ML20091H747

Forwards Responses to NRC 840425 Comments on Seismic Capability of Backup Thermocouple Reading & Display Sys. Responses Address Five Listed Concerns.Response Also Satisfies Concerns of Restart Certificaton Item 113

ML20091H747
Person / Time
Site:	Three Mile Island
Issue date:	05/31/1984
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 5211-84-2125, IEB-79-14, NUDOCS 8406050278
Download: ML20091H747 (17)

Text

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W-GPU Nuclear Corporation Nuclear  :::er,sxeo e

%ddletown Pennsylvania 17057-0191 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number:

May 31, 1984 5211-84-2125 Office of Nuclear Reactor Regulation Attn: John F. Stolz, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

Three Mlle Island Nuclear Station, Unit 1 (TMI-1)

Operating License NO. DPR-50 Docket No. 50-289 Seismic Capability of Backup Thermocouple Reading And Display System By letter dated April 25, 1984, GPUN was informed that the alternative method of reading incore thermocouple temperatures for the backup system is accept-able, provided the concerns resulting from the plant audit on January 4, 1984, are addressed adequately.

Enclosure 1 addresses all five (5) concerns and GPUN's responses. It is shown in the enclosure that (1) the tube carrying incore instrument channnel from the reactor vessel has adequate seismic capability; (2) the cables and electrical penetration assemblies have adequate seismic capability and are classified as safety grade; (3) the signal conditioning unit including its contents have adequate seismic capability; (4) the welded connections for the thermocouple lead cable sleeves have the required strength; and (5) procedures for converting hand held voltmeter readings into thermocouple temperatures do not require special test and verification.

This letter satisfies the concerns of restart certification item number 113.

Sincerely, H. D. kill Vice President - TMI-l HDH/MI Enclosure (1)

Attachments (4) cc: R. Conte J. Van Vliet GPU Nucler Corporation is a subsidiary of the General Public Utilities Corporation

/900 i 8406000278 840531 l f PDRADOCK0D00028]

Enclosure 1 Response to MC coments on TMI-l Seismic capability of backup thermocouple reading and display system.

Comment #1: Demonstrate that the tube carrying the incore instrument chan-nel from the reactor vessel has adequate seismic capability.

Response: The subject tubing was reviewed as part of the E C IE Bulletin 79-14 program and was analyzed for SSE Earthquake during original plant design. The analysis is filed under GAI analysis ME-101 and ME-102 by GPUN Letter No. LIL-307, dated October 23, 1981. The stress smmary pages on these analyses are attached (Attachment 1). This analysis was checked against the criteria specified in the TMI-1 FSAR Section 5.1 and was found to be in compliance with those criteria.

Comment #2: Demonstrate that the non-safety grade cables and electrical penetration assemblies (EPA) have adequate seismic capability.

Response: Extension wiring for the thermocouples constituting the backup system are routed through safety grade EPA's. The Resistance Temperature Device (RTD's) are also routed through the same safety grade EPA's. The penetrations utilized are #204E (instrument channel A), #205E (instrument channel B), #313E (instrument channel C) and #314E (instrument channel D). These penetrations were designed by G. E. and the test results are documented in " Qualification Test for F01 Electrical Penetration Assembly, General Electric Co., April 30, 1971".

Qualification of these electrical penetrations has been sub-mitted to the NRC in compliance with rule 10CFR50.49 (Environmental Qualification of Safety Related Electrical Equipmert). In addition, these documents are available at GPUN Headquarters in Parsippany, NJ.

The wires and connectors IJsed inside containment at these EPA's are safety grade and consist of cables (GPUN B/M E15AA), #16 wires and butt splice and heat shrink tubing connections.

Furthermore, the connectors at the incore detectors are potted.

Comment #3: Demonstrate that the signal conditioning unit including its contents has adequate seismic capability.

Response: The above mentioned seismic qualification is addressed in the Acton Environmental Testing Corporation technical report No.

140496 " Evaluation by Dynamic Analysis of Foxboro Base Assembly D0126WJ mounting for N2ES instrment Rack," (page #2)

' dated 8/16/78. The Foxboro manufacturer, does not provide serial numbers for instrument racks of this kind, however, GPUN l

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will place an equipment number on the instrument rack for identification. Furthermore, GPUN will obtain the design drawings from Foxboro and will check the subject instrument rack for its compliance with design criteria by cycle-6 outage.

The test report, along with other Foxboro documents including Certificate of Compliance is available at GPUN Headquarters in Parsippany, NJ. A copy of relevant pages are attached for your information (See Attachment 2).

The qualification of the cabinet and its contents as a free standing cantilever is conservative compared to a redundant cantilever which is its as-built condition. This is demon- -

stated by the analysis in Attadrnent 3.

Comment #4: Demonstrate that the welded connections for the thermocouple lead cable sleeves have the reqJired strength.

Response: The cable sleeve to the seal plate welds have been analyzed and added to the subject document (Calc. #C-1101-625-5320-001, rev.

