ML20148J817

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Forwards Amend 19 to RESAR-414,documenting WE 3820 Mwt Nuc Steam Supply Sys.Amend Includes Revs to Sections 3A,7.6,9.3, 9.A & 10.1
ML20148J817
Person / Time
Site: 05000572
Issue date: 11/15/1978
From: Anderson T
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Varga S
Office of Nuclear Reactor Regulation
References
NS-TMA-1983, NUDOCS 7811160127
Download: ML20148J817 (12)
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Westinghouse Electric Corporation Power Systems-ewasystemsomsm Box 355 Pittstx;rgt1Pemsylvania 15230 November 15, 1978 NS-TMA-1983 DOCKET N0 'STN 50-572 Mr. Steven A..Varga, Chief Light Water Reactors Branch No. 4 Division'of Project Management Office ~of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr..:

Varga:

Enclosed are sixty'(60) copies' of Amendment 19 to RESAR-414, the Reference Safety Analysis Report, documenting the Westinghouse 3820 Mwt Nuclear Steam Supply System.

Amendment 19 includes revisions to Sections 3A (Regulatory Guide 1.124),

7.6, 9.3, 9A, and 10.1.

The revisions to Appendix 3A and Section 7.6 are provided in response to the remaining NRC Staff open items, and the revisions to Sections 9.3, 9A, and 10.1 are corrections to miscellaneous editing errors.

Very truly yours, O

T. M. Anderson, Manager Nuclear Safety Department O

/bek Enclosures O

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STATE OF PENNSYLVANIA COUNTY OF ALLEGHENY I

T. M. Anderson, being duly sworn, states that he is Manager, Nuclear Safety Department, Water Reactor Divisions of the Westinghouse Electric Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission this application and exhibits attached thereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

h T. M. Anderson Subscribed and sworn to me, a Not y Public in and for State and County above named, this M day of AML 1978.

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RESAR-414 AMENDMENT 19 INSTRUCTION SHEET The following instructional information and check list is being fur-p(]

nished to insert Amendment 19 into RESAR-414 Reference Safety Analysis Report.

Since in most cases the original RESAR-414 contains information printed f~s on both sides of a sheet of paper, a new sheet is furnished to replace

-(

sheets containing superseded material.

As a result, the front or back of a sheet may contain information that is merely reprinted rather than changed.

Discard the old sheets and insert the new sheets, as listed below.

Keep these instruction' sheets in the front of Volume I to serve as a record of changes.

Remove Insert (Front /Back)

( Front /Back)

---/- -

3A-82a/3A-82b 7.6-6c/---

7.6-6c/---

9.3-63/9.3-64 9.3-63/9.3-64 9A-13/9A-14 9A-13/9A-14 10.1-1/10.1-2 10.1-1/10.1-2 J

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.('v RESAR-414 A19-1 AMENDMENT 19 NOVEMBER, 1978

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RG Number Title (O

1.124 5.

Paragraph C.4 of the Regulatory Guide states that increases in Level A or B service limits does not apply to limits 'for bolted connections.

The Westing-house design.of component supports restricts the use

'V of bolting material to the following applications:

a.

Westinghouse design uses bolting predominantly in tension. Oversized holes are generally provided and a mechanism other than the bolts is provided to take any shear loads.

Shear or shear & tension interaction occur only in isolated locations; b.

Westinghouse bolts are limited to the following material A490, SA-354, SA-325, SA-540.

c.

The diameters used range between 1/2" and.3".

These limitations on bolt usage are standard in the Westinghouse supports. We will limit tensile loads in the bolts to 0.7 Su, but not to exceed in any_ case 0.9

.Sy.

The allowables are taken at temperature.

In those few cases where bolts are used in shear or ten-sion and shear, ASME Code Appendix XVII - 2460 Requirements will apply with an increase f actor that is defined in Regulatory Guide 1.124 or in Appendix F-1370, whichever is more restrictive.

This provides C

an adequate margin of safety for the Westinghouse design.

