce FLOW ELEHENT

  • OUA'ITITy 2

4 4 /,Y

  • SERVICE Recire. Purnp Primary Steam g

Flow T1ov Restrictor

/,j, ELEMENT:

I TYPE

(.9 MATERIAL t

+

PIPE SECTION LG

  • PROCESS FLUID Demin. Water Steam
  • DESIGN TEMP 575'F 575 *F
  • DESIGN PRESS 1274 psig

' 1150 psig i

3

  • MAI FLOW 70,000 gpm 7p[t6 bgr
  • HORMAL TEMP 532*F 550*P
  • NORMAL PRESS 1200 psig 1015 psig 6
  • I:0RMAL FLOW 45,4 00 gpm 2.618x10 1b_/hr 0 107.24 ft.

4

  • SP GRAVITY el 2.34 lb/ft i
  • LINE SIZE /SCP/MATL 28"Nin. Wall /SS 24"/100/c5 TAP SIZE 4

FLAN.iE SIZE / RATING jgj6)ft;n{g

  • METER DIFF-MAX FLOW jfffg6;"g 9 4

p 4

CONU TO ITEM NO FT-2-110A-D bIi366

. j g_,

Note 1:

  • REQD ACCURACY

+ lt.00 gpm 25 410 lb/hr Flow range and 7

RATED ACCURACY differential based PURCHASE SPEC or. differential VENDOR Press. switch op-CAT NO erator tor s team a LOCATION Local Local line isolation

.t.

P&lD 719E415BA 719E415EA Note 2:

Choke flow NOTES:

See Pur. Spec.

See Pur. Spec.

'~

21A1368 & VPF 21A1058AJ 4

5.235x106 lb/hr 4

F2651-1-3 VPT SUPPLY DB DB i

_ Essential Class.

NE/A/-

E/A/1

+

  • TO BE FILLED IN BY APED NTS TO

_ _. _ _Bg_ _ _ _ _ _ %k 234A9301 RK SAN JOSE, CAL!F 25 24 n

y g

wa l

NEW YORK POWER AUTHORI_Ty NUCLEAR ENGINEERING & DESIGN SECTICM TELEPHONE DISCUSSION DOCUMENTATION'TUPu Call DATE 4/2 /91 TIME 3:15 PM OUTGOING vvy INCOMING BETWEEN Fernando Granitto OF THE AUTHORITY t

AND Roger SanR OF PERultTTT rn.

AND OF REFERENCE i

u del TG SUBJECT Permutit Venturi Type Flow Fle-ent.

n DISCUSSION / ACTION:

On 4/24/91 at apntnv. 3:15 nm. I dienneceA with Annlicatinne Fnnineer Rocer Sanc about the exnecre? value for the uncertainty of the Main steam Flov Elerent. Mr. R.

r Sanc exclained that since the element for the Main senam Flow was not calibrated i

when it was installed. the accuraev vould he in the rance of.5! rn sY nr th, r,,11 spen.

Mr. Sane would nne corritt to a cor percentace cince the flow element was uncalibrated and the media beine saturated steam.

Previnnc discussions with Mr. Pm Sent resulted virh the same e nnlis ci nn e as on the 4/76/01.

Mr.

R.

sane nicn <rnrea in these discussions rhmt he vould send doeurentation nn the venturi Flow Element.

As of the 4/24/91 1 have not received the doc's-en t a r i nn -

DISTRIBUTION:

NUC GEN FILES NO.

FG-01-91 D FILE FO.

haab$%.

$25l91 SIGNATURE

's DATE i

i ATTACHMENT 3 TO JPN-93-016 NYPA Calculation JAF-CALC-NBS-00224, Revision 1, "02DPT-116C,D; -117C,D; -118C,D; -119C,D Main Steam Hi Flow PCIS",

November 17,1992 i

i i

I t

New York Power Authority James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 i

DPR-59

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