ML20042F255

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Instrument Accuracy Calculation 1LT-63-176,-177,-178 & -179 (RB Sump Switch)
ML20042F255
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 04/25/1990
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20042F248 List:
References
NUDOCS 9005080055
Download: ML20042F255 (184)


Text

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SET POINT AND SCALING CALC #SQN-EEB-MS-TI28-0013 REVISION LOG Revision N0' DESCRIPTION OF REVISION Approved 0

Initial Issue, supersedes SQNP Calculation RB SUMP (Rins # B87 890601 001) for Unit 1 Instrument Loops' 1-LT-63-176, 177, 178, and 179.

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E CALCUIATION DESIGN VERIFICATION (INDEPENDENT REVIEW)

FORM scu-cro-us-rzza40 I\\

~ Calculation NO.

Revision i

e Method of design verification (independent review) used (check method used):

.. 1.. Design Review

2. Alternate Calculation
3. Qualification Test Justification (explain below):

Method it In the design review method, justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc.).

t Method 2:

In the alternate calculation method, identify the pages where the alternate calculation has been included in the calculation package and explain why this method is adequate.

Method 3:

In the qualification test method, identify the QA documented sourco(s) where testing adequately demenstrates the adequacy of this calculation and explain.

TGcurll&AL AD ECL/ACY WAS WKmEh A6 BEJAlb-PGA (ALCULA17

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BRANCH / PROJECT IGENTIFIER SCN"#88"N5*T//F-(NJ DEMONSTRATED ACCURACY CALCULATION Reference Material Review The roforences cited in this calculation were reviewed.

The references which have a

critical impact on the caluclation were updated.

Additionally, appropriate chan were made to the calculation to reflect these latest revisions. ges i

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BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-a n r w DEMONSTRATE ACCURACY CALCULATION FSAR COMPLIANCE REVIEW THIS REVIEW IIAS BEEN PERFORMED TO COMPLY WITH PM B7-31 (EEB BRAN INSTRUCTION) FSAR COMPLIANCE.

Ti!E FOLLOWING FSAR SECTIONS AND TECH SPECS liAVE BEEN REVIEWED.

RESULTS OF REVIEW:

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CALCULATION DESIGN VERIFICATION (INDEPENDENT REVIEW) FORM SON-EEB-MS-TI28-0013 0

Calculation NO.

Revision Method of design verification (independent review) used (check method used):

1. Design Review
2. Alternate Calculation
3. Qualification Test Justification (explain below):

Method it In the design review method, justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to

another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc.).

Metho11_21 In the alternate calculation method, identify the pages where the alternate calculation has been included in the calculation package and explain why this method is adequate.

Rothed St In the qualification test

method, identify the QA documented source (s) where testing adequately demonstrates the adequacy of this calculation and explain.

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i BRANCH /PRCA7ECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCUIATION FSAR COMPLIANCE REVIEW This review has been performed to comply with PM 87-31 (EEB branch

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instruction) FSAR compliance.

The following FSAR sections have been reviewedt 6.3.2.1 7.1.2.1.2 9.3.4.2.2 15.2.4.1 6.3.2.2 7.1.2.1.9 15.2.4.2 6.3.5.4 7,4.

fo b RESULTS OF REVIEW:

The results of the review indicate that the above FSAR sections are in compliance with this calculation.

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l BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION TADLE OF CONTENTS SHEET PURPOSE 2

ASSUMPTIONS 2

SOURCE OF DESIGN INPUT INFORMATION ( REFERENCES )...........

3 DESIGN INPUT DATA............................................

7 A)

DEFINITIONS AND ABBREVIATIONS 7

B)

LOOP COMPONENT LIST................................

9 C)

LOOP FUNCTIONS, REQUIREMENTS, & LIMITS 10 D)

COMPONENT DATA 12 E)

COMPONENT DATA NOTES 14 DOCUMENTATION OF ASSUMPTIONS..................................

COMPUTATIONS / ANALYSES A)

PROCESS UNCERTAINTY DISCUSSION / CALCULATION 21 B)

WATERLEG UNCERTAINTY DISCUSSION / CALCULATION............

22 C)

ACCURACY DISCUSSION 23 D)

ACCURACY CALCULATION INDEX AND CALCULATIONS 29 SUPPORTING GRAPHICS A)

LOOP DIAGRAM 36 B)

INSTRUMENT SENSING DIAGRAM

......................... 37,38._.

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SUMMARY

OF RESULTS 39 CONCLUSIONS 44-

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BRANCH / PROJECT IDENTIFIER 80N-EEB_-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION PURPOSE The purpose of this calculation is a) to determine the accuracy of the instrumentation covered by this calculation, and b) to demonstrato that the instrumentation is sufficiently accurate to perform its intended function without safety or operational limits being exceeded.

This calculation is performed por the methodology defined in Westinghouse setpoint methodology.(Referenco 29)

ASSUMPTIONS This calculation contains no assumptions.

X The following assumptions were used in the performance of this calculation. These assumptions require further analysis.

Tnis calculation may requiro revision if the assumptions below are shown to be invalid.

og/l 1.

The -boron-concentration-of the-sump-water-is-sma-14--ernd-I,p

.has-a-negl,igible-effect on loep accuracy.

bl 2.

A calculation shall be modo to support the maximum allowable margin stated in the OIR, reference 18.

5, ( w Gauu*) f*41/pv Cy ?pl>c REQUIREMENTS Calibration for each loop must be within 22.5 months, and g 1.

the. Ea3 t 2) Wks w.)) be funchnally tested every 3 rnenths.

t 2.

The acceptance band for calibration of the transmitter shall be within 10.5% of calibrated span.

3.

The acceptance band for calibration of the Eagle 21 I/O System shall be within 0.2% of calibrated span.

The acceptance band selected for Eagle 21 I/O system is one times the-reference accuracy of Eagle 21 I/O system.

A digital current motor shall be used for calibration of 4.

the transmitter.

5.

The Eagle 21 shall be calibrated using a digital meter or MMI for input; ICTe =

0.2% of CS.

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DATE 3ho/fu sitEET 2 _ C/O 1 REV PREP DATE CllECK '

DATE-Si!EET C/O I

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BRANCH / PROJECT IDENTIFIER. SON-EEB-MS-TI28-0013 DENONSTRATE ACCURACY Calf 0LATION S O U R C'E OF DES I GN I NPUT INTO RMATI O N.

(REFERENCES)'

RET ATT REFERENCE'(RIMS f)

_1__

1 CALC. # SON-OSG7-0042. REV. 2r SAFETY-ANALYSIS WATER LEVEL LIMITS FOR RB SUMP AND RWST(RIMS # B45 880805 426)

_2__

2 CALC. SON-SOS 4-0072. RANGE AND ACCURACY REOUIREMENTS FOR PAM VARIABLES (RIMSW B87 890818'002)

'l 3

3 STATHAM CATALOG. " NUCLEAR OUALJFIED PRESSURE TRANSMITTERS" 3200 SB 1-9-87.

__ 4 4

WESTINGHOUSE LETTER WAT-D-4983. INDICATING CALII1 RATION CHANGE FOR CONTAINMENT SUMP WATER LEVEL AT SOP 1 RIMS $ NEB 820721 264) 5 5

f;ALC # SON-SOS 2-0063. FORTY YEAR NORMAL AND 100 DAYS ACCIDENT DOSE TO LEVEL TRANSMITTERS 1.2-LT-63-176 TO

-179 USING FINITE VOLUMES (RIMSS B25'890510 824).

6 6

CALC 8 SON-SO54-0070. RG 1.97 CATEGORY AND OPERATING TIMES-FOR CATEGORY 1 AND 2 VARPABLES (RTMS8 B87 890922 015)

REV O PREP _ JVL DATE J-/V 94 CHECK ('In)

DATE ?*h/* f SHEET _;L__C/O -~ 4 -

REV PREP DATE CHECK #

DATE SHEET-C/O' REV.

PREP DATE' CHECK-DATE SHEET

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BRANCH / PROJECT IDENTIFIER - SON-EEB-MS-TI28-0013

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DEMONSTRATE ACCURACY CALCULATION

'S O U-R C E O-F

.D ES I'G N I NPUT

'I NF0 R'M A T=I-0 N=

(REFERENCES)

REF ATT_

REFERENCE (RIMS #)

7

'7 EAGLE ANALOG INPUT BOARD PERFORMANCE SPECIFICATIONS -

FROM WBN EAGLE 21 TECHNICAL MANUAL, CONTRACT

  1. 71C62-54114-1.

8 8

EEB-TI-28, SETPOINT CALCULATIONS 9

9 SONP ENVIRONMENTAL DWG 4?E235-45, REV.

5.

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10 10 PROJECT ENGINEERING REPORT NO. 1006. REV. B (SHEET D-66) TEST PERFORMANCE RESULTS OF STATHAM-

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11 11 OIR NEB 87272.(RIMS *B45870826 259)~AND OIR NEB 87271.

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(RIMS

  • B45 870826'260)

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12 DNE CALC SONAPS2-038', COMTAINMENT RESPONSE TO~SBLOCA-

!l CONDITIONS REM 2,0 (RIMS f B04 900108 300)-

]8 13 13 EOUIPMENT OUALIFICATION BINDER NO. SONEO-IFT-001 1

l sj 14 14 TELECOPY DATED 11-22-88 FROM DAVID KO OF STATHAM

" TEMPERATURE EFFECTS OF STATHAMsP3200 SERIES".

TRANSMITTERS TO MIKE MUSTAFA OF UNITED ENGINEERS' &

j CONSTRUCTORS.

l i

15 15 OIR SOP SON 88829ERO. (RIMS fB25 881208 025.)

.:l REV O PREP _,J_VJu DATEgd-9# CHECK f' }M DATE ? #/ '/O _ SHEET 4 C/O 5 I

REV___ PREP DATE CHECK /

DATE SHEET C/O REV PREP DATE CHECK DATE SHEET C/O n..

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BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATIONf S-0 U R C E O F D'E S-I gin-I-N P U-T I-N P O R!-M-A T I ONR (REFEREllCES)

REF

.ATT REFERENCE-(RIMS #)

. 16..

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WESTINGHOUSE CANISTER ELECTRICAL' Ppjf(QMQJJ_JINDER SONEO-PENE-004.

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17 17 TELECOPY DATED 12-14-88--- FROM DAVID KO OF STATHAM CONCERNING "PD/PDH ' 200 NUCLEAR OUALIFICATION TO ' MIKE i

3 MUSTAFA OF UNITED ENGINEERS ~& CONSTRUCTORS.

18 la QIR NTB SON 88220. (RIMS eB45 880802 4 26) - MAXIMUM

' ALLOWABLE MARGIN'FOR INSTRUMENT ERROR AT SWITCHOVER'IN THE POSITIVE DIRECTION.

-j 19 19_

CALC dSON-SOS 4-0104. R E V.' 3 SWITCHOVER'TO RECIRCULATION MODE FOR A SMALL BREAK LOCA (RIMS

  • B45'8507262426) 20 20 CALC ESON-OSG7-0008

-REV. 5; MINIMUM CONTAINMENT SUMP LEVEL AT SWITCHOVER FOR A LARGE BREAK-LOCA/

(RIMSS B45 880707'429).

b j

l) 21 21 TVA LETTER NO. 5664 TO WESTINGHOUSE, (RIMS EMEB' -7 7 0 50 5 176) l 1

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scopoyAH FSAR TABLE 6.3.2-5

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DATE 3/4 9C SHEET S C/O 6 REV PREP DATE CHECK DATE SHEET C/O REV PREP DATE-CHECK DATE SHEET C/O l

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(IRANCH/ PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION SOU R C E O F DES I G N I N P UT I N FORMA T'I ON (REFERENCES)

REF

ATT, REFERENCE (RIMS #)

2.2_,,,

23 WESTINGHOUSE PROCESS CONTROL BLOCK DIAGRAM 108D273 SHEET 37. R2 (CONTRACT f89 NNP-75380A) 24 S.YEIEM 63 INSTRUMENT TABULATION DRAWING 47B601-63 SE,JtIES SI-98.4. REV. 4 i

25 26 SEOUOYAH FSAR FIG. 6.2.1-22 27 GENERIC CALCULATION GEN-EEB-MS-TI28-0002 REV 0 ON EAGLE 21 SYSTEM ACCURACIES.

28 CALC. SSON-OSG7-040. REV. 6; CONTAINMENT SUMP' LEVEL INSTRUMENTATION PAM ACCURACY REOUIREMENTS I

29 WESTINGHOUSE SETPOINT METHODOLOGY.

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24 SETPOINT & SCALING DOCUMENT. REV.

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REV PREP DATE CHECK DATE SHEET C/O j{

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BRANCH / PROJECT IDENTIFIER-SON-EEB-MS-TI28-0013 DEMON;TRATE ACCURACY CALCUIATION D E.S I G N INPUT DATA A)

DEFINITIONS & ABBREVIATIONS Aa ACCIDENT ACCURACY - ACCURACY OF A DEVICE IN A HARGH ENVIRONMENT CAUSED BY AN ACCIDENT Aas COMBINED ACCIDENT AND SEISMIC ACCURACY Ab ACCEPTANCE BAND - THE RANGE OF VALUES AROUND THE CORRECT VALUE DETERMINED TO BE ACCEPTABLE WITHOUT RECALIBRATION Afc ACCEPTABLE AS FOUND - COMPONENT Afl ACCEPTABLE AS FOUND - LOOP Alc ACCEPTABLE AS LEFT - COMPONENT All ACCEPTABLE AS LEFT - LOOP An NORMAL ACCURACY - ACCURACY OF A DEVICE LOCATED IN A ENVIRONMENT NOT AFFECTED BY AND ACCIDENT OR PRIOR TO AN ACCIDENT-Anf NORMAL MEASURABLE ACCURACY DURING CALIBRATION As POST SEISMIC ACCURACY AV ALLOWABLE VALUE.

SETPOINT Anf; USED FOR THE PURPOSE OF DETERMINING REPORTABILITY ONLY.

CS CALIBRATED SPAN De DRIFT INACCURACY HELB HIGH ENERGY LINE BREAK IAD INTEGRATED ACCIDENT DOSE l

l ICRe INPUT TEST INSTRUMENT READING INACCURACY l

ICTe INPUT TEST INSTRUMENT CALIBRATION INACCURACY INDRe INDICATOR READING ERROR IRo INACCURACY DUE TO CABLE LEAKAGE LAa LOOP ACCIDENT ACCURACY LAn LOOP NORMAL ACCURACY LAs LOOP POST SEISMIC ACCURACY LOCA LOSS OF COOLANT ACCIDENT l

REV 0 PREP JVL DATE #/WO CHECK !'87 DATE 24-9C SHEET 7 C/O 8 REV PREP DATE CHECK DATE SHEET C/O REV PREP DATE CHECK DATE SHEET C/O 1

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION DES IGN INPUT DATA A)

DEFINITIONS & ABBREVIATIONS (CONTINUED)

LOe INACCURACY DURING LARGE BREAK LOCA DUE TO ACCIDENT TEMP EFFECT M

MARGIN - THE DIFFERENCE BETWEEN THE SAFETY LIMIT /. OPERATING-j LIMIT AND THE NORMAL / ACCIDENT ACCURACY (Mn= NORMAL MARGIN-Ma= ACCIDENT MARGIN).

N/A NOT APPLICABLE j

OCRe OUTPUT TEST INSTRUMENT READING INACCURACY OCTo OUTPUT TEST INSTRUMENT CALIBRATION INACCURACY f

PRCSe PROCESS UNCERTAINTY PSEe INACCURACY DUE TO POWER SUPPLY VARIATIONS RADe INACCURACY DUE TO ACCIDENT RADIATION EXPOSURE Re REPEATABILITY INACCURACY RNDe NORMAL RADIATION DOSE BETWEEN CALIBRATION Se INACCURACY FOLLOWING A SEISMIC EVENT

-q SECu SPAN ERROR CORRECTION UNCERTAINTY SL SAFETY LIMIT SP SETPOINT I

SPEe ZERO ERROR DUE TO EFFECTS OF OPERATING PRESSURE l

SUBe INACCURACY DUE TO SUBMERGENCE TAe TEMPERATURE EFFECT AT ACCIDENT CONDITIONS TID TOTAL 40 YEARS INTEGRATED DOSE TNe TEMPERATURE EFFECT IN THE MAXIMUM-/ MINIMUM ABNORMAL' TEMPERATURE RANGES

]4 5

TPRe TEST POINT RESISTOR ERROR WLe WATERLEG UNCERTAINTY j

WLHP WATERLEG HIGH POINT l

e WLLP WATERLEG LOW POINT 1

REV O PREP JVL DATE l N-90 CHECK dDYt_ DATEl/+90 SHEET 8 C/O 8A i

REV PREP DATE CHECK DATE SHEET C/O REV PREP DATE CHECK DATE SHEET C/O i

j

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION DESIGN INPUT D A T'A A)

DEFINITIONS & ABBREVIATIONS (CONTINUED)

CSA CHANNEL STATISTICAL ALLOWANCE (/AR)

PMA PROCESS MEASUREMENT ACCURACY (F C C S*-)

PEA PRIMARY ELEMENT ACCURACY SCA SENSOR CALIBRATION ACCURACY (4'c) l SMTE SENSOR MEASUREMENT AND' TEST EQUIPMENT ACCURACY (IcZe iCf*2, G I#;/ ##

j SD

' SENSOR' DRIFT C De)

STE SENSOR TEMPERATURE EFFECTS (TN R) l SPE SENSOR PRESSURE EFFECTS RCA RACK CALIBRATION ACCURACY

( R c).

l a

RMTE RACK MEASUREMENT AND TEST EQUIPMENT ACCURACY (JCI4'-)

RCSA RACK COMPARATOR SETTING ACCURACY [/16) 1 RD RACK DRIFT ( D4)

I RTE RACK TEMPERATURE EFFECTS ( TM EA ENVIROMENTAL ALLOWANCE h/9Bv 8"N ## #d y

/

l 4

CSA = EA + [PMA8 + PEA' + (SCA+SMTE+SD)* + STE8 _+ SPE8 +

2 (RCA+RMTE+RCSA+RD)2 + RTE']'

i.

[ICTe2+ICRe'+0CTe2+0CRe')b SMTE =

l v

/JC/2**

e 7Ms & in 15 C6 YtH7/cuS ris Acscre75,tss //crea dao)'.l"

/s 'tr s

f St.'f?ft.*5g/r TM r//C //ABisu t'asq Ocy,g d.S 6%~ fn/dD /A/ FMW AM/3 ~ J.2J' Afs' /

.Scrnwv)~ c4w/sTsw-d REV 0 PREP JVL DATE 2 /d cic> CHECK Ofid DATE 8N 9 SHEET 8 A C/O 9 REV PREP DATE CHECK '

DATE SHEET C/O REV PREP DATE CHECK DATE SHEET C/O

]

1

BRANCH / PROJECT' IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION DESIGH INPUT DATA B)

LOOP COMPONENT LIST LOOP ID#

COMPONENT ID#

1-LT-63-176 1-LT-63-176 1-LM-63-176AA (I/E CONVERTER) 1-IR-6 3 -7 6 A B (A/D CONVERTER) 1-LM-63-176AD (PROCESSOR) 1-LS-63-176 (BISTABLE) 1-LM-63-176AF (D/D CONVERTER) 1-LT-63-177 1-LT-63-177 4

1-LM-63-177AA (I/E CONVERTER) 1-LM-63-177AB (A/D CONVERTER) 1-IR-6 3 -17 7 AD (PROCESSOR) 1-LS-63-177 (BISTABLE) 1-LM-63-177AF (D/D CONVERTER) 1-LT-63-178 1-LT-63-178 1-LM-63-178AA (I/E CONVERTER) 1-LM-63-178AB (A/D CONVERTER) 1-LM-63-178AD (PROCESSOR) 1-LS-63-178 (BISTABLE) 1-LM-63-178AF (D/D CONVERTER) f 1-LT-63-179 1-LT-63-179 I

1-LM-63-179AA (Y/E CONVERTER) 1-IR-63-179AB (A/D CONVERTER) 1-LM-63-179AD'(PROCESSOR) 2 1-LS-63-179 (BISTABLE) 1-IR-63-179AF (D/D CONVERTER)

REV O PREP JVL DATE /-/F-10 CHECKlH"l DATE '-N-@

SHEET 9 C/O 10

REV-PREP DATE CHECK -

DATE SHEET _

C/O REV

_ PREP DATE CHECK DATE SHEET C/O N

m-

BRANCH /PRCGECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE-ACCURACY CALCULATION DESIGN I-N P U T DATA C)

LOOP FUNCTION THE FUNCTION OF THIS LOOP IS AN ENABLE-TO THE REFUELING WATER STORAGE TANK (RWST) SWITCHOVER LOGIC.

THIS LOOP MONITORS THE CONTAINMENT SUMP WATER LEVEL.

UPON A LOCA. THE RWST PROVIDES WATER TO THE RHR PUMPS AND CONTAINMENT SPRAY PUMPS.

WHEN THE RWST LEVEL REACHES A LOW LEVEL SETPOINT. THE SUCTION FOR THE PUMPS IS SWITCHED FROM THE RWST TO THE CONTAINMENT SUMP GIVEN THERE IS AN ACCEPTABLE VOLUME OF WATER IN THE CONTAINMENT SUMP TO SUPPLY ADEOUATE NPSH TO THE PUMPS AND TO PREVENT VORTEXING.

f C)

LOOP REQUIREMENTS AND LIMITS RESPONSE TIME:PER SONP CALC. SON-OSG7-0040. (REF. 28)

DUE TO LARGE VOLUME OF SUMP. THE PROCESS RESPONSE TIME WILL BE SLOW. THEREFORE. THE INSTRUMENTATION LOOP RESPONSE TIME IS NOT CRITICAL.

SAFETY LIMITS:SMALL BREAK LOCA PER REFERENCES 1 AND 2:

1.

TO PROVIDE ADEQUATE NPSH - A MINIMUM OF 0 FT ABOVE THE CONTAINMENT SUMP FLOOR.

2.

TO PREVENT UNACCEPTABLE VORTEXING - A MINIMUM OF 2.5 FT ABOVE THE CONTAINMENT SUMP FLOOR.

PER REFERENCE 18:

3.

TO ENSURE-SWITCHOVER WILL OCCUR BEFORE THE LOW LEVEL SAFETY LIMIT ON THE RWST IS REACHED, THE SUM OF THE SETPOINT PLUS THE POSITIVE INACCURACIES MUST BE LESS THAN.5.03 FT ABOVE THE CONTAINMENT FLOOR.

THIS WILL BE' CONSIDERED THE UPPER SAFETY LIMIT TO PROVIDE FOR THE MOST LIMITING CONDITION.

LARGE BREAK LOQA PER REFERENCES 1 AND 2:

PROVIDE-ADEQUATE NPSH

'A MINIMUM OF 1.2 1.

TO FT ABOVE THE CONTAINMENT SUMP FLOOR.

2.

TO PREVENT UNACCEPTABLE VORTEXING - A MINIMUM OF 5 FT ABOVE THE CONTAINMENT SUMP FLOOR.

~

REV O PREP JVL DATE8 WYO CHECKP MI DATE ? d 'D SHEET 10 C/O 11 REV PREP DATE CHECK DATE SHEET C/O REV PREP DATE CHECK DATE SHEET C/O

BRANCH / PROJECT IDENTIFIER SON-EED-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION DES IGN INPUT D-A T A C)

LOOP FUNCTION SAFETY LI?4ITS:IARGE BREAK LOCA PER REFERENCE 20:

3.

TO ENSURE THE SWITCHOVER PERMISSIVE FROM THE CONTAINMENT SUMP LEVEL INSTRUMENTATION IS GIVEN BEFORE THE LOW LEVEL SETPOINT ON THE RWST LEVEL INSTRUMENTATION IS REACHED, THE SUM OF THE SETPOINT PLUS THE POSITIVE INACCURACIES MUST BE LESS THAN 12.4 FT ABOVE THE CONTAINMENT FLOOR.

MAIN STEAMLINE BREAK IN THE YARD i

PER REFERENCES 1 AND 2:

1.

TO PREVENT SWITCHOVER FROM RWST TO A DRY CONTAINMENT I

SUMP UPON LOSS OF RWST DUE TO A MAIN STEAMLINE BREAK IN THE YARD, THE SUM OF THE SETPOINT AND THE NEGATIVE INACCURACIES MUST BE GREATER THAN THE ZERO PERCENT LEVEL (ZERO PERCENT INDICATES THE SUMP IS' DRY).

THIS IS BECAUSE NO WATER FROM RWST WILL DUMP-j INTO RB SUMP AND THEREFORE, ACTUAL LEVEL IN RB SUMP WILL BE ZERO PERCENT.

i OPERATING LIMITS:N/A SINCE SWITCHOVER FROM RWST TO RB SUMP DOES NOT OCCUR DURING NORMAL PLANT OPERATION.

i

(.30 3hha C5,ni;ws gg y fw M;Sc c ph+/$2 SETPOINT: TJJE SETPOINT IS E 64 INCHES OR 11.1% OF SPAN ABOVE THE i

i SENSOR AND THE SENSOR IS APPROXIMATELY 6 INCHES ABOVE THE BOTTOM OF THE CONTAINMENT FLOOR.

SINCE THE 4

l INSTRUMENTATION CAN-NOT MONITOR BELOW THE SENSOR. THE SENSOR ELEVATION WILL~ BE USED AS ZERO PERCENT LEVEL IN TI{E CONTAINMENT SUMP.

i l

l

[

.s i

REV 0 PREP JVL DATE2/+90 CHECK 01/4 DATE 2 /P1d SHEET 11 C/ O 12__, -

REV PREP DATE CHECK' DATE SHEET C/O l

REV PREP DATE CHECK DATE SHEET C/O i

i j

i nm_..~

CRANCH/ PROJECT IDENTIFIER SON-EED-MS-TI28-0013' DEMONSTRATE ACCURACY' CALCULATIONi D E S-I GEN

- I N P.U T D A-T A-D)

COMPONENT DATA VALID FOR DEVICES IDENTIFIED ON SHEET (S): 9 COMPONENT: Level Transmitter CONTRACT-#: 89NLD-74929A REFERENCE.#: 1.;L. '

MANUFACTURER /MODEL:STATHAM/PD3200-400' REFERENCE #.:.L;L.

REFERENCE.#: 3 INPUT RANGE & UNITS:0-400" H2O NOTE #:=

REFERENCE #: 3 OUTPUT RANGE & UNITS:4-20 mA NOTE #:

OVERRANGE LIMIT:2000'PSIG NOTE _#:

REFERENCE-#: 3 CALIBRATED SPAN:0-240" H2O NOTE #: 21_. REFERENCE #: 21_

ROOM #/ PANEL'#:SEE NOTE 20 NOTE #:

2_Q_' REFERENCE #: -

ELEVATION / COORDINATE:SEE NOTE 20 NOTE #: 20 REFERENCE #:

MIN / MAX ABNORMAL TEMP:50/130*F NOTE #:

4' REFERENCE #:_1_

ACCIDENT TEMPERATURE:259'P NOTE _-#: 11_ REFERENCE #: 9 RADIATION TID (RAD):33X105 RADS NOTE =#:-

' REFERENCE.#:'~5 5

RADIATION IAD (RAD):33X10 NOTE'#:

_ REFERENCE #: 5 I

-l INSTRUMENT TAP INFORMATION REFERENCE #:SEE SHEET 37 1

WLHP TAP '. ELEVATION : 68 0. 2 8 '

WLHP CONDENSING POT' ELEVATION:N/A' WLLP TAP ELEVATION:

N/A

-WLLP CONDENSING. POT ELEVATION:N/A EVENT

/ CATEGORY-/ OPERATING TIME:

' NOTE #:

REFERENCE #: 6 l

L

/

A

/100 DAYS

.1 MS/C

/

A

/100 DAYS j

\\

i FW/C

/

A

/100 DAYS RH/C

/

A

/1-MONTH CV/C

/

A

/1 MONTH 1

l l

t REV 0 PREP JVL DATE NF10 CHECKN M DATE J/d 9C SHEET 12 C/O '13

'I REV PREP DATE CHECK !

DATE SHEET ^

C/O REV PREP DATE CHECK DATE SHEET C/O j

i i

l s

BRANCH /PRCETECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMON;TRATE ACCURACY CALCUIATION DESIGN INPUT DATA D)

COMPONENT DATA (CONTINUED)

COMFONENT: Level Transmitter PARAMETER VALUE/ UNITS NOTE #

REFERENCE #

Re 0.25% of CS 1

3-De 1.56 % OF'CS/22.5 MO.

2&3 3

TNo 2.07 % OF CS/200'F 4

3 SPEe N/A 23.24 SEcu N/A 24 3

PSEe 10.01% OF URL/ VOLT 5

3.7 RNDe 3.0% OF URL 6

f i

TPRe 0

7 ICTe 0.25% OF'CS 8

ICRo 0.25% OF CS 9

OCTe 0.25% OF CS 8

-j OCRo N/A 11 I

Ab 0.5% OF CS 12 8

3 i

Se 0.5% of URL 13 3

RADe t3% OF URL 14 3.5 1

tao N/A 10.15 3,9.14 l

WLe N/A 16 i

q,f " ^a s ^/g 4 0 35%

PRCSe y;,,,,q,

.?"t OF CS 17 PAGE 21

, Sl I INDRe N/A 1

ire

-0.42% OF CS 18.19 PAGE 25 i

LOe iS% OF URL

-10 3.10 SUDe 0.25% OF URL 22 13 REV O PREP JVL DATE C-/V9 CHECKd/tt/

DATE F-N-90 SHEET 13 C/O 14, REV /

PREP UM DATER 5'9( CHECK 'CTol DATE b9-%'

SHEET /3 C/O d REV PREP /

DATE CHECK DATE SHEET C/O l

?

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMON!TRATE ACCURACY CALCULATION DESIGN INPUT DATA E)

COMPONENT DATA NOTES COMPONENT:Leve1 Transaitter NOTE 1

PER STATHAM INSTRUMENT SPEC SHEET ACCURACY IS 0.25% OF CALIBRATED SPAN (CS) OF 240" WATER THIS INCLUDES LINEARITY.

HYSTERESIS & REPEATAMILITY.

(ATTACHMENT 3) 1 PER STRATHAM INSTRUMENT SPEC. SHEET THE DRIFT (STABILITY) ERROR IS < 0.25% OF UPPER RANGE LIMIT (URL) PER 6 MONTHS.

(ATTACHMENT 3).HENCE. 0.25% X 400/240 0.417% OF CS. NOTE ERROR

=

IS CALCULATED BASED ON FULL UPPER RANGE LIMIT (URL) OF 400"-

WATER.

TO CALCULATE " TURN DOWN" ERROR FOR CALIBRATED SPAN THE FOLLOWING RELATIONSHIPt UPPER RANGE LIMIT (URL)/ CALIBRATED RANGE X % ERROR = ERROR AT CALIBRATED SPAN (CS).

3 PER SURVEILLANCE INSTRUCTION SI-98.4 REV. 4 THE CALIBRATION CYCLE FOR THESE INSTRUMENT LOOPS IS 18 MONTHS, BUT PER TECH. SPE

C. PROCEDURE

S 25% IS ALTriWED ON CALIBRATION INTERVAL AND CALIBRATION CAN BE PERFORMED AS LATE AS 22.5 MONTHS.

HENCE SENSOR DRIFT =

0.417% SPAN X 22.5/6 =-1.56 % OF SPAN.

REV O PREP JVL DATE WFfo CHECKOM7 DATE 2W-90 SHEET 14 C/O 15 REV PREP DATE CHECK V DATE SHEET

_C/O REV PREP DATE CHECK DATE

__ SHEET C/O L

s l

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013' l

DEMON;TRATE ACCURACY CALCUIATION DESIGH INPUT DATA E)

COMPONENT DATA NOTES COMPONENT: Level Transmitter NOTE 4

PER STATHAM TELECON (ATTACHMENT 14). MAXIMUM AMBIENT TEMPERATURE EFFECT AS % OF CS PER 200*F IS GIVEN BY v = 0.865 (MAXIMUM SPAN / CALIBRATED SPAN) +0.625 0.865 X 400/240 +0.625

=

j 2.07 % OF CS/200'F

=

BY ENGINEERING JUDGEMENT THE. CALIBRATED TEMP. IS MINIMUM AMBIENT TEMPERATURE.