1). This analysis indicates the welds are capable of with-standing the seismic event (SSE), without loss of structural integrity or safety function, and is attached. The two 1/2 in.

dianeter bars connecting the cable sleeve to the seal plate are detailed in the aforementioned calculations. A copy of the above referenced calculation is included as Attachment 4.

The floor response spectrum (FRS) used in the analysis has been incorporated into the reference calculation.

Due to the high flexibility of the cable analyzed and its close proximity to anchor points, the differential seismic anchor movemen'ts will have a negligible effect on the final analysis of the cables.

Comment #5: Demonstrate that proper calibration procedures are adopted for converting handheld voltmeter readings into thermocouple temperatures.

Response: The instrument loop that comprises the backup incore thermo-couple system consists of several compensating signal con-ditioning modules that provide a linear 0-10V DC signal to the digital meter that represents 100-23000F temperature. The voltmeter used in place of the digital meter that has com-

, parable accuracy would display the same 0-10V that normally drives the digital meter. The conversion from voltage to temperature for the voltmeter is the same as the conversion utilized by the digital meter.

i.e., Temp. (oF)= (220) (volts) + 100 Both primary and backup thermocouple systems are calibrated through the temperature range stated in NUREG 0737.

The portable voltmeter is periodically calibrated per Plant Procedures per Standards for Measuring and Test Equipment certified by NBS.

GPUN contends that the portable voltmeter is very reliable (as demonstrated at TMI-2). Since this physical phenomena will affect both primary and backup incore systems in the same manner, results will be consistent. Although, a test comparing the primary and backup readout is not required, GPUN will compare the computer readings with the results of the portable voltmeter at various power ranges during the Start-up and! Test Program per T.P. 846/1, Incare Tnermoccuple Operation Test.

The physical phenomena discussed in item 6 of the subject

~

letter results in an anomaly which is independent of.the display device. Hence, it seems that the non-linear thermocouple behavior at high temperature is a generic issue and should be dealt with separately.

In addition, item number 5* of the attachment to the subject letter refers to item (8) of II.F.2, NUREG 0737 and infers 99%

availability for the display channels following a large earth-quake. However, it is not credible to assume seismically ,

qualified thermocouples will fail during a large earthquake. <

Although, the discussion (item 5) was correct in its con-clusion that tapping into the primary system thermocouples to substitute a new thermocouple for a failed backup system thermocouple would be quite time consuming, the closest source to access any primary system thermocouple would not be at an electrical penetration as stated, but at the plant computer tennination cabinet tenninal. This is about seventy feet away from the PLF console to which the thermocouple would be routed.

• NOTE: Paragraph 5 states the backup system consists of 32 thermocouples...,

the correct number is 16 thermocouples.

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Report No. 14096 - -

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.. Technical Report d.. .

[ EVALUATION SY OYNAMIC ANALYSIS 0F FOXBORO BASE ASSEMBLY D0 126 WJ

! MOUNTING FOR N2ES INSTRUMENT RACK .

l, E N VlM O N M E N TAl.

• ACTON

( ,

c Q RPCM ATION Date August 16, 1978

}

Prepared Checked Approved By .

_M.Qndall,,, K. Martini M.L.Tolf Signed O J1 [///gh' )-) [,[gj[

. Date 8 /fe>~763 f ~/) .7f h ' lj rlly

'. en/8mr

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1, .

TABLE OF CONTENTS ,

SECTION PAGE

1.0 INTRODUCTION

1 ,

I

2.0 CONCLUSION

2 3.0 RESULTS . 3 4.0 METHOD 4

TABLES I I RACK ACCELERATIONS - WITHOUT BASE ASSEMBLi 5

!! RACK ACCELERATIONS - WITH BASE ASSEMBLY 6 h III PERCENT INCREASE IN ACCELERATIONS AT INSTRUMENT LOCATIONS 7 Y IV WEIGHT ADDITION

SUMMARY

8 .

FIGURES I COMPUTER MODEL PLOT OF RACK MODEL 9

!! COMPUTER MODEL PLOT OF RACK & BASE ASSEMBLY MODEL 10 APPENDICES I COMPUTER NODE & ELEMENT NUMBERING WORK SHEETS 1-3 g

!! BEAM PROPERTY CALCULATIONS 1-15 III COMFUTER PRINT OUT 6

Report No.

b mm.e COR*0s* A feet i

- ... . _=

y* .

f,..

~ 1.0 INTR 000CTION 3

This report documents the analysis performed to compare the dynamic performance of the N2ES Instrument Rack (fully loaded) as normally floor mounted to the dynamic perform-l ance when mounted on the 00126WJ Base Assembly, Rev D.

s s The purpose of the analysis was to ensure that under seismic loading, the rack mounted equipment would not i experience significantly higher excitation tbms when the Sase Assembly was used.

Detailed finite element models of the N2ES Rack and the f.

Base Assembly were developed. A ig respcase spectra was

> imposed on the floor mounted Rack and to the Base Assembly mounted Rack. -

J The resulting response accelerations were compared to evaluate'the performance of the Base Assembly.

a c .

q

.s 14096 Report No.

TeenNe IO$e gygg ~.

