Text

Rosemount Transmitters Model 1152DP & AP (PT-LM-101A,PT-LM- 101B)
	ML18139C258
Person / Time
Site:	Surry
Issue date:	04/30/1982
From:	; NUS CORP.
To:	;
Shared Package
ML17054D434	List: ML17054D432; ML18130A387; ML18130A389; ML18139C255; ML18139C256; ML18139C257; ML18139C258; ML18139C260; ML18139C261;
References
	NO8.1-VOL-289, QDR-5437-201-01, QDR-5437-201-1, NUDOCS 8303110302
	Download: ML18139C258 (80)
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{{#Wiki_filter:e QDR-5437-201-01 QUALIFICATION REVIEW PACKAGE ROSEMOUNT TRANSMITTERS MODEL NO. 1152DP&AP (PT-LM-101A,PT-LM-101B) SURRY UNIT 1

810 CLOPPER ROAD ,;,A~AITHERSBURG, MARYLAND 20878. ~01 J 258-6000 Mr. A. L. Parrish, III Manager, Multiple Power Projects Virginia Electric & Power Co. P.O. Box 564 Richmond, VA 23204 Attention: J.E. Wroniewicz N08. l-VOl-289 April 30, 1982 File 4.1

Subject:

Surry Unit 1 Transmittal of Qualification Review Package No. QDR-5437-201-01 for TMI Item, Rosemount Transmitters

Dear Mr. Parrish:

Transmitted herewith is one (1) copy of the qualification document review package QDR-5437-201-01 for Rosemount Trans-mitters PT-LM-101A & PT-LM-lOlB for your review and acceptance. In this package because sufficient justification for aging is not provided we reconunend includinq these transmitters in an Ongoing Aging Surveillance Program-~--- Upon your review and acceptance of this, a final revised signed off copy of the complete package will be transmitted for your permanent files. cc: N. :Garg-,* w/e_nc*. : R.

Bell; w/enc.

B. J. Reckman, w/o enc. J. L. Renehan, w/o enc.

s. B. Gerges, w/o enc.

Very truly yours, R. C. Wilson Project Manager 0 A Halliburton Company

e TABLE OF CONTENTS Section 1 2 3 4 Qualification Document Review Checklist List of Reference Documents Qualification Report Review.Summary Attachment #1 VEPCO P.O. No. 39306 dated June 17, 1980 Rosemount Report No. 117415, Rev. B Dated September 24, 1975 (Ref. No. 6) Conclusion Section& Reference Section ILLUSTRATIONS (Section 1) Figure 1 2 3 3A Table 1 2 Block Diagram for Qualification and Typ~ Test Procedure for Pressure Transmitter, Rosemount Model No. 1152 AP, DP, GP Rosemount Report No. 117415, Rev. B dated Sept. 24, 1975 (Ref. Report No. 6) Class IE Equipment Qualification Type Test Program per IEEE-323 Standard 1974 LOCA/HELB Temperature Transient LOCA/HELB Pressure Transient .TABLES (Section 1) Special Environmental Requirements Special Requirements Worksheet QDR-5437-201-01 1 5 8 10 2a 3a 4a 14 15 16 17 6 7 18 NUS CORPORATION

ROSEMOUNT TRANSMITTERS MODEL NO. 1152DP&AP (PT-LM-101A,PT-LM-101B) Surry Unit 1 QDR-5437-201-01 SECTION #1 COMPLETE CHECKLIST,

FIGURES,

& WORKSHEETS NUS CORPORATION

r1. -:-** *.... -........ I...,. *

a....... -

Rev Date By App f'... Porm QDR-3/01/80 Client ID: Virainia Electric & Power Company Sheet 1 QDR-5437 -201-01 Plant: 5ur:ry Unit 1 Qualification I>ocument Review Checklist Review for: DOR Guidelines[] WREG-0588 0g

1.

Name of the Reviewer: Manhar Patel Date: 2-17-82

2.

Equipment Covered: Rosemount Transmitters Model No.1152DP&AP

3.

Equipment Tag No(s).: PT-LM-lOlA, PT-LM-lOlB

4.

ooes the report address all o( the Class IE equipment in this catiegory listed in the master IE equi~nt list?

s.

Is the report traceable to the plant equipment?

6.