THE MINIMUM AND MAXIMUM ABNORMAL TEMP. IS 50*F AND 130*F RESPECTIVELY (ATTACHMENT 9).

i 5

PER STATHAM INSTRUMENT SPEC. SHEET-(ATTACH. #3).

THE ERROR INDUCED BY POWER SUPPLY SHIFT IS 0.01% OF URL/ VOLT.

PER WESTINGHOUSE EAGLE 21 TECH. MANUAL (ATTACH.

7). MAXIMUM OUTPUT VOLTAGE VARIATION IS 10% NOMINAL VOLTAGE OF AND THE-NOMINAL OUTPUT __yOLTAGE IS 30VDC.

THEREFORE. THE VOLTAGE DRIFT 1

IS ( 10%) X 30 3VDC.

=

6 PER ENVIRONMENTAL DATA (ATTACH. #9) THE NORMAL TID IS 2X102 RADS OVER A 40 YR. PERIOD. WHICH IS LESS THAN THE DOSE APPLIED s

BY STATHAM.

TO PRODUCE CONSERVATIVE An. RNDe WILL BE SET EOUAL TO RADe WHICH IS 3% OF URL. HOWEVER. TO PRODUCE A CONSERVATIVE Av.

RNDo WILL BE CONSIDERED AS UNMEASURABLE AND WILL THEREFORE-i l!{QT BE INCLUDED IN Anf.

REV O PREP JVL DATE WF14 CHECKOl#l DATE 7N-VC, SHEET 15 C/O 16 REV PREP DATE CHECK /

DATE

_ SHEET C/O REV PREP DATE CHECK DATE SHEET C/O i

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION DESIGN INPUT DATA E)

COMPONENT DATA NOTES COMPONENT: Level Transmitter NOTE

_1_

THE TRANSMITTER WILL BE CALIBRATED BY JAKING OFF THE LEAD AND PLACING A DKM TN SERIES TO READ THE CURRENT PER SI-98.4. REV.4-

t 8

THE ACCURACY OF THE CALIB. TEST INSTRUMENT IS ONE(1) TIMES THE.

{

ACCURACY OF THE TESTED DEVICE. WHICH IS 0.25% (ATTACH.

  1. 3).

J';j.

9 THE READING ERROR OF THE CALIB.

TEST INSTRUMENT IS ONE (1)

THE ACCURACY OF THE TESTED DEVICE.

I 10 PER STATHAM INST. SPEC SHT. AND PROTECT ENGINEERING REPORT (ATTACHMENT 10) ERROR DUE TO' LOCA ENVIRONMENT 5.0% URL.

THIS I

i CONDITION WILL BOUND TAe AND SHALL BE USED IN LARGE BREAK LOCA CALCULATION Aa FOR TRANSMITTER. HOWEVER. NOTE THAT FOR A SMALL DREAK LOCA CONDITIONS. THE TEMPERATURE DOES NOT EXCEED 130'F WHICH IS THE MAXIMUM NORMAL TEMPERATURE. THUS FOR A SMALL BREAK LOCA CONDITIONS. TNe IS USED IN PLACE OF TAe. (ATTACH.12) 11_

THE DMM HAS NO READING ERROR.

i 12 BY THE ENGINEERING JUDGEMENT. THE ACCEPTANCE BAND SELECTED FOR' l

TRANSMITTER IS 2 TIMES THE REF. ACCURACY OF THE TRANSMITTER.

i Ab=2XRe=2X( 0.25%) =to.50 OF CS.

e REV O PREP JVL DATE #-/710 CHECKN P1 DATE 2-/Y 90 _ SHEET 16 C/O 17 REV PREP DATE CHECK d DATE SHEET C/O

^

REV PREP DATE CHECK DATE SHEET C/O 3

1 BRANCH / PROJECT IDENTIFIER. SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCUIATION DESIGH INPUT DATA E)

COMPONENT DATA NOTES COMPONENT: Level Transmitter NOTE 11 PER STATHAM EOUIP. SPEC. SHEET (ATTACH. #3) THE POST SEISMIC ERROR IS 0.5% OF URL AFTER A iSG EVENT.

L 11.,,

PER STATHAM EOUIP. SPEC. SHEET (ATTACH. #3) THE POST SEISMIC ERROR INDUCED BY RADIATION EXPOSURE IS 3% OF URL.

PER OIR SOP 5

SON 88760 RO. B25881027051. THE MAXIMUM TOTAL DOSE IS 33x10 RADS WHICH TS LESS THAN THE DOSE APPLIED BY STATHAM'(SEE ATT. 5) 15_,,

PER ENVIRONMENTAL DWG 47E235-45. ATTACH #9 MAX ACCIDENT TEMP.

=

259'F. MIN. TEMP = 50'F.

PER ATTACHMENT 14 TEMP ERROR IS 0.865 i

X (400"/240") + 0.625 = 2.07%/200'F.

TAe=( 2.07% OF CSif(259-50/200))

TAe= 2.16% OF CS-HOWEVER, PER NOTE 10. USE 5.0 URL (LOe) WHICH BOUNDS TAe, i

E THERE IS NO WATER LEG IN THIS EOUIPMENT ARRANGEMENT.

THE TRANSMITTER IS DIRECTLY AT THE TAP.

CONDENSATE THAT MAY

.j COLLECT IN THE REFERENCE LEG WILL BE REMOVED BY A DRIP POT i

ARRANGEMENT.

SEE SENSING DIAGRAM PAGES 37'AND 38 OF THIS CALC.

g Y%%,y- +&$Q1 12._

PRCS e=44%,OF CS FOR SMALL AND LARGE BREAK LOCA SEE PAGE 21 h,

OF THIS CALCULATION.

REV O PREP.JVL DATE #N W CHECKf_ln)

DATEl-/^/~90 SHEET 17 C/O 18 REV /

PREPO O# DATE M <<' CHECK C3M DATE M90 SHEET n C/O IS REV PREP (/

DATE CHECK DATE SHEET C/O I

BRANCH / PROJECT IDENTIFIER ~ SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION DESIGH INPUT D A.T A E)

COMPONENT DATA NOTES COMPONENT: Level Transmitter NOTE la_

PER CALC ON PAGE 25 THE CABLE INSULATION RESISTANCE EFFECT (IRei IS -0.42% OF CS DURING ACCIDENT.

L I

11_

CURRENT LEAKAGE ERROR DUE TO CABLE INSULATION RESISTANCE (IR)

THROUGH ELECTRICAL PENETRATIONS WERE CALCUALTED IN BINDER NO.

3 SONEO-PENE-004 (ATTACH. f16) AND FOUND NEGLIGIBLE.

HENCE, IN THIS CALC., PENETRATION IR WILL BE NEGLIGIBLE.

RQ_

PER DRAWINGS SUPPLIED AS SUPPORTING GRAPHICS. PAGES-37 AND 38.

THE ELEVATIONS AND LOCATIONS OF THE LEVEL TRANSMITTERS ARE ' AS j

FOLLOWS:

{

i l

1-LT-63-176 ELEV.

679'-9"-ON 46'-6" RADIUS,0AZ 176*OUTSIDE POLAR CRANE WALL 1-LT-63-177 ELEV 679" ON 46'-6" RADIUS,0AZ4' OUTSIDE POLAR CRANE WALL 1-LT-63-178 ELEV 679'9" ON 46'-6" RADIUS.O AZ40' OUTSIDE POLAR CRANE WALL s

1 - LT-6 3 - 17 9 ELEV.

679'-9" ON 46'-6" RADIUS,0AZ70' OUTSIDE POLAR CRANE WALL REV_0 PREP JVL DATEMV9 C H E C K 0 )til DATE 2-/d-90 SHEET 18 C/O 19 REV PREP DATE CHECK V DATE SHEET _

C/O-REV PREP DATE CHECK DATE-

_ SHEET C/O I

3 DRANCH/ PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION DESIGN INPUT DATA E)

COMPONENT DATA NOTES COMPONENT Level Transmitter i

NOTE 21_

PER WESTINGHOUSE LETTER WAT-D-4983 (ATTACH. #4) THE CALIBRATION SPAN IS 225.4" TO 14.6" H O FOR TRANSMITTERS USING DOW-CORNING SILICORE OIL IN LIEU OF WATER.

THE TRANSMITTER HAS NOW BEEN i

RELOCATED, AND ITS CENTERLINE IS THE CENTERLINE OF THIS EXISTING i

TAP.

tipW. 240" OF WC WILL BE ACTING DIRECTLY ON THE DIAPHRAGM SO THE CALIBRATION SPAN SHOULD BE Ql'-240" WC INSTEAD OF 214" 26" OR 225.4"-0-14.6" WC.

22_

EMPMERGENCE PERFORMANCE TESTS WERE PERFORMED ON THE PD3200.

IT WAS FOUND THAT THE MAXIMUM INACCURACY DUE TO SUBMERGENCE IS I

0.25% URL.

SUBMERGENCE MAY OR MAY NOT OCCUR DURING AN ACCIDENT l

BUT TRANSMITTER SUBMERGENCE IS THE WORST CASE AND INCLUDED IN SMALL AND LARGE BREAK LOCA CALCULATIONS.

23 THE ERROR DUE TO STATIC PRESSURE IS NEGLIGIBLE. AS'THE PRESSURE CHANGE IN CONTAINMENT SUMP WILL NOT BE LARGE ENOUGH TO INTRODUCE SIGNIFICANT ERROR (ATTACHMENTS 3 AND 9).

SPEe= 0.5% OF URL/1000 PSI PER ATTACH. 63.

s 24 PER ATTACHMENT 3.

SPAN ERROR DUE TO PRESSURE EFFECT IS < 0.2% OF CALIBRATED SPAN.

CONSIDERING THIS ERROR TS PER 1000 PSI. SPAN ERROR IS NEGLIGIBLE AS THE PRESSURE _ CHANGE IN CONTAINMENT S WILL NOT BE LARGEENOUGH TO INTRODUCE SIGNIFICANT ERROR.

REV O PREP JVL DATE A914 CHECKO'l/O DATE2-14 9()

SHEET 19 C/Oc20 REV PREP DATE CHECK DATE REV PREP DATE CHECK DATE

_ SHEET C/O

__ SHEET

_C/O k

1

ERANCH/PROJCCT IDENTIFIER SON-EEB-MB-TI28-0013 DEMONSTRATJ ACCURACY CALCULATICN DESIGN INPUT DATA D)

COMPONENT DATA VALID FOR DEVICES IDENTIFIED ON SHEET (S): 9 COMPONENT: EAGLE 21 I/O SYSTEM I

I/E CONVERTER A/D CONVERTER PROCESSOR D/D CONVERTER r

PER WESTINGHOUSE METHODOLOGY (REF. 29) AND USING VALUES FROM GENERIC EAGLE 21 CALCULATION (REF. 27), AND NOTING THAT THE ACCEPTANCE BAND FOR THE EAGLE IS NOT APPLICABLE BECAUSE OF THE NATURE OF DIGITAL SIGNALS:

i[(De*+ ICTe + Re)8 An(I/E)

+ (TNe)']*

=

. 3.5 An(I/E) = 1[(O M + 0.2% + 0.2%)8 + (0.25)8)*

i An(I/E) = i(

7

% + 0.0625%)*

, ~10 An(I/E) = !O. A GA8 3/J0/10 SINCE THE I/E MODULE IS THE ONLY DEVICE WITH ACCURACY:

. ~10 An(E) = An(I/E) = 10.

OF CS

.70 As(E) = An(E) 0 OF CS

=

Aa(E) = An(E) = i0r'M % OF CS bab 3/30/90 FOR REQUIREMENTS, SEE SHEET 2.

s 4 A 1)e va.loe of. 25 1.s used for consuten:.y wra Westmghouse Methodology, per Westmghouse h>o shop Letter TVA -Bi-8234 wMc.h i.s aBached (ottachment I) to ue Genera. Eagle 21 Calculahrn(Ref 27)

WH r,c DATE T U-90 CHECidqh__ DATE 3-77-90 REV 1 PREP WL SHEET _20 C/O 21 REV 1 PREP _)4 DATE 3/30 /96 CHECK MGk-DATE 3he/To SHEET to _C/O 11 REV PREP DATE CHECK DATE SHEET C/O-

BRANCH / PROJECT IDi~NTIFICR 80N-EEB-MS-TI28-0013 CEMONSTRATE ACCURACY CALCULATIEN i

COMPUTATIONS / ANALYSE-S A)

PROCESS UNCERTAINTY DISCUSSION / CALCULATION NO PROCESS UNCERTAINTY EXISTS FOR THIS CALCULATION BECAUSE:

THE M'EASURED PARAMETER IS THE PARAMETER OF CONCERN; THEREFORE, PROCESS VARIATIONS ARE ACCOUNTED FOR IN THE DETERMINATION OF SAFETY AND/OR OPERATIONAL LIMITS.

OTHER: SEE DISCUSSION BELOW.

X PROCESS UNCERTAINTY DOES EXIST AND IS DETAILED IN THE FOLLOWING DISCUSSION / CALCULATION.

NOTE: THE SPECIFIC WEIGHT OF WATER AT THE FOLLOWING TEMPERATURES IS DERIVED FROM THE STEAM' TABLES.

ALSO, THE SPECIFIC GRAVITY OF THE 2500-2700 ppm BORON SOLUTION FROM THE RWST IS 1.00375'(PER REF.'30)

AND IS CONSIDERED IN ESTABLISHING THE PRSCe FOR THE FOLLOWING CONDITIONS.

SG, REFERS TO THE SPECIFIC GRAVITY OF THE BORON SOLUTION.

PRCSe 928"* LEVEL = H O LEVEL x SW 068 'F-Hg0 LEVEL x SW 0190

  • F**

SW 068'F (28") x 1 -(28") x (60.34) x 1.00375

=

62.32

= 28" x 1 -28" x 0.97

=

0.84"****

= 0.84/240 x 100 = +0.35% OF CS AT 0% LEVEL THERE IS_NO PROCESS ERROR.

t P (26.64") ACROSS TRANSMITTER AT SWITCHOVER'SETPOINT AT' AMBIENT JONDITIONS (SUMP WATER AT 68'F) IS SHOWN ON PAGE 11

HOWEVER, PER DCN M01343A (UNIT 1) LOWEST ELEVATION OF TRANSMITTER'IS 680'2".

THEREFORE, MAXIMUM AP AT SWITCHOVER IS (682'6"- 680'2")

2'4" = 28". THE 28" AP AT SWITCHOVER IS CONSERVATIVELY ROUNDED l

UP, NOTE:

FOR CONSERVATISM PRCSe = 0.35% WILL BE USED FOR BOTH SMALL AND LARGE BREAK LOCA.

FOR THE STEAM LINE BREAK IN THE l

YARD PRCSe = 0% SINCE NO WATER REACHES THE SUMP.

FROM SEQUOYAH F.S.A.R. FIGURE 6.2.1-22 REF. #26 i

MAXIMUM SUMP WATER TEMP. = 190*F

        • THE PROCESS ERROR IS SUCH THAT THE LEVEL-TRANSMITTER WILL INDICATE LESS LEVEL THAN IS ACTUALLY PRESENT AT THE' ACTUAL SETPOINT.

REV 1 PREP DATE 7 2MO CHECKf5 or DATE #/7N0 SHEET 21 C/O 22,.

h l

REV PREP DATE CHECK DATE-SHEET C/O REV PREP DATE-CHECK DATE.

SHEET-C/O 1

l BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CAIEULATION-C0MPUTATIONS/ ANALYSES B)

WATERLEG UNCERTAINTY DISCUSSION / CALCULATION

,_X APPLICABLE TO ALL LOOPS LISTED ON SHEET 9 APPLICABLE ONLY TO LOOPS I,

A l

X_,

WATERLEG UNCERTAINTY IS NOT CONSIDERED FOR THE CALCULATION BECAUSE:

i

_.X NO WATERLEG EXISTS FOR THIS CALCULATION.

THE EFFECTS OF WATERLEG CHANGES ARE INSIGNIFICANT.

SEE DISCUSSION / CALCULATION BELOW.

OTHER: SEE DISCUSSION / CALCULATION BELOW.

A WATERLEG UNCERTAINTY DOES EXIST FOR THIS LOOP.

SEE CALCULATION / DISCUSSION BELOW.

X SEE SENSING LINE DIAGRAM ON SHEET 37.38 OF THIS CALCULATION.

s l

REV O PREP JVL DAT VV-fd CHECKO O DATE 2 /*/ ')d P

SHEET 2 2. C/O_.2)__,

REV PREP DATE CHECK" DATE SHEET

_C/O REV PREP

'DATE CHECK DATE

__ SHEET C/O 8

BRANCH / PRO:TECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCUIATION C0MPUTATIONS/ ANALYSES C)

ACCURACY DISCUSSION-X The accuracy of this instrument for normal, post seismic and accident conditions will be determined by considering the parameters tabulated in the design input section of. this calculation.

The accuracy calculation for seismic (As) is bounding for all seismic events.

_.X_

The square root of the sum of the squares method shall be used in this calculation for calculating accuracy since the - factors -

affecting accuracy are independent variables.

_.X_

Bi-directional errors and uni-directional errors will be combined in a

manner such. that the sum of the positive uni-directional errors will be added to the positive portion of the bi-directional error (obtained from the square root of the sum of the squares method),

and the sum of the negative uni-directional errors will be added to the negative portion of the bi-directional error.

This method is conservative.

Therefore,-it will be used in this 1

calculation.

Example:

(+/-)10 = bi-directional error

+5 = first uni-directional error

-2 = second uni-directional error Total Error = (+10 + 5) to ( 2) = +15 to -12 s

other:

k For the purpose of this calculation, accuracy is defined'as the range of actual process values that may exist for a given indicated or bistable trip value, e.g.

an accuracy of +1 ps'ig to--5 that for an indicated or bistable trip value,0 100 psig, psig means of the actual process pressure may be anywhere between 95 and 110 psig.

All system analysis based on or using accuracy values from this.

calculation should take into account the fact that operator action and/or automatic initiations may occur at a process value differing form the indicated or setpoint values by the amount of the calculated inaccuracies.

REV O PREP JVL DATEM-94 CIIECKO'hn DATE 2-N-9d REV PREP DATE CIIECK #

SHEET. LLC /O 24 DATE

_ Sl!EET C/O REV PREP.

DATE CIIECK DATE--

SilEET C/O I

t 1

n__....

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMENSTRATE-ACCURACY CALCULATION C0MPUTATIONS/ ANALYSES C)

ACCURACY DISCUSSION (CONTINUED)

._2L THE FO.LLOWING DEVICES ARE CALIBRATED INDIVIDUALLY.

THEIR ACCEPTANCE BANDS ARE AS FOLLOWS:

DEVICE Ab REFERENCE'-

1-LT-63-176 0.5% OF CS REOUIREMENT 2 1-LT-63-177 0.5% OF CS REOUTREMENT 2 i

1-LT-63-178 0,5% OF CS REOUIREMENT 2 1-LT-63-179 iO.5% OF CS REOUIREMENT 2 EAGLE 21 I/O SYSTEM 0.2% OF CS REOUIREMENT 3 THE FOLLOWING DEVICES ARE CALIBRATED TOGETHER.

THE ACCEPTANCE BAND FOR THE COMBINATION OF THESE DEVICES ' IS AS' FOLLOWS:

4 DEVICE Ab REFERENCE i

1

~

f i

i REV_0 PREP JVL DATE 2/M4 CilECK010)

DATE 2-/Y'98 SHEET 24 C/O 25-REV-PREP DATE

_ CHECK' DATE-SIIEET C/O-REV PREP DATE CHECK _

DATE SHEET C/O L_

8 3

cad 45 f n sc/o a 7/o d 285is7W^feir[ Ige) z!*r7sc75 cN ;77tanssa/Ne4

.7A5 fJTsC73 HCf' o4SSM// Pro ad' Nodl'OC'M'~ A'A A s%Waf N f

A o

o

)P fdc~ Z.

u)/// /f (#M/ #sNep J Mr/2.

~

ojJ A

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4 de l

lf

/

f i

BRANCH / PROJECT IDENTIFIER-SON-EER-MS-TI28-0013

/

DEMONSTRATE ACCURACY CALCUIATION 1

C0MPUTATIONS/ANA-LYSES i

C)

ACCURACY DISCUSSION (CONTINUED) 100 % Le ve l --- ------ - ---"- ----- - ----

i

- - --- - - - - - --- --- - 70 0. 2 8 '

L 240"

.)

i i

Switch Over

.i Setpoint 682'6" I

0% Level ---------- \\2L 4 '

\\

LT


48 0 3, 6"

-l 1-LT 63-176 Reactor Building Sump -

1-LT-63177 '

1-LT-63-178 1-LT-63-178 i

i Density of water @ 68'F = 62.321 lb/ft3 Density of water @ 160*F = 60,99 lb/ft3 l

-- FIGUR E 1 --

l REV O PREP JVL DATEf-N#4 CHECKCld DATE 2-// 9t> SHEET 26 C/O_22,_,

^

REV PREP DATE CHECK DATE SHEET C/O

)

REV PREP DATE CHECK DATE

SHEET, C/O 1

(

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONHTRATE ACCURACY CALCUIATION COMPUTATIONS /AN'ALYSES C)- ACCURACY DISCUSSION (CONTINUED)

CALTBRATION OF TRANSMITTER THE READING - ERROR ASSOCIATED WITH THE CALIBRATING TEST EQUIPMENT IS CONSIDERED TO BE THE SAME AS THE ACCURACY OF THE CALIBRATIN EQUIPMENT.

FOR PURPOSES OF CONSERVATISM IN THIS CALCULATION, AN ACCURACY AND READING ERROR ON ONE (1)

TIMES THE ACCURACY / REPEATABILITY OF THE TESTED DEVICE WILL BE USED FOR CALIBRATING TEST EQUIPMENT ACCURACY AND READING ERROR.

TI-93,

" GUIDELINES FOR CALIBRATING TRANSMITTERS SEPARATE FROM. THE REMAINDER OF THE LOOP", REV.

O,.9-5-85, ALLOWS CALIBRATION TECHNICIANS.

TO DEVIATE FROM THE APPLICABLE SI OR IMI WHEN -CALIBRATING THE~

TRANSMITTER IN THAT LOOP.

THE DEVIATION ALLOWED IS THAT IF THE APPLICABLE SI, OR IMI INSTRUCTS THE TECHNICIAN TO USE THE TEST POINT RESISTOR TO CALIBRATE THE TRANSMITTER, THE TECHNICIAN MAY ALTERNATELY CHOOSE TO CALIBRATE THE TRANSMITTER BY LIFTING A.

LEAD ON THE TRANSMITTER AND PLACING AN AMMETER IN SERIES ' WITH THE TRANSMITTER TO MEASURE ACTUAL OUTPUT CURRENT.

BECAUSE OF TI-93, THE EXACT MANNER IN WHICH ANY GIVEN TRANSMITTER WILL BE CALIBRATED CANNOT BE DETERMINED.

A REVIEW OF PREVIOUS CALCULATIONS SHOWS THAT WHEN THE TWO METHODS ARE COMPARED, THERE IS ' ONLY ANg APPROXIMATE 10.01%

DIFFERENCE IN MAGNITUDE BETWEEN THE TWO LOOP CALIBRATION METHODS.

THIS DIFFERENCE IS NEGLIGIBLE AS FAR AS THE FINAL RESULTS ARE CONCERNED.

THEREFORE, FOR THE PURPOSE OF THIS CALCULATION, USE A-DIGITAL MULTIMETER (DMM) IN SERIES WITH TRANSMITTER TO READ CURRENT VALUE.

Ammeter Power Source O

C OC s

T Dropping

/

Resistor 5

4 REV O PREP JVL DATE4 W fe CHECKO@7 DATE ?/'/-%'

SHEET 27 C/O 29 REV PREP DATE CHECKv DATE-

_ SHEET C/O.

REV PREP DATE CHECK DATE SHEET C/O i

BRANCH / PROJECT IDENTIFIER-SON-EEB-MS-TI28-0013-i DEMONDTRATE ACCURACY CALCUIATION COMPUTATIONS / ANALYSES C)

ACCURACY DISCUSSION (CONTINUED)

CALIBRATION OF EAGLE 21 COMPONENTS A SIMULATED SIGNAL IS USED TO PROVIDE AN INPUT TO THE EAGLE 21 COMPONENTS, AND THE DVM IS USED AS THE OUTPUT MEASURING DEVICE.

THE DVM IS USED TO ASSURE THAT THE CALIBRATION FALLS WITHIN

.AN ACCEPTABLE BAND.-SOURCES OF CALIBRATION ERROR FOR THE EAGLE 21 COMPONENTS ARE IDENTIFIED IN CALCULATION GEN-EEB-MS-TI28-0002 (REF #27).

THIS CALCULATION INCLUDES THE SOURCES OF CALIBRATION ERROR FOR THE INDICATOR. THE SKETCH BELOW SHOWS THE CALIBRATION HOOKUP.

DVM l

Eagle 21

[

Components Simulated Input Test Point i

I i

l' 5

l l

REV O PREP JVL DATE 2 W-f/ CHECKOfD1 DATE f /'/ 90 SHEET 28 C/O_11 REV PREP DATE CHECK /

DATE SHEET C/O

_t REV PREP DATE CHECK DATE SHEET C/O e

t

BRANCH / PROJECT IDENTIFIER- ' SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATICN COMPUTATIONS / ANAL'YSES D)

ACCURACY. CALCULATION INDEX 1.0 TRANSMITTERS (T) 1.1 REPEATABILITY

, Re 1.2 DRIFT De 1.3 NORMAL TEMPERATURE EFFECT TNe 1.4 INACCURACY DUE TO POWER SUPPLY VARIATION-r PSEe 1.5 INPUT TEST INSTRUMENT CALIBRATION ERROR ICTe 1.6 INPUT TEST INSTRUMENT READING ERROR ICRe i

1.7 OUTPUT TEST INSTRUMENT CALIBRATION ERROR OCTe 1.8 ACCEPTANCE BAND Ab 1.9 INACCURACY FOLLOWING A SEISMIC EVENT Se 1.10 PROCESS UNCERTAINTY PRCSe-1.11 NORMAL RADIATION EXPOSURE INACCURACY RNDe 1.12 ACCIDENT RADIATION EXPOSURE INACCURACY RADe a

1.13 CABLE LEAKAGE-INACCURACY ire 1.14 SUBMERGENCE' INACCURACY SUBe 1.15 LOCA INACCURACY LOe 1.16 NORMAL ACCURACY i

1.17 POST-SEISMIC' ACCURACY An(T) l 1.18 ACCIDENT ACCURACY FOR'SMALL BREAK LOCA-As(T) i 1.19 ACCIDENT ACCURACY FOR LARGE BREAK LOCA Aa-SB(T) 1.20 ACCIDENT ACCURACY FOR MSLB Aa-LB(T) l 1.21 NORMAL MEASURABLE ACCURACY-COMPONENT Aa-MSLB(T) 1.22 ACCEPTABLE AS FOUND-COMPONENT Anf(T) i 1.23 ACCEPTABLE AS-LEFT-COMPONENT Afc(T) j Alc(T)

-)

2.0 EAGLE-21 I/O SYSTEM (E) i l

2.1 NORMAL ACCURACY 2.2 POST-SEISMIC ACCURACY An(E) 2.3 ACCIDENT ACCURACY As(E)

Aa(E) i i

t s

J REV 1 PREP UV DATE3-M O CHECE %

DATE_3 W fe SHEET _29 C/O.30 REV PREP DATE CHECK DATE-SHEET C/O-l REV PREP DATE CHECK DATE

_-SHEET C/O-

i BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0011 3

DEMONSTRATE ACCURACY CALCULATION C0MPUTATIONS/ ANALYSES D)

ACCURACY CALCULATION INDEX 3.0 LOOP ACCURACIES 3.1 NORMAL ACCURACY LAn 3.2 POST-SEISMIC ACCURACY LAs 3.3 ACCIDENT ACCURACY FOR SMALL BREAK LOCA LAa-SB

{

3.4 ACCIDENT ACCURACY FOR LARGE BREAK LOCA LAa-LB 3.5 ACCIDENT ACCURACY FOR MSLB LAa-MSLB 3.6 NORMAL MEASURABLE ACCURACY-LOOP Anf (L) 3.7 ACCEPTABLE AS FOUND-LOOP

'Afl 3.8 ACCEPTABLE AS LEFT-LOOP All 3.9 ALLOWABLE VALUE - SMALL BREAK LOCA AVSB

'3.10 ALLOWABLE VALUE - LARGE BREAK LOCA AVLB -~

3.11 ALLOWABLE VALUE - MAIN-STEAM LINE BREAK

'AVMSLB v

s

'. f l

REV 0 PREP _JVL DATE#-/Ffo CHECKflID DATE 2f/~90 SHEET _30 C/O 31 REV PREP DATE CHECKV

__ DATE SHEET C/O-REV PREP.

DATE CHECK DATE SHEET C/O

BRANCH / PROJECT IDENTIFIER 80N-EEB-MS-TI28-0013 CEMONSTRATE ACCURACY CALCULATIEN COMPUTATIONS / ANALYSES D)

ACCURACY CALCULATIONS 1.0 TRANSMITTERS 1.1 R$ = 10.25% OF CS 1.2 De = 11.56% OF CS 1.3 TNe = 12.07% OF CS PER 200'F TNe = (i2.07%) (130-50) 200 TNo = 10.83% OF CS 1.4 PSEo = 10.01% OF URL PER VOLT PSEe = (10.01%)(400/240)(3 VOLT POWER SUPPLY VARIATION) OF CS PSEe = 10.05% OF CS 1.5 ICTe = 10.25% OF CS 1.6 ICRe = 10.25% OF CS 1.7 OCTe = 10.25% OF CS 1.8 Ab = 10.50% OF CS 1.9 Se = 10. 5% OF URL (400")

Se = (d O. 5 %) (4 00/24 0) OF CS Se = 10.83% OF CS 1.10 PRSCo = +0.35% OF CS 1.11 RNDe = 13.0% OF URL OR 3.0 x (400" URL) i5.0% OF CS

=

240" CS 1.12 RADo = 13.0% OF URL (400")

RADe = (13.0%)(400/240) OF CS RADo = 15.0% OF CS l

\\

l i

REV 1 PREP _

DATE7 U 90 CllEch b^ DATE 3-n-9*

SHEET. 31 C/O_,12_..'

REV.

PREP DATE CHECK DATE SilEET C/O REV PREP DATE CHECK DATE.

SHEET C/O 1

i I

l BRANCd/ PROJECT IDENTIFIER

&QN-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATYON C0MPUTATIONS/ ANALYSES D)

ACCURACY CALCULATIONS L_Q,@.llT.a.

1.13 13e = -O'.42% OF CS 1.14 SUBe a 10.25% OF URL (400")

SUBe = (10. 25%) (4 00/240) OF CS SUBe = 10.42% OF CS 1.15 Los = 15% OF URL (4 00")

LOe = (15%)(400/240) OF CS LOe = 18.33% OF CS THIS VALUE WILL BE USED IN LARGE BREAK LOCA ACCIDENT ACCURACY CALCULATION FOR TAe SINCE LOe BOUNDS TAe TEMP. CONDITION.

USING I

THE WESTINGHOUSE METHODOLOGY (REF. 29):

1.16 An(T) i[(Re + De + Ab + (ICTe8 + ICRe8 + OCTe8 )

)*

+ TNe8 +

=

PSEe8 )* + RNDe (SYSTEMATIC)

+ 0. 258 ) b)

  • An(T) 1[(0.25 + 1.56 + 0.5 + (0.258 + 0.2 58

=

+ 0.838

+ 0. 058 )* 1 5. 0 An(T) 12.87% OF CS i5.0%

=

1.17 As(T)

Se8]% + RNDe (SYSTEMATIC) 1(An8 +

=

Ac(T) = i((2.87%)8 + (0.83%)8)* i5.0%

As(T) = 12.91% OF CS 15.0%

1.18 FOR SMALL BREAK LOCA (USING THE WESTINGHOUSE METHODOLOGY):

+ OCTe8)b)8 Aa-SB(T) = 1[(Re +-De + Ab + (ICTe8 + ICRe8

+ TNe8 PSEe8 )* i (RADe8+ SUBe8)*

+

l Aa-SB(T) = 1[(0.25 + 1.56 + 0,5 + (0.258 + 0.258 + 0.258)*

I

),

+ 0. 8 38 + 0. 058 )* i (5.08 + 0.428)%

(

Aa-SB(T) = 12.87% OF CS 15.02% = 17.89% OF CS s

i REV O PREP JVL DATE '2 /^/ W CllECK Chr)

DATE 2-/'l W SHEET 3 2 C/O_13,

^

REV

, PREP

_ DATE.

