ML20234C109

Issue B to Effect of Firewater Cooldown Using EES Bundle on Steam Generator Structural Integrity

ML20234C109
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/25/1987
From:	Almajan I, Antoinette Lewis, Ryder R GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20234C111	List: ML20234C109 ML20245C018
References
909204-ERR, TAC-63576, NUDOCS 8707060335
Download: ML20234C109 (5)

Text

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ISSUE

SUMMARY

EFFECT OF FIREWATER C00LDOWN USING EES O R&D APPROVAL LEVEL 2

O aS BUNDLE ON STEAM GENERATOR STRUCTURAL INTEGRITYg g

DISCIPLINE SYSTEM 000. TYPE PROJECT l 0OCUMENT NO.

ISSUE N0/LTR.

B M

22 CFL 1900 l 909204 QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLAS$lFICATION QAL I FSV-1 FSV-1 N/A APPROVAL REP ^

ISSUE DATE DES Al T10N/

BY FUNDING APPLICABLE ENGINEERING QA CWBS NO.

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CONTINUE ON GA FORM 14851 NEXT INDENTURED DOCUMENTS N6082 8707060335 870626 PDR ADOCK 05000267 F

PDR REV SH REV SH 29 30 31 32 33 34 35 3G 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 63 54 55 56 REV SH I

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909204/B LIST T mu;nVE PAGES PAGE NUMBER PAGE REV PAGE NUMBER PAGE REV COUNT COUNT Issue Sumary 1

B Eff. Page List 1

B 2 through 26 25 A

27 and 28 2

B-29 through 35 7

A-36 1

B-Al through A6

-6 A'

B1 through B20 20 A

C1 through C22 22 A

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d 909204/B TABLE 5-2 SUPERHEATER II TUBE STRESSES Stress Direction Loading Stress GADR-9 Section. Hoop Longitudinal Condition Calculation (a) 6.3.4 Page No.

(psi)

(psi)

Flow ind, vib.

Insignificant 0

0 Deadweight Insignificant 19 0

0 Seismic Hoop 20 0

Seismic Longitudinal 20 2,156 Pressure hoop 3,291(-613)/1,822 28 1,107 Pressure long.

389(-613/1,822 28 131 Bearhug 5,702(175)/136 39 0

7,337(b)

Wall thermal 42,916(135)/210 32 27,589 27,589(c) ress Direction Allowable Stress Stress Combinations Hoop Long.

(psi)(d)

Primary membrane stress 1,107 131 17,920 (pressure only)

Primary membrane plus primary 1,107 2,287 26,880 bending' stress (pressure and SSE)

Total stress, Inc. secondary 28,694 37,213 (e) bending and thermal (pressure, 47,800 SSE, Bearhug and wall thermal gradient)

(a)This calculation converted fall power operation stresses (first number) to Firewater Cooldowa stresses using multipliers /

dividers obtained from Table 5-1.

The full power operation stresses were obtained from GADR-9, Ref. 7, Section 6.3.4, page numbers as indicated.

(b)"Bearhug" stresses are restrained thermal stresses caused by the temperature difference between the helical tubes and their support plates. The tubes want to be at a different helical radius than the location of the holes in the support plates.

This produces radial loads between the tubes and the plates, as the tubes are loaded in bending they are subjected to significant stresses for relatively small radial loads. As these stresses are caused by thermal strains and would self relieve, they are classified as Secondary stresses, this is the same as in the FSV Steam Generator Design Report GADR-9,

)

Page 27 l

l

909204/B i

l TA3LE 5-2 (Continued)

I Ref. 7.

Because these Bearhug stresses are classified as secondary,4

]

they are not required to be evaluated for a Faulted category event, even though this was done in this table.

(c) Tube wall thermal gradient stress is a secondary stress caused by temperature difference through the tube wall from the heat flux.

Because the thermal gradient stresses are classified as secondary, they are not required to be evaluated for a Faulted category event, even though this was done in this table.

(d) Allowable Stress for faulted conditions:

Primary Membrane Allowable Stress is S.

I y

Primary Membrane plus Primary Bending Allowable Stress is 1.5 S.y The appropriate ASME Section III code, 1968 Edition, (this is the first edition of the ASME B&PV Code where limits are provided for Faulted conditions) waives the evaluation of the Primary plus Second-ary stresses for Faulted conditions. This is subsequently clarified with a definite statement " EVALUATION NOT REQUIRED" in the Summer 1969 Addenda, Fig. N-414.

Material properties of SB-163 Grade 2, (Saniero 31) were taken from: ASME B&PV Section III Code Case 1342-1.

Sy = 17,920 psi @ 385'F Sm = 15,930 psi @ 385'F The peak tube temperature is calculated from temperature data presented in' fable A-1.

The 385'F peak surface temperature is the mean tube temperature plus slightly more than half of the tube wall thermal gradient.

The tube wall thermal gradient is not exactly linear through the tube wall, therefore more than half the thermal gradient was used.

The values on Table A-1, are conservatively based on a Firewater Cooldown from 105% power.

(*)To determine the relative magnitude of the total stresses in comparison to an Upset allowable we used the allowable stress of the ASME B&PV Section III, of three times S '

m Primary Membrane plus Primary Bending plus all Secondary (Total stress) Allowable Stress is therefore 3S -

m This evaluation showed that the total stress is less than the allowable stress for an Upset condition, emphasizing the fact that there is no cause for concern.

Page 28

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CALCULATION REVIEW REPORT 4

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go DISCIPLINE SYSTEM D D C. T YPE PROJECT DOCUMENT NO.

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INDEPENDENT REVIEWER:

NAME h T A*^ N ORGANIZATION McNR h N% 5+ N W 6-23-87 REVIEWER SELECTION APPROVAL: BR MGR 4^

DATE

\\

REVIEW METHOD:

YES NO ERROR DETECTED

/

ARITHMETIC CHECK LOGIC CHECK ALTERNATE METHOD USED SPOT CHECK PERFORMED I

COMPUTER PROGRAM USED V

REMARKS: (ATTACH LIST OF DOCUMENTS USED IN REVIEW) l?;y/stscp CM4NCc.5 Yo

$wi.5 6 9092c>sbf 909

• A CALCULATIONS FOUND TO BE VALID AND CONCLUSIONS TO BE CORRECT:

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INDEPENDENT REVIEWER DATE SIGfijTUREI J

D mts 76

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