If future revisions to the bolting criteria in ASME Section III modify the Westinghouse criteria f.

listed above, we will review the criteria at the time.

R ESAR-414 3A-82a AMENDMENT 19 NOVEMBER,1978

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6.

Paragraph C.6(a) of the Regulatory Guide. appears con-

. fusing as to what stress limits may be increased for the emergency condition.

Westinghouse will interpret this paragraph as follows:

"The stress limits of XVII-2000 of Section III and Regulatory Position 3 increased according to the provisions of XVII-2110(a) of Section III and Regulatory Position 4, should not be exceeded for component supports designed by the linear elastic analysis method."

7.

The method described in Paragraph C.7(b) of the Regulatory Guide is overly conservative and incon-sistent with the stress limits presented in Appendix F.

Westinghouse will use the provisions of F-1370(d) to determine service level D allowable loads for sup-ports designed by the load rating method.

If future revisions to Appendix F modify this criteria, it will be reviewed further.

If the load rating method is used, further details of its implementation will be provided at that time.

O O

R ESAR-414 3A-82b AMENDMENT 19 NOVEMBER, 1978 i

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' Relief through the valve wili Jower the RCS pressure, clearing the

'd actuation signal.. Removal of Gis

!gnal causes the PORV to close.

The system returns to a ready status for reactuation if required by subsequent pressure increases.

7.6.5.2 Analysis of Interlock r

-The actuation. signals as shown in Figure 7.6-3 are processed in the elements of the Integrated Protection System (IPS).

For the criteria to which the IPS is designed, see subsection 7.1'.

The primary purpose of the Low Temperature RCS Overpressurization Preventive Interlock 'is automatic. transient mitigation.

This system does not perform a protec-tive function but rather provides automatic pressure control at low temperatures as a backup to the operator.

However, to assure a well-engineered system and improved operability, the Low Temperature RCS j

Overpressurization Preventive Interlock function will be included in the IPS.

By being implemented in the Integrated Protection System, the-Low A,

Temperature RCS Overpressurization Preventive Interlock will conform to IEEE-279-1971, with the exception of seismic.

19 O

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RESAR-414 7.6-6c

' AMENDMENT 19 NOVEMBER, 1978

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TABLE 9.3-2 m' t]

CHEMICAL VOLUME AND CONTROL SYSTEM PRINCIPAL COMPONENT DATA

SUMMARY

Positive Displacement Pump Number 1

Design pressure, psig 3200

- ys -

Design temperature, 'F 250

(/

Design flow, gpm 35 Design head, ft.

5800 Material Austenitic Stainless Steel Maximum operating pressure, psig (forReactorCoolantSystem hydrostestpurposes) 3125 n.

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Centrifugal Charging Pumps Number 2

Design pressure, psig 3100 Design temperature, F

250 Design flow, gpm 160 Design head, ft.

5800 19 Material Austenitic Stainless Steel O

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RESAR-414 9.3-63 AMENDMENT 19 NOVEMBER, 1978

TABLE 9,3-2(Cont.)

CHEMICAL VOLUMC AND CONTROL SYSTEM PRINCIPAL COMPONENT DATA

SUMMARY

Boric Acid Transfer Pump Number 2

-Design pressure, psig 150 Design temperature, F

250 g

Design flow, gpm 125 Design head, ft.

235 Material Austenitic Stainless Steel Baron Injection Makeup Pump Number 1

Design pressure, psig 150 Design temperature, F

250 Design Flow, gpm 35/100 Design head, ft.

250/200 Material Austenitic Stainless Steel Chiller Pumps Number 2

Design pressure, psig 150 Design temperature, F

200 Design flow, gpm 820 Design head, ft.

200 Material Carbon Steel RESAR-414 9.3-64 OCTOBE R,1976

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h diifor amb'ient temperature,betw'een 100;and :120 F,land for ' containment.

s pressure;betNeen"10 and 15' psia..