CHECK DATE SHEET C/O-

~

(

REV PREP DATE CHECK DATE SHEET-C/O l

l l

L I

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION C0MPUTATIONS/ ANALYSES D)

ACCURACY CALCULATIONS 1.19 EOR IARGE BREAK LOCA (USING THE WESTINGHOUSE METHODOLOGY);

Aa-LB(T) 1[(Re + De + Ab + (ICTc8 + ICRe8 + OCTe8)*

=

),

+ PSEe8)* i (LOe8 + RADe8 + SUBe8)5 Aa-LB(T) = 1( (0. 25 + 1. 56 + 0. 5 + (0. 258 + 0.258 + 0. 2 58 ) %) 8

+ 0. 058 )* i (8. 338 + 5. 08 + 0.428)*

Aa-LB(T) = 12.74% i9.72% OF CS 12.46% OF CS

=

1.20 FOR MAIN STEAMLINE BREAK IN THE YARD ACCURACY OF THE TRANSMITTER UNDER THIS CONDITION WILL BE THE SAME AS UNDER THE NORMAL OPERATING CONDITIONS SINCE THERE IS NO ACCIDENT INSIDE CONTAINMENT Aa-MSLB(T) = An(T) = i7.87% OF CS 1.21 Anf(T) = An(T) - RNDe Anf(T) = 17.87 - (15. 0) =

2.87% OF CS 1.22 Afc(T) = Anf(T)

Afc(T) = i2.87% OF CS 1.23 Alc(T) = Ab Alc(T) = iO.5% OF CS 2.0 EAGLE 21 I/O SYSTEM

,y kne 3/Jel%

2.1 An(E) = 10.444 OF CS AA$ 3/J0/9#

2.2 As(E) = An(E) = 10.'-

% OF CS 70 kne s/Joho j

2.3 Aa(E) = An(E) = 10.-944 OF CS 5

REV _L PREP DATE N NO CHECK h DATE 3-77 90 SHEET ")3 C/O 34 t

REV i PREPJto DATE 3/30ho CHECK AA%> DATE 3 /1*/9 o SHEET 13..C/O REV PREP.

DATE CHECK DATE-SHEET-C/O l

i

BRANCN/ PROJECT ICENTIFIER EON-EEB-MS-TI23-9013 DEMONSTRATE ACCURACY CALCULATICJ COMPOTATIONS/ ANALYSES D)

ACCURACY CALCULATIONS L,Q LOOF ACCURACIES AT SWI,TCHOVER FROM MWST JO RB SUMP 5

3.1 LAA = i[An(T)8 + An(E)*1 i RNDe (0.g) * )5 LAn = ((2.87)8 +

i 5.0%

LAn = 19wett OF CS

~1s%A % MS S/peltel 3.2 LAs = 1[As(T)8 + As(E)8)* i RNDe LAs = 1[(2.91)8 + (0.g)8)*15.0%

LAs = 10. Zt OF CS 7.91 %M6 J/ls)M 3.3 FOR SMALL BREAK LOCA LAa-SB = i(Aa-SB(T)8 +

a(E)8}5+ PRCSe + ire +

LAa-SB = i[(7.89)8 + (0

)8)

+ 0.35% + (-0.42%)

LAa-SB = i7

+ 0.35% -(0.42%)

LAa-SB = :. 20%,

0. %,, OF CS

+ S. 2,7

-3.3+ hs 3/se/op 3.4 FOR LARGE BREAM LOCA LAa-LD = 1[Aa-L'B(T)8 E) 8 )% + PRCse + ire

+

LAa-LB = 1[(14 6)8 + (0

)*)* + 0.35% + (-0.42%)

LAa-LB = il2

+ 0.35% -(0.42%)

LAa-LB = :.

000, 1^.^1, OF CS tl1.83

- 1 2 1 Det 3/J e/ 9 0 3.5 FOR MAIN STEAMLINE BREAK IN THE YARD LAa-MSLB = LAn M 3/30/90 LAa-MSLB = 16w94% OF CS 7.95 3.6 Anf(L) = LAn - RNDe 2, 15 b u J/J8 M Anf(L) = 18.01 - (i5.0) = tav 04 % OF CS 3.7 Afl = Anf(L) = 1GwG4% OF CS i

1.15 has 3/Jo/98 3.8 All = Ab(T)

All = 10.50% OF CS l

i l

l

\\

a REV 1 PREP L DATE MD CHECh 96_ DATE 3 irfo SHEET 34 C/ 0,_31,...

REV 1 PREP. lt# #

REV PREP ~

DATE 3 /36 /90 CHECK /W DATE S he/9e SHEET _,4C/O K.

DATE CHECK DATE SHEET C/O l

t

BRANCE/ PROJECT IDENTIFIE3 SQM-XRB-M3-TI28-0013

[

CEMONSTRATE ACCURACY CALCULATICN COMPUTATIONS / ANALYSES D)

ACCURACY CALCULATIONS 2.95 L.08 Aas she/1*

(Adbe I nf)/WHERE Adbr 3.9 AVSB = SAFETY LIMIT -

A

= LAa-SB

+AVSB =- (22.7 - 11.3)

(8.2t

2. 1) - S.64 OF CS.

-AVSB = (11.3 - 0) - (4. 0 5 0.01) = 0.05% OF CS 4.3 4. -- 1.95 =

F.it M8 1158/t' 3.10 AVLB = SAFETY LIMIT - (Adbe - Anf) WHERE Adba = LAa-LB E

7

+AVLB = (59.5 - 11.3) - (10."t 2.01) - 20.37% OF CS t

-AVLB = N/A f 1. 51 - 2.95 s 18.32.

Ses J/Jo/90 3.11 AVMSLB = SAFETY LIMIT - (Adbe - Anf) WHERE Adbe - LAs

+AVMSLB = N/A h 3/se/9 e

-AVMSLB = (11.3 - 0)

(4,46 - -h6t) = 6.26% OF CS T.44 1.9G 3.13. The Ta:A Sea:. AV I.s de6.e( by de Westmf ouse Satp/nT h

MetioJ.legy (Ref M) as AV = RD +RCA

  • RMTE.

(convertad t.TVA MebJol.97)

= Re + De. t ICTe.

From %et 2.0 O. 2. +. 2.5 +,2.

88. 7 s

REV _1_ PREP 7V L DATE N TO CHECK

'Iw DATEm;fo_, SitEET_15_C/O__36 REV,_J_ PREP.,kte DATE 3/30hd CHECK 6 DATE_3h /9o SilEET_3F C/OJ(,

REV PREP DATE CilECK DATE SIIEET-C/O-s

BRANCH / PROJECT IDENTIFIFR SON-EEB-MS-TI28-0013 DEMONUYRATE ACCURACY CAICUIATION SUPPORTING GRAPHICS A)

LOOP DIAGRAM APPLICABLE TO ALL LOOPS LISTED ON SHEET -9 APPLICABLE ONLY TO LOOPS:

\\

I LT I

I b

j 1/E l

l ADC Processor Eagle 21 DbC I

I l

D/D I

1 l

l Auto Recirc l

low Interlock (and Alarm)

(SSPS)

REV O PREP JVL DATE)/NC CHECK 0781 DATE 2 4 90'_ SHEET 1 C/O 37

^

REV PREP DATE CHECK '

DATE SHEET-C/O REV-PREP DATE CHECK DATE_

SHEET C/O

.I

BRANCH / PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATION i

SUPPORTING GRAPHICS B)

INSTRUNENT SENSING DIAGRAN

,X APPLICABLE TO ALL LOOPS LISTED ON SHEET 9

n '

(Dc,_c.er#

' d....,,..

i o

I f..,.. s e.,

w[~f~, ::M._. :.y:,::n.s,/,

oetsw as see.s

't:.':

c...

"_._p

, O*

7 4

c. b ; ""

I t

bdt

= ~/ W

d,~,,

i m,,, nas-

'.,.v.

1,,=;*.:,*,%.., -

/t a. *nn*

ee,

..e r- -

.r.

/

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,4 p,,,,,e,,,,,,,,,, _ m Pr**teg cee 8 8f 43**

Lo n or oas (su run oms no% /Hl*4 we 4,M OAANY $* L rusm) 3,,ga pcum 8 7a n*p os une,

aln.N! JG"llia ? "0 u$ ?Ettatin f

  • '"'"l ##

Q[-T~

64sk.g_;

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$ce*ocu !/149 nre RuintNCE Ctb l 47W600 //45,lo Auv cco l-41Y60* % 4 6,Ro f,ww swc.)..-

REV O PREP JVL DATEb'F'94 CHECK (Yll?

DATE 2 N-90 SHEET._;}.2.,_C/O._2.Q,

^^

REV PREP DATE CHECK' DATE

_ SHEET C/O REV PREP DATE CHECK DATE SHEET C/O I

I i

BRANCH /PRCATECT IDENTIFIER SON-EEB-MS-TI28-0013 l

DEMON;TRATE ACCURACY CAICULATION SUPPORTING GRAPHICS

)

B)

INSTRUMENT SENSING DIAGRAM

_X_

APPLICABLE TO ALL IDOPS LISTED ON SHEET 9

i I.t r. u.n,

\\

g o*

At 7C*

Par $*"4l

,e L os t f

I.cr.

3.i,.

c A % 174*

[ t.LT.63 'lT7 A1. 4' cNut watt 9

180*

3

_g.

1 l

3.. l o g k' ' ',/

b FL. EL. (47 S'.9' b3 2.t. T. G 3 1 7 6 i

^ ? - O '#

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V1AI W,

KCV. l 01AZ. 13t, i

g7o.

KEY PLAN uni f 2 s

His REF. War.

  • 2 - 47Wie 00" 1145 AND l-47 W6co - 114 6 DATb-/V-94 CHECKO707 REV O PREP JVL DATE 7-N M SHEET 23 C/O_.2.9_,,

REV PREP-DATE CHECK #

DATE.

SHEET C/,0 REV PREP DATE CHECK DATE-SHEET C/O

BRANCN/ PROJECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMO!. STRATE ACCURACY CALCULATI'N

SUMMARY

OF RESULTS (BISTABLE - INCREASING SETPOINT)

SMALL BREAK LOCA 1

APPLICABLE TO ALL LOOPS LISTED ON SHEET 9

APPLICABLE ONLY TO LOOPS:

7 SAFETY LIMIT 22.70 (NOTE 5)

,K1 MARGIN

+ 3.11 PV = SP + Aa

+19. W 348 3/8*/98 J9 PV = SP + As

+19. M-has 3/38/0) i

.Z5 PV = SP + An

+19.-M An 3/At/1L SETPOINT (SP) 11.M30 Jan 3/seno 35 PV = SP - An

+ 3.M JM 1/30/90

.31 PV = SP - As

+ 3. M 3 (a 3/Je/90 PV = SP - Aa

+ 2.4 Ada 3/Jeht, MARGIN

+ 2.% Ada NJo/94 SAFETY LIMIT 0.00 (NOTE 3)

SEE NOTES ON PG'S. 42.43 ALL VALUES SHOWN ARE % OF CALIBRATED SPAN FROM SENSOR LEVEL g

(REFER TO ACCURACY DISCUSSION, SHEET 34 FOR CLARIFICATION OF ADOVE)

+ AV = 6.12%

Aas N/A

- AV = 5.95%

REV 1 PREP DATE 3'DNCHECK h DATE /-77-?4 SHEET 39 C/O_40 PREP.)L e,_ DATE 3/3*/90 CHECK /% DATE_1/t./90_ SHEET _)_L.C/O Vo REV i i

REV.

PREP DATE CHECK DATE

___ SHEET

_C/O

't

~

~ - -.

BRANCN/ PROJECT IDENTIFIER SQM-BEB-X8-TI28-0013-DYMONSTRATE ACCURACY CALCULATI O i

SUMMARY

OF RESULTS (BISTABLE - INCREASING SETPOINT)

LARGE BREAK LOCA

,_L APPLICABLE TO ALL LOOPS LISTED ON SHEET 9

APPLICABLE ONLY TO LOOPS:

i SAFETY LIMIT 59.50 (NOTE 4)

.13 MARGIN + 35.36 PV = SP + Aa

+ 2 4. M Aas thw

.M PV = SP + As

+19. WJu A//sh.9

.23 PV = SP + An

+19.

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.35 PV = SP - An

+ 3. P9 Ana 3/38/#

.31 PV = SP - As

+ 3.-es-Ada 380/90 PV = SP - Aa (NOTE 2)

SAFETY LIMIT fNOTE 2)

SEE NOTES ON PG'S 42.43 ALL VALUES SHOWN ARE,L QE_pALIBRATED SPAN FROM SENSOR LEVEL r

(REFER TO ACCURACY DISCUSSION, SHEET 34 POR CLARIFICATION OF ABOVE)

+ AV = 38.37%

i Aas N/A

- AV = N/A REV_1_ PREP N DATE 7'27*90 CHEC N/

DATE377"o __ SHEET 40_C/O 41 REV 1 PREP,,J!bL DATE3/2cho CllECK 4%-- DATE 3 h* A o_ SHEET vu C/O,9/_

REV-PREP _

DATE CHECK DATE-SHEET C/0,

BRANCM/ PROJECT IEENTIFIER goN-EEB-MS-T128-0013 DEMONSTRATE ACCURACY CALCULATI1N

SUMMARY

OF RESULTS (BISTABLE - INCREASING SETPOINT)

STEAMLINE BREAK IN YARD X

APPLICABLE TO ALL I40PS LISTED ON SHEET 9

APPLICABLE ONLY TO LOOPS:

t SAFETY LIMIT N/A I

PV = SP + Aa N/A PV = SP + As N/A PV = SP + An N/A SETPOINT (SP) 11.30

.35 PV = SP - An

+3 ee9_ lu shaha

.31 PV = SP - As

+3.s Ata 2/3o/n PV = SP - Aa N/A

,3)

MARGIN SAFETY LIMIT 0.0%

_+ 3. N. MS 2/1Mb SEE NOTES ON PG'S 42,43 ALL VALUES Sl!OWN ARE % OF CALIBRATED SPAN FROM SENSOR LEVEL i

(REFER TO ACCURACY DISCUSSION, SHEET 34 FOR CLARIFICATION OF AB0VE)

I l

l

+ AV = N/A Aas -

N/A l

- AV = 6.26%

'7-MO CllEChk /*M DATE5-/7-ro REV_1_ PREP-DATE Sl{EET 41 C/O 4 2.....-

REV.J_, PREP 346 DATE_3/Jo /f o CHECK P419' DATE t/t*/td i SHEET '1i C/O V2-REV PREP DATE CHECK DATE-SHEET-C/O L

I BRANCH /PRMECT IDENTIFIER SON-EEB-MS-TI28-0013 DEMONSTRATE ACCURACY CALCULATICN COMPUTATIONS / ANALYSES D)

ACCURACY CALCULATIONS NOTES 1.

NOTE la PER REFERENCE 1, MINIMUM 1.2 FT ABOVE CONTAINMENT FLOOR FOR ADEQUATE NPSH SL = SFT (SAFETY LIMIT) - 0.5FT (SENSOR ELEV OFF THE FLOOR) = 0.7FT OR 3.5% OF SPAN NOTE 2:

THE AUTOMATIC SWITCHOVER I4GIC FOR THE RHR PUMPS OPERATING IN THE ECCS MODE IS AS FOLLOWS:

A) AN "SI" SIGNAL IS PRESENT AND B) THE RWST LEVEL IS BELOW THE I4W LEVEL SETPOINT ON TWO OF THE FOUR RWST LEVEL CHANNELS AND C) THE CONTAINMENT ' UMP LEVEL IS ABOVE THE HIGH LEVEL S

PERMISSIVE SETPOINT ON TWO OF THE FOUR CONTAINMENT SUMP LEVEL CHANNELS.

IF THE ABOVE CONDITIONS EXIST, THE RHR PUMP SUCTION WILL AUTOMATICALLY RE-ALIGN FROM THE RWST TO THE CONTAINMENT SUMP.

BASED UPON REFERENCE 1,

A MINIMUM DEPTH OF 2.SFT (SMALL BREAK) OR SFT (LARGE BREAK) OF WATER IS REQUIRED IN THE CONTAINMENT SUMP TO PREVENT UNACCEPTABLE VORTEXING.

THE WORST CASE FOR INITIATING AUTOMATIC SWITCHOVER IS THAT THE RWST LOW LEVEL SETPOINT WAS ACTUATED ON THE HIGH SIDE DUE TO POSITIVE INACCURACY OF THE RWST LEVEL INSTRUMENTATION.

THEREFORE, IF THE PERMISSIVE SIGNAL FROM THE CONTAlliMENT SUMP LEVEL INSTRUMENTATION WERE ACTIVATED BELOW ITS

SETPOINT, AUTOMATIC SWITCHOVER WILL NOT OCCUR UNTIL THE RWST LEVEL DECREASES BELOW THE RWST LEVEL INSTRUMENT SETPOINT PLUS POSITIVE INACCURACIES.
HOWEVER, WHEN THE RWST LEVEL DECREASES.TO THIS LEVEL, THERE WILL BE A MINIMUM DEPTH OF 3.65FT (SMALL BREAK)

OR 12.4 FT (LARGE BREAK) OF WATER ABOVE THE CONTAINMENT SUMP IRRESPECTIVE OF WHAT IS ACTUALLY MEASURED BY THE CONTAINMENT SUMP LEVEL INSTRUMENTATION, AND NO PUMP DAMAGE WILL OCCUR DUE TO VORTEXING.

THE ONLY EFFECT THE CONTAINMENT SUMP INSTRUMENT LOOP INACCURACIES WILL HAVE ON THE AUTOMATIC SWITCHOVER LOGIC IS THAT IT COi!LD GENERATE A. PREMATURE PERMISSIVE SIGNAL FOR SWITCHOVER.

HOWEVER, SWITCHOVER WILL NOT OCCUR UNTIL THE "AND" LOGIC IS MADE UP BY THE LOW RWST LEVEL.

AS DISCUSSED PREVIOUSLY, ONCE THIS "AND" LOGIC IS MADE UP THERE WILL BE THE REQUIRED 2.5FT (SMALL DREAK) OR SFT (LARGE BREAK) DEPTH OF WATER IN THE CONTAINMENT SUMP.

IN CONCLUSION, THE INACCURACIES IN Ti!E NEGATIVE DIRECTION OF THE CONTAINMENT SUMP LEVEL INSTRUMENTATION FOR THESE TWO SCENARIOS WILL NOT INITIATE SWITCilOVER WITl!

INSUFFICIENT WATER IN THE CONTAIliMENT SUMP.

REV O PRER JVL__ DATE,NFVO CHECK 0fm DATE N#C' SHEET,.12,_C/O 43 REV PREP-DATE Cl!ECK '

DATE_

SHEET C/O REV PREP DATF CllECK DATE S!!EET C/O I,

i

PRANCH/PRCATECT IDENTIFIER SON-EEbMS-TI28-0013 DEMONSTRATE ACCURACY CALCOLATION C0MPUTATIONS/ ANALYSES D)

ACCURACY CALCULATIONS NOTES:

NOTE 3:

PER REFERENCE 1, PER REF 1, A MINIMUM OF OFT ABOVE CONTAINMENT FLOOR FOR l

ADEQUATE NPSH OR 0.5FT AT SENSOR LEVEL (0% AT SENSOR i

LEVEL) 1 NOTE 4:

NOTE PER REFERENCE 20, THE MINIMUM EXPECTED LEVEL IN THE CONTAINMENT SUMP FOR A LARGE BREAX LOCA IS 12.4FT.

THE CONCERN TO BE ADDRESSED WITH RESPECT TO THE UPPER SAFETY LIMIT IS THAT SWITCHOVER IS NOT PREVENTED DUE TO POSITIVE INSTRUMENT INACCURACIES.

SO, THE MINIMUM i

EXPECTED LEVEL WILL BE USED AS THE UPPER SAFETY LIMIT TO PROVIDE FOR THE MOST LIMITING CONDITION.

(12.4 FT - 0.5 FT) = 11.9 FT OR 11.9'/20' = 59.5% OF SPAN.

I NOTE 5:

PER REFERENCE 18, f

SL = 5.03FT (SAFETY LIMIT) - 0.5FT (SENSOR ELEV OFF THE i

FIh0R) = 4. 3 5 FT OR 22. 7 % OF SPAN I

t i

(

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4 v.

REV O PREP JVL DATE> # 9 CHECK /' 0 DATE 2-N'9# SHEET _ D_C/O 44 REV~

PREP DATE CHECK DATE SHEET C/O REV PREP DATE CHECK _

DATE-SHEET C/O

.. L.

BRANCH / PROJECT IDDTIFIER SON-Ren-MS-?I28-0013 DEMOl3 STRATE ACCURACY CAIEULATION C0NCLUSIONS

_.X APPLICABLE TO ALL IDOPS LISTED ON SHEET 9

APPLICABLE ONLY TO LOOP 3 l

The indicated loop accuracies at switchover are within the required accuracies.

Also, recalibration is not required following a seismic event. Summary of results are shown on sheets i

39,40,41.

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REV O PREP JVL DATE #-/F-f4 CHECKO701 DATE 2-M'90' SHEET 44 C/OFINAL REV PREP DATE CilECK "

DATE-

__ SHEET C/O REV-PREP DATE CHECK DATE

_ SilEET C/O I

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CA1,CU1ATION DESIGN VERIFICATION (INDEPENDENT REVIEV) FORM

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A 2.

Calculation No.

Revision 1*

Method of design verification (independent review) used (check method used):

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1.

ossign Re,iew 2.

Alternate Calculation 3.

Quelltieation feet i

Justification (emplain below):

Method 1:

In the design review method, justify the technical adequacy of the calculation and explain how the adequacy was eerified (calculation is similar to another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc.).

Method 7:

In the siternate calculation method, identify the pages where the alternate calculation has been included in the calculation package and esplain why this method is adequate.

Method 3:

In the qualification test method, identify the QA documented source (s) where testing adequately demonstrates the adequacy of this calculation and esplain.

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ATTACHMENT TO' ADMINISTRATIVE PROCEDURE SASP 1.02 Page 1 of 3 SUPPLEMENTAL. REQUIREMENT FOR CALCULATION PREPARATION AND REVIEW CalculationTltiek, ^* h c, /e.w-i a / wr _% Identifier: SC*l-703 4 - c K i b \\ T og Preparer-Checker Reviewer 1. The "statoment of problem" on the cover sheet is a clear, concise description of the actual proDiem addressed by the calculation, d 2. The " abstract" on the cover sheet i I is clear, concise and captures the essentia1' nature of the calculation. As worded, it provides a high level stand-alone description suitable for use by researchers who must consider the applicability of a large number of calculations. Abstracts should be less than 250 words in length and i suitable for inclusion in a - i computer data base. 'bY 3. Sufficient background is provided l (or referenced) such that future users can appreciate this calculation in the context of the actual factors or concerns which initiated it. A clear statement of the purpose /1mf 4 of the calculation is provided. W 5. Inputs, including codes, standards and regulatory requirements have been correctly selected, referenced and applied. o Attachment No_ i Sheet _22 of 2=i. Loop si/ldentifie QN-EEB-MS -T128-0013 DNE1 - 3323Q NEB 1/13/87 ..I.

t ATTACHMENT TO ' ADMINISTRATIVE PROCEDURE SASP 1.02 Page 2 of 3 SUPPLEMENTAL REQUIREMENT FOR CALCULATICN' PREPARATION AND REVIE'd Preparer Checker Reviewee 6. References indicate document name. 4 number, data and, revision level._ If appropriate, a distinction is .r. made between references used for background and those used as a 1 /F-basis for the calculation. gg y d' 7. Assumptions are adequately f identified and documented. / p l r 8. A1A unverified assumptions are I clearly identitled. -{ 9. Action has been identified in the I e calculation for resolution of all l unverified assumptions (e.g., QIR number requesting needed information or other action is noted in the calculation). g 10. The calculations methods ..f (including assumptions) are reasonable, appropriate and based on sound engineering principles. 11. Limits of the-calculation are readily apparont, i.e., a calculation may be conservative for its purpose, but non-conservative for other uses. The calculation should be so clear that its misuse is unilkely. /M7 12. The calculation process is completo and accurate. 13. Consideration of system performanco, safety martins is adequate. Attachrnent No_ I Sheet D af 24 DHE1 - 3323Q Loop si/ldantifiersnu-m.MS -mm nn13 NEB 1/13/87 I

~. - _ _ _, Page 3 of 3 ATTACHMENT TO ADMINISTRATIVE PROCEDURE SASP 1.02 g SUPPLEMENTAL REQUIREMENT FOR CALCULATION PREPARATION AND REVIEW i Preparer Checker Reviewer 14 Consideration of applicable jI d i codes.. standards and regulatory ( r_a e 7 b /76;( requirements is adequate d 15. Consideration of operational l j f actors (e.g., assuntptions on f i 'M _I operator actions) is adequate. 16. Results have been stated clearly and concisely. l 'M1 17. ..sults completely address the initiating concern. M 18. An atte:rpt has been to flag i features or assumptions that would be particularly sensitive to possible future plant changes. Particular care should be taken to identify known subtle mechanisms j 1 whereby a future ECN could invalidate the conclusion reached in the calculation. E' / bd i i y l 19. Revisions which void calculations t provide adequate justification and reasons why the calculation may be ,/ M[A N[/% voided. j 1 l. l l l 5 ( l I l l i k I l f .l .-s Attachment No. I Shee+ M afM ( / r loco ni/ldentifier SQN-EEB-MS -TI28-0013 2 DNE4 - 10164 NES 10nj7 .i l _}

Attacnm3nt !!c. 1 Pass I of 2 cat.__:. AT:Cn C:. ass: C2T:CN , -.. e -. -,,... - - PLANT / UNIT M 8 (( ICEN!! TIER,54 -O$$ [-M h Rins No.

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//d 2 M E re e __ / d ken ~k J"ks/Ai ~zni dw e. c3 Y 22 f REVISICM LEVEL areTCTIC sv?TE**rft), PLANT FEATURE: SYSTEM /CCnPCNENT CEEC?. PT!CN: / SYSTIM NO. h h SATITY SYSTIM O eLa",T E"v:R="nE"T (EC ETC.) ] NCN-5AFETY SYSTEM SYSTEM NO. 0 assE..C:x R 4 [ CIVIL STRUCTURES ' / h (INSTRUMENTATICN 1.S7,PAM.ETC) O LICENSING O CTxEn .e ' o t S t e ? ? ? ? ? E A * ? E *1 / [ FILE CNLY h ESSENTIAL j 5 / j E sueERCECEn O Cas4asty 4 d / /[,

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? Actac..m:nc ..o, Pego 2 of 2 a 5 CAL uta::en c:.ess: ::2::en .9Chl-OC(-s,7 - o /-f Z.R 'I i. t:En::r:ER: TICA:::N: .=RE_:5!NAFp C:. Ass: r::.s ent.y O Essrin:A t. ~ l O crstaarts O suPract::so cat.:u:x:en ct.asste::A::en Jus :r: car::n: sven::::a k lJ - A sWsY n-2 , wL n Ax.Ar w0'{ l f .r-el 1 ..s<. a s / ~ x./ 6 r J f t' V ( 4 !EU:EUE3: 43REE U:!M ] ::sAGREE -: nnE.'cs RE u:RE: m - class!?!CA:::.'l 1 AdREE WI:M DISAGREE -CC'* men!s APORCUER: v s RE e:REa c:. Ass:r: car: n I Sheet.fsicf 24 Attachment No SQN-EEB-MS -TI28-0013 W Want:Her 2 1----- - - - -

SQN-SQS4-0072 Rev. O By tuct Date __*t].)_oJjg_ Checked 94%/ e Page 27 of 77 ~ Date W hite 71397 TA8LE 1 - s. TYPE A VARIABLES EA E E AND ACCURACY REOUIREMENTS FOR THE CONTAINMENT SUMP HIDE RANGE LEVEL INSTRUMENTATION - 1. Accuracy Reautrements The PA'1 accuracy requirements for this variable are specified in DNE Calculation SQN-0SG7-0040 " Containment Sump Level Instrumentation Post Accident Monitoring Accuracy Requirements". 2. Rance Reauirements The containment sump level instrumentation should be capable of measuring from 0% level to the maximum expected flood level. Note 5 of Environmental Data Drawing 47E235-45 states the maximum surge level of the containment water level is elevation 698.8 ft. and the maximum steady state level is 694 ft, for Unit I and 694.5 ft. for Unit 2. DNE/NES calculation SQN-SQS4-0138 states the level instrumentation lower tap is 0.5 f t. above the bottom of containment sump and extends up to 20.5 feet above the containment sump bottom. This provides a range in elevation from 680.28 ft. to 700.28.ft. thus encompassing the maximum surge level with an approximate 7% margin to prevent pegging. The Reg. Guide 1.97 recommended range is-bottom of containment sump to 600,000 gallon water level equivalent. Using the formulas and data of calculation SQN-SQS4-0138, the volume in containment sump at the existing upper instrumentation limit is 577,763 gallons, which meets the intent of Reg. Guide 1.97 requirements. Therefore, the recommended instrument range is from elevation 680.28 f t, to 700.28 ft. Attachment No-2- Sheet I of I ~, Looo #/tdentifier54N-EP'-MS-TIZE-onl3 4 g' I i

NUCLEAR QUALIFIED PRESSURE ~ TRANSMITTERS ( AUToesAtic coerfacm, -p TtcHeeotooga esec. P o. goa asp-k'.- 8&iomeo. To.% 37933.iggy IkEh8 i i Statham Division l Solartron Transducers ( x 4 ..x ~~,- m > b- ^ ' ~ .y 2.i .nu e } } ; ^. :a ga vg s ? ~ u ~ q, j ,e + g's 4 ) g 4'}* -s .y g. ,r a+ = .R_' w %\\ i ( $= 7,. , + - 'f.C ~. y W. k k., w -~ . f ~ m, y ;x e m. s 7 4 +. l [ ?..;' I Sifb $ h y .] 1....... l.. g / C,..., ' N q'/ " i ; ~ \\ /7 ^ ' ' ' ' ' ; * ~ " %,. '". ,r. ..r -:v ; R. = "f *'~ '. P [%WQ. .O., i g.g.g. r i j + l 1, = _ v k 4': A! e. + v <c ..'c. ~. t ~ , L.. J'

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Nuclear Qualified Differential Pressure Transmitters Aftschment No. 3 Wulf 7 Loco v/ldenttherS&l-EEB-MS-TU&ool3 r 1 PD3200/PDH3200 t w bndge The output of the sensor is a mithsoluge proportional to the fonce or differential pressures ensued. The sernor has been designed mth an equal oil volutne on both l ) sides of the seruor to mmamite suue preuure and thermal trievts j j l apocuted with Avid compressibihty or expansion, Sensor pnxection (,, to the full sutic pressure ratina of the transmitter is actiewd hv the use of hydraube and mechanio' overpressure stops. SIMPLE DC ELECTRONICS ,f,- The PD3200/PDH3200 transmmers utihre a simple DC ekttrome amphfier to excite the Shearsone hndse and convert *he sensor s .s@. 4 ", " ',,j*. milhvoltage output to a +20 muianal proportional to the differential - ..f y,, y - Es.g : precure sensed. Components have been Larefully selectedand tested g W.P y'# N.~M to emure long term subehty and radiation reststance. All amphriers e are bumed m at an elevated temperature to ehmmate premature t .'.,',3 component fatture or unft poor to mstallation. The elettrotuts are hermeticily sealed m a 316 % housing. MAGNETICALLY COUPLED ZERO AND SPAN 'm A0JUSTMENTS - The extemal stress which control zero and span are coupled to their correspondmg intemal potentiometers by magnets mou;.e.RAk to-j back tm the stamless steel housing. This permir,s simple strewcener I o Nuclear Service Quahlied adiustments of zero and span without nolation of the hermetic seal te mo and span are nmencmg ca6 adictmem m to x e Hermetically Scaled 316 $$ Housing mad onN once o LCCA Profile to 265'f (Temperature Margm included)

