ML20203F940

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Forwards Responses to Sqrt Audit Questions Re Allowable Faulted Stress Limits for Auxiliary Feedwater Pump,Per SER Open Item 1, Equipment Qualification
ML20203F940
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/25/1986
From: Bailey J
GEORGIA POWER CO.
To: Youngblood B
Office of Nuclear Reactor Regulation
References
GN-1014, NUDOCS 8607310210
Download: ML20203F940 (5)


Text

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Georgia Pbwer Company Not Offica Box 282 Waynesbora Georgia 30830 Telephone 404 554-9961 404 724 8114 Southem Company Services, Inc.

Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Project July 25, 1986 Directer of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood Log:

GN-1014 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.

20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM 1: EQUIPMENT QUALIFICATION

Dear Mr. Denton:

As requested by your staff, we are providing the enclosed responses to SQRT audit questions concerning allowable faulted stress limits for the auxiliary feedwater pump.

If your staff requires additional information, please do not hesitate to contact me.

Sincerely, J. A. Bailey Project Licensing Manager JAB /sm Enclosure xc: -R.

E. Conway B. Jones, Esquire R. A. Thomas G. Bockhold, Jr.

J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey M. A. Miller (3)

L. T. Gucwa Jag Singh Clarke Kido Vogtle Project File 0616V 8607310210 860725 O

PDR ADOCK 05000424 E

PDR 3 \\

2 i

Enclosure NRC Question 1 What is the basis for the faulted allowable stress limits identified in Design Criterion (DC-1017) Table 197 GPC Response S is the ASME allowable stress from ASME III Division 1 Appendices.

From Appendix II,Section III - 3210 the "Procelure for Establishing Stress," the deviation for ferritic steels is:

At any temperature listed below the creep range, the maximum allowable stress value for ferritic steels is the lowest of the following:

(1) One-fourth of the specified minimum tensile strength at room temperature (2) One-fourth of the tensile strength at temperature (3) Two-thirds of the specified minimum yield strength at room temperature (4) Two-thirds of the yield strength at temperature.

All the BOP active pumps listed in FSAR Table 3.9.B.3-8, Amendment 23 have been reviewed and the actual stress is less than the yield stress. The refore,

the faulted loading condition will not impair pump operability.

NRC Question 2 Why aren't seismic loads considered for the casing flange, casing, stuffing box bolt and main flange bolt in the pump qualification report (Bechtel Log X4AF03-3-223-3, page 10, Table 2.2)?

GPC Response 1

In Section 2.1 (attached) of the seismic qualification report the vendor identifies the critical locations and loading conditior.a to be considered.

4 The vendor also states " Deadweight and seismic effects are very low relative to pressure effects, and hence are not included" for these components.

NRC Question 3 Why weren't the SSE loads presented on the SQRT form (BOP-3, page 9, lib) for the pump mounting bolts and foundation bolts?

i l

GPC Response l

The vendor examined normal, upset and faulted load conditions. The condition considering OBE was presented in the SQRT form because it was the most critical. The results for the loading conditions considering SSE are as follows:

Pump Mounting Bolts Faulted Nozzle Loads + SSE + Shaf t Torque + Static Weight = 26,831 psi Allowable Stress = 84,000 psi Source of Allowable =.6Sy x 1.33

Foundation Bolts Faulted Nozzle Loads + SSE + Shaft Torque + Static Weight = 21,947 nei Allowable stress = 84,000 psi Source of Allowable =.6Sy x 1.33 The basis for deciding which case was critical was the ratio of actual stress to allowable stress as follows:

Pump Mounting Bolts For upset condition 22,354 =.35 63,000 For faulted condition 26,831 =.32 84,000 Foundation Bolts For upset condition 17,060 =.27 63,000 For faulted condition 21,947 =.26 84,000 0616V 3

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SUMMARY

OFSESULTS 2.1 Identification of Critical Locations The stresses or operability criteria were evaluated at the following critical locations.

In cases where loads or sections vary in a particular component, the worst case location is evalu-ated.

Locations have been selected on the basis of those that are most affected by the dynamic acceleration loads, and/or l

those affected primarily by pressure or other static loads, t

t Load Combination Critical Locstion A.

Stress Evaluation

(

1.

Casing wall sections.

(1)

P D

2.

Casing main flange bolting (1)

P l

D 3.

Suction nozzle flange.

(1)

PD+N e

4 Discharge nozzle flange. (1)

PD+N 5.

Stuffing box bolts.

(1)

P D f

6.

PumpMountingboitsar[dpins.

N+S+D+T

?.

Pump casing foot N+5+0+T O

8.

Pump pedestal welds.

N+$+0+T

!f.

Foundation bolts N+$+0+T 8.

Pump Operability _ Analysis 10.

Pump shaft stress S+H+T w

,----+,--g w,,,,-,--

om-eew.

m----,p-----oewgey---

- -g-e-,mg<

c--w- - - -

w-.-,%

-e----

ww-m e+.

y--,-

w-e aw-*-w-y----

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a i:: :

no, ucm c ar.o

r. o 3 i

[8 PQ10- riMnroa. ;'73-3 009 1

(

11.

Bearing loads, life.

S+H 12.

Critical speed.

13.

Coupling misalignment / loads.

(5)

N+$+D+T+H l.oad Nomenclature Po = desi[In pressure N = nozz e loads S = static weight 7

0 = dynamic (seismic) loads (2)

T = shaft torque H = hydraulic operating loads internal to the punp (thrust)

I Notes (1)

Deadweight and seismic effects are very low relative to I

pressure effects, and hence are not included.

(2) The three orthogonal component seismic acceleration motions are asstned to act simultaneously, and combined total re-sponses are calculated using the SRSS fomula applied to unidirectional responses.

l (3) Where multiple loads are applicable concu'rrently, stress effects are summed linearly.

(4) Nozzle loads specified as maximum FR and MR values for each nozzle are applied in the direction representing the " worst case" load condition.

P (5)

Deflections and torques are evaluated against coupling manu-facturer's published criteria.

l (6)

The analysis demonstrate-thct-the tm feed-w:4eo-punp..wi.11..

operate nomally when subjected to the maximum seismic accel-erations and mar.imum faulted condition nozzle loads

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,--e--,.

,,a

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