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(bil.ity'6ff Westinghouse (fpther heat losses are' estimated;for the-g onvenienceo{the@urchaser# bActualoheat losses must be deter-W

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-Outside Containinent Ventilatio'n S stem Interface Requirements'-

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Heat Loadsffrom W Supplied Electrical and/I?and C. Equipment located 1

outside containmentL are found in' Table 9A-l'.

The heat loads con-191 U

- tained :in the;above < Table 'ars: typical?" envelope" requirements which.must' be'usedlto. detsrmine heat removalirequirements.

2

-lieat loads' from the motors located outside the containment, are determined by assuming the motors are 90% efficient, and>using.the r%

load for thdt motor.given in Table 8.161.

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.9A AMENDMENT-9.

NOVEMBER, 197.8

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STANDARD FOUR LOOP PLANT TYPE'4"L g'

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? HEAT DISSISPATION FOR THE MAJOR ELECTRICAL AND I&C-EQUIPMENT-e b

w sed.1PkglTItem No.)

Eouioment, iArrangement

-Heat Dissipation ~ _ _

2 u 9 2[J T. -' Pressurizer Heat Controller

13 Uni t ~

-5050 watts?

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-3 [

' Reactor Trip -Switchgear 2 Uriit. Assembly

-500 watts l total-E

'.3g Rod -Drives' MG Set Switchgear

~1-2.UnitAssembif-

-1000 wattsitotals

-3 E Rod Drive MG Sets.

.2 Units (10,000 watts total 4

Instrument Power Supply Inverters'

'4 Units-7(5 KVA:

112000 watts? total' g

16

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Protection System Racks 1.-19 Unit. Assembly.

T5150 watt'sntotal

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6 Control. Board :Demultipiexer Rack 1-Unit -

500 watts :' '

~7.

Gross Failed Fuel Detector System 1 Unit-420 watts 8

RC-Loop Stop Valve Protection Racks

2 Units 800 watts total' 8

' Auxiliary Relay Racks IUnits

~ 1600 watts-total -

10 Process I&C Racks 8 Units-6000 wa~tts-totali 11 Waste Processing / Boron-Recycle-Panel-1-3 Unit Assembly.

'750wattstotall 11 Steam Generator Blowdown Panel 1 Unit-

~.300 watts:

.[

- 12' Nuclear Instrumentation Racks-1 4 Units.AssemblyL 994 watts totali

~k 131 Rod Control Equipment (full' and part length) 1-BiUnits: Assembly -

19500 watts:

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.15 Rod Position indication Containment Cabinets

.2~ Units.

11400 watts total-

_16

. Radiation' Monitoring - Racks '

1-2 Units:Assemblyf

.1790 watts total?

17 Movable Detector Flux Mapping System Racks

'l-4 Unit Assembly; J1220' watts'- total.:

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INTERFACE->INFORMATION STEAM ~ AND POWER: CONVERSION' SYSTEM-

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13,034ix[ld.HBTV/hrJ Jhermal41nputi f(.l_00%jpower)

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lPressuse4(100%{ power)?

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ms TemperatureT(),00%. power)H, 556 3 F'

. Instrumentation Refer {to: Chapter;7, A

Appendix,7A Electrical: Requirements:

Refer =toChapter8, Appendix-8A'

]

Il9 Total.Feedwater Flow or Ll7.35 x. -10 itdhr' Steam 6

Steam Flow '

1 Steam Line1St'op, Valves 5' seconds ('afterLreceiving' (f ast-acting)'. Closure' Time actuation signal)

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+ 60 psi.

  • O Pressure Measurement-

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Accuracy

  • of Feedwater-

. +.'2 F

Temperature Measurement For breaks Jdownstream of' the isolation valves, closure;of all. valves M ul.d. completely; terminate the blowdown..

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Fast acting isolation valvesoare"provided in Leach steam linethat will fully' close withinLS seconds af ter; receipt 'oNan isolation signal.

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' Accuracy # inclul des}ch'an'nell calibration :and-drif t from sensor to '

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11 9.1.2 L AMENDMENT '.19 -

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