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A unique feature of this design is the avadabdity of a tamper proof e 10 Year Quahfied lafe at !!5'F installatic,n bP removing the extemal adiustments magnets. The Sutham PD3200/PDH3200 Differenual Pressure Transmitters haw CORRO$10N AND MolSTURE RESISTANT STAINLES l been devaned for maximum long term accuracy, stabihey and STEEL NOUSING AND PRES $URE RETAINING PART reiubibry m the nuclear power industry usmg state-o(4he art sensing, The PD3200/PDH3200 differential pressure transmmers have been 4 tiettforue and pachgmg technoiogy. t designed and budt to mthstand all aspecs of a design bam esent (DBE). The sensor ahd electronics are welded shut m a 316 i 0.25% THIN FILM ACCURACY AND LONG TERM h mma to guard agamst caustic spray, high humidttv and corrosion STASIUTY Process wetted pressure retaining components are manufactured trom traceable 316 sumless steel. wtham s ultrastable thin Alm stram page senior assures the trammitter of hawng long term stabihty and acruracy over a mde NUCLEAR QUALIFICATION range of temperatures and irradiatiort The sensor constses of a beam-duphragm assembly mth a thm film Whearstone bndice sputtered The PD3200/PDH3200 differental pressure trart.mitters has e been under vacuum upon a canadever beam. The vrain gage produces a designed and tested to IEEE 323.19M and IEEE JA 199 imear output with excellent temperature and irradiation requirements. After thermal agmg, t'est transmitters were irraduted at sharactenuws. The sputtenng proceu produces a molecular bond 3,2 and i Mrad /hr. for a Toul Integrated Ibse (TID) of 33 \\trad between the ihm film struin gage and the meal bendmg beam. The gamma, seismgully tested for a Safe Shutdomt Ewnt t SSE ) at 15 GN 5.am is then mounted in coniunction mth a force semmg diaphragm peak accelerunon and subiested to a 265

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~ 0-80 to 400*iMao g verpressure eweiss lem than the static POM3300 pmssun mung dthe transminer O 6 to 030 psed. Power suoptv eefect 001%V of poove sunpiv unnanon 0 20 to 0100 psid load eMect No efect if power supply vo remams m ocecama qws. luge 0- 0 o00 P8'd ung paa m p to HiO W W m o shih Ourout 4 20 rrw maximum 30 mA (limnedI perpendicular to damphagme Power Required 12 to 55 \\DC as measured at (corrected by zero adeusmentt No eNm m ph ddiaphmsms; no span transmmer f reverse polanty protected) eNm toad hmaanons see soecincanon chart ~ PHYSICAL SPECIFICATIONS Enclosure etassification NEMA 3,4. 6. 7. 9 o Matetials of consruction .emperature hmits Storage -Pressure Reuaung 316 55 -Operanon. electronics -65' to +200'F (-54' to +93'C) Componenu -DBE electronics +40' to +1BO'F (+5' to +82'C) -Pmcess connections -Wximum process +40' to +250'F(v5' to +122'C) %* NPT on 2't' cemers +40' to +250*F(+5' to +122*C) _o.nnes Viton A Sune pressure hmus 2000 psig (13 8 MPs) at enher _pg g g g connection mthout damage to -Electromt.s houtmg ] -316 SS transmmer sywem I 3000 psig (20.7 MPa)-r=W si -Electncal termmation i leads KJpton maulated 14 Ege stranded tuth B Humidity hmits OL100% pff polvutethane ponirg .I 100% of Upper Range limst ~ Yellow /%:te = nemmtve. Black = Zero elevation ^ I 2ero suppression +s0% of Upper Range uma - _ -Junctum Box Epouv coated alummum m Sum Wspan and elevason or Electncal connections %* NPT - suppreasson cannot exceed the t pper i NOTIL Consuk factory for addaional orlower.x lima PERFORMANCE SPECIFICAtl0NS 0088ons (% OF UPPER RANGE UMT)

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-m/ s x 8 M O kii) I NOE Petfotmance is bmed on PD/PDH3200 mth 31655 diaohraams, sihcone od DC 702, i..a conditiorn --Ancuon Box v *i. > to.25% of cabbened span, meludmg, CALIBRATION ~ Accurac 2 6 lbs ( l.2 kg) linearmt hyseresas and repeaubihty _- _ Repeatabihty 20.1% at maximum span ararnmers a e factory cahbrated from aero to the maximum canae unless specified otherwise sten urder is placett _%5incy ) <r0.25% of upper ranee hmic/ 6 months TAGGING Ocad band _ None Trarummers mil be idemified m xcordance with cu Temperature effect t1.5 (g.%/200'F between 40' to 250'F requirements 15 character mxttmu:a). Stamped un _ C2hbrau o e v(er. OfmONA1.: $l6 $$ tag wire to H22'C) a max span t$ 0%/200'F betsten 40' to 250'F DOCUlWENTATION ~ j 1 (+5' to t t22*C) at mm soon prew.re effect 6-Ceruficate (Oripliance and final cahbration mil be - furnished miu each transmmer. Manutiacturmg and Tes I -ero ems .~ t05% of upper range hmit/1000 psi Procedures. Matenal Certifications and QA Documents m'{ (69 MPa) ~5 pan esrur reviestd at Sutham Dmston Omard. CA. i < to.2% of cahbrated spun (both zero i .j ii

t +, Attachment No.. 3 _$be,g 7 ag g LOCD s'/Ident fierf>W*EEB-MS-TI28-ool3 i ORDERING INFORMATION CODE DESCRIPTION I MODEL P03200/PON3200 NUCLEAR QUAuFIED 1 OlFFERENTIAL PRESSURE TRANSMITTER RANGE 7 P03200 ~ 100 0 20 to 0100* H4 ~ 200 040 to o200* H4 400 oso to 0400* H4 PON3200 030 06 to 030 psed 100 420 to 0100 psed 300 060 to 0300 psed ( 01M 0-200 to 01000 psid PRESSUREFLAN05CONFIGUR' ATION r0 2000 ps: SWP mm open ports 1 2000 ps: 547 eth 316 SS plugs 2-2000 ps 54P mth 316 SS drain / vent nhes 5 3000 ps 549 mth open ports 6 3000 ps: S49 mth 316 55 plugs t 7 3000 ps 549 mth 316 SS drainAent vahes ELECTRICAL TERMINATION I2 3 lends,36' long,3rd mre ground 18 Factory rnounurig of electncal accessory (e s. Nuclear Junuction Eax) PRESSURE RETAINING PART$ PIES $UllE PLUGS OR r Ft.ANGE3 \\TNr/ DRAIN DtAPHRAGMS BOLT 5. FILL t_ 22 31655 316 SS 316 55 316 SS ', Silicone Oil DC '02 Fit'1D ACCESSORIES (MOUNTED) ELECTRICAL I XX None l_ 36 NuclearJunction Box 4 lP03200l-[IiXl.(E8) ].h 9 (TYPICAL MODEL NUMBER) 12 i

l ) A $heet M ( 1 Atteshment N3 Laso f/lfannfidQN-EEBM-TI28-00l3 set n..... . e rps pr eme.

1998, 0.t N. 5. oppouse, v11A,PA.f R. m. Ptero o,106 W TVA.4635 e.g WAT 0 4943 J. C. Standtfer. 304 Stet
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~ .. msnfusesnsutine TVA Centract Nos. 60C40-91984 and 71C62 54114 1 h jQ L,,... J 5.0. TVA/ TEN.320 Mr. J. A. Rawlsten WAT/W87-320 Chief Nuclear Engineer Tennessee Valley Authority Ref TVA Itrs. TVA-Stas / 400 Commerte Avenue, W10 Citt WAT 0-4490 Raesville Tennessee 37902 0"II I' IE ftNNES$tt VALLEY AUTHORITY SE0uoVAN AND WATTS SAA NUCLEAR PLANTS Tennessee Valley Sequeyah Suse Level Transmitters 821101E0412 D Deer Mr. Raulsten The reference letter advised TVA that the containment same water level system and containment pressure system transmitters should be filled with specifically ~ processed Dew Corning DC 702 silicone oil in lieu of water. Due to a difference in the specific densities.of water and the OC.702 eil, the calibrated spans of the transmitters will have to be changed from (214 0-26 in.W.C.)to 3s> (225.4 0-14.6 in.!I.C.)forthesequeyahNuclearPlant. I Please be advised that the systas must be filled properly and a linearity check run en the transmitters after the calibration. NEB'921014 979 WESTINGHOUSE ELECTRIC CORP 0AAT10N gasestentltfe'1 6 4 W" O 4+5 M< J. L. Tain, Manager . Tennessee Valley Authority Pro,1ects b I" / EANNotnak/cm J. A. Raulstem 3L ig

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cc., e,s.gecs TE.E; #!Es' cic-:.!-tc-Ei: ;12':m ; b! t-; !!O-507..;e 05/10/1999 15123 NTB i&? !4 GIS 8.01 Attachreent No. E Sheet L of 1 L.cos W/ldentifier Seu-EEB-Ms-TI2a*6cn i S O N - S G S *,-s.".i6 7 F 1 Abstract s c e n t a n u p c.' This analvs13 was done to determine the total (camme

  • DetM coge to containment sumu level transmitters 0-i.T-o!.-176 to -170 wh a r,h were relocated to the containment raceway per DCN MQO*- A.

Tht, cal cul at t on wat. conuested uv C. N. Itchnsoorta in QIF,-BQF-SON-EP-775 FQ. RIMS # CB 5 591011 00*:J. The 40 vear. normal dore-was obtained from GENNALO-QQ1 FO. The 100 dav accident gamma dose was calculated from.TI-RPS-48 F0. The beta ccse'given in TI-RPS-48 was ad,iusted to eccount. i or.a fantte <olume in thw raceway. The methodology behind the reduced vol umes came f rom GENNAL*:-Q17 R0. Since n beta carticle witn a given energy can oniv travel a certain c1 stance, the eange, only beta carticles within their-rance can contriuute to the dose. the beta acT2 to a point with a definec mutmum rance (the distance from the cotnt to the furthest cerner an thw 2egment) is calculated by taking tne maximum bete enorav in a-definec energy group and-calculating a quarter of schere with a ractus equal to the range of that ceta energy in na r, If the range of the max 1 mum neta energy as greater F.han the height of the raceway. then a nemi-circular area times the neignt ab used. If the range of the ma::1 mum beta-energy 13 greator than half the chord of a cefinee segment. the segtrent area timen the height is used. If the volume calculated in the two orter casos results in a larger volume - than the segment, the segiment volume is used. This crocess in continuec for all 20 energy groups defined in GENNAL7-013. Each volume calcul ated in the above steo as multiplied by the pr oba0111tv that a beta particle exists in that unergy group. The orobability was calculated an GENNALO-003 R;. The sum of the products for all energy groups is the traction ot beta particles that can contribute to the beta cose. Q mocif t uc ver sion of the i j FC program f rom GENNAL!-013 w s used to calculato' the contributton. l The f rac t.i on cal cul ated bv. the code ti mes suec t i t c ' bota cose teFen from TI-RPS-40 RO (The 100 cav accident beta dose divicec-l by the volume of

c. on t a i nmen t. ) gives the new 100 day occident bete

( dose. The rusult is that the 1evel tr9nsmatters must wtth5tand a tetal cose (40 vcw normal 8 100 day accident for both rant at t un) et at l east "Oa 1Q* Reds. camma and beta, l Fiom OIR-50P-SQN-80117 RG. RIMS # CB77 80 Q505 0Q23. the elevatton of the unit 1 )ovel transmitters are thu same as the [* unit 2 level transmitters: tnerefore the total doze will De tho same as the unit 2 level te en nmt t tur>s. I w - - - - ' - - - - - - - - - - - - ~ ~ - '

SQN-SQS4-0070 by 2Ve3C Dato rhht Checked b 4F Date :P3FA 9 Page 27 'of 79 ' '~ AttacMeet No-b Sheet I af L TABLE 5 Loco s1/Idsntifier SM-EE.B-MS-T17.8-00 3 PAM Variables and 10CFR50.49 Category and Operating Times Containment Sprsv Heat Exchanger Inlet / Outlet Temperatures, Instrument Event Category OP Time TE-72-6B L A/C 30 days /31-100 days 8B RH/A C N/A 288 CV/A C N/A 31B AF C N/A AB C N/A Justification g Containment spray heat exchanger inlet / outlet temperatures are an indication of the effectiveness of cooling by the containment spray following a high energy line break (RELB) inside containment. After a LOCA, containment temperatures will have subsided within 30 days such that containment spray is no longer needed. Therefore, these instruments are required to be Category A for a LOCA for 30 days and are not required (Category, C) af ter that time. For auxiliary building events, these temperatures are not used; further, incorrect indication would not interfere with operator diagnosis of auxiliary building Therefore, these instruments are not required. for the auxiliary - events. building events. p containment Sump Water Level (WR) Instrument Event Category OP Time LT-63-176 L A 100 days 177 MS/C A 100 days 178 FW/C A 100 days 179 RH/C A 1 month CV/C A 1 month Justification g High containment water level readings alert the operator to a 8ELB inside containment and assist him in identifying the type of HELB (all events). In addit. ion, these instruments are used by the operator to switch SI to the recirculation phase for long term core cooling (all events). These instruments are required for the duration of the classified events. e 1218K

SYSTEM DESCRIPTION EAaLE 21o PROCESS PROTECTION UPGRADE SYSTEM TABLE l-1 EAGLE ANALOG INPUT BOARD PERFORNANCE SPECIFICATIONS (Cont) Atto:hment No. 7 $ Feet I my l Leon Sunely Characteristics Loop */lde. td:er54N-EEB-MS.T128-ool3 Number of loop supplies: Four Output voltage: {30ydcnominal_ Output voltage regulation: 110% maximus j Output ripple voltage: 10.1% maximus Maximum regulated current: 55 mA Short circuit current limit: 60 mA nominal, 10% Common-mode isolation: 125 vde or 125'vac ras Normal-mode overvoltage: 125 vde or 125 vac rms, with input fuse Surge withstand capability: As pec IEEE-STD-472-1974 Powce Sunoly Reauirements Nominal voltage: 15.6 vde (two sources for local auctioneering) Voltage for rated performance: 15% of nominal value Power consumption: 9.92 W maximum, 8.10 W typical, normal 15.17 W maximum, 11.70 W typical, in test 7.52 W maximum, 6.90 W typical, normal Power dissipation: 12.77 W maximum,10.50 W typical, in test Board insertion / removal: Power ON, board insertion or removal l Overload protection: Series fuse, 130% ofstated maximum current

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6 N "' i ^ I "==!== Attscomeet No-W edenM'er SGM-EEE-M& tit &-coo SETPOINT CALCULATICES EES-TI-28 l 13.0 DEFINIT 1058 AND. ABBREVIATIONS 13.1 Allowable Value (AV) - AV is defined as the analytical limit (AL) minus the difference between the Design Basis Event accuracy band (Adbe) and the normal i measurable accuracy band (Anf), which does not consider calibration unmeasurables (i.e., waterles errors, process errors, etc.). It is reasoned that following aaIdesign basis event that the output of an instrument may { change by the difference between the normal and design basis bands. Therefore, if the output exceeds the AV value during normal operation, the analytical limit would be exceeded if to design basis event occurs during this time (See subsection 15.7.4.1 notes 1 and 2). 1 g AV = AL - ( Adbo - Anf) The details of the calculations for these errors are included in Subsection 15. 13.2 p Acceptance Band (Ab) - During calibration or calibration checks, the required / deviation from the true value deemed acceptable without requiring readjustment. (An acceptance band should be selected such that the instrument inaccuracies fall within the band.) Ab should never be less than . reference accuracy. " Rule of Thumb"-Ab = 11 (Reference Accuracy) [ 13.3 Accident Accuracy (Aa) - Accuracy of a device in a harsh environment caused by an accident (excluding a seismic event). 13.4 Bias Error - The difference between the average of the measurement population and the true value. In this standard, a bias error is as error that has ai certain fixed value for a given instrument under specified conditions. The exact value of the fixed, error is unknown, however, the range of uncertainty is known. 13.5 Confidence Interval - The bounds about the measured value within which the true value is believed to lie. 13.6 Drift - An undesired change in the output over a period of time. is unrelated to the input, environment, or load. This change 'n 13.7 Instrument Society of America (ISA) 13.8 Loss of Coolant Accident (LOCA) I e e 0 am DNE4 - 0610W-

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~ CONTAINMENT TEMPE%AfURE DOUBLE ENCED PUMP SUCTION BLEAK ILOCAI AND MOST SEVERE STEAHLINE BRElik M4EL81 OOMBINED seel '" **' 'l ,,, f l lcl e l iar" 7 ~~""' % s 3 k e.s T _I suf. -l toco I usu u l';-F 2 8 % /"" Lask h l ~ \\ f I g' a 7g y..y*t s n.bg i-i" s V 1 i F 1 A,,--4 N - s I sii s a, \\ i G 63, 5_ %mT4 l ItzaerI i ete j _yreen cas.aenemi nli esor,e i sol l 1 ed Il o' 40 a s ne8 a 5. s e' a s s e* a 5 i s* a g t# a 'l time ewes a 4 c_ DEAD-ENDED COMPARTMdNT TEMPEW5TURE MOST SEVERE STEAM LINE DREAK - EFIGUeE 43 ~f s 'a m-w,n w 'I T N tf-l '1 ~ ' ' ( 'i' i' 4-.. l 8 _l_. p, f 8 m I i j ll l. . 1 !.!., i .[- 'L . II. ~ .... t L 7 .. p g,, - i., ._ q.- u _ }.i...... s.n. p'..,, g l ! 'i., , i t! ilt.h i1 - 19 - uI g J lI, lh ' !iIlli;, I ll !d I jl.i i lil % i~f[i[~~~~IT[7t ~ 3 - i i "', TF

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CONTA!NMENT PRESSURE - 00UBL.E ENCED PUMP SUCTION BRE% (LOC Al (Flevet $l weI_i._tl..,_. II l. l, lllI{ l I .I ,. j _.u _.1 p __. _a g!..,. g"E. _4 ..g,. g p. .f_ L. ' hI 5, y l,... y s [ ii., t N, ._.d is.., 3..o N ) w i,.i L_ .L _.._ I l ,14 e ta g e i Attacherent No. 9 $ beet 4 af 4 SQN EEB Ms.TI28 oo 3 Looo #/lder.tif ter DWG 41E235-4-5, REV, S

3 i i i Attachmert No. 10 $heetMf1 f l Laos W/ldenhf:er sou rta-MS.Tita oot3 P%16CT ENGINtInlN6 a ~ AtPORT NO. 1006 R$V!5!0M 6 f t 6.6.3 performance Test $eeuence I 6.6.3.1 The perform 6pce test sequence euring LOCA consisted of a series of Functional fests (Reference Paragraph 6.2) curing I the LOCA and Post LOCA environmental profile. Functional test h data were obtained before the LOCA test began, during the J q temperature transients, and 4% various times througneut the test. Figures 6-7 and 64 illustrate the relationship betweea the LOCA profiles and the Functional Test timing. 6.6.4 Perforw,nce $secifications 6.4.4.1 The performance specification for the LOCA and Post LOCA environment is as follows: t The transmitter output error due to the LOCA environment i shall not exceed 16.05 of upper range limit (URL) ] 6.6.6 g i 6.6.5.1 Performance data, including environment temperature, appears i in Figures 6-7 and 64. 6.6.5.2 Functional Test data before and gfter LOCA testing appears in T4tle 6 12. j 6.6.6 g j 6.6.6.1 As can be seen from the data in Figures 6 7 afic 64, the t?tnesHtter output error due to LOCA did not exceed 16.01 URL for Serial Net. C6439 and C6430. Serial Nos. C6414 and' C6666 i exhibited errors in excess of the specified 5:01 URL. An entlysis of the error mode displayed by Serial Nos. CM.<3 and C6565 is presented in Section 8.0 of this report. 63 - SHEET 0- M' -.,n..- .n ._.,,_..,,..__.._,.,_.-,,,-n_,...-,,

I i I w e S h '*1 4 QUALITY INFORMATION REQUEST / RELEASE (olR: { DIVISION OF NUCLEAR ENGINEERING 1 (INitfhAL V$$ 018LY1 l !"'" TR 'A7 n k 3 4 l10 M. l.. Jones. Ipst, Moll), 391 100CUMENf7 **fA ~ ~~S :: o i l fele wits 7272 5 l Fitpl F. A. Aeonte W10 0224 C 4 l 1 g lasct i er i lrrei or 00C.Enf 60*tt lc ) e a st wtt0 Ontt AUG 261987 i..............................I in u t a=0 unii m attrAsa st r. tn e wits 7 .I 508 va tt ' aad 2 i ......................."PiRMtg g e rg,,',,,,,,,,,,,,,,,,,,,,,, i l A,ailan t e la One e # me el seg t,s tems l A"mannen t *e this Qlm { lg s eent 6..iaa #meer lh i l I A >*ae*ama s ww ee, l giggeg33717) A2 tal 870024 251 l l I I I I I I 15uSJECT l SWP waftR ftM'LAATUM i l$v5ftse A7FtCTED lukt0/ST5fLM 10 l 6L 74 1 wth ] QUAI.lTY thP0funfloh MMITLD/IELtAtt0 I l Art.2 has eseeleted Its Investigetlen of se oral snelI break 10CAs (SSLOCA) es reevested in reforensa 1. I hone ef the cases investigated e,ec enAibitod the plant centIgwretten reeuested in me reforenced CIR RHR en recireviation wim ne containment sprey estivated orler to switchever). A Phase 8 signal was elways l roschee or 6er to ttie avtesetie soi tchever ef the feel to the amorgency swee. es.o.r. tor..t m. ti..e nHn s.itene e Cansewenti y, the esaimun suse l.. t., l MW57 temaerature of 10S*F. .iii me.eer = 4 eat.iv.co.i to m.,oiu.e...re,.e e m i. l 58LOCA te ll0*F ter the 2000 pel/ min $8LOCA.(br calculations shmed suse toeparature reagir1 fra l l Th. t r.tur. et the ti.e s .eter nwi sos tehe,ec sen me es,seted to re.ein beien th. t.c.tures ust l.me,.e.,mefosie.iagrees.si I l1 The escay hoet eaergy at the flee ef IDWI seitchever has been reessed substantially. l2. Fer $8LOCAs, the ejeraters see be eapested te wee the steen gener4ters to reso,e aost ei the es I

  • aertV.

\\). The PDWt heet eachsegor(s) and sentainment sprey heet enehant$f(s) have suf fielent heat rene, : i Lee, me s,..ter teaserstwo t er holes the teneocatures liste$.ne enee eeen sys,ee tr.nsitions in,e ga,ecity,, I th. e irculottee mode. l4 For the Iargn break WA ao deteribed in the FSAR, Westiaghouse has ca1outatod a tentInu l active suas tesseraters stil all the les is melted. The sway temperature thee rises aeorselestely l e*;e to the relatively high desey heet level of the LaLOCA et les melt versus that of the $8LOCAs at10'r I Ice mel, l The above results will be documented in calevletlen fl.50h.APS2 034. l leurAnto N latvitut0 (ntLtAsts Osa l e.a . k.a.J. 'ehrin ! kawa m.7) g,,a. //ste 'vPftovt0 (&AANCH CHitF/P40JLCT tesGiwltRP Artscherient No - Il $ beet I af 1 y/gg Looo d/ldentdier *M-M&M-Tuo E3 w= amu,4 a =se mm v.s..~. gso t

wo.. ~... ; w QUALITY INFORMATION REQUEST / RELEASE (Ql DIVISION OF NUCLEAR ENGINEERING (INTtalaAL W54 ONLY1 !"'"' V4Y '870326 260 ,70 R. C. vililass. 048 05C.Pl07, 504 l 100C*ENT tapetA ^ lot seette7??l ~ lFIOi M. L. Jones. 3NE MOU). SON l l ! Pact t 0F I ITYet of Docuntwi---- lt > mtoutsi o 10Att g 251%?

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et l a,alisale la One ef *** einst f.e+ean \\baruman* l lesa'6'vlae 8h84h*P A M ammana + *e thi s ois - l... l hJ ieinetner:1,nD t aMaciv. eat Ng nas oT0eo) too I { Olfgetag717)R2 l tal 870824 154 l l l 1 1 l5UBJECT I ~ l CONTAllsetNT Sule Ltytt. UNytAIFit0 A151sFT10N I 15Y51tsel AFFICTttr -*43 -~~ ~ ~ I lustD/5YSTEA 10 LT4).4 76,.4 77. 178,.4 79 I {0uALtTY thf 0pB4ATION Rt9UtSTED/ RELIA 5tp ~~~ g l mtB/W5 2 has cr.nelated its investigetlen of several Smell tream LOCAs (SBLOCA) e o -- I ene 2. la all cases investigated ($00. 1000., and 2000 get/ain $bLOCAs), ttie etassaneri e n refeceases i , sect switchever tras tne 8tf5T to the senteirament sume.ene crane sell at ' tie locat s tessereture outslee ee of ttie evemotic i m ei,e..,de.em sizes is as teil..si The maalman etessaneric temperature et the svitenes for I l troen $lse stem Tamperature (*F) et (T41 \\ inal/eia) .376. .177 379..179 l l 900 IO7 l 8000 108 \\ 2000 124 l 1 The eso,e results will be ensusented la calculotten fl.50N4PS2 418. I I I I I \\ I l-lemuAnto ra) IRivitwt0 (atttAsas Outn l

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8l25'/ 97 ] W hddh.h 1.h41 ( APP 9Cvt0 t& RANCH OlltF/PRDJECT, ()[lGlhttR) >M/[M jd Attst,bmer't No. II - $bett S #f Loco vietetifetSQil EE8-MS.T128 ool3{ sc8F9 (DNE-CA4-861/ .. ( A t tec wea t si t A t MS, 54, e4 - ~

  • W. S OnL4.astt.ca/24157 01070 C. W. Seecator, vg 0802 C.A
0. v Rewghley. 4 Cl26 C.K J. B. Hosmer, DNE. CSC.4, Scal w6 t uwi, vl0 Cl26 C4 I

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A JfN-Q9 0&1r;.E 06144 IDtHIV5CH-GOstG -4;.19:9 TEL tC: W 6 Pa2 'QO TU / cp is 15sda ..< w + w e. 6 hesia i.e-w ++ p e cet o x o 'c,o e.u wa teso tutc.a.9) DNE CALCULATIONS DA_ Record T IT L.f. PLAlt1/LMit erstamwtut erstewtr MQMPMt tttu tt1Me.emwi r;tFnts W mittIhi PetfAnt u ctetstrttlen (tv het'ns (censuit R!n> Otscairtcas List) ) est/mr mstto. 'eeA Htuver. trwettmar ta.v:=::::: :0j::11rm.: t..:. u ii.e.. s. w).ui.n.. .....y. prwervre assi erovre tan toe ensinei t=vi um e, tee.,on e.,e,,e m io,in. SQNAPS20$8 - 'av " - n wr use) uni greenin. ar BO'4 '90 0 :.08 30 0

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4 8 lAtlittl0h!$) p!D SYlftMS A.,, w/a w/a _ Devtiton 0 l el if R3 (CN ho.(Or E01 AppflCatle) tafulv.Petat.r' vea ff) Na f 1 N/A llettment Cf Ir08308 Pr se Determine the following infomallen for twll .C asw r # A r briek itse.cf t:Dient assid:nte of 800. 2000 C et. and 2000 gal /ala in w* tith all tetok water fleet W to into the teetter tevity! _ had !) Timo to reach Phase $ signs). u A" .' e e

1) Amouf4 of ice melted at 8'R twitt: hover.

m. j Cate

3) (mergency sump volsee et AHR eeltc. hover.

N W""*

4) bead ended compartment teirp st RIR twitchover

__ %a s,, /9870 $) (mergency sump tamperature et RHit switthover.. g (fit eli p pu oddeo ov m e.. u es T.o snelyon ihov1d be rerfomos for och breeks one anunine the.. In.or co,.netinent coeter. Liet all teste (elc.ted by this tevitiesi-oprote until the Phase il stenal occurs, eart tha cther essening no coolers coerate at any tire. t t t v o Abstr8Ct l These calcunnibne contain an weierif ted utveptiom(s) that must be verif ted later. Yes ( ) to(K) 6 The Porrase for thit calculatice in to te. pond to three Qvality Information Reevests: QlR N(8 all?) At. QlR, $(6 87113 20, and Qlt !!l C?)fl $... A Mdel an titt vp to etterste the roerter cavity feta the lower statertinent le en e y. Corstent rats and efergy flown of 400.1000.. ne4 2000 gel /eto wert 60$td to this reatter cavity region, v. for constant break lens of 2$0. and !!0 gal / min (with tio 10wer tooltis) ere acted in provide 40dition61 In Acoltional runs the follpwing reiv)Je were obtainerf: h3 (C'.-(R 400L(ill Iren etre (gst/ min) f>t([ LOVCR C00(tts WO 1000 t000 500 1000 reg 0 II*etoreachPhasa'8(seconds) 481 100 to til 802. p ice mettod et switdover(il ltt?S6 280776 50!908 141415 2408 3 44341g Sw*n volu*e et twlt hover (ft) 29114 30 % 6 $t238 tiill 30330 31613 Cesd ences tercerat steets/o('F) 109 110 113 It0 111 114 lt",Lerp st sattchwer('F) 106 101 106 100 107 10s C >t velvet represto t d above do not incisor the effects of b'strui.ent arror. l ) Hiernf h ett stor colsulations in Alps service teuer. t en mem es!.. turn eniygmi m L h v'" Attachment No.-- R Sheet I 'f 1 et, klx5.st 28 C.K W #idcWiersnn-rrnJtt-n an nni'3 ~ l

BINDER NO. SQ10-I[E981 MANUFACTURER Gouto/sI4inast Isam5sgliTER$_ PAGE 2 OF 2 TAB A - EQUIPMENT IDENilFICATION fRTRIX (Mti DEVICE HDDEL NO./ JDCallL CAI OPERATING MITjGAIING LU15 IfL _ID NO. DLICRIPTION [0FifRACT NO. [Lly RQWI JL _fCCIDiE SAFETY fimCTIM SQfs-2-1 I-063-0176-D 2-LT-63-IT6 Cl TNT SUMP PD3200-400 680*3" C-RW A 1000 L.MS/W.FW/C PROVIDES SI9 tat 70 ttYtt XMTR 22-XX-XX A IMO RH/C.CV/C All0W SWITCHOVER FROM 89NtD-74929A 1% RWST TO THE CNTMTSUMP. MUST FUNCIIONTO MEET NUREG 0737 (II.F.1 PART 5) SQ 2-2-t i-063- 0171-E 2-ti-63-177 CNTMT SUMP PD3200-400-2?- 680*3" C-RW A 1000 L.MS/W.FW/C PROVIDES SIOest T0 tEVEt mMia 22-xt-XX A iMD RH/C.CV/C Alt 0W SWITCHovER TROM 89NtD-74929A RW5T TO THE CNINT SUMP. MUST FUNCTION TO MEET NUREG 0737 (II.T.1 PART 5) 5(;fs-2. t I- 003-0 t 70-F 2-4 T-63-3 78 CHTMT SUMP P03200-400 680*3" C-RW A 1000 L.MS/W.FW/C PROVIDE 5 SI984L 10 LEVEL XMTR 22-XX-XX A IMO RH/C.CV/C ALLOW SWITCHOWER FROM 89410-74929A THE RWST T0*THC CNTMI5 UMP. MUST tn FUNCTION TO MEET leUREG 1* 0737 (II.F.1 PART 5) rw 5fst t i-063-O l19-G 2-tf-63-179 CNIMT SUMP PD3200-400 680*3* C-RW A 1000 L.MS/W.FW/C PROVIDE STOIAL TO 8W d LEVEL XMIR 22-XX-XX A IMO RM/C.CV/C ALLOW SWIICHOWER FROM 89N!D-74929A h, THC RWST TO THE CNTMT SUMP. MUST FUNCTION N TO MEET feUREG 0737 (II.T.1 PART 5) '-j

  • Elevations sts.m are #itual elevations for equipment located

'in tie Reactor Building and flggr elevations for equipment located a a R outside the Reactor Building. /.1041 elevations for all equipment Preparer /Date IRI2 4-27-n are documented in IAB f. See SQEP-125 for Reactor Building abbreviation definitions. Checked /Date T.I fI, / *' F - 6

    • 5ee Page 8-1 fer source of Category and Operating Time Assignments.