N N ADON

2.0 CONCL.U5!0N The acceleration levels realised at the instrument loca- ,

tions are not si nificantly increased by mounting the N2E5 Instrument ack (fully loaded) on the 00126WJ Base Assembly, Rev D. -

Tht.refore, equipe.ent qualified for service by test or analysis for a direct floor mounted application are quali-

'ffed for service when the Rack

• is mounted on the Base  :

Assembly. ,

,f . . . . . .

I 9

l'

')  !

t 14096

. Report No.

aCTON '

(

+

, , , 3.0 RESULTS .

Tables I and !! give the response modal accelerations at the instrument face mounting locations. The four groups of nodal locations represent the instrument mount loca-tions at each corner starting at the lower power supply

• These locations mounting are shown and working!.The in Figure upward to the top.

accelerations are given for

. each axis independently and then the square root sum of s squares value is calculated for each nodal location. The i floor mounted rack and the Base Assembly mounted rack are j similarly treated. Table !!! then offers the percentage l A . increase in the response modal acceleration for the Base '

• .. . Assembly Mounted Rack over the Floor Mounted Rack at each instrument mounting location. .

f At the lowest location, the percentage difference is high.

J. a maximum of 18.75 but the absolute numbers are low at i

( this level in the rack. At the second location, the maxi. '

mum difference is 8.411 and at the top where the absolute k acceleration. values are highest the maximum difference is .

3.295. Some of the percentage values shown on Tabis III from lower acceleration realized f .

are in thenegative Base Mounted arisinbck. This condition results from slightly different. dynamic mode shapes with the Base Assem-bij and we are concerned mainly with the maximum differ-

, ences. . .

ij 3 .

E l

Report No.

3 b'8 insme

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, , . . - - , , _ _ , . . . _ . . . , , , . , . , , . . , _ __ ,,,,,_,____._.mm__.,________,__,_,-m._.m.

4.0 NETH00 1

Finite element models of the N2ES rack and the Base Assembly wre developed.

The Rack model employs plate elements exclusively in the Base Weldment. 00126V8, which most accurately represents the stiffness and lead paths in this critical area. Forty-four quadrilateral plates and thirty-two triangular plates are used. The structure above the Base

. Weldsent: the Equipment Mounting Channels, the Centar

. Frame Assembly, Equipment. Supports and the Top Assemt,1y, are all modeled with beams. Appendix !! contains the Beam. property calculations: centroid, moments of inartia h ,

and area. Figure I is the computer plot of showing the nodal locations, beam connectivity and plate outline con-nectivi ty. The nodal numbering'for the instrument mounting locations reported in section J.0, Results, is given in Figure I. All other nodal and elecent numbering sketches are provided in Appendix 1.

. The non-structural items, side covers, doors, top assem'bly

. and instrument weights were distributed as shown. Table IV. Thg rack model is given six degree restraint at the -

. six 1/2 bolts. ,

The Base Assembly, model Figure !!, .is* comprised of fif ty-

• two triangular plates, twenty-four quadrilateral plates and is attached to the rack model by six comon nodes at the 1/2-inch bolt locations. The Base assembly is given six degree restraint alcng the lower weld edge.

3 L .

I 14096 e

Raport No. _

1. s Peo. =4 ogan%e,, ==

p .,,

Jmm

I Attachment 3 Respo..se to Comment #3 Seismic Qualification of Foxboro Rack GPUN has done a Preliminary Evaluation of the as installed N2E5 Foxboro rack, using dynamic test and analytical data supplied by the manufacturer.

This data is obtained from a standard dynamic analysis of the subject rack and dynamic test done for Foxboro by Acton Environmental Corporation. The results of the GPUN Evaluation indicated that the first five modal frequencies for the rack are:

Mode Frequency (Hz) 1 37.77 2 122.74 3 255.96 4 437.9 5 667.67 The above was based on a model for the rack as a uniform redundant Cantilever with a simple support at the free end, which GPUN considers conservative.

The associated G values based on the TMI-1-response curve in figure #1, for the as installed Foxboro rack are:

Mode Frequency Horizontal Acc., g (Hz) SSE (1/2% Damping) 1 37.77 .56 2- 122.739 .40 3 255.964 .40 4 437.9 .40 5 667.66 .40

~.

.The above results indicate that all modal frequencies are above 33Hz. It is well known that components with modal frequencies above 33Hz will respond as rigid bodies during an earthquake, i.e., the dynamic amplification is unity. Consequently, the component can be analyzed in a static manner and i transfer functions are such that the response of the component does not show amplification due to the dynamic input.

The qualification response spectrum used by Foxboro for the test of N2E5 racks (installed at TMI) is depicted in the attached figure. The TMI-l SSE response spectrum for the floor where the rack is installed is also shown in the same figure. It should be noted that the former envelopes the TMI-1 spectrum by at least a factor of 3. Furthermore, during testing, the horizontal and vertical components of the curves were assumed equal and applied simultaneously. In the TMI-l FSAR, the vertical acceleration is only 2/3 cf the horizontal acceleration.

It is GPUN's conclusion that the subject rack (N2E5) is seismically qualified, i.e. it should maintain its structural integrity and remain functional during and after a SSE Event.

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