Does the report specify an acceptance criteria for ~ipment performance?

7 *.

was a base line test done. to estab-lish the reference basis?

8.

Do the maximum and/or accident temperature and pressure used in the* test envelope those for the plant? (Table l)

9.

Are thermal aging parameters chosen and used in the test~_supported by adequate doc:umentation or references? Note: Aging times less than 100 hrs not acceptable.

10.

Is radiation aging addressed? (Test or analysis. If analysis, is ad~ate documentation provided?)

ll.

r:>oes the radiation dose profile, i.e., integrated dose for normal operations and accident for the plant, fall with-in the envelope ~sed in qualifications? IIO'l'E: Asterisk* indicates items applicable to %)OR iUidelines~ YES NO X X X X X X X X NA Page Ref. P.O. No. 39306, Ref. Report #6, Sect. 6 & Work-sheet #10.3-1&2 Attachment #1 Ref. Re~ort #6, Page 2, ec.4.1, & Attachment #1 Ref. Report #6, Page 3,Sec.5.2 Attach. #1,Fig. 3 &-3A & Sec. 5.5 of Reference #6 Attach. #1 & Sec. 5.2 of Ref. Repor

6 Ref. Report #6' Page 5, Sec. 5.3 Attach. #1 and worksheet nos.

10.3.1 and 10.3.2 NUS =~~~TION t

Rev Oate By ApP Porm Q:OR-3/01/80 Client ID: Virqinia Electric & Power Company Sheet 2 QOR-5437-201-0l Plant: Surry Unit 1

12a.

Does the total integrated dose include Beta radiation?

b.

If not is there an analysis for this?

c.

Is it require~?

13.

was humidity aging considered? (Not required for cables.)

14.

Was vibration (ambient) aging addressed'?

lS.

was mechanical and/or electrical cycling addressed?

16.

Do the DBE test parameters meet or exceed those given in the spec-ification? Make a copy of the temperature envelope used in the test and superimpose it on the required environmental envelope. Assure that deviations between the two are justified in the report.

17.

Does DBE temperature envelope used in the test contain the double peak required by IEEE-323-74?

18.

19.

20.

Does the DBE qualification include chemical spray? {Test or analysis) Ooes the spray concentration used in tests meet or exceed those to be used for the plant? - was the spray testing done while under the extremes of pressure and temperature?

21.

A.re the margins used in DBE test para.meters defin~?

22.

Do the margins conform to those required by IZEE-323-197, and any applicable daughter standard for this equipment?

!Yes 5o RA Page Ref.

X X X X X X Transmitters are located outside the containment Ref. Report #6, Sec.5.5&Attach.#1 X Attach. #1, Fig. 3 & 3A and Sec. 5.5 X X X X X X of Reference Report '

6 Transmitte~s are located outside the containment & work sheet #10.3-1 &

10.3-2 Attachment #1, Sec 5.3 thru 5.5 of Ref. Report #6 NUS COJ:IPO~TION ~.. ~-.... - ~

aev Oate By APP e e Form QDR-3/*11/80 Client II>: Virqinia Electric & Power Company Plant: Surry Unit 1

23.

Did the specification provide the required operating time for the equipment in the DBE or other specified harsh environment?

24.

Does the test operating time under the harsh environment equal or exceed that in the equipment specification? Assure that ade-quate justification is provided for deviation.

25.

Does the specification call out the submergence requirements if any?

26.

Does the test program include submer-gence tests? If not assume that the justification is provided.

27.

Is the accuracy demonstrated during testing equal to or better than that specified?

28.

Are the mounting and installation interfaces used in the test config-uration similar to those used in the plant?

29.

Was the test measuring equipment (TME calibration addressed in the report?

30.

Does it specify that the calibration of the 'l'ME is traceab.l.e to NBS or other secondary standards?

31.

was the seismic testing/analysis done on aged component or equipment?

32.

Did the seismic testing/analysis address effects of age?

33.

I)oes the seismic test response and/ or criteria ased envelope the re-quired response speetra for the plant? Yes X X X X ) X X X X No X ... ~- ** Sheet 3 QDR-5437 -201-01 NA Page Ref. Worksheets 10.3.1 and 10.3.2 Attachment #1 X Worksheet No. 10.3.1 & 10.3.2 X Ref. Report #6, Sec. 5 & Attach.