V ( 0209. nim...mst No U Sheeg_1, of I IHFORM TIOJJ FOR UmT.L WILL BE SIMILAR.

flav 2 0,9 9 12 : 5 2 STATHAM ::: /,.;;;,;;g g 7g33g f.g,3 Attechreeet No, l+ $pe,, L f, 3,, Loes W/ldentifier54*HB-Ma-T12a cot 3 Mike Mustafa and fred Riva 70: FRON: Steve Zager DEPT: Marketing baTC: 11-27.-88 COPD: David Ko FAKf: 615 643 7689 SUSJECT: TEMPERATURE EFFECTS OF $TATHAM P3200 SERIt$ paar Mr. Mustata, e Pursuant to your recent discussion with David Wo of as sending the following information in

Statham, alarification of the referenced sumject.

As a catalng specification stathan must Itst both the minimum and sowimum errore for the entire product line. This includes all pressure ranges for both the maximum and mininua open (LRL). In this manner we are span (URL) accurately expressing errors without prior knowiedge of the specific pressure range and desired calibration for 1 each application. The catalog specitication is therefore a guideline in which the unct can comport and anticipate the maximum deviatione from the bemaline accuracy. This specification should not be utilised to anticipate the g performanew for each individual prese.ure range. exact P3200 Catalog Specification 11.55/2000F at the maximum span (URL) 15.04/200 F at the minimum span (LRL) 0 During the manufacture of all (100%) Pi?no series nuclear l qualified electronic pressure trancaitters at St.athas, the units are calibrated to the exacting pressure range am specified by the user, then temperature enapensated at this ca11bration to optimise performance. In this manner ( the temperature induced errore are minimited because no additional turndown (signal amplifiention) is required i after campensation. Thue it can not be aveumed that a particular presouro range operating below the spoolfied I will indicato exaggerated thermal maximum span (URL), errore of nearer 5% as suggested by the minimum span 5 specification of the catalog. l = t 0 h l 0 I

Hov 22,se 12:53 STATHAM DIV.-3OLATRON TRAN50UCERS .....n P.*3 J i Attachtreet No-IO SheetMf 1. t.coe W/ldentifier htth&EAdQS.H& 2213 Por this reason we ef ter the fo110 wing equation to arrive mora.aocurately at a convenient expression that relates the ambient temperature effect to the transmitter's oaaibratad apan. yamx+b where y a maximum ambient temperature ef fect as par. cont (4),of calibrated span................................ m a slope of the line x e amplitiar galh b = y lntercept of the 11ne solving for slope a................................... y 5-1.5 =0.8h5 g. = x 5-1 Put a into the equation and solve for k................ yama+b 1.5 = 0.875 1.5,0.075 =(1) + b b = 0.625 Thus.................................................... y = 0.875 x + 0.625 'ince the amplifier gain in simply the ratio betwoon the naminue und calibrated span, the above equation can be simplified te the following............................. maatsum span x=- cal 1brated span a. Martmum ambient tems =0.865(c(maximumspan) effect 5 calibrated per206'F alibrated span) 3s A 8(o "> (4"/E40) 4 0,61f ?.E.bl.1b s w c m,,,,, w

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t i QUALITY INFOR44Afl0N REQUER / RELEASE (QIR) N5p-3 OlV4480N OF NUCLEAR ENelNGERING metammenew.3 i =venmaa, we enn,v s ames i es, ah "' Tid 'im 4 ,nn asc ,ty) f. S r n i < Me.@ osa eopna M t U 9 A' o i mr.o .m o- '*** 'A 3in ea l y - Re-A '"* * ' ** A m oseu.., mars ._O___neopes7 weep Oars M n8L8 Ass ___.......... -_... _.____../2-f-8B i j ASP. 01A SC2A/ C/A// 7" E. n PERthC80 DOCUMSNTE .. mu,. r... e mei. ( _ 000WuGN? .m ent,. v

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me ~ ma ,eu.sr D^'"^M di~ <4d-d'4aw t/gp J.re en' ?- t 7-l,3 /7k /77 l"I8 A* ' H* Ysed" LAvn.sen4 Mom / /d TMs A/L /A//s,s, ' Br / SifM We"0 UhA/ J$'.saneer" as A/78 C,4g ey,,ju. Sc]g/n M $ 2 -e@ f'; M, / Attachment No. 15 Sheet I ^f 2a., L, y ggn,peramu EEE-MS-TitA-ool3 T]llb dt.lf $VfEACEOGD 61 cat.t. $$.9-SG 52.-00 67 Rebl Rgy,\\ SEE SHE.5 T 2 0F1 of This ArrAcamENT pngpARGO ROYl8W90 lROL4Asta Y Yh 9 ISRA4fCN CMIEP/PROJ8CT EN0lNSERI / L,./*) l[ j N . 0. 0Y$& '*" ? tvA 1085910888448) r.i.ripfl V h 9f,fe WY 6 p, W.L 1/i&, Me-A S4p' / I ...-m -,.a.- - - - - - - - - - - * ^ ' " "

i er, e,; End *E.Eue:E8 cic 5-10 56 atwm: $;5 t.: g ;s. ,g;,,,, 'l 05<10 1969 14 ?9 NTS 619 543 !I16 p.c; ) WA.*3-t" / " i n )i i DNE CALCULATIONS \\ >.. yr n y $.,, t, rva ionet tDweessi s f Title CON 4 EA S A Tt* N GN TMs ' N#e s4, W u s, ope VS#v t P t.ANiiu'vi f y,j, 7,.,., i LlMS TW @h fe M M i8 wN sT L .mePanise0 0RGAftetAt:0g KEY NOUNS (Conevil alMi DESCRIPTORS Li&Tl N t lteTim Core % skMN. VrAi T h9,n I,. Av m o un.onc , Aem, erm > DRA8eCMAPM0 JECT ID4hTifIERS tesh "'n'.i'** **6:wimA are swuos, preseren awn em toe oeipaes im0) miws me ~, . si-in. 3, y,,,,,, n aus. i.nno,,,. n., nus vesi, a-890127F0057 ses 89011a a37 A,<,cA.u..... oocu.~,.. ggg3,y,,, M V B25 890510 823l @

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884e aNeen sesi # m as @<T* oeie Q. pg, d*,dfaff AiLEC 74 si A4 eve, yet el( pages acoes ON 6 sesame 6-tw# 5 Le e.sise d.s o 1. es, j* by this revielen. O,'s y g g pin,N g Tug g,,.,uf, y ees suavgA -}1' u it en pe. oeietes s.ascree to core esa en Gaci+ ld'i by this tevision. /I4- %7 g,, 4, veien. e.,en o v. u i. v. pv mi. c mi.n. 8,ia, ic, i.e Abetreet These calculations contein en unverifies assumption (s) that inutt be votified later. Yet O No S '> e E ATTACHEQ Attachreetit No, 16 $ beet 1 f ir, Laos # / ldntifi e r 68tW

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Attschm:nt N2. - I(* Sh:et I atl Loop d/ldentifistm-tum.ns vism.coi3 .i 4 ] SIN 0gR NO. IoMEo* FEME-004 Pt. ANT 10N UNITI5) 1 AND 2 ggggy 1 0F 1 R 14 m 1 SIN 0gR TITLg Vtt*ncaoctt f"Aw11*ER COMPUTgG DDD DATg 11/10/R$ atx ru 3/24/37 I/7/87. L ttrentait Petrrmnen f tet/cifi CHgCxg0 ktM OATg 11/19/85 Tso VM 3/26/47 5 43/37 j l TABLE Cy CCirTENTS gg i l 1. Digital Engineering System 1000 Material Aging Data 1. Analysis of Epony Seel/ Petting Lif e 3. Analysis of Ampetity Test l 4 Analysis of Short Circuit Tests T. ' ~~ 5141 Li'Tia tien ' Analystr~vFOkeaite/Okeprese Pig alle 6.' Qaalifitation Analysis of lestrad 7 Pigtails 7. Justificaties of Sequence and Response to NBC Questies en Separate Eff ects Testing 3. Justifitation of Operatics Time l 9. Basis f or C4tegory and 0perting Time Assignments

10. Analysis of Short-Time Overload capability j

11. Response to NRC Questies en IR Measurements 1

12. Justification f or 1/4-inch Raychen Splice Overlap on Neopreae-Jacketed Okenite Pigtails
13. Qualifisaties Analysis of Eerite ITE Pigtails 14 Pos t-Aasident Operating Time Extraplaties f or PEU-RLK-3-26-73 M

i l i PAGE d' i enset ? 49 TVA 19537103 3.g31 - * ~ ~ ~ ~ ~ -. I. -.

ii i Attachm:et Na - W Sheet 1f1 ) Looe W/ldentifier SGW-EEE-M1-T12A-eeG glNDgM NO. 80"IC"EUI'004 PLANT SCN UNITIS) I AND 2 $HEgT I op. glNOgR TITLg DCMOUst CANISTER COMPUTED CATE DC ElLICTRICAL ptNETRATION (LYF/C&I) CHECKfD DArg i - n. e.. ret?CN$t TO OUISTION COWUIANINC tR Mt.ASURNIN*3 SURINC *!STtNC (SQNtQ-FENE-QO4) e NRC QUTST!CNt ~ It appears that 11 (Lasulation resistance) asasurements were not conducted tu,gigg,the LOCA test of Westinghouen canister eteatrical penetrastese. If this is the case, how do you kaev i that ihstrumentaties circuits will perform se required 7-~ ~ Rennennet The test report (pp-RL1-26-73 binder page D-15) states that ) the lowest IR asasured during the test was 2.5 x 10 shes got l i 30 conductors and af ter the test 29 had better than 6 a 10 obas for the la AMG instruneatation conductors (page 0-17). 4 The report states the It asasurements were takaa every neur during the LOCA test (page D-17). se further detail with respect to IR asasurement is gives in the test report. t Since the Its asseured were acceptable, it is apparest to perassent damage had takaa place. The primary cause of It i i degradation during peak accident conditions is due to asisture j permeating through the pigtail sonductor jacket /issulation Some 13 drop may also occur due to sciature permeating l systes. through the epory petting to the.isternal pigtail sonnectica area but this is salikely due to the meisture resistance sad thickness of the pettlag. Desage to the opeuy petting / sealing systou toads to be permanent and would be evidensed in the 11 or leak rate testing. There is se evidence, therefore, of peraament damage. '!be only other area of concern is the penetration pigtails. The 8eguoyah pigtails are separately qualified by tests that includsd IR tests during test conditions well La escess of Sequoyah's with acceptable gg - regalts.- Okemite report 141 (biadgr page D-214) shove a minimum It during test of 0.5 a 10 olme per 1000 feet. Westinghemse report PD-TR-75-19 (binder pa'ge D-144) covering terite l'It pigtails shows a sinimum It during test of 5 a 10 i gg5 The Qualification Analysis of lastrad 7 pigtails (binger'; ehas. page C-51) shoes a alaisum 11 during various tests of 7 a 10 ohns. In addities, the pigtails were esposed to direct impingessent of chemical spray. gewever, the penetration pigtails at Segueyah are located inside the penetration j junction bem and are protected from direct lapingement of i chemical spray. Therefore. Il values can be aspected to be ' higher than the test values. The connected instrumentation loads f ed through these penetrations fall into category III as listed in SQNtQ-CEN-001. PAGEM .c57e n.ot m....,,..,..... _ _ _, _ _._ _d.

l ) Attacnment No. IG Sheet l of.,1. Looo c/ldenhfier *A"-EfB-MS-T128 e t3l l SINDER NO. NNIQ*.ftWI-004ptANT SGW UNIT ($1 1.AND,2 gnggi,,,,,! op, 1 j il~m n. m SINogR Titte WI571NGHolfSt CANIE COMPUTED /Ri DDD D ATg 1/16/ %, ML'M 3/ 26/ 07 M(I i .ElgRICAL PEMETRATION (},VP/C61) CHECKED /Ri /lLM f W r 1/17/5 T3.0" _6M i i '3/F67 set /67, l ,gg;ggicz emravin it watttneurirts attafM ?tittun ( 2G NIQ.PtWE.00ll) (Continued) The Category I!! cables associated with these penetratiens (M8 s.nd instrumentaticn level cable) can be divided into three basio l groups based on the end devices. g Dayina.Funation 1 Switches 2 Transmittore 3 PTDs and Acoustic honitora The sinisq insulatten resistgnce measured in any of the LOCA tests k was 5 x {0 ohas (the 0.5 x to ohns/1000 ft can be converted to 2 5 x 10 ohns for 20 feet for a typical per.etrattori application). The effect of this IR on switch circuits is negligible since the voltage and current are relatively high. The effect on the i acoustic monitoring circuits is also negligible. See EQ Binder 7 l SCNEQ.!!T 001. The effect on transsitter and RfD oircuits can also l be shown to be negligible se demonstrated below. l 1 The methodology used in OE calculation 50N-107 39 can be used to I eh1.- L i evaluatt the effect of this IR value. Note that the test lonath and the installed length are the same and therefore, the IR value i is not adjusted,for cable length. For transsitters, substituting the IR value of SM ohma the effective IR is 5M + SM ohns : 10M ohns. AT 500 VDC the leakage current would be : 500 V/10M chas = 0.05 mA AT 73 Vf4 liasisua leakage would be l (73/500) x 0.05 mA e 0.0073 m( l t PAGFo-"/S* 1 TVA 19537 40E.3 8el

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Attachment N3.- Ib. Sheet 4 ^f 0L. 1.003 #/ldentifier 5964-EEB k45-T12b*e3 tin 0tA NO. 50 N tQ-PEN.*-00' PLANT SON UNITISI 1 MD 2 _. _ SHEET IA 2 I Op T R m 'u SINDER f(fl.g VISTINCMOUSE CANISTER COMPUTED DATE __ T v_ / E so W8s it... s.7 E:.tC3! CAL PENT!1tA!!0N (t??/C&:) CHECKt0 DATg _ 35.R <J s. l .... n.n.g i : i ' ne error due to current leakage is then 0.0073 mA / 40 mA a 100 e + 0.0181 et s pan. l l r., ano ti..f f estiv. :n is i un on.. sx ossen:.sn si.e t ne sensed resistance is. 4!!.147 uM 458.147 + 3x The crror due to current leakage is then: 4?!.' - 4?t.14? a 100 * -0.01 454.147 lased on our evaluation of $be penetration application and the test results of the penetration canister and the pigtails, we constude that the Vesting-house canister penetrations -demonstrated acceptable perf ormance for their applications at Sequoyah. I l I \\ l l k ? l t l PAGE 0 * A A 'Y TVA 1953710E.3 461 ~ pggg,g .J

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4.s -s' ..r-f...:.s - 12 15ec8 10 23 9 805 487 7129 SCHLW.BERCER 2 002 = T0: UNITED ENG"NEER$ CORP ATTN: Mike Mustada DA@E: FA David Ko T 12-14-88 FAX #: 615 843 7689 5UBJECT: PD/PON3200 NOCLEAR QUALIFICATION The Statham Model PD/ PDM 3200 differential pressure transmitters have been palified for submergence testing per Stathan Engineering Report 0648-64-200-NUC-0711. The sero output of the differential pressure transmitter, s/NtC6431 in five ($) feet of water for 14 days is within 10.25% FS (See Table 6-1 of statham Engineering Report 0648-a4-200-NUC-0711). The accuracy of the transmitter after submergence testing is within 10.25% FS (See Table 6-3 of Statham Engineering Report 0648-W4-200-NUC-0711). h e Full Scale output of transmitter 3/NIC6432 which apparently shifted 1.5% FS during submergence testing was due to span pot movement during test set-up. It is a handling error not related to submergence performance. should you have any further questions, please do not hesitate to contec: the undersigned. Best Regards, hJ M V David No Senior Engineer Attachment No.- I7 _$best I afi cci P.tesoren. J.sett m-MB-M 28 W I

I, QUALITY INFORMATION REQUEST / RELEASE (Q1R) DIVISION OF NUCLEAR ENGINEER!NS (Internal Une Ontv) IRIMS ACC g Qh Q ITO M.. R. Sedlac1k IDOCUMENT NUMDER ~ I ran. DBC-P. SQNP l IFROM V. A. Bianco Q1RNTBSQN98220 t IPAGE 1 OF 1 NT3. DRC-A. SONP 1 t iTYPE OF DOCUMENT I IDATE f( ) REQUEST NEED DAT I 1-~~~~~~-~~~~~~~~~~~- E l_ 8/1/98 1 ~~~----*----~~~1 PLANT AND UNIT !(Y)RELEAEE REF. OtR I I SQN 1 &2 I _. REFERENCED DOCUMENTS i i Available in the RIMS tvatema i Attachment to thtm OIR I I Qgcument. Identifvine N g lDocument I Attachment NumberI ISDN-OSG7-0042 345 870601 426 i ISON-SQS4-0104 845 950726 426 I i I t i I l t ISUBJECT i i Maximum allowable margin for containment sump I instrument error ! I. at switchever in the actitive direction. ISYSTEMS AFFECTED I 63.72.74 IUNID/ SYSTEM ID ,1 l I n/a lOUALITY INFORMATION REQUESTED / RELEASED l i l i This is the lowest RWST level by whir.h the automatic switchover I 1 been stopped by the time the level reaches 31.2 inches. sequence mus I I I lowest level at which it This is the I is known that vortexing will not occur in I the RWST. Based on a sump i level of 3.65 feet corresponding to a RWST I I invol of 154.08 inches (SON-SGS4-0104), the 110.4 inches in the RW3T t I is equivalent Thus the maximum allowable margin for sumpto a water depth of 5.03 feet in th 1 sumo. I level instrument error in i I the positive direction is 2.28 feet setpoint of 2.75 feet for automatic switchover).(5.03 feet minus sump permissive I i I 1 i t I I i I 1 1 I I I I I s 1 l - i ! PREPARED I 1 REVIEWED (RELEASES ONLY) I $$ $Awl. t 1 APP VED(2NCHCHIP%JECTENGINEER) w asw e/e sa TVA 10829 (DNE-6f/6) - (AttachmentsM RIMS, SL 26 C-K cc Attachment No. I8 Sheet-_L__af L.aos $/ldentifierm-rnm ann _nnis 'i 8

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INATION OF MINIMUM LEVEL IN CONTAINMprr SUMP AT TIME OF SWITCHOVER TO RECIRCULATION HODE TOR REVI5 ION L0G A SMALL LOCA SQN-SQS4-0104 ~r a** * ~ DESCRIPTION OF REVislON 4,$'Z.. Lower compartment volumes have been changed to agree with 1 the recalculated volumes in reference 10.1. Section 7.5 j has been revised to consider more realistic estimates of 4'/f p t water in the containment sump. Other sections changed and references 10.5 and.10.6 added to support and reflect the above. Section 9.0. Additional Water Available al comotetton of Switchover has been coleted ano subsequent sections renumbereo accordingly. 2

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4,9c, h lqf APPcU: gp.g w '~ " Attachment No. 19 Sheatif IE 1 . % d**eim,SQN-EEB-MS-TI28-0013 T I

4 ATTACHNENT TO ADNINISTRATIVE PROCf; DIM f:/.D 1.03 Page 1 of 3 SUPPLINENTAL REQUIEW.;.T tua OALCEATION PREPARATION AND RETnte ~ Calculaties '1 tie D fM e a 'nu Et u i -^u e o Yd iS 7 a Mmb a mA L en .e e eVA 6 M kMa Identifier: SON- -d Id4 Ml kOca,. og / sek U 1 Preparer Checker Reviewer 4 1. The ' statement of problem" on the cover sheet is a clear, concise description of the actual problem addressed by the calculation. t i 2. l The " abstract" on 's cover sheet i 1s clear, concise and captures the essential nature of the calculation. As worded, it provides a high level stand-alone description suitable for use by researchers who must consider the applicability of a large number of calculations. Abstracts should be less than 250 words in-length and suitable for inclusion in a computer data base. Sufficient bactaround is provided M 3. (or referenced) such that future users can appreciate this calculation in the contest of the .c actual factors or concerns which i initiated it. A clear statomient of the purpose /2d 4 of the calculation is provided, i 5. Inputs, lacluding codes, standards and regulatory requirements have been correctly selected, reforested and applied. g On Attachefterit No-I9 Sheedf Loog si/ldsrttifist O' DNt1 - 3323Q NE8 1/13/87 e i' i 3

ATTACHNENT TO ADNINISTRATIVE PROCEDUtt SA3p 1.02 Page 2 of 3 SUPPLENENTAL REQUIRERENT FOR CALCULATION PREPARATION AND REVIEW 4 Preparer Checker Reviewer 6. References indicate document name, number.l ata and revision level. Yf~aWropriate, a distinctica is ~ ~ ~ ~ ~ ~ ' - " made between references used for background and those used as a basis for the calculation, g p 7. Assumptions are adequately identified and documented. l W 8. All unverified assumptions are clearly identified. f K 9. Action has been identified in the ( calculation for resolution of all I unverified assumptions (e.g., QIR number requestin's needed f information or other action is y noted in the calculation). i 5 als N/A 10. The calculations methods / / 4 (including assumptions) are reasonable, appropriate and based M$ on sound engineering principles. 11. Limits of the calculation are readily apparent. i.e.. a calculation may be conservative for its purpose, but non-conservative for other uses. The calculation should be so clear

t. hat its alsuse is unilhely.

/2d 12. The calculation process is complete and accurate. M 13. Consideration of system performance. safety margi,ns is adoquate. fg DNE1 - 3323Q 4o I9 Sheet 11 sfl NES 1/13/87 g, ggnng;,, SQN-EEB-MS -TI2P-00G l-

T L m To Page 3 of 3 43333 3g34r173 pgDCEDU33 8487 1.02 suppuumst&L angarramuser poa cALeutarzos Fampanastos Ano anytau 4 Preparer checker Reviewer. 14. consideratism of applicable b eedes, standards and regulatory k ko j requirements is adequate bI M4 i r 15. consideration of operational fasters (e.g., asse ptions on operater actions) is adequate. ' OInf 4 16. j Results have been stated clearly and asasisely. M l 17. masults completely address the initiatias sensern. 18. An attempt has been to flag features er assumptions that would 4 be particularly sensitive te i i possible future plant shanges. Partjeular care should be takaa to identify known subtle mechanisms I whereby a future ECW could invalidata the sonalusion reached in the calculation. {f 19. Revisions which void calculations provide adequate justification and why the calculation any be I s ~ l Attachment No-19 . Sheet 1 f Loco si/identifierSON-EFR-MATTM-nnG ' DEE4 - 1016Q BER 10/87 N I-

QA Reaord TVA 10697 (DNE 6-84) ITITLE CONTAINMENT SUMP MINIMUM LEVEL AT TIME OF IFLANT/ UNIT I ISWITCHOVER TO RECIRCULATION MODE FOR A LARGE LOCA ! SON 1 SO t IPreparing Organization i Key Nouns (Consult RIMS Descriptors Last) i DNE/ NEB /BDB4 1 Water Level i IBranch/ Project i Each time these calculations are issued, t !!dentifiers I preparers must ensure that the original' I l SQN-OSG7-0003 I (RO) RIMS accession number is filled in. t l t Rev (fer RIMS use) RIMS ACC NO I IApplicatie Design i RO I I I IDocuments i 1 860102E0068 1 945 '951019 005 1 l*M:ni:'s:, l "' l uxlacca l wn aus na l l5^"5S'""- l ^2 l 1848 '88 n7o7 42 ci 2 IUNID Eystems i Rh i I t i N/A 1 1 1* I l Revision O 1 R4 1 R5 1 R6 ISafety Related" Yes!X1Not il IECN No. (or N/A)! I I IStatement of Problem i I N/A t N/A i N/A I I I IPrepared IM.S. i?2awwq #.1 IDetermine if assumptions t 1 E. J. Sheehv 1Andriu11114-s6 /W1 Imade in other documents that! IChecked ID.K. I I Ithe water depth in the 1 R. L. Cl ar k 1Rhyne 1 ! active sump will always be 1 1 Reviewed ID.G. I I B. K. Williams !Renfro > Ah7$1 g lat least ' t.2 f eet at the i lonset of the switchover to I Approved IV.A. Kk d, M'I ! recirculation mode are I H. E. McCennell !Blanco $LWA MA/<0 Ivalid for a large LOCA 1 IDate i I / f I i 1 ~ 1 12/18/85 t 5/6/891 7/7/fD 1 I IList pages added i I I / I I I lbv this revision t t I i ~ 1 List pages deleted! I I I I lbv this revision I 1 1 1 IList pages changedt 14-7,11-1 I I lbv this revision I all 113.15 t i 1 i I 1 Abstract i 1 t IThese calculations contain an unverified assumption (s) I lthat must be verified later. Yes __ No 1. 1 I \\ IA study of the water level in the containment sump following a large t ILOCA was performed. This study used assumptions that are conservative I trelative to minimum water level. The'resultssof the study show that thet Iminimum water level occurs for a break located at the reactor vessel t-Inozzle which floods the reactor cavity. At the initiation of switchovert 'lto the recirculation mode (RHR pumps realign to the sump) the minimum 1 Rf twater level will be 12.4 feet (el 692.20). At the completion of I lewitchover (CSS pumps realign to the sump) enough additional water wi11 1' ({ { thave entered the sump to bring the %ater level to 15.9 f eet (el 695.78) l' ISome of this water will flow through the unsealed penetrations in.the I tcrane wall above el 693.0. Therefore, at the onset of switchover the I twater level will be below the 13.2 foot level, but will increase to at t, lleast 13.2 feet at the completion of swi tchover. 1 I t i NOTE: This computer generated form has been reviewed / compared with thel form in NEP 3.1. 1 I X Microfilm and return calculation to David Renfro MU225BCP-K I l cc: RIMS, SL 26 C-K Attachment No-

2. 0 Sheet 1 ^f 23 o a na -

ner_a, ann t..,. y ~ g.SQH-EEB-M5-TI28-0013 l

TvA 106g7 remE.on.4.as) DNF CAIculATIONS QA Rem"3 l Title CX3ffAlleGJff Star M181184JM LEVEL AT TIME OF SwlTCHOVER TO REclRCULAfl0N 800E (Plant / Unit. ~[ F(5t A LAlm ie I SON I and 2 l aremering Organisstlen M /4ER/0987 l KEY NOUltS (Consult RIMS ooscriptors List) -l l Water level g iranch/ Project lemattflers lEach time ttiese calculations are issued, properors must ensure that the _{ l l original (M)) Rip 6 accession neeer is filled in. l l S1210547.G2 l siev (for RIM 5' use) DIMS ACCECQ' M JUMBER _j ) i l l l l ~' l l l #0 l 860102E0069 l 649 896269 229 1 l Applicable ossign o mont(s) - l .i I I l SON-0C.V.13.g.S lAl l 86120900005 I 845 861820 996 \\ l sou-oC.v.27.3 l l l 1 l_ SON.E.V.27.4 & '0" 0C.V.27.5 l R2 l 970919E0029 A B49 870906 427 l Ir"Na':'6 l,T, '"-"> !, l8 7 09 01 B 0 0 4 0 (.@B45 '87 0 8 2 6-426_j i l Revision 0 i 44 1 42 i R3 ISafetv.celated? Yes (r) No ( ) { lECM leo. (or indicato leet Applicable)l l l l Statement of Preelen l N/A l N/A I ECN 68S3 l l l lPropered loetermine if assumptlens previously made In l lMinne B. \\Minne B. lM d' lother documents that the water depth in tSe l lE,J.Sheehv IKine lKine l Checked I 8 Whl active sume will alweys be et least 13.2 feet l it. J. \\M. A. ( ('lettheonsetoftheswitchevertorecircule-l lR.L. Clark ISheehv ISeehal l l Reviewed ltlenmodoarevalidforalargeLOCA. l lR. S. lR. S. l l8,K, Williams le W ehen flurchen ,_--s l t l Approved lM. E. lH.E. l { lH E, etConneIi !aneccz,;1I IMcConne1I r-j pl l u'4 loete l l l l l 182/18/89 111/20/86 I S/9/97 l TdUN7l l l E F0fDI l List all pages eened l l lffgggg,,ggll A10534lby +his revision l I l l F MORE lListallpagesdeleted l l l l l l SPACE lby+%Is, revision I l l g,,g l l l REQUIRED l List eli pages changed l l lJ- % l l l lby t%Is revision l l l/s.'F l l l ABSTRACT (These calculations contein an unverified asseption(s) that must be verified later. l l Yes ( ) No(x))l l A study of the water level in the contalmeent suo following a large 1.0CA was performed. l lcsspotions that are conservative relative to identification of the ninlense water level. This study used l lcre that at the onset of tfie switchover to recirculation mode of ECCS operation there will be et le lretorintheactivessp. t of l This is evea feet less than the water depth esswetions of 13.2 feet made previously in lst** doe =ents. gj l l I a.95 g,g l l l I l l l l l I l l l I r I l I Attachmenf No- '2-Sheet Z afl2. t.co, yleentifietSQN-EEB-MS -TI28-0013 I l l N l4 ) Microfilm and store calculations in RIMS Service Center l Microfilm and destroy. () r) Nierofilm 'and return calculations tot ^- ECL 0 G. PENfRO Address: W10 A52 C.K cc: RIMS, SL 26 C-K M. C. Brickey, W8 0213 C.J( H. L. Jones, ONE, DSC.A, Sequoyah ONEl.24370 l - - - - - - ^ ~ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ~ ^ ' ^

,~- l ~ J 1 TITLE 1 REVISION LCG t I CONTAINMENT SUMP MINIMUM LEVEL AT TIME CF 1 i EWITCHOVER TO RECIRCULATION MODE #CR A LARGE LCCA SCN-CSG7-0009 I I Revision ! DESCRIPTION OF REVISION Date No. 1 ! Accreved I i I i 1 4 ! General revision to refine the calculation. I I I ICorrected deficiencies in operating deck and i I I trafueling canal models, and correcteo errors in I i 11ower compartment volumes and in upper compartment! I I l atmosphere model. Portions of the calculation I troquiring long analyses and/or many computations 1 1 I thave been moved to appendices so that the main i I lbody of the calculation can maintain continuity oft I l ! purpose and clartty. Also included in this l 1 Irevision is a curve illustratsng sump level versust t l l Isump volume. I 1 I 'l g[g [gg _ l I 5 IHeviseo to reflect revision 5 of instrument I I laccuracycaQulation (ref erence 9.18). I / / 1 I I I t i 1 1 I I I I I I i I i i i 1 1 I I t t t I I I I I i 1 1 I l I I t 1 i I i l i 1 I I 1 1 I I t i l I I I I t i I t 1 1 I t i I s 1 1 I I 1 I i t i I I 1 l 1 i i I I 1 1 I Attachment No.-_ _2O Sheer E af M 1 i We W/ldsnnFeyQN-EEB-MS-TI28-00l3 1 t TVA 10534 (EN DES-4-78) f

r-- - - - -. CouTAIUMENT SUMP MINIMUM LEVEL AT TIME OF SWITCHOVER TCREVISION LQG RECIRCULATION MODE FOR A LARCE LOCA SQW-CSCF-008 i Title : " '[,' DESCRIPTION OF REVISION a.7... 1 General revision to remove over conservatism and to 11/20/86 develop a more realistic model. Added reference section. 2 changed title and revised to include background 5/5/87 (Section 1.2), and the water held up in the upper compartment atmosphere (Section 7.1). on the operating deck (section 7.2), in the accumulator rooms (section 7.3). and entering the reactor cavity through instrument penetrations (section 7.5.1). Also included additional j assumptions (sections 2.0 and 3.0) and references. (boction 11.0) added Figures 5.2-1,-5.3-1, 7.2-1. 7.2-2 7.5-1, and 7.5.2-1, and Attachment B. Recalculated volumes for containment sump, reactor cavity, and refueling canal. Also replaced all pages except Figures and Attachments with typed pages. 3 1. Deleted section 9.0 Allowable Martin for i Instrument Inaccursey, as not pertinent to this calculation. 2. Resolved unverified assumptions I 2.1 Extensions to vortex ruppressors have been verified as in place in unit 2, and not in place in unit 1. See assumption 3.14% reference 11.24 2.2 This no longer applies due to assumption 3.15 i 2.4 and 2.5 Work on curbs and drains in accumulator rooms 3 and 4 and on curbs on operating deck are field complete. (See references 11.15, 11.21. and 11.22) s 2.6 DER Calculation SQN-SQS4-0104 has determined the small LOCA to be more limiting for minimum level at switchover. 2.7 Revision to FSAR section 6.3 to take credit for RCS inventory when flooding the reactor cavity will be completed by December 1, 1987, for inclusion in the next FSAR update. Attachment No. 10 $hegg 4 af g Laco $/ldentifieSOM-FFR MS-TT28-0013 DNE1 - NEB - 31350 TV A 505 34 (EN 0114 74) I

COWTAIUMENT SUMP MINIMUM LEVEL AT TIME OF SWITCHOVER TO REVISION LOG y,,,, RECIRCULATION MODE FOR A LARCE LOCA SQN-0307-008 " 'E,',' " DESCRIPTION OF REVISION a,,U',.. 3. Changed title to reflect deletion of section 9.0 (see 1 above). L 4. j Deleted flow into reactor cavity through neutron i monitoring windows (see assumption 3.11). L saue u m s

    • Hs Clewey 5.

Changed holdup in refueling canal to reflect extensions to vortex suppressors. (See assumption 3.14). k i = s Attachment No.- 2 0 . Sheef $.gf 2.3 ' ~ Loco si/ldsntifiap0N-EEB4tS -TI28-0013 TVA 10134 (EN 0554 70) DNE1 - NEB - 3135Q l

CONTAINMDIT SLHP MINIMUM LEVEL AT T!ME OF SWITCHOVER TC REVISION LOG RECIRCULATION MODE AND ALLCWASLE MARGIN FOR RWST LEVEL Title tutM?MFW ' M A f'f"4 MV FfD A f 1Df E LOCA $0N-0SG7-008 " 'U,',' " OESCRIPTION OF REVISION a,,U',.. d[ff 1 General revision to remove over conservatism and to // f develop a more realistic model. Added reference section. 2 Changed title and revised to include background j/ (Section 1.2), and the water held up in the upper I f/// f compartment atmosphere (Section 7.1), on the operating deck (section 7.2), in the acccumulator rooms (section 7.3), and entering the reactor cavity through instrument penetrations (section 7.5.1). Also included additional assumptions (sections 2.0 and 3.0) and references (section 11.0) added Tigures 5.2-1, 5.3-1, 7.2-1, 7.2-2, 7.5-1, and 7.5.2-1, and Attachment B. Recalculated volumes for containment sump, reactor cavity, and refueling canal. Also replaced all pages except Figures and Attachments with typed pages. \\ Attochment No. 2o Shee* U -f 3 Loco si/ldentifie50N-EER-dt -TI28-0013 l DNE1 - NES - 313SQ TV A 19834 (EN DES-4 7%) C I

J l NEP 3.1 Page 1 of 1 cal.CUI.ATIC:1 DESIGN VERITICATICN (INDEPENDENT REVIEV) FOR'M I S94 - est 9-cco 8 / 5~ Calculation No. Revision Method of design verification (independent review) used (check method used): 1. Design Review- / 2. Alternate Calculation. ,1. Qualification Test-Justification (esplain below): 1 Method it In the design review method. justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods.' appropriete sensitivity studies included for confidence, etc.). Method 2: In tha alternate calculation method. identify the pages where the e.1 ternate calculation has been included in the calculation package and esplain why this method is adequate. I i Method 3: In the qualification test method identify the QA documented j source (s) where testing adequately demonstrates the adequacy of this calculation and esplain, t/swerecier/ coup onow reis ensc w on w as prept uo canvra o=/

  1. twe.wn tw,9ernover worw TA O /.02 - SUHJsM1*e tcA,stt.nswTs c'sW couner/W MrnonT/aw ese MwN, tr Aage c woonao TMg Hernes Maruuowy. Asswamous Ase Joe wnent h atest weve' - M99=dnt f. Ayc ei.,esi,rnar %irM nar# ' way 3.1 ese word can sme earu Necries-A3 Awtrax3

/N 2/mi444 CAtrainr/rWT \\ -l Attachment No. 20 sheer 1 ~t.,k?. f 7y 2 - 4 1.cosp si/ldentifierEM-mM M A An G sign ferif,ie / /Date.- (I pendent Re i wer) / - -9 r - ~ ~ ~ ~

CCNTAINMENT SUMP M!N! MUM LEVEL SHEET _ / QF /7 AT TIME OF SWITCHOVER TO RECIRCULATION MODE FOR A LARGE BREAK LOCA FREPARED BY>@Sf6' f/r#7T CHECKED BY D FM SQN-OSG7-0008 R4 1.0 PURPOSE AND BACKGeOUND 1.1 Purcess The purpose of this calculation is to determine the mininum water depth in the active containment sump at the time of switchover to the recirculation mode following a large break LOCA (LBLOCA). 4 1.2 Pachmecund Following a LOCA. steam and het tJter from the break cause a rise in temperature and pressure in containment as well as a loss of primary coolant. The engineered safety systems actuate, supply 1ng cooling water to the reactor coolant system (RCS) from the cold leg accumulators (CLA) and the refueling water storage tank (RWST) and to containment through the containment spray system (CSS) from the RWST. Ice in the ice condenser also melts. The CSS sprays water into the upper compartment atmosphere through nozcles in two spray headers to help ensure that containment pressure and temperature do not exceed design values. Each no=zle head is i r.dep enden t l y criented to maximize coverage of the containment volume tutside the reactor cavity and inside the crane wall, prohibiting flow .nto the ice condenser. During the injection. mode, the water has a maximum temperature of 105'F. This has a slight warming effect on the upper compartment atmosphere. The water falls through the upper compartment atmosphere to the operating deck and into the refueling canal. From there it flows to the lower compartment through two 14-inch drains. Approximately ten minutes after the CSS starts, the two air return fans in the upper. compartment start. Some of the CSS water will be drawn through the fans and will be deposited in these accumulator rocms. Drains in each of these rooms -allow this water to flow into the containment sump. The majority of the water from the various sources drains into the containment sump. Water unavailable to the containment sump for ~ recirculation is that wnich is falling through the upper compartment atmosphere; that which is held up on the operating deck. in the refueling

canal, and in accumulator rooms 3 and 43 that which remains in the RCSt and that which flows into the reactor cavity.

On receipt of high sump level and icw RWST level signals, the residual heat removal (RHR) pumps automatically realign to stop taking suction from the RWST and to begin taking suction from the containment sump. That is, the valves between the RWST and the RHR pumps close while the valves between the sump and the RHR pumps open. During the time that it takes.for'tht's realignment', the operator manually r e a.1,i g n s the safety injection pumos (SIPS) and the centrifugal charging pumps (CCPs) to stop taking suction from the RWST and to begin taking suction from the RHR pump discnarge. The CSS numps entinue tc take suction from the RWST until RWST low-low. level is esched. Ahwhment No 2O Sheg g [2Y l Loop s/ldentifier SQN-EEB-MS.TI28. col 3

f 4 CONTAINMENT SUMP M2NIMUM LEVEL' SHEET""*~~~F AT TIME OF SWITCHOVER TO RECIRCULATION MODE FOR A LARGE BREAK LOCA PREPARED BY E^6 M WJf CHECKED BY Y S/M SON-OSG7-COOS R4 2.0 ASSUMPTIONS [ 0.1 Maximum flow rates are assumed for all pumps taking' suction-from the I RWST. This is conservative since it mintmt:es the time to switchover by has t er.i ng the depletion of the water in the RWST. The shorter time to i switchever minimizes ice melt. 2.2 All technical specifications were conservatively chosen to minimi:e i the water level in the containment sump. (i.e.. RWST level is at minimum-full at the onset of the event and at-the h1gh level limit of setpotnt at switchover.) o -a r 2.3 The water held up in the upper compartment has reached equilibrium. (i. e., The water flowing into the refueling canal (RFC) equals the water draining from the refueling canal to the lower compartment.) 2.4 All penetrations in the crane wall below el 693.0 feet are sealed. (See references 9.1.10 and 9.19) l 2.5 Because the upper head injection system is likely to be removed in the.

future, it was not considered as a water source.

This is conservative relative to this calculation since it minimizes the volume of. water available for recirculation. 2.6 The pipes in the CSS are full of water up to the spray headers during-l normal operation. This is a reasonable simplifying assumption as tho' I addittonal water volume to fill the spray headers'is negligible relative l to the total water volume. 2.7 Water droplets from, the containment. spray will remain constant in l size. Since the CSS water warms the upper compartment atmosphere during the injection

mode, and water condenses-onto c' col or
surfaces, this assumption is conservative.

2.8 Due to turbu1'ence in the upper compartment atmosphere, assume CSS water homogeneous throughout. l 2.9 Per Technical Specification, M!-1.0, SI-20,tand FHI-8 refueling covers will be removed and the vor t e:t suppression devices (normal operating covers) will be in place whenever the plant is in operation. 2.10 Flow into the reactor cav'ity.through the neutron monitor windows is negligible (ref erences 9.1.11, 9.1.12, 9.1.13). ~ 2.11 An allowance of 0% for equipment volume between el*679.78 feet and-el 690.0 feet is conservative relative to minimum water level. This 0% is i based on the engineeFing judgment of Robert S. McKeehan and Edward J. t Sheehy. This allowance is not used for the sump pocket, the refueling anal or the reactor cavity since they do not contain equipment. 2.,10 Screens provided on drains from accumulator rooms and 4'are properly sized to assure flow into the sumo (reference 9.1.14). EO Attachment No-_ Sheet 1 ( E 1.400 ti/fdsnhfier SQN-EEB MS -TI28-0013 j 1

CONTAINMENT SUMP MINIMUM LEVEL SHEETaf__OF_/" AT TIME CF SWITCHOVER TO RECIRCULATION MODE FOR A LARGE BREAK LOCA PREPARED BY, 8 r/:-/?T CHECKED BY D N S/WW SGN-OSG7~0000 R4 0.13 Per reference 9.17, the extensions to the vertex suppressors an the RFC drains arg in place in Unit 2. They are assumed to de-sn place in Unit 1. Thiw is conservative since it maxim 1:es water held up in the refueling canal. O.14 All CSS water falling onto the reactor enclosure in the upper compartment is assumed to flow to the operating deck. This is a simplifying assumption which is conservative since it massim1:es the watee volume held up on the operating deck. O.15 The decrease in flow rate from the RWST from 20,900 gpm to 9,500 gem is linear with time for the two minutes it takes for the valves to close (reference 9.5). This is a simplif ying assumption. 3.0 VOLUME OF ACTIVE SUMe i See Append 1:t A 3.1 Bel ew el 6e?.0 feet Volume of Sump Pocket = 2,697 gal /clume between el 679.78 f t and el 683.54 ft = 112,560 gal (29,936 gal /ft) Volume between el 683.54 ft and el 687.78 ft = 101,543 gal (09.666 gal /f t) Volume between el 687.78 ft and el 693.00 ft = 119,290 gal (20,659 gal /ft) Total volume equals the sum of the above volumes 118,380 gal Volume = 2,697 gal + 110,560 + 121,543 gal 055.080 gal i + = 3.0 Above el 69?.0 feet Volume between el 693.0 f t and el 693.54 ft = 12,775 gal (23,657 gal /ft) Volume above el 693.54 ft = 24,155 gal /ft See Figure 3-1 for an illustration of sump level versus sump volume. 4.0 WATER SOURCES 4.1 STS (Cold Lee) Accumulaters Per reference 9.3.0, there are f our accumulators at a minimum of 7,957 gat each. Therefore, V(SIS) = 4(7,857 gal) = 31,409 gal ArNMhment No. 20 h f o,( 23 Loco W/ldinWr$QN-EEB-MS gTI28-0E3 t

CONTA!NMENT SUMP M2N! MUM LEVEL AT TIME OF SWITCHOVER TO RECIRCULATION SHEET _jd_:F _ / ? MCCE FCR A LARGE BREAK LCCA FREFARED BY28MJf v4 /et CHECP:ED BY 7 7[M SON-OSG7'0008 R5 4.2 Pe4ueline Water sterace Tank fRWST) Minimum volume of water gal (reference 9.3.3). in the RWST during normal ocer ations is ~70.000 Setpoint for automatic switchover (Iow level) is 130 inches accve the bottom of the tank (references 9.3.1 and 9.00 and attachment A). Setpoint for containment spray pump realignment (low-low level > ts 54.2 inches above the bottom of the tank (reference 9.00 and attachment A). Demonstrated accuracy of level transmitter at automatic switchover is 2 4.7% of span (reference 9.18). g{ Demonstrated accuracy of level transmitter at low-low level is 2'5.0% =f span (reference 9.18). Instrument span is 0 - 087 inches beginning 24 inches above the bottom =f the tank (ref erence 9.20 and attachment A). Inside diameter of the RWST is 43.45 f t (reference 9.1.4). Volume per inch = (w/A)(43.45 ft) (7.48 gal /cu ft)(1 ft/12 in) 924.25 gal /in = 4.2.1 Volume of Water Discharged from the RWST-to Automatic Switchover V(RWST) V(i ni ti al ) - V(final) = 370,000 gal - C1'30 in +.047(387 in)3(924.25 gal /in) V(RWST) c l V(RWST) 370,000 gal - 1148.19 in) (924. 25 gal /in) = V(RWST) = 370,000 gal - 136,964 gal 233,036 gal = 4.2.2 Additional Water Discharged at CSS Realignment AS' VA(RWST) 135,533 gal - C54.2 in +.052(387 in) 3 (924. 25 gal /in) = VA(RWST) 135,533 gal - (74.32 in)(924.25 gal /in) = VA(RWST) 135,533 gal - 68,694 gal = 66,839 gal ~ = 4 Attachment No. 20 Sheet Il af M

t. coo W/ldentifiapQN-EEB46S -TI28-0013 I

CCNTAINMENT SUMP MINIMUM LEVEL SHEET 4~ CF /"' AT TIME OF SWITCHOVER TO FECIRCULATION FREFARED BY>Td8 r/4Aff MCDE FOR A LARGE BREAK LOCA CHECKED BY D / SCN-CEG7-0008 R5 4.0 Melted Ice 0.3.1 Volume from Melted Ice at Automatic Switchover Per reference 9.5 ( 2CQ(RHR) + Q(CSS) + Q(SIP) + Q(CCF)] l Flow rate f rom RWST = Q tRWST) = Q(RWST) =-2(4500 gpm + 4750 gpm + 650 gpm + 550;gpm) 20,900 gal / min l Q (RWd T) = V(RWST)/Q(RWST) j Expected time to automatic switchover, T1 = I T1 = 230,006 gal /20,900 gal / min = 11.15 min Per reference 9.2.3 the amount of ice melted in 11.15 minutes is 1.04Eh-Ib (1.04E6 lb) (.016395 cu.ft/lb G 160*Ft)(7.48 gal /cu ft) V(ice) = 164,000 gal V(ice) = t Per Ref 9.2.2, sump temperature is at 160*F. 4.3.2 Additional Water from Malted Ice at CSS Realignment Per assumption 2.15, the decreasing RWST. flow rate is linear with t:me. The total volume of water discharged between automatic switchover and CES realignment (66,839 gal,, section 4.2.2) is equal to the area under the curve in the figure below. It

  1. d80

,,(20,900 - 5,700t)dt + 9,500(t - 2) 66,939 gal } Q s2c,900 - t;74df = 47 k'I ### C20,900t - 2,850tt] 9,500t 8 + / I a] l 19,000 = 66.839 gal P j l n e I 20,900(2) - 2,950(2)2 + 9,500t t I 19,000 = 66,909 gal lima,f(Mrd t= (66,909 + 19,000 + 11,400 - 41,800)/9,500 = 5.84 min }. Total expected time to CSS realignment. T2 = T1 +t T' = 11.15 man + 5.94 min = 16.99 min Attochment No. 20 $ beet IE af 3) L.cos si/idsntif trSON-FFB- %TT7R-ont A

-i l CONTAINMENT SUMP MINIMUM LEVEL SHEET & CF /* AT TIME OF SWITCHOVER TO RECIRCULATION " ODE FOR A LAR3E BREAK LOCA FREFARED BYMS' - /3/tf CHECKED BY SQN-OSG7-OOO4 R5 For reference 9.2.0, the amount of ice melted in 16.99 man is 1.5;E6 lb. 4f Therefore. the additional volume of water due to ice melted at-CSS realignment is

1. 04E6 lb) (. 016 95 cu ft/lb 4 160'F)

(1.5 E6 lb VA(ice) = (7.49 gal?cu ft) VA(ice) = (.19E6 l b ) (. 016095 cu ft/lb 4 160*F) (7. 48 gal /cu f t) VA(ice)s = 00,000 gal 4.4 Peactor Coolart System (TCS) Inventerv After a LOCA the liquid volume remaining in the RCS is dependent on the location of the break. Two cases will be considered. 4.4.1 Break in RCS Piping at Any Location Except at the Reacter Vessel No::le In this case, the volume of water remaining in the RCS is dependent on the location of the break. The water discharged will flow into the containment sump. It is conservat1vely assumed that the RCS inventcry 4t 11 not contribute to the water level in the :entainment sump. 4.4.2 Break in RCS Piping at the Reactor Vessel Noz=le I 3n this

case, water discharged from the RCS will flow into tne reacter cavity through the het or cold leg piping penetration.

The amount of this flow dependu on the si:e. type, and location of the break. It is assumed that the RCS inventory will drain to the centerline of the reactor. vessel no::le. The discharged RCS water, V(RCS) = RCS liquid volume - free volume of RCS-below el 695.0 ft (centerline of het/ccid leg no::les) RCS liquid volume = 11,892 cu ft (ref erence 9.6) Free volume of RCS below el 695.0 ft = 21. 692 gal '(ref erence 9.14) 21,692 gal = 67.260 gal (11,892 cu ft)(7.48 gal /cu ft) V(RCS) = 4.5 Tetal Water Volume Discharegg 4.5.1 Volume Discharged to Automatic Switchover 4.5.1.1 Break in RCS Piping at Any Locati=n Escent at the Reactor Vessel No::le V(total) = V(SIS) + V(RWST) + V(ice) 409.794 gal 164.000 gal 21.408 gal + 2 0,006 gal = + V(total) = ! Attachment No.- 2 0 13 Sh t 0 l % s/ksntsfier 1

CCNTAINMENT SUMP MINIMUM LEVEL ssgg; y p /- AT TIME OF SWITCHCVER TO RECIRCULATICN MCCE FCR A LARGE BREAK LCCA FREFARED BY # M 74 h 7 CHEChED EY YN < / SCN-OSG7-0008 R5 4.5.1.2 Preak in RCS Piping at the Reacter Vessel Nc=cle V(tetal) = VtS!S) + V(RWST) + V(ice)

  • V(RCS) 67.060 gal 164,000 gal 01,408 gal + 230,036 gal

+ + V(total) = 496,054 gal V(tetal) = 4.5. 2 Volume Di sem arced 9etween Autemati 9witc% eve-3-e ces co al i c--s-t f P VA(total) = VA(RWST) + VA(ice) VA(total) = 66.839 gal + 23,300 gal = 90,109 gal 5.0 VCLUPE OF WATER UNAVAILABLE TO CONTAINMENT SUFA i The volume of water unavailable to the containment sumo consists of the water in the upper compartment atmosphere, the water en the operating

deck, the water in the accumulator rooms.

the water in the refueling I canal, and the water diverted to the reactor cavity. 5.1 Water in the Uccer Comoartment (UC) Atmoschere Water sprayed by the CSS which has not yet fallen to the ccerating dacP is not avail abl e to the containment sump. The amount of _ this unavallatla water is a function of the droplet sica, the vertical velocity.-and the drag force exerted on the droplet due to the resistance cf the uccar compartment atmosphere. ~ See Appendi:t B for analysis and computations. The average volume of water in the upper compartment atmosphere is 1,138 gal V(UC) = 5.2 Water Gemainino on the Oceratino Deck ) See -opendix C Water will accumulate on the operating deck bef ore dratring into t e refueling canal. The two inch cureing (reference 9.1.8) surrcunding the refueling canal acts similar to a weir, and the volume of water, wnten ~ will accumulate, will be determined at equilibrium (flow in ecuals 41cw out) using the Francis formula for rectangular weirs (reference 9.15). O = 0. 00Lh" (Francis formula) lhere O = ficw rate in cu ft/sec L= length of flew in feet h = head of water above the curt in feet Attachment No. 20 Sheet 14 afM 1.000 ai/ldentifiepQN-EEB4tS -TI28-0013 i I l r-

q CONTAINMENT SUMP MINIMUM LEVEL SHEET 7 0F

  • 7 AT TIME OF SWITCHOVER TO RECIRCULATION MODE FOR A LARGE BREAK LOCA FREF ARED BY 1941 f'r'M CHECKED BY D R M / L SQN-OSG7-CCOS R4 At equilibrium
flow, all the spray not going directly into the refueling canal

-(RFC) will be assumed to fall onto the operating deck (CpDk) before flowing into the RFC. Spray is assumed to be evenly distributed ever the entire area inside the crane wall. Therefore, the flow rate of the portion of the spray falling onto the operating deck will be cetermined as the ratio of the area of the operating deck to the total area multiplied by the total CSS flow rate. Q(OpDk) = (CA(total) - A(RFC-!CW)3/A(total))C(total) j A(RFC-ICW)/A(Total)3 Q(Total)C1 Q(OpDk) = (9,500 gpm)C1 - 509 sq ft)/5,411 sq ft3 = 8,606 gpm Q(OpDk) = The length of the flow, L, is equal to the perimeter of the RFC in contact with the OpDk. Therefore, L= 104 ft. It is conservative to assume that all water from the reactor enclosure 1 f alls onto the OpDk. Solving for h, the above equation becomes h = CQ/(0.30L)3

  • h=

((8,606 gpm) (min /60 sec) (cu f t/7. 48 gal) /C (3.30) (104 ft)3[* (10 in/ft) = 1.74 in (.145 ft)(10 in/ft) h = The total height of the water held up on the operating deck then is h(total) = h(curb) +h = 2 in + 1.74 in = 3.74 in The volume of water held up on the operating deck is (2,442 sq f t) (3.74 in) (f t/12 in) (7.48 gal /cu f t) 5.690 gal = V(OpDk) = 5.0 Water in Accumulater Rooms T. and 4 Fan capacity = 40,000 cfm (ref erence nos. 9.4 and 9.13) Upper Compartment Volume = 651,000 cu ft (ref erence 9.0) Water lost through the air return fans (ARFs) is V(ARF) = water in upper compartment divided by volume of upper compartment times fan capacity (1,100. gal /651,000 cu f t) (2) (40,000 cf m) V(ARF) = 140 gpm or 70 gpm per fan V(ARF) = 1 Attachment No - 2.0 Sheet i s sfJ,g,, Looe t/tdtntillerWEI'5~M8~000 I

4 CONTAINMENT SUMP MINIMUM LEVEL SHEET f OF e v AT TIME OF SWITCHOVER TO REC 1RCULATION MODE FOR A LARGE BREAK LOCA PREFARED BY N7 b M V CHECKED BY Dk f/f/<A SQN-OSG7-0008 R4 / The air return fans start to minutes after the containment spray begins. Therefore the volume of water entrained by the f ans and deposited in the accumulator rooms at automatic switchover is 171 gal V= (140 gpm)(11.20 min - 10 min) = The additional water deposited in the accumulators at containment spray realignment is VA = (140 gpm)(6.02 min) = 843 gal Both of thase amounts are negligible and will not be considered in this calculation. 5.4 Water welduo in the cefueline Canal See Appendix D. 5.4.1 Refueling Canal Drain Fipes Not Submerged V(RFC-NS) = 04,672 gal' 5.4.0 Refueling Canal Drain Pipes Submerged (5,070 gal /ft)(:g - 690.88 ft) V(RFC-5) = 01,466 gal + 5.5 Water in the Reactor Cavitz See Figure 5,5-1 for an illustration-of the Containment showing the reactor cavity. After a

LOCA, the water which flows into the reactor cavity is dependent on the location of the break.

Two cases will be considered. 5.5.1 Break in the RCS piping at any location except at the reactor vessel no::le. For this

case, the water discharged will flow into the containment sumo.

A small amount of this water will-flow into the reactor cavity through the small annular areas of eight instrument penetrations at each of two

levels, elevation 680.79 feet and, elevation 686.78 feet.

The amount of this flow is negligible (assumption 2.10). 5.5.2 Break in the RCS piping at the reactor vessel no::le. See Appendin A V(RC) = 115,608 gal For this case the reactor cavity will fill diverting 115,608 gal of water from the containment sump. Attachment No-20 Sh e I4 m# y Loop i/ldennfiegow-vrn MS_. tin.co g 1

CONTAINMENT SUMP MINIMUM LEVEL SHEET /JL_CF i" AT TIME OF SWITCHOVER TO RECIRCULAT'ON F REPARED BY)N940/ {/s~'l;f MODE FOR A LARGE BREAK LOCA CHECKED BY Y f/MfT SON-CSG7-CCCS R4 5.6 Total Volume e4 Water Un avai l abl e to the Centainment Some Volume unavailable = V(UC) + VtOD) + V(RFC) + V(RC) to containment sump 5.6.1 Break in the RCS piping at any location encept at the reactor vessel no::le. 1,108 gal + 5,690 gal + 01,466 gal (5,070 gal /f t) V(unavailable) = + (:a - 690.88 ft) (5,070 gal /f t) (:a V(unavailable) = 08,097 gal 690.88 ft) + 5.6,0 Break in the RCS piping at the reactor vessel no::le. V(unavailable) = 1,1!8 gal + 5,690 gal + 01,466 gal (5,070 gal /ft) + (:a - 690.88 ft) + 115,608 gal V(unavailable) = 150.905 gal (3,070 gal /ft)(:, 690.88 ft) + 6.0 DETEFMINATION OF MINIMUM WATER LEVEL IN CONTAINMENT SUMP l As can be seen by the figure in section D.2 (Appendix D), a change in the water level in the sump has a corresponding change in the water level in the refueling canal. Therefore, when determining sump water levels l greater than the " floor" of the refueling canal (el 690.88 ft). the I additional volume'in the refueling canal must also be considered. Volume in centainment sume te el 6co.99 4t (4 rem section T.0). j V = 2.697 gal 110,560 + 121,543 gal + (690.88 ft-687.78 ft) + (20,659 gal /ft) i 007.043 gal = Volume in refuelina canal between el 6#0.98 4t and 3 V= (:2 - 690.88 ft)(5,070 gal /ft) Vol ume in centainment sume and re4ueline c anal between el 600.99 4t and :. The volume in the containment sump and in the refueling canal betwee,n el. 690.88 ft and :a depends on :g. For : 4 690.0 ft: 3 690.88 ft)(20,659 gal /ft + 5,070 gal /ft) V= (: V= (:2 690.88 f t) (27,709 gal /f t) Attachment No.-. 2.0 __ Sheet M afA

l. coo p/ldentifietSQN-EEB-MS -TI28-0013

CONTAINMENT SUMP MINIMUM LEVEL SHEET // CF /7 i AT TIME OF SWITCHOVER TO RECIRCULATION " ODE FCR A LARGE BREAK LOCA FREFARED BY # E 4/;r CHECKED.BY W '//7/TS SQN-OSG7-0008 RS // I For 693.0 ft < :s 5 693.54 ft l V= (690.0 f t - 690.88 f t) (07.709 gal /f t) (=g - 690.0 ft) + (20.657 gal /ft + 5,070 gal /ft) V = 58,785 gal + (:a - 693.0 ft)(08,727 gal /ft) For : > 690.54 ft 3 69':.54 ft)(04.155 gal /f.t V = 58.785 gal + 15.513 gal (:a + + 5,070 gal /ft) 693.54 ft)( 4,155 gal /ft) V = 74,298 gal + (a Volume available = minimum volume of discharged water - volume to fill sumo and unavailable excluding volume in refueling ~3 fueling canal canal between el 690.88 ft and :. - volume in cetween el 690.88 sump to el 690.88 ft ft and z g l 6.1 Minimum level in Centainment Sume at Automati c Swi te*ever- .1.1 Break in the RCS piping at any location except at the reactor vessel no::le. 428,794 gal - 38,297 gal'- Volume available (el 690.88 ft to :,) = 307,043 gal 83,454 gal = Therefcre, j l (:a - 693.54 ft)(24,155 ga1/ft) = 83,454 gal 74,298 ga1 + (:3 - 693.54 ft) = 9,156 gal /24,155 gal /ft f j h 0.38 ft + 693.54 ft = 693.92 ft z = a s i Water Depth = 693.92 ft - 679.78 ft = 14.1 ft 6.1.2 Break in the RCS piping at the reactor vessel no::le. 496,054 gal - 150,935 gal Volume available (el 690.88 ft to :2) = 307,043 gal 35,076 gal i = .1 J Attachment No. 20 ggfy Laos si/idenhfiap0N-EEM-44e -TI28-0013

CCNTAINMENT SUMP MINIMUM LEVEL SHEET ka F em AT TIME CF SWITCHOVER TO RECIRCULATICN MODE FOR A LARGE DREAK LOCA FREFt. RED :-Y #1/3fe y///pr-CHECKED BY W M7/IT SGN-CSG7-0008 R5 / ' l Therefore, (:a - 690. 88 f t) (27,709 gal /f t) = 05.076 gal (24-690.88 ft) = 35,076 gal /07,729 gal /ft 1.26 ft + 690.88 ft = 690.14 ft = Water Depth = 692.14 ft - 679.78 ft = 10.4 ft 6.0 Minimum Level in Centaimment Sumo at CSS Realimr-ent 6.2.1 Break in the RCS piping at any location except at the reacter vessa. no::le. Vclume available (el 690.08 ft to :,) = 80,454 gal + 90,109 gal 1 170,593 gal = Therafcre, 170.590 gal 693.54 ft)(04,155 gal /ft) 74,298 gal (:, = + ( :, - 693.54 ft) = 99,0*r5 gal /04,155 gal /ft l h, 4.11 ft + 693.54 ft = 697.65 ft

a

= i 17.9 ft Water Depth = 697.65 ft - 679.78 ft = l 6.2.2 Break in the RCS piping at the reacter vessel no::le. Volume available (el 690.88 ft to :g ) = 35,076 gal + 90,109 gal 105,215 gal = l Therefcre, 125,215' gal. 74,298 gal + (z - 693.54 ft)(24,155 gal /ft) = a -1 (:2 - 693.54 ft) = 50,917 gal /24,155 gal /ft = 2.11 ft + 693.54 ft = 695.65 ft

  • l Water Depth = 695.65 ft - 679.78 ft = 15.9 ft 4

Attachmnt No. '2D Sheet 19 mp 2.3 L809 $/ldentifietSQN-EEB-HS-TI28-00I3 iC I'

F CONTAINMENT SUMP MINIMUM LEVEL EnEETg,:r /, AT TIME OF SWITCHOVER TO RECIRCULATION FREPARED BY Mde /g/py " ODE FOR A LARGE DREAK LOCA CHECYED BY $ NY W7 5 SQN-OSG7-0008' R5 7.0 EUMMARY OF RESULTS Water Sect" Staen of Switchever 'B r e ap met at Ne-:le Peau at *!er :I n 14.1 ft 10.4 ft Automatic Switchover 17.9 ft 15.9 ft' CSS Realignment 8.O CONCLUSIONJ b On the bawis of the above assumptions and calculations, it was determined k that the minimum water level in the containment sump at the initiation cf cutomatic switchover to the recirculation mode occurs for a break located et the reactor vessel noz:le. The minimum water level for this break is feet. At the comoletion of switchover (CSS realignment) there is 10.4 water available due to the continued CSS iuttien from the-RWST to the more low-low level and additional ice melt. At than time. when the CSS pumos 1 begin to take suction f r om the - containment sump, the minimum water level i

  • s 15.9 feet less that watch has flowed through the unsealed penetraticns n

the crane wall above elevation 693.0 feet. Therefore, there will to at i least 13.02 feet of water in the containment sump at the time c4 owitchover to the recirculation mode. l s .l Attachment No; 20 Sheet 20 af E}, l Loop i/ldentifierSQN-EEB-its -T128-0013

~ _. _. _ _ _. _. _ _. _ _ _ i CONTOINMENT SUMP MIN! MUM LEVEL SHEET _L_d_OF 17 .AT T!ME OF SWITCHOVER TO RECIRCULATION MODE FOR A LARGE BREAK LOCA PREPARED BY N !"/f/M' CHECKED BY STM'T SQN-OSG7-0008 R4 ~ '/

9.0 REFERENCES

9.1 Drawinen I 1. 41N710-1 Rio 6. 48N400 R5

11. 541F677
16. 49N996 R14 2.