1 Attachment #1 Appendix 1 ' Page 28 of Ref. Report
6 and Attachment
1 1-Ref. Report #6 Page 6' Sec. 5.4

1.

NUS COF=ll='O~ 'ilON

llev Date By App Perm QD:R-3/01/80 Client ID: Virqinia Electric & Power Company Plant: Surry Unit 1

34.

Was the same test specimen subject to the entire test sequence? (In-cluding aging tests? - NOREG 0588)

35.

Compare the block diagram for this report against the one you have pre-pared from your understanding of what test and procedures are required as per IEEE-323-1974 and any applicable daughter standard for thi~ equipment. Do you believe the report meets the intent of these standar~s?

36.

Is the qualified life (QL) explicitly stated? Fill this information in the master IE equipment list.

37.

Do the aging tests/analysis results support the Qt conclusion and is adequate documentation provided to support this conclusion?

38.

Review the test results on a relative comparison basis (i.e., performance parameters of the base line tests versus those during the various tests) Was there any major disc:epancy?

39.

If so, was it satisfactorily explained in the report?

40.

Are maintenance requ~ements and com-ponent replacement intervals specified

41.

Have you compared maintenance and re-placement requirements to those in the standard instruction/maintenance aanua!s and identified any special items in Table 2? Yes X X X X X ? No X X

Sheet, QOR - 5 4 3 7-2 0 1-0 1 NA Page Ref.

Ref. Report #6, Page 3, Sec. 5.1 & 5.5.2 Figures 1 and 2 Sec. 5.3.4 of Ref. Report #6 and Attach. #1 Sec. 5.2 of Ref. Report #6 & Attachment #1 Attachment #1 X NUS COF=i?Ql=\\A'T'ION I, T "'I' Ill 1 '*.'

* "*, "* *,*, -c-;-,-,.**i- "'*"I~ *,-:.- ~~
- ,-, "l,.. 1 1

... -. 'j, 'I lL 'I"., *

.... *.*, '°\\ '"* *,, -. "* -.,

~.' ' '-,9-y---;.

Porm QDR-3/01/80 Client ID: Virginia Electric & Power Company Plant: Surry Unit 1 Rev Date By App Sheet 5 QDR-5437-201-01 List all the reference documents used for this review by their titles and identification no., with their revision level and date.

1)

IEEE Std. 323-1974 - IEEE Standard for Qualified Class IE Equipment for Nuclear Power Generation Stations.

2)

NUREG-0588 - Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment.

3)

IE Bulletin 79-0lB - TMI Review Response Submittal, dated Feb. 1, 1981 Wqrksheet Nos. 10.3-1 & 10.3-2. 4_) Environmental Zone Description, dated Aug. 24, 1982 VEPCO Surry Power Station Units 1 & 2.

5)

VEPCO Purchase Order No. 39306 dated May 17, 1980 for Differential Capacitance Absolute Pressure Transmitters.

6)

(Reference Report No. 6) Qualification Tests for Rose-mount Pressure Transmitters Model 1152. RMT Report No. 117415, Rev. B,dated Oct. 26, 1976. ... *. -., \\'......... J; ** ~

[ e I ' ' I I I i TABLE l Rev. Dated Sheet_6_ ODR-5437-201-01 Surry Unit 1 Special Environmental Requirements ROSEMOUNT TRANSMITTERS MODEL NO. 1152 AP PA~..ETER SPECIFIED OPERATING 120 Days TIME Accdt: 205°F Max. TEMPERATURE Norrnal:100°F Accdt: 15.2 psia PRESSURE Accdt: 100% RELATIVE HUMIDITY Normal: NC* 40 Yrs: 3 4.87xl0 RADIATION Accdt: 5 9.3xl0 SUBMERGENCE NR NR = Not Required NC= Not Calculated QUALIFIED ')- 120 Days 350°F Max. 84.7 psia Max. 100% S.x10 6 NR DOCUMENT REFERENCE SPECIFIED QUALIFIED Ref. Report #6, W Ref. Ltr. Sec. 5.5.2 and No. NN-SS-Attach. #1, 79287 Question 8 of this QDR S&W Cale. Ref. Report 12846.44-PE-

6, Section 050-0 5.5.2 SAME SAME SAME & Attach.