41N716 Series 7. 4GN404

10. 593F092
17. 47WS12-1 R10 3.

47W200-10 R5 8. 48N971 R15

13. 541F676 it. Westinghouse 4

47W309-3 R5 9 48N919 R5 14 48N966-1 Drawing 5. 47W476-0,4 R12

10. 47B470-1 R9
15. 47W437-5 R17 686J506 9.0 Sequoyah Nuclear Plant Final Safety Analysis Report

,i

1. Table 4.2.1-6 2.

Figure 6.2.1-22

3. Figure 6.0.1-03 9.3 Sequoyah Nuclear Plant Technical Specifications 1.

Page 3/4.3 "E 3. Page 3/4.5-13 2. Page 3/4.5-1 9.4 SON-DC-V-13.9.5, Reacter Buildine Environmental Centeel Svstem 9.5 SQN-DC-V-27.", Safety Injection Svetem /.6 SON-DC-V-27.4, Reacter Ceelant Svstem, Table 3.1-1 9.7 SON-DC-V-27.5, Cant.ainment Serav Svetem 9.8 Crane Technical Paper No.

410, Flew of cluids' Thecuch Val ves,

t l Fittines. and Atees, 1985 l 9.9 Phvsten, Paul A. Tipler, Worth Publishers, Inc., 1982 9.10 Mechantes of Fluids, Irving H. Shames, McGraw-Hill, 1980 9.11 Fundamentals of Classical Thermodynamies, Van Wylen and Sonntag, John Wiley and Sons, Inc., 1973 9.12 Robert H.. Bryan, knowledgeable person on-coQtain' ment atmosp.here 9.13 W. Emerson Rudacille, knowledgeable person on air return fans l l j 9.14 TI-ANL-89, Secuevah One-Leem RETRAN-OO Medal Centrol Velume and Clew I Junction Geometric Calculations (NEB '930607 236) 9.15 Marks' Handbook, 7th Edition 9.16 CRC Standard Mathematical Tables, 26th Edition, Wm. H. Beyer, PhD. RC Press, Inc., Boca Raton, Florida, 1981 Attachment No. KO Sheeg El 4R Loe9 ii/idgnnfier SON-EEB MS -TI28-00l3 I

il i CONTAINMENT SUMP MINIMUM LEVEL SHEETg F /7 4 l AT TIME OF SWITCHOVER TO RECIRCULATION PREPARED BY M y/3/pr j

  • 0DE FOR A LARGE BREAK LOCA CHECKED BY SQN-OSG7-0000 RS

// f 9.17 David

Humble, knowledgeable person on extenslens to verten l

cuppressors b[ 9.19 DNE Calculation RWST-Level, Instrument Accuraev Calcul att ens, RE (843 '971'001 915) 9 19 DNE Calculation SGN-SOS 4-0102, E44ects of the Failure of ream till ed ~ ! Seals in the Crane Wall Penetratiens en Centainment Sume Water Level, R1 j (B45 '890114 426) 9.20 Sequoyah Nuclear Plant Instrument

Tabs, February 6,

1986.(see l Attachment A) 9.21 1967 ASME Steam Tables, The American Society of Mechanical Engineers ) 9.00 Nuclear Power

Systems, C.

D. Gregg King, The Macmillan Company, New York, New York, 1964 4 i i 9 da i I Attochment No -_20 Sheef 22 of 2f I Loco si/ldentif'er ON-Ern-Mc;.mo nnu S

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i gg 770505 174 TENNE 5ste VALLay AuTMontyv' womva.Ls. m wesser s7eca W10c126,1400 Cosmarco Avenue May 6, 1977 ArtesMwet No-M g,3,g,5QN-ETB g h j0 J3 Vestinghouse Electric Corporation post office Box 355 Pittr. burgh, Pennsylvania 15230 Attention: Mr. M. A. Siano 81RUOYAH E'CIJAR PIANT S NUCIZAR STIAM SUPPIX SYSTD5 com%cT 68c60-91934 IETTr.R Ho g e CCMAI!t2E SUMP LEVEL INSTRUMDfTATION - N2M-2-15(DC An instrument channel span of to feet will be necessary to monit anzieus expected level in the containment sump during post-I4CA c or the An instrument span of 20 feet makes.the setpoint of 2 feet (El ons. suggested by TVA in our letter number 5625 impractical. ev. 681 78) limitations of the drining equipment which win be used to Due to the wan penetrations i above the floor.,With a span of 20 feet, this would cause make the erane suggested sotpoint to be at less than 10% of the total instrument reviously This is unacceptable. setpoint win only add 16,830 ganons to the water requiremen span. tha setpoint level. System considerations indicate that this is fully achieve acceptable. that a dual sensor beRows is required.Considering the advance i a, we do not believe indicate that the dp across the crane wall vill be equalized iContainment p short time, and will not cause an error in the level msasurement at t n a relatively time the auto-switchover is required, or during long ter e t m level annitor%g. Therefore, please consider the foMowing parameters in the d specification of the sump level instamentation: esign and-s Iower sensor benows: Spea: 6 in. off floor (elev. 680.28 Setpoint: 20 ft. (elev. 680.28-700.28)~) Transmitter elevation: 2 ft. 6 in. off floor (elev. 682.28) alev. 698 Capinary length: $0 ft. \\ Field-flu capability win be required for the instanation of th transmitters. ese l An Equal Opportunity Emo l h ,m ' ~ ~ ~ --~~ ~

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00TSIDE CONTAINWENT d"@ % (tm&S2All) M:,--- M (ui-0-174AA) M:;,;- ni. (im-g3-17eAn) .i tt . c,a 34 ' i fin-1,3 -52A6) i( tm-b3-17bns) i(L/1143-176AE) kg~ a4 1EJ o west. t-s 5 LCP i 83C i cuasswt t-sa LCP LaoE_I flT)-f3-52AD,i cuasset t-o.e ] 3 y vs (::ava)ge-a-me (r.svayw-o-17snp)- L t pawst(tvtt gcw co=rier su e tr e q ?: g w g%ceitant sua uwt b ya k L54 h b D f G f( , 6 DE h h ~ D (@ O' 4 ur tr e - gh R un tr m w y te-szca = .c7 aio y 4 u y e.lc man FEon a gan te.wo. ro F5cc F "'o b'SEbh l 0 S-Uk. (M-$3-174) h h (LS-b3-178A) I (,G-l3-178) i !,Its*I--- Ma ---N') I vse I--- %, --- Mi h V ($0 V (l/Il-5T173AN)' 5 ~ (jg.y.17(, j I I ljyy-43-52) v iu itv iu o Q( '**C (p -i n. nio " are g ___j r tf E l . M ----! e s. !---- M l --- - O'd s -4 to D -a I n4 : aio are h3 O O) c i d' i _3 if l I J n* L 1 y n auto accinc g g i S MIGN INTERt00t aove sucrac ( laesD atAmuj

  1. 88 8 Nf8W f*ff8t8DI IO fa' l

l55P$} l (ass atspu) {g y _Q_)y l5tFl ^ ~- g -l-1,m ,1 1111 n-e-m I g a.r.e r,, g scoo'a= = @ @,,, ,;,,,,,,,,t,,,,m,,,, I I 8 .. _ -. + -~. 5lUNira,r,ies tie a*-! f? pet-gt s,.

l r.BlifffM) : rei TC4 8 @ ::: r mi .c,3-53 l LT-63-175. "'(LT-fof - O""'; L_ r-4,3-119 ) INSIDE CONTA b *-a =* b* "

  • OUTSIDE CONTAIMMENT S'S MM M e;';,--- ei; gm-a-177M)

= ;,,-- 07. Im /7SAA) E! E

=

s*i t,1-53bs) l(im-a-177AB) l (lAl-U-IMB) i) \\ o ase. t-sis LCP Lio_cJ c>a'=Et 1-sto LCP Lao._c_I a-s3hD) omasset L-see 29 v nee-17 tap) } g l ) (!='!;a)(tm-63-177Ab (!='sa) ,f r tevtt f c%contenst sunF LEvtt en g<w Costumpf gar tgvet l\\ ts-G ) R W (LS-U-/7)f fp A -f77 i ? O A X El ) s A w h &,n tur.'~P% ) 5 w$rs.n r: 2 70m# h m rm ~ w.n i rm e }} l

f LS-O-177A)

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  • F--

0[Ii. --- E X i ~ j V (IM & fli) V Lp)-(,3-17141/) { //-f3f3) UM-O-177);tygj [,j njc_ M,,, y j o; a m. ,tt,

    • '____i up, e

i____=yt i --- - gg ' e. Wej wa ed ~ i i a = sgz w0 i t sulo 88FCint .,ogie *rtatocs a"*1 I l awfe mEcleC Ia'e "si meer reertataar h isse I t** at***8 7 I (LJ-63-177) N l j l l l l stevevan arctr u etaar = II Put )M t FNLLEY RugngulIY g

  • 3 et aer e

3 i WRIT 5:.. 1 5 2 55'34 ; Igg 4W5-U3 3 0 e ST41u5: tt aitt tgo ron C04%Tastf f 89 itsTIFIC ATIOe t ie. #6.. Tea-89-913 e j Agiwettiv:

f. a. 1990I t

) ,e I g g ___ tese, t re. es:

  • * " - **y -

I l NUCLEAR ENGINEERING S~, yam ENG;s---* SEQUOYAH ENGINEERING P;0 JCT = pg k..gi ...l PROACT MANUAL 1 TENNESSEE TENNESSEE VALLEY AUTHORITY p,, VALLEY orvIsION OF M23.f>A EMINEDIM ENGINE f Auy.gst.I.; SEQUOYAH NUCLEAR PLANT l l s SE 30::s ANo SCA_::\\G JOC_ V EN" FOR INSTRUMENT LOOP NO. I - LT - a - 176 I R I N Attachment No. $ beet I '= f. ).-1 Laos p/ldtnnfie)0N-EtB4ts -tt:3 0013 l \\ i ij l REVISION RO RI %WRe C.l %".hk,%' .p4. g3[,"34 e OATC,2-ty Sp 3-9-90 3 23.qo 3.go.yo t 5 PREPARED Lj;/gg. Q,,,jf;(Q, & a. % Qg/f g l vERIr1Eo . t.4yan/Ee:(fd!Pis-K"n. )y_. REVIEWED h,AM,7)/2.naA%$7? %%-$M/jgt APPROVED pg g l'SS Nfh Ma

~ ~ -l SETPOTh r-Af(D SCALING DOCUMENT LOOP NUMBER l1-LT 176 CSSC7* Yes X No_ LOOP FUNCTIONIMEASURES THE LEVEL OF FLUID IN THE RCAcTe3a. Suoi% SUMP'TO PROVIDE MCR INDICATION FOR POST ACCIDENT MONITORINGr LOW LEVEL ,SuitTHovt1dTO WE REACTOR BLDG. CONTAINMENT SUMP FOR IDNGER TERM r--~~ RECIRCULATIONr - (* LOOP ACCURACY l +4.90 Allowable Acceptable Acceptablo g Punction M1 Value As Found As Le f t f . f4 SUMP Lev t.L TudoTsoiJ ' Fort PkM M M il& -!r.#67.*

  • -S. F(o %

+ g,og'% i

  • S u cre s eve n.

s e tz. A c c.inc utono AJ M :.0 W. - Neve 9 r4W '?.7 i ) o l* ste ucrte 8 LOOP COMPONENTS Process Calibration Value Acceptable Acceptable. NO. UNID No. Rance/Setcoint Inout Outout As Found As left 1 1-LT-6 3 - 176 o-Noa Hs0 f o.2N O H ao 10-50 MA 2 1.9 h or. 2 0. 5% of-(NOTE 5) (NOTE 6) ? OUb' mA t o. 2 0 fa6,, 2 1-LM-6 3 176 AA o-240"Hao 10-50 mA (NOTE 2) (NOTE 1) (NOTE 1) 3 EAGLE 21 EXT. POWER SUPPLY N/A t4/A 'lc> V cle-t \\Oh ' ~ /#o-l + g 4 1-LM-63176 AB O 24 0" h o' (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) COMPONENT DESCRIPTION l Original NO. Manu f acturer / Model Number Contract No. Location. 1 GouLO - STA n4Ati / P D 3'200 -4 0c. W AN S NIT T'UL. 89NLD 'bh2.9 A G79 ' NNel f (cAuc 2 WESTINGHOUSE /EAI-01 I/E CONVERTER wau.l 89NNP-75380A NOTE 4 3 EAGLE 21 EXTERNAL POWER SUPPLY 69 HWP-75%OA NOTC ( ~' ~ 4 INTERCORP/ISBC88-4 0A A/D CONVERTER 89NNP-75380A NOTE 4 6.DDITIONAL CALIBRATION REOUIREMENTSl CALIBRATION FREQUENCY REQUIREMENTS _ CALIBRATION CYCLE MUS l tMONTHS .l l CA LIBRATION F.QUIPMENT ACCURACY REQUIREMENTS > 1 m s.s m a .i et e.p t st e,w e c. FoR C.AuB. cp mA4SOg1;l Ae cuRAcd. CfL Oc i n.ft, U Sc in c,iTA L tupkrw r Wm 4 I STATIC HEAD CORRECTION: NEGLIGIBLE - N/A ' TECHNICAL SPECIFICATIONSC SCCh u ' V'i - 3. L 7. 7 A u. et w r N ow ero w c. ~' S E C.Ti o N 3/14 3-2B ( Fort ATO sbytt a Ov Eg REFERENCES l No. BRANCH / PROJECT IDENTIFIER No. BRANCH / PROJECT IDENTIFIER 1 SON-EEB-MS-TI28-0013 2 SON-EEB-MS-TI28-00IO' ,' Attochmeet No. M ' $heetbf k % gjignnt;y0N-EEBMS -1128-0013 REV._Q, PREPARER /DATEQ/ J-/F.-96 CHECKER /D E,dfM/4V M d _SHT 1 C/ O._._;._,, Rev l /Pe n'n Xf h w fj_tf.^ cas:m) p HE fc l'5')JM _ Sur, ck !L ,:c a -

I SETPOINT-AND SCALING. DOCUMENT LOON wuMsERI -im Or-Ub-iv esse?: Yes_ t Ne_ s... LOOP.FUNCTIONl-See-sheet 1.'- .-m... w s MOP ACCUR&QXl Allowable Acceptable Acceptable Funetion Value As Found As Left See sheet 1. LOOP COMPONENTS Process Calibrat:.on Value Acceptable Acceptable NO. U N I t>- N o,.. - - Ranee /SetDoint - -Inout .-Ou t e u t. As Found As Le f t 5 1-LM-63-116 AD 0- E'io " H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 6 1-LM-6 3-l?G AG 0- No " H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 7 1 - LM-6 3 -876 0-60 " H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 8 1-LI-63-l% 0-240 " H O 10-50 mA 0-100% 13. o '/*

  • 2.0%

2 s GOMPONENT DESCRIPTION l Original 90.I Manufacturer / Model Number Contract No. Location 5 WESTINGHOUSE / EAGLE PROCESSOR LCP 89NNP-75380A (NOTE 4) 6 BURR BROWN /MP8316-V D/A CONVERTER 89NNP-75380A (NOTE 4) 7 WESTINGHOUSE /EAO-02 E/I CONVERTER 89NNP-75380A (NOTE 4) ~ 8 WESTINGHOUSE /VX-252 INDICATOR 90NLC-74545B C12/1M6 ELEV 7'32'O ADDITIONAL CALIBRATION REOUIREMENTS l CALIBRATION FREQUENCY REQUIREMENTS:_See sheet 1. l CALIBRATION EQUIPMENT ACCURACY REQUIREMENTS: See sheet 1. s STATIC HEAD CORRECTION: See sheet 1. -1 ~l TECHNICAL SPECIFICATIONS: See sheet 1. PEFERENCES_l Mg, BRANCH / PROJECT IDENTIFIER No. BRANCH / PROJECT TDENTIFIER See sheet 1. 3 Attar.hment No.3 $ beet h f A t.aos i/ldannf terson-Fit we MSe.not3 - t REV Q PREPARER /DATEh8A WW# CHECKER /DATF d/W//W'/d SHT 2 C/O 3 ) ji .i \\ .j).C...

SETPOINT AND SCALTNG DOCUMENT IDOP WUMBERl. j-t,,.g -(,$ -g/6 CSSC7: Yes W No-LOOP FUNCTIONI See sheet.1. IDOP ACCURACYj Allowable Acceptable . Acceptable Value As Found As Left Function See sheet 1. LOOP COMPONENTS Process Calibration-.Value Acceptable Acceptable NO. UNID No. Rance/Seteoint Ineut Outeut As Found As Left 9 I-LS. 0-l% l gg'gu /. - '/*h / (How A) (Norc 2) (NOTE 2) go l-L.f.1-65-476 AF "g e.g " //*O % 1,hoyg2) . (Nort 7.) (Nort -1) ll g L.,5 65-l76 A { / N d p II.O b i ca duct- ~ t, <: t s we-e o,72.%

c. 2*ro'

...N ,.i COMPONENT DESCRIPTION l Or.iginal. NO. Manuf acturer / Model Number Contract No. Locati.on 9 wcs,TsN G HCuSE / CAGL.E PRocESGQR Bt5 TABLE 89 MNP-7F3 80A (ROTE 4) to W C 578 H G Ho u s'C / t>( D cot 4vcRrept 99MMP -7F380A (gere 4) n wcsT NG House / D/o asoLATOR. h Ht4 P -7FSScA (HoTE 4) ADDITIONAL CALIBRATION REOUIREMENTSl CALIBRATION FREQUENCY REQUIREMENTS: See sheet 1. CALIBRATIO.N EQUIPMENT ACCURACY REQUIREMENTS:-. See sheet 1. STATIC HEAD CORRECTION: See sheet 1-TECJMICAL SPECIFICATIONS: See sheet 1. REFERENCES l } l No. BRANCH / PROJECT TDENTIFIER No. BRANCH / PROJECT IDENTIFIER l S c e'. S h e e t '.1 : .u. .. h.. -.... l ~19 Shier WA 2.ql _A,tter.hmer Na L. coo #fdtntiNr SON-EEB-M -T Z 2 8-0013 REV Q PREPARER /DATE NM W"f4 ' CHECKER /DATEAkW D SHT 3 ___ C/O 1 / / V I ~-

} I TRANSIER FUNCTICNS - emoeur.wo. i cut'PdT (E A) * ( 4 0 m A x ( twp t.9 )e10mA9 rio.2.mA ,o

s 240 " ko a

~ 2 -7 COMPONENT N.o.

-JwA.1 h r4 behe r e shhd += y+b --

N. "ud is d: ua.c c.oy o,l, a L_.S } ' ~' ' j COMPONENT NO. 8 \\ od J (%) ( inps ( s A)- i o m AQ t 2.0 */. = 1oo x P 9, o 4 A - J C O MrowcwT 93. 9 -It No NdMJud % sfte Co.,o,5 j eJ t d co-pon e-t-11. P j 15 A co nta t.+ clo s ure.. l i 4 -COMPo4 Car No. Attschment No. "14 $ beet 6 *f E8 Loop p/tdratifier SON-EEB+tS -T! 28-00t 3 i .i j j REV Q PREPARER /DATFf4M M - W 8 CHECKER /DATE. S/#2/2-// 'Jo SHT 4 C/o 5._ y 'h. '. g.I [.'$it'$..,

mmm 1l..%.AL T-(o3 -I'7(r) d im *... g (ut-0-174Ab) , #4 ! ( 4 #1 /74A8) LCP L6 5i o w e a L. ore dh[d*kdhh ha CK QEN CtDitsart gap Lgygg LS' I N D Qb ^ @.W 4 wi tem-L6 8204 i aD ("E

  1. 4 l

l lo.scaA:. t.63 4) i l n r _.. ;<,;4 g A4 0M-G~IIS l l lLv l gy, ...{ me bt;;...] a l / l e! i t i Auto nretac t s N ow tutto.oca i Ae Alanu) l (55PE) g ,/ l, 8 i .l g t i ILD/ 'i' Attachment No.-- 14 Sheethf 3d. are h7-S3'/75) Looo y/ldentifierw 3. m a s. m n. M ll .~ I CONTROM f REV Q_ PREPARER /DATO/fd'M'-f4 CHECKER /DATE I' #"' / ^ > ^ D SHT_ 5 ' C/C '6 y i e f ,h*,

COMMENTS AND NOTES 1. Encompassed by the indication's value. 2. For specifics see the references and the Eagle 21 Technical Manual. ~ 3. See transfer function sheet for value. 4 4. Components 2 through 7 are part of the Eagle 21 RPS System located in the auxiliary instrument room at elevation 685' and cooroinate panel C-1. 5. The pressure is applied to the high pressure port of the transmitter'. 6. The transmitter is calibrated separately from the other loop components. 7. Output is energized on decreasing signal for auto switchover and de-energized on decreasing signal to alarm. 8. Most stringent AV values based on small break LOCA conditions. 9. AV value for switchover is from Tech Specs and applies only to the Eaglo 21 equipment (transmitter not included). Refer to referJe ce 1 for calculated AV values, The AV values are .,. m.Vy/*pe 4 (",,c8f, - 5.917c s 24 (2Sf[ Attachment No. t y%nt;,,50-EEPgtT- -00 0 REV O PREPARER /DATE_ h/[/WM4 CHECKER /DATE CM/2 wad

SHT b C/OFINE PREPARER /DATE b NHECKER/DATNA /'/".r/ sbe REV I

/ SHT b C/OFINAL t

NUCt.F.AQ ENGINEERING UC ENGINEE '4 sh-- sEOVOYAN ENGINEERING PROJECT ECEP-REVISIC. U PROJECT MANUAL TrwNessEs TENNESSEE VALLEY AUTHORITY gr.,,, VALLEY cmsION CF 6 DCIGIm ENGINE wo SLP".m e SEQUOYAH NUCLEAR PLANT s SE 30::\\" AND SCA_::sG JOCM EN" t. FOR INSTRUMENT LOOP NO. I - LT - G,'s - 177 5 i E 2 Attachment No. M $heet U 'af..d \\ '\\ j W p/ldtenfiepON-EEB%'tS -T128-0013 l g REVISION RO RI R2,d" #My[ -Re-N [f[d@$- ~ DATEpty.Sp Z-f-ft 7 21 <fa 3.po.70 l PREPARED Q M/)ML. lf//g,1 MQ((_/ g VERIFIED (d[d7 d S;6N[)k',hM.C M. SM-REVIEWED Made.T M_(MJ$36 MM [1 r 4 /./p k j APPROVED X Mgg I ISS'E ' X X w.v.: 'i

{ -.. j SETPoln r AND SCALING DOCUMENT LOOP NUMBER l 1-LT 177 CSSC7: Yes X _ No-LOOP FUNCTIONIMEASURES THE LEVEL OF FLUID IN T H E-RcA62, hgo% .s SUMP to PROVIDE MCR INDICATION FOR POST ACCIDENT MONITORINGr LOW LEVEL .fs m Hovt11,fTO'tME REACTOR BLDG. CONTAINMENT SUMP FOR LONGER TERit N-~ + 'R ECIRCULATION f ~ ~ LOOP ACCURACY l /4.18g pilowable Acceptable Acceptable Function ( i. w.Value As Found As Left RB sum 9 Le.v t.L TwonoiJ Foft PAW WM -5'.t47.*

  • '5. !!rlo %

+ 2.06% _N ite a ovest Fort A c c.itte u t.AT t o8J Not ;. 0 ; P. Note 9 ! '!.7 i e o o a l* sce udte 8 LOOP COMPONENTS Process Calibration Value Acceptable Acceptable i NO. UNID No. Rance/Seteoint Inout Outeut As Found As left 1 1-LT-6 3 - 177 O-No' Hto .e o 240 H30 10-50 MA 1 f.9 t'. er. 1 0. 5 \\ o r-fNOTE Si fNOTE si O.N'mA o. 2 o 3._,, 2 1-LM-6 3 177 AA o-2*4 0" H ao 10 -5 0 :t.A (NOTE 2) (NOTE 1) (NOTE 1) 3 EAGLE 21 EXT. ~! POWER SUPPLY N/A bil^ Sc> V cle-t \\ 0 */= i/Mol i 4 1-LM-63 177 A B O - 24 0" H.o' (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) t COMPONENT DESCRIPTION l Original No. Manufacturer / Model Number Contract No.

Location, 1

GouLD - STAT 4Ati / PD 3' 00 -M cec, 'TR AN 5 nit t'ER. 6.9NLD ~1t29 A (179 ' wrnoct 2 uwc wuq 2 WESTINGHOUSE /EAI-01 I/E CONVERTER 89NNP-75380A NOTE 4 3 EAGLE 21 EXTERNAL POWER SUPPLY 89WP 'iS%OA NOTE'44 '~~ 4 INTERCORP/ISBC80-4 0A A/D CONVERTER 89NNP-75380A NOTE 4 ADDITIONAL CALIBRATION REOUIREMENTSl CALIBRATION FREQUENCY REQUIREMENTS:= CALIBRATION CYCLE MUST NOT EXCEED 2fal, iMONTHS l .i CALIBRATION F.QUIPMENT ACCURACY REQUIREMENTS > l h s.5 n4E R e.F cR e.ne t. Fen cat.ss; es: inAushirnit'g Ac cu 0.A c.M. crL tht':TTttit. L4 9C m ce T ^ t. cwRrm Mcim STATIC HEAD CORRECTION: NEGLIGIBLE - N/A TECHNICAL SPECIFICATIONS 4 scc now v4 3.1. i. 7 a c.otwr sowitcasC, ~! S E C.Ti o N 3/4 3 *2.B ( Fop Au.ro ges,.re a o v et

pyyygguctsl

....... - - - ~ - - - - No. BRANCH / PROJECT IDENTIFIER No. BRANCH / PROJECT IDENTIFIER 1 SON-EEB-MS-TI28-00)J _2 SON -EEB-MS -TI 2 8_-0 01o-d 'ArtocJveeer so. D ' Sheet._.2.:hf.3.8 - % ggnnpy0N-EEBAS -TI28-0013 l ~~~~ REV _q PREPARER /DATEhN'/f'14 CHECKER /DATE, O/#/2-P/ 90 ; SHT 1 - C/ O.__s,, Rev L /k'WMcV&hl.ifi-f'N' C"E"CC / M72- $3Mf3-940 Sat' ' - Cl* ?- 4 :h.v ~

I. sETPOINT -AND SCALING -DOCUMENT toop NUMBER l-i: Or. Lh-17 y CSSC7 Yes.. 1 No_ g... inop.rUNCTION L See sheet 1. - 3 Loop ACCURACY l Allowable Acceptable Acceptable Function value As round As Left See sheet 1. ...L. LOOP COMPONENTS Process Calibration Value Acceptable Acceptable, NO. UNI D-Nch Ranoe/E-etroint - -Inout Cutout. As Found AsLeftjl 5 1-LM-63-177 AD 0-110" H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 6 1 -LM-6 3 -l? 7 AG 0- No " H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 7 1 - LM-6 3 -177 0-NO" H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 8 1-LI 177, 0-2'40 " H O 10-50 mA 0-100% 2 3.O '^

t 2. 0 %

2 COMPONENT DESCRIPTION l Original (LQ.,1 Manufacturer / Model Number Contract No. Loeotion_, 5 WESTINGHOUSE / EAGLE PROCESSOR LCP 89NNP-75380A (NOTE 4) 6 BURR BROWN /MPB316-V D/A CONVERTER 89NNP-75380A (NOTE 4) ,7 WESTINGHOUSE /EAO-02 E/I CONVERTER 89NNP-75380A (NOTE 4)"~"~ 8 WESTINGHOUSE /VX-252 INDICATOR 90NLC-74545B C12/1M6 ELEV 732'O ADDITIONAL CALIBRATION REOUIREMENTSl CALIBRATION FREQUENCY REQUIRF.MENTS: See sheet 1. = ]l CALIBRATION EQUIPMENT ACCURACY REQUIREMENTS: See sheet 1. STATIC HEAD CORRECTION: See sheet 1. l TECHNICAL SPECIFICATIONS: See sheet 1. REFEPENCESl No. BRANCH / PROJECT IDENTIFIER No. BRANCH / PROJECT IDENTIFIER-See sheet 1. ~ Art achreent No__ M_ $hegehtg ~ Looo i/ldtanfterSOM-Ert-wc.me.noa i i l REV Q PREPARER /DATE W M W W CHECKER /DATF (D/H//-/VM SHT 2 C/O-3 ( i j..).s2.. :-

s SETPoINT AND SCALTNG bcct.iiiiENT LOOP.NUMBERI..._...d... Lg-M -l7 7 CSSC7: Yes W No_ IDOP FUNcTIONI See sheet.1. ..~ 1h0P ACCURACYj Allowable Acceptable Acceptable Function Value As Found As taft See sheet 1. thop COMPONENTS Process ' Ca librat nen..Value Acceptable Acceptable NO. UNID_No. Rance/Setnoint Ineut outnut As round As Imft 9 1-LS.O 177 l g gy <,g. a ti,0% (9 o tv. 2.) (NorE 2) (NOTC2) to j -t t 1.M.177 AF j'p <. g iko's @o7gg) (Hore 7,) (Norc j,) It

- t.S.O-177A l 8J'b g '

T

11. 0 %

Mct-o,82. % c.1% e.t. s <r-a. ..l,, COMPONENT DESCRIPTION _l Or_igina.3.. pp.' Manufacturer / Model Nutnber 1. Contract No. Location 9 W c sTs N 6 House / C AG L.E PRocE%QR Bt 5TABL E 89 NNP-7F380A (HoTE 4) { to WC Fit 4G Ho u fE / D/ b con VERTEpi 99N4P -7F380A (Notc q) i in WC STING house. / D2D 15cbATOR. . h Nttf -7F580A (e4cTE 4) I ADDITIONAL CALIBRATION REQUIREMENTS _l. CALIBRATION FREQUENCY REQUIREMENTSi See sheet 1. \\. CALIBRATION EQUIPMENT ACCURACY REQUIREMENTSL See sheet 1. STATIC HEAD CORRECTION: See sheet 1. TECHNICAL SPECIFICATIONS: See sheet 1. REFERENCES l No. BRANCH / PROJECT IDENTIFIER No. . BRANCH /i)ROJECT ID'NTIFIER E I See neet:1. s.u...... u :. a.. - :. Attachmene N. E suc_.!.l.,3, _2.s j 1 i i/fdtatiner SON-EEB-MS-T!28 001 REV 9, PREPARER /DATE A ~/ N ' CHECKER /DATE bl#7!8-M Od SHT __3 C/O 4 i i i, i i i

TRANSTER FVNCTIONS . ComPo4CNT.tJc. l l duTPRT (fw A) * ( 40 m A W ( twps#'A 'l .9 , e 10 mA-76 o,i m a J' 240"14s0 / j 2-7 COMPONENT N.o. No

-cb v i.1

+ c A., r A r b 4%.T7 c b.Wd +e yd v -- ud ind oac, t.ogo.,'emi-E',-S} ~ ~ " j COMPONENT No. 8 1 ow+ PJ ( %) ( in g + ( m A) - t o m,Q + y, = 10 o x O g coscoweur 93. 9 -it No NdMJud % :F u C., A t j e s g,.t of t,_ g,,,g gt I5 4. Co ntut dosure. i 1 s ~ COMPot4 CW No, .l j 14 Attachment No. _ Sheet IE f d l Loop p/fdtntifier SON-EEB M -TI28-00l3 x e. ,. i l REV Q PREPARER /DATF Mr M-/VW CHECKER /DATE,.L/10/8-l'/~Y#_ SHT 'i C/O_ 9 l Iu '., J M1if4.., s.,

wog rdACRAM ""I '1 l LT b3-179 ft T-fet - ~ 4.,. .a i l - g i n L si;f --- Lili (tnt-G- 1774A) i 34 , A4 r i(uM3-17 7M) l LCP L'oiJ C:"' M L*8FC l (,'a'a'!a 7LM-63-/77Ab lA:0NTearf SU/ LEVfL l LS-63 ) h -17.7 n G. i ,, am. tm u LS li$a - / 72Af) o 4.: i ~ l I,1(LS 63-!?7A). l(15***** ""g-D-177) ~ j $284 %stu;, l m l i (l/06F/7 j

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j .t n, I a4 :. f seio areta: H lh t!8P.0CX wo 4apel iws; l q i

,1 i

J-jif Artxhment No. 24 Sheet i f lk. [ y. 43.j 77 Loop p/ldentifier RO'3-""*3 *"* AS f 3 L co" tao'J 1 Rtv.,,g_. PREPARER /DATEQ/8/-N-f4 CHECXER/DATE h5/?/FM SHT. S 'C/c 6 V i~i G ..l.'..'

r COMMENTS AND NOTES 1. Encompassed by the indication's value. 2. For specifics see the references and the Eagle 21 Technical Manual. 3. See t'ransfer function sheet for value. 4. Components 2 through 7 are part of the Eagle 21 RPS System located in the auxiliary instrument room at elevation 685' and coordinate panel C-1. 5. The pressure is applied to the high pressure port of the transmitter'. 6. The transmitter is calibrated separately from the other loop components. 7. Output is energized on decreasing signal for auto switchover and de-energized on decreasing signal to alarm. 8. Most stringent AV values based on small break I4CA conditions. AV value for switchover is from Tech Specs and applies only to the 9. Eagle 21 equipment (transmitter not included). Refer to reference 1 for calculated AV values, TheAVvaluesare+6.12%,-L.554.ffspo/p 4 Gi.08k; - T.91!$. s D 5QN-EERgt ( 2S *[ Attachment No. T 001) W #fdunflu REV._9_ PREPARER /DATE h/[/#-/MA CHECKER /DATE ON8 wad SK _ b C/OMNAL REV \\ PREPARER /DATEb *^ llECKER/DATEE /W $/tr/fd SHT. b f C/OFINAL I L

.NUCLEAD ENGINEERING g U"* M ENGIN'- '4G -- EOT SEQUOYAH ENGINEERING PROJECT p

REVISI,

_o, PROJECT MANUAL TVA. TENNESSEE VALLEY AUTHORITY itwNEsses m,,, Ju$$EITw Ivtst e cr e cr e rws ELor~c ~. + SEQUOYAH NUCLEAR PLANT g SE" 30::s AND SCA_:: NG JOC VEN" s. FOR INSTRUMENT LOOP NO. I - LT - (c,'J, - 178 - ? D i t I Attachmeet No. AN _$ beet i 5 ' f. _Q \\ '\\ La,,jgggnnt;,p0N-EEBs'tS -TI 8-0013 i REVISION RO RI -A2- $$ $djjn Rd. [3 ' # j(45-f g DATEp-/y.p .3 -p.fo 7.r).ga p.y E PREPARED h ) /) M, };gg4 Whu_$[ [p ^ f _ VERIFIED jJ/,[gf, jff'7g[7fhh[t%f,4gy,, 3 REVIEyEO ), gay')Ra,Q fy jfg .g]/;,f APPROVED g i ISSuto X X >g.,

( ~ r- ~- SETPoli,r AND SCALING DOCUMENT LOOP NUMBER l 1-LT 178 CSS C"t Yes, 2L, No___ LOOP FUNCTIONIMEASURES THE LEVEL OF FLUID IN THE RC As mk fku t tt>iN c,, i fuMP *FO. PROVIDE MCR I)fDICATION FOR POST ACCIDENT MONITORING t LOW LEVrt TsertMo q fro 'rHE REACTOR BLDG. CONTAINMENT SUMP FOR LONGER TERM-~~---- - RECIRCULATIONf ~ ~ LOOP ACCURACY l f +.'l8 Z.Allowable Acceptable ' Acceptable 9gY kM&Y' Value As Found As Left Function AS SUMP Le.v t.L Tu t>un o J Fott PMCW3 -fr.t47. 8

  • ~5. F(o %
  • ?., o(.'%

ha m.< ov e n. F.o rt f.E c. int u t.ATlotJ f/rAA--l i. 0, % - Norc 9 '! T t.7 3 i r I o l,se,een, 8 i _ LOOP COMPONENTS Process Calibratdon value Acceptable Acca.ptable NO. UNID No. Rance/Seteeint Ineut Outeut As Found As left 1 1-LT-6 3 - 17g o - 2*( O

  • H 2,0

,e 0-2'iO H o 10-50 MA 2 f.9 F. or-2 0. 5 % of-fNOTE Si (NOTE 6) t O.*7I.' mA t 0. 2 0 r=3,,, 2 1-LM-63178 AA o-2*40"Ka0 10-50 mA (NOTE 2) (NOTE 1) (NOTE 1) 3 EAGLE 21 EXT. POWER SUPPLY N/,_A t4/A 'lo V ckc. t \\ 0 */. t/g 4 1-LM-63176 AB O - 2.4 0 " H.p' (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) t CQMPONENT DESCRIPTION _l Original NO. Manufacturer _/ Model Number Contract No. Location _, 1 CrouLD - STAT 4AM / PD3?Co Moc W AM5 nit R Sc)NLD ~ih2c) A 6'79 ' wts *M ~ tchuc coatt 2 WESTINGHOUSE /EAI-01 I/E CONVERTER 89NNP-75380A NOTE 4 3 EAGLE 21 EXTERNAL POWER SUPPLY 8%4P-75HsOA NOTC4 ~ ~ ~ INTERCORP/ISBCB8-4 0A' A/D CONVERTER 4 89NNP-75380A NOTE 4 ADDITIONAL CALIBRATION REOUIREMENTSl CALIBRATION FREQUENCY REQUIREMENTS: CALIBRATION CYCLE < MONTHS CALIBRATION F.QUIPMENT ACCURACY REQUIREMENTS > 1T~$ m e s na e. Re.F ER.e sc r. Ac cuRAcd. crL GCTTED_. 149C D WTAL tuihNh Mi. Tut STATIC HEAD CORRECTION: U.Efq.LIGIBLE - N/A FeR Coun. c,c TRMSMrd ~ TECHNICAL SPECIFICATIONSW secwy ' v4 - 3.1.7.7 As c.0tur N ow croRiN C, ~ SECTioN 3/4 3-2B (1~ OIL NTD St rere H OV EQ perparpersl No. BRANCH / PROJECT IDENTIFIER No. BRANCH / PROJECT IDENTIFIER 1 SON-EEB-MS-TI29-0013 .? SON-EE,B-MS-TI28-0010 I 'Artechmeet No.'- D '$beee,_l$L f 28-." Laos $/ldentifiep0N-EEB AS'-II28-00 83 REV.,Q_ PREPARER /DATEh/W4'//1~d CHECKER /DATE, bN2-N 9F ~~~~~ .. - - ~ RN 1 /E*uWm'0/?/: /&FR.,. pea.CC/ MTG. f titj $.s).9u &n* L clo. L SHT 1 C/O 0

1 I 5ETPOINT.AND SCALING. DOCUMENT LOOP NUMBER l-U Or-(.'b-l*/$ CSSC78 Y e 5,:,.'t.,, N o 1...... LOOP.rUNCTION I See shee t 1.. s - t i + s LOOP ACCURACY l Allowable Acceptable Acceptable Function Value As Found As Left See sheet 1. i LOOP COMPONENTS Process Calibration Value Acceptable Acceptable NO. UNI D. Nch Rance/SetDoint- _Inout -O_u t et* t. As Eeund As.Left 5 1-LM-6 3 -17F AD 0- 2,10 " Ho (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) j l p. 6 1-LM-63-nTEAG 0-140" H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 7 1 - LM-6 3 -176 0- 240 " H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 8 1 - LI - 6 3 - l'T2 0-2*to" H O 0-50 mA 0-100% 13.0 'A,

2. 0 %

2 Original COMPONENT DESCRIPTION l NO.? Manufacturer / Model Nunber Contract No.

Location, 5

WESTINGHOUSE / EAGLE PROCESSOR LCP 89NNP-75380A (NOTE 4) 6 BURR BROWN /MP8316-V D/A CONVERTER 89NNP-75380A (NOTE 4) l 7 WESTINGHOUSE /EAO-02 E/I CONVERTER 89NNP-75380A (NOTE 4)"~ .1 8 WESTINGHOUSE /VX-252 INDICATOR 90NLC-74545B C12/1MG ELEV 732'0 j ADDITIONAL CALIBRATION REOUIMEMENTS l CALIBRATION FREQUENCY RECUIREMENTS: See sheet b _ll CALIBRATION EQUIPMENT ACCURACY REQUIREMENTS: See sheet 1. 3 I STATIC HEAD CORRECTION: See sheet 1. ~1 l -. \\ ) TECHNICAL SPECIFICATIONS: See sheet 1. l REFERENCES l No. BRANCH / PROJECT IDENTIFIER No. BRANCH / PROJECT IDENTIFIER See sheet 1. ~ Attat.hment No M --$heet1,Zaf A Laos i/ldtnnf:pSON-Fr*- ws.m e.not 3 { i REv o_ paEpragafox7tQpM.n.fe CHECKER /DATr (?/vY/-/790 SHT 2 C/O 3 y / 9 1 g....:

s SETpoiNT AND SCAI TNG DOCUMENT .., ~ IogP _tttDtBER l'.. 1-U..t....M - f78 CSSC7 Yes Y _ Nog ~ ~ IDoP FUNCTIONI See sheet.1. -. ~ 3 LDOP ACCURACY l Allowable Acceptable ,Ac.ceptable' Function Value As Found As I,tft Ege sheet 1. ~ IDOP COMPONENTS Process Ca librart n on..va lu e Acceptable Acceptaale NO. UNID No. Rance/Seteoint Incut Outeut As Found As Le f t _ 9 i-ts-b3-i7e i gg, y <, 11 0 % l (eow.2.) 640rt 2) (Nott 2) ', pg '- g' r

18. 0 %

((N, ow 2) lo l L.M-63-USAF . ( N o r c 2.) (N O Tr. ".J.) f... il g - LS.(jb-(7F A l S' h,, <.g y 11.0 % ' M et ' O.8 ?. % o.2. 9lf. c.t. w a. COMPONENT DESCRIPTION l Or.igina.l.'... ~ gO. Manufacturer / Model Number 1. Contract No. Location _ h 9 \\n tsTiH G Heus E / E Af.LE pro cE550R Bt5 TABLE 89 NN P-7!73 CCA (HoTE4) to WC5TlHr.HouTE / d(n coNvegun 99 NNP -7F380A (goTc y) west No House / D/o isoLATCR. h NNP -7f5SCA (NOTE 4) ADDITIONAL CALIBRATION REOUIREMENTSl, ~ CALIBRATION FREQUENCY REQUIREMENTS _See sheet 1. .r CALI.BRATIO.N EQUIPMENT ACCURACY REQUIREMENTS: See sheet 1. t STATIC HEAD CORRECTION: See sheet 1. TECHNICAL SPECIPICATIONS: _See sheet 1. REFERENCES l Noi BRANCH / PROJECT IDENTIFIER 4 No. BRANCH / PROJECT IDENTIFIER 1,- ~~ See ghnec'1, .. ~.. ........a...,,,. . ~ '.. ;,;,,,,,,,.

Aetachsene Na W Mf 2;,,,,, l 1,o,og pggng, SON-EEB.etS-TI28-00f 3l REV Q PREPARER /DATEOMNbfW _' CHECKER /DATEI)# f-M94 ' _ SHT ~3 C/O i,

n.

i TRANSTER FVNCTIONS i - CO MP o4(NT*. N O... _ - I l CuTP4T (ek A) * (! 4 0 m A W ( imp g.ptojh e 10 mA.)7d o,2 o, A o i l i l {s 240 " t4 o / .] t 4 l

  • ~

I 2 -7 COMPONENT N.o. No in div *dw a k' O An t~h

  • h n' 4N 6aT 7'
  • C h. bMkfd h '

3 V' * -- i wid in d: udor c.cy o.,'c of. W -.% } ~ " ~ ' i j j ( CCMPONENT No. 8 '~ / O w+ p% t ( Y*) = lOO x ( ing t [% A)~ g o m A 3 l 4, o 4 A J t C ANowc47 90. 9 - 11 ) D bM ud N% 5(t r ke d*> g j e sd p% t cf % p pn g,,, p Q con % + d osure.. s I l

~

s

  • COMPoMA)y po,

.l Attachment No. D $heet N *fd Loop i/ldentifiet $QN-EEB.Ms.TI 2 8-0013 l .. i REV 0 PREPARER /DATE /#"/VW CHECKER /DATE. If. Ah'-/'/Y# ,. S H T 9 C/O 5 i

  • 1.ifj@.. _

wer-meru . ~ "; i ~ . 'T-6 3 -'.'L ..uo I 3 t hti,, M (im 43-/7tAA) i(L M-O-??S AB) LCP i.A1EJ c alm (.cM%QLM D /7/AD) O l ?g N etstfuut s w Ltva. Jt.s.e 14 k .d.n;!'hx*8 a 5 :s: i TTaT1 nie i i t -l (4.5 63 E84) I [X.S-S.I j j t% - - Q - - g5l P (IAl* O~ pI f p $3-/7&)p) g " nie it, in " aio nio ,j---a J----aq,,,' e. j .i i l -:~,

  • s

(. l 1 I I wto arcine Ye'"d!E l (42 0-/73 (5 W l l .l I, .t I ~ ~- .~ 1 Attachment No. M Sheet 2.0.t 23 NE' nrs i I Loco e/ identifier M'3 r"#9 "'o 'al3 CONTROL REV D PREPARER /DATE 9/2//~/F'N CHECKER /DATE (IM /SN 4) y i SHT_ 5 C/c b -- .i e d6

1 COMMENTS AND NOTES 1. Encompassed by the indication's value. 2. For specifics see the references and the Eagle 21 Technical Manual. 3. See transfer function sheet for value. 4. Components 2 through 7 are part of the Eagle 21 RPS System located in the auxiliary instrument room at elevation 685' and coordinate panel C-1. 5. The pressure is applied to the high pressure port of the transmitter. ~ 6. The transmitter is calibrated separately from the other loop components. 7. Output is energized on decreasing signal.for auto switchover and de-energized on decreasing signal to alarm. 8. Most stringent AV values based on small break LOCA conditions. 9. AV value for switchover is from Tech Specs and applies only to the-Eagle 21 equipment (transmitter not included). Refer to reference 1 for calculated AV values, The AV values are w.12h C.95t-p 3pyp t 6. 0 82., - S M/,. j s Attachment No. M EPger (29 { 00 0 Laos i/tdtnnfier REV._Q_, PREPARER /DATE h/NWM4 CHECKER /DATE CIAf8 mod ' 'SHT b C/OFINAL PREPARER /DATE WINCHECKER/DATEM (P.' # N "# REV I SHT 6 C/OFINAL

sEEEi!?SH G PROJECT PROJECT MANUAL itswEssEr TENNESSEE VALLEY AUTHORITY J v. yuSSITw = ~ SEQUOYAH NUCLEAR PLANT s SE 30::s" AND SCA_::\\G JOCM EN" r. FOR INSTRUMENT LOOP NO. I - LT 179 l 8 i C I i i Attachment No. D $beetMt 2.1. \\ \\ 3 % gygnnt;,)0N-EEB4tS -TI 8-00: 3 I g REVISION RO RI 42- (( 'MD[f -Re E[ ' [q'. b e DATE2v490 3-9 f4 3-27-90 3 3o.70 l PREPARED d.Lj pgs'4, 1,.,,jgfff, )6')kRf/ M l vERIeIED i11.bl~of,t rLWatfMT",'.2 M '.,A g REVIEWED )ftl_:.Our d % %* #%g .}.Opc4e ! iranovED <wp 1 IssuEo 3,3 y

u, ~. SETPOInr AND SCALING DOCUMENT LOOP NUMBEEl1-LT 171 CssCt Yes _X No_ ~ LOOP FUNCTIONIMEASURES THE LEVEL OF FLUID IN THE R C A cT t R. (knoiN G,. _ _/ AIMP.'TO PMOVIDE MCR INDICATION FOR POST ACCIDENT MONITORINGt LOW LEVEL JwvtMovntfro '*fME REACTOR BLDG. CONTAINMENT SUMP FOR LONGER TETLF----- - l 4 RECTRCULATIONt - i LOOP ACCURACY l 9# Y.98

  • AlloWeble Acceptable Acceptable 44 y

Punction Value As Found As Left ,RB SUMP LEVt.L TM bomo tJ

  • Fo ft PAM M"a-F.4 */. *
  • S.F6 %
  • f.. O (.' %

,'_ b ite s even. Fe tt. Acc 4e utAotJWM A Z" Nove 9 1 ' !.7 i o o 1* sce ucrre 8 t LOOP COMPONENTS Process Calibratdon Value AcceFtable Acceptable NO. UNID No. Rance/SetDoint Incut Outeut As Found As Left j 1 3 - LT-6 3 - 479 O - 24 0 ~ H a.O .e 0-29 0 H ao 10-50 MA 2 1.9 fe or. to.20 1, 2 0. 5 % of-(NOTE Si (NOTE 6) t O.W mA 2 1-LM-63 179 AA o-2640"Hao 10-50 mA (NOTE 2) (NOTE 1) (NOTE 1) 3 EAcLE 21 EXT. POb'ER SUPPLY N/A t4/A So V cle-t: \\ O */. & /05l. 4 1-LM-63177AB O - Mo" H c9' (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) l COMPONENT DESCRIPTION l Original NO. Manuf acturer / Model Number Contract No. Loc a t i c_ n... 1 GOutO - stAm4At1 / PD 3200 -%c, 'TR AN 5Ni h d 89NW 'N')2*>A ( 73 ' wrss9cl f uAuc us : 2 WESTINGHOUSE /EAI-01 I/E CONVERTER 89NNP-75380A NOTE 4 3 EAGLE 21 EXTERNAL POWER SUPPLY 6%W P-75%OA NOTC9 ~' 4 INTERCORP/ISBC88-4 0A A/D CONVERTER 89NNP-75380A NOTE 4 ADDITIONAL CALIBRATION REOUIREMENTSl CALIBRATION FREQUENCY REQUIREMENTS:_ CALIBRATION CYCLE ' MONTHS ,,,,,, ),! CALIBRATION F.QUIPMENT ACCURACY REQUIREMENTS > lit ~m.5 1i mE n e. n R e.s e t. l Ac e_uRA c.H. crL OcTT1trb L4 9c plc,iTat cuFbNY M Gt u Fett entfs. cc TTUWS STATIC HEAD CORRECTION: NEGLIGIBLE - N/ A I TECHNICAL SPECIFICATIONS.+' 5 CCW u ' W - 3.1.7.7 Act. 'OcNr N ow i roa N C, i SEC.TIO N 3/44 3 ~2 8 (1 oR. /h'ro S u yrcw 0vEff\\ I a pEEERENCESl - --- - " ~ ~ - * ' ' -'-' ~ ' No. BRANCH / PROJECT IDENTIFIER 'No. BRANCH / PROJECT IDENTIFIER 1 SON-EEB-MS-TI28-0043 2 SON-EEB-MS-TI28-0010 i Artochdent No.' D hethf.,3,8 = I l.cos #ldtnhfyQN EEBMS -TI28-0013 _Y

  • REV 9._ PREPARER /DATEDN#-/M4 CHECXER/DATE. b/4/8-/Y 70 SHT 1

C/0_ ;,, ret?. l )*/r//4*rxl&firO $ f_fG CHSMl *'AIE IC3h1l s') 'tu cfo Z- . W1*

E ). SETPOINT AND SCALING-DOCUMENT Loop - NUM BER l - i - Qr. ("b" l *7 9 CSSC78 Y # 8...1 N o g... inop.FUNCTIONl.See. sheet 1. ' .i c. t + s 1DOP ACCURACY l Allowable Acceptable Acceptablo ru n e t i o n Value As round As Left See sheet 1. __ LOOP COMPONENTS Process Calibratten Value Acceptable Acceptable NO.I UN I D-Nes. -. Rance/Setroint -._ Input -Ou t eu t - _As Found As Left 1 5 1-LM-63-177 AD 0 - 110 " HO (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 6 1-LM-63 ) AG 0- NO " H O (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) 2 7 1 -LM-6 3 -479 0-do" H o (NOTE 2) (NOTE 2) (NOTE 1) (NOTE 1) y 8 1-LI f77, 0-240 " H O 10-50 mA 0-100% 2 3.o '<,

  • 2.0%

2 COMPONENT DESCRIPTION l Original NO. Manufacturer / Model Nunber Centract N o.__

Locatien, 5

WESTINGHCUSE/ EAGLE PROCESSOR LCP 89NNP-75380A (NOTE 4) 6 BURR BROWN /MP8316-V D/A CONVERTER 89NNP-75380A (NOTE 4) 7 WESTINGHOUSE /EAO-02 E/I CONVERTER 89NNP-75380A (NOTE 4) ~ '8 WESTINGHOUSE /VX-252 INDICATOR 90NLC-74545B C12/1M6 ELEV 732'O ADDITIONAL CALIBRATION REOUIREMENTSl ~ CALIBRATION FREQUENCY REQUIREMENTS: See sheet 1. ~~~ p CALIBRATION EQUIPMENT ACCURACY REQUIREMENTS:_See sheet 1. ] j I STATIC HEAD CORRECTION: See sheet 1. i " l TECHNICAL SPECIFICATIONS: See sheet 1. R E F E R EN CES_ l No. BRAT 4CH/ PROJECT IDENTIFIER No I BRANCH / PROJECT TDENTIFIER-See sheet 1. .,_ d Atterhment No. M - $heet&Qt), L.aeo 6/ldtanfierSON-rit wSme.nm 3 __ t REV Q PREPARER /DATE h/ N #-/F WCHECKER /DATF 0/M b-/'F/d _ SHT _1 0/0 3 f / af k Q

SETPOINT AND SCALTNG Dor _u G T ~ LOOP NUMBER l j- ..... t.,y - g - r7 9 CSSC7 Yes Y No-mop FUNCTIONI Sein sheet.1. [. ~.. = ....-s p>0P ACCURACY l Allowable Acceptable . Acceptable Function Value As round As Left See sheet 1. LOOP COMPONENTS Process Calibration..Value Acceptable Acceptable No. UNID No. Rance/Seteoint Incut Outeut As Found As Left 9 l-LS O-179 l ' g // Il. 0% (p o7t. 2.) (NorC 2) (t4cTE 2) H.0 ** so j tt.1 6,3..n9 AF ...,g g2. '. g " g (No rE ?.). (Norc 7.) (NoTC 1) 'n i. t.s.u-n9 A l 4 8 3,-4, l H,o % ' I c 4= ct- 'o,s2.% A z %. et. s e s. .~ 1 COMPONENT DESCRIPTION l Or.igi.na.1. ( No. Manuf acturer / Model Number ?- Contract No. Location t 9 WESTsNG house / CAGLE PRocE%cR B t STABt.E 89 tte4P-7FB 80A (HoTe 4) ( l to WC578NG HoufE / tyb con vcBrcM 99Ni& -7F560A (NoTc y) n wc5T NG House / p/o 15cLAToR. h Ht(P -7T54cA (NOTE 4) \\ ADDITIONAL CALIBRATION REOUIREMENTS( CALIDRATION FREQUENCY REQUIREMENTS: See sheet 1. l g.

  • ,,,, g,

CALIBRATION EQUIPMENT ACCURACY REQUIREMENTS: See sheet 1. . - ~. STATIC HEAD CORRECTIONt_See sheet 1-TECHNICAL SPECIFICATIONS:.See sheet 1. B.Ef_ER ENCES l No. BRANCH /fROJECT IDENTIFIER ~ No. . BRANCH /PRCATECT' I' ENTIFIER D gce ineet t,. ..........,,g,

Attachment P4 D

Mi_2S l - l Loco i/fdtntif4r QN-EEB.MS-Tt28 0013 i S REV Q PREPARER /DATEh/2 WW ' CHECKER /DATE O N-/'/.70 HT. ~3 C/01 ! .. ~...... -,

TRANSFER FUNCTIONS - Co m Po4(.NT*. N C. l l - curP4T (m A) = /40- A i (i ps*9 o)) e 10 mA44of m A 9 t y 1 \\.- 240 " Aso 1 COMPONENT NO. 2 *7 '~

mdwSal

%.,s-b b 4*6 r7 twMy&d b yb - - No co on e J A,-% M Ind; dos- ) l COMPONENT NO. 8 ow+PJ (%) ( inp + [m A)- ( O ~ A iOO x + 2.O 4 i,o 'A j m s L coscowcur 90. 9 -i t No l' t.h 'i d u d %+ s (t.r b c.% f f oJp%t c4 - (c>mpon eM-11, is w conta(+ clo s ur e.. I l i 4 l l s -t'OM Po4Dyr No. -l Attachment No. - 19 _ $ beet-16 sfd Loco si/ld:ntifier SON-EEB MS -TI28-000 j REV_ CL., PREPARER /DATN8M/#*/F4# CHECKER /DATE.kl'/[d/U94'SHT 9 C/O 5 / / r t 4* .I . Ib.,,

1 t teer-oracRxn .----1, ~ -- _ _ _._. _.h..r-6.3 -i_u)Lys t oE cpri t w ~ n., OU.1510E CONTAlb i. ti i n:Laie--- @ Im. 63-17eM) ..i. l ( L M. f 3 -) 7'?AS). LCP i*i (tm.63-/7fAP) C% t.sAo v C RAaN C4CN j CALC ttvtl. T m$ gcw Cnwr= T suur Livet N 1(ls.&I7) y o M A f~I e, Y y .0% w$, vQ .v 0 YEQLW e.: i icei ,w .i. i (L5-63-177A ': .5 j m w..

t;... g 07,;1
(u1.er/1) jg;q : tp).(,3./7ygy) aio it, et, s
    • nio

8 s..L /....j IL nio i... g i...

t;;

ai i alo j nio l l l l i 1 I I f j l AUfo 81ECf RC ' i p4. i l NIGN lNf(RLOCK-l il A8C AL AN) l .= l (LI-63-/ 79). t l ~ i. I i ~ f g iLc/ Attachment No.- 24 Sheet M sf 2e-saa I CONTROL "" b " " #3 ^ t REv p_ PREPARER /DATE4/8/#-N f4 CHECKER /DATE Of/d/^N-fe' / / SHT-- S C/C b ,e ,,U,, - - - - + - - -

  • l l

COMMENTS AND NOTES i 1. Encompassed by the indication's value. 2. For specifics see the references and the Eagle 21 Technical Manual. 3. See transfer function sheet for value. 4. Components 2 through 7 are part of the Eagle 21 RPS System located. in the auxiliary instrument room at elevation 6858 and coordinate panel C-1. 5. The pressure is applied to the high pressure port of the transmitter'. \\ 6. The transmitter is calibrated separately from the other loop components. 7. Output is energized on decreasing signal for auto switchover and de-energized on decreasing signal to alarm. 8. Most stringent AV values based on small break LOCA conditions. 9. AV value for switchover is from Tech Specs and applies only to the Eagle 21 equipment (transmitter not included). Refer to reference 1 for calculated AV values, The AV values are 40.120, -3. %%[vyggm AC,.sey),-$3lyo 4 D I2( Artochment No--- % #fdenMiepQN-EEBg-T 0043 l

  • =e REV O PREPARER /DATE hM[/W M4 CHECKER /DATE C N 2W Ad' SHT_ 6 C/OFINAL 1

REV l PREPARER /DATE 3' N HECKER/DATE F/n 8-Di# SHT b C/OFINAL 1

OUALITY INFORMATION REQUEST / RELEASE (OIR) N E p-3.3 ~ / DIVISION OF NUCLEAR ENGINEERING Arvaconneur 1 ( OA (INTERNALUSEONLYl 0%4De 1 CDP 1 "'H T nnnino ann IVl, {. [Ebl A(e K OIR 5 P5 +490 o Fl R,o W.L-Etu O T PAGE'1 OF ' 2., TYPE OF DOCUMENT DATE / C REQUEST NEED DATE I PLANT AND UNIT Q RELEASE REF.OlR SGP%dio 02.6 R.o 544f* vain / 4 2. REFERENCED DOCUMENTS' AVAILASLE IN ONE OF THE RIMS SYSTEMS ATTACHMENT TO THIS OIR DOCUMENT IDENTIFYING NUM8ER DOCUMENT ATTACHMENT NUMBER = Ne bt (cht./ W A490-S Q SUBJECT PAfW C4NCE*JTV.ATicAJ bac g.& hse. "To ' No r, dt.4 M bMP 3 SYSTEMS AFFECTED UNID/SYSTEMID M T"1 i M TE cTI M $9 tTEM Cw Oft _ SGP5Qu9 ooze CD QUALITY INFORMATION REQUESTEDQt.EAM ( Sec. At%hd E Sn-repst' c/ <h fe< uduk e kw h bem 6A Tfect'$-I y f*d L cvee#w temse au MasG ctps, M R. S.. 5L g, h .'A4 4 4 4~ knr k-perbr4 A D o J m o z, n W 5 Attachment No. c'l5 Sheer I mf 3 LooD s/ldentifierSON-EEB-MF TT2A-nnl3 PREPAR - I REVIEWE D (RELEASES ONLY) aw z/s/e y&ea da APPROVED (OnANCH CHIEF / PROJECT EhGlhEER) / ( g' /f .?l'W TVA 10829 (ONE 646) g n 1/t/fo cc ( Attachnwnts): HIMS.61. MG M ET St.E 2-(. P. K WWE-BEWC' E., DS C - G., SGMP E t. ~'

M 1 < }" u............. ^ &I(LSQPSQMo O 5 I R.O .lf hWMW5 Westinghouse Energy Systems $3fg.4,= mmy.s - Electric Corporation s Mr. P. G. Trudel TVA-90-567' Project Engineer < February 6, 1990 Tennessee Valley Authority Sequoyah Nuclear Plants PO Box 2000 s _. Soddy Da.isy T.N 37379 i Terinessee Valley Authority Sequoyah Nuclear P .SecuoyahSpecificGral ants- 'i vities ~ l

Dear Mr. Trudel:

i Per Sequoyah requ'est (QIR SQPSQN90028 RD),' the following are the specific i gravities of the boron solution in the Sequoyah RWST, Cold Leg Accumulators (cl.A) and the Reactor Building (R8 sump. These values reflect the recent increase in boron concentrat on in the tanks (RWST: 2500-2700 ppm, CLA: 2400-2700 ppm). Please note that a specific gravity of 1.00 is found in most fluid Systems. calculations; the difference is assumed negligible, Comoonent zSeecific Gravity RWST 1.00375 CLA 1.00375 .j i RB Sump 1.00250 Should you have any questions or comments, or require additional information, please contact me. y Very truly yours. WESTINGHOUS'E ELECTRIC CORPORATION' .e g, y 4./ B. J. Garry, Manager TVA Sequoyah Project Customer Projects Department D. H. Lafever Attachment No d23 _ Shege_ 8,( Loop s/ identifier $QN-EEB-MS-TI28-00ls M(, PAUL s.inr4mf % X ITl7 i

c.., 9,r; ,p y -TENNESSEE VALLEY AUTHORITY SN 157B lookout Place i TVA-SQN-TS-89-26 10 CFR 50'90 U.S. Nuclear Regulatory Conunission ' ATTN: Documer.t Control Desk. ~" Washington, D40. 20555 centlemen ~rY'- ..G.r. Y..*

  • U.1'-i u.x.

In ~t6e~Mitter of -) Docket Nos. 50-327'. Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN)'- TECHNICAL SPECIFICATION (TS) CHAN BORON. INJECTION TANK DEACTIVATION L In accordance with 10 CFR 50.90, we a're enclosing a requested amendment to licenses DPR-77 and DPR-79 to change the TSsLof SQN Units 1 and 2. The proposed change reflects the effects of the boron injection tank deactivation.= e The proposed TS change is-identified in Enclosure 1. 3) the proposed TS change is provided in Enclosure 2. The justification for A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is- ,) provided in Enclosure 3.. This TS chtuge is being requested for implementation,during the Unit 1 Cycle 4 s.-. and Unit 2 Cycle 4 refueling outages. approved Unit 1 amendment between April 1, and MayTo support the schedule, we request 15, 1990'. Unit 2 amendment is expected to be required between October 15, and.The approved December 1, 1990. Please direct questions concerning this issue to K. S. Whitaker at (615) 843-7748. Very truly yours.. TENNESSEE VALLEY AUTHORITY \\. '. 1 _'{# ~ Manager, Nuclear Licensing U. and Regulatory' Affairs Sworn to and subscribed before me y this. day of 1989 .?ft g',.,;',.,p Notary Public My Commission Expires Enclosures Attachment No U Sheet L F.,f, _. cc: See page 2 L. cop #/identifiep0N-EEB HS -TI28-00l3 .I 4}}