SAME

1, Quest. 13 of this QDR.

S&W Cale. Ref. Report 12846.44-UR

6, Section (B) -043-0 5.3 I

Env. Zone Description Table AB-13A NR ( 0) I I l .I

Porm QOR-3/01/80 Client ID: Virginia Electric & Power Company Plant: Surry Unit 1 Table 2 Special Requirements

l.

Maintenance Requirements/Intervals Rev Date By App Sheet 7 QDR -5437-201-01

1)

Consult manufacturer's recommendations as sated in his maintenance manual.

2)

These transmitters are recommended for inclusion in an on going aging surve~llance program.

2.

Replacement Requirements/Intervals

1)

As we calculated the 18 month life of these transmitters we recommend to inspect and conduct usual tests during each refueling outage for any required replacement.

3.

Storage Requireme~ts* N/A

4.

Installation Requirements* None special

Applies to spare parts and replacement only for operating plants.

NUS CCl=il='Ol=\\A'ilON .,... II...... ~..... _. 4.. _ .. ~..... ----..

e Rev Oate By App Porm QDR-3/01/80 Sheet 8 Client IO: Virainia Electric & Power Company Plant: Surry -Unit 1 QOR-5437 -201-01 QUALIFICATION REPORT REVI:?W'StJMMARY

l.

Equipment Qualification Reviewed: Qualification Tests Report

117415, Rev. B for Rosemount Pressure Transmitter Model 1152. dated oct, 26. 1976.

2.

Status of Qualification Records: X X Records identified (Full/Pa~tia!), obtained (Full/PaF~~~~), and review (Full/~~~~i-a--a.) summarized onQDR-3/01-SOfcrms. The following additional documents have been requested:

1.

2.

3.

4.

5.

6.

Following areas/documents require additional review: Vendors New Aging

1.

'.Ie~t E~;r:awete;r:s

2.

3.

4.

s.

6.

Other comments on status of qualification records:

3.

Status of Qualification ~ X Equipment qualification meets the guidance of NIJREG-0588. For additional comments and recommendations, see section 5. Additional evaluation is needed to justify qualifica-tion status. Oetails of additional evaluation needs attached. Qualification tests consistent with the recommendations of '!ftraEG-0588 for Category l equipment should be per-formed on the equipment. NUS CCF=il='Qi=tA.TlCN ~ ** ~

- ~*.-.... --

.., *~* -~ ~.... -

e Rev Oate By ADP Por111 QDR-3/01/80 Sheet 9 Client ID: Virqinia Electric, Power Comp~y QDR -5 4 3 r-2 0 1-0 1 Plant: Surry Unit 1 Equipment should be rel.ocated to an area where it will not be expoaed to a harsh environment. Other recommendations:

5.

Additional Com.11ents/Recommt!.nd-ations

1) Rosemount tested model no. 1152 transmitters in 1975 per IEEE-323, 1971 and now is committed to retest them to qualify per IEEE-323-1974.

Initially Rosemount tested these transmitters for two cycles (100°-0°-200°-100°F) of eight hours each which

is not enough to establish a qualified life of 40 yrs.

We are unable to justify more than 18 months life even after taking the credit from extended steam pressure test (See Question 9 in Attachment #1). Hence we recommend including these transmitters in an ongoing aging surveillance program.

2) For additional comments see attachment no. 1.

Environmental qualification documents for the equipment identi-fied herein have been reviewed and determined to be adequate and auditable. Date: Prepared by: -:.M ** ~N_. __ P_a~t~e~l ____ t?T}~_)2~iz'-.*~*--- o/,\\ <? certified by: __ R~--J __ ._B_e_1_1 __ ---4~~,~L-**~'~2-*~ Date: Date:

1) ate:

4/7/82 4/28/82 NUS CO~l='Ol=lATION

e ATTACHMENT #1 Question Nos. 4 & 5 Sheet 10 QDR-5437-201-01 Surry Unit 1 System component evaluation worksheets for PT-LM-lOlA and 101B indicate only Rosemount 1152 AP transmitters are used in Surry Plant. Reference Report #6, Section 6.0, covers type testing of the 1152 AP transmitter. Hence the report is considered. traceable to the plant equipment. Question No. 6 Per reference report no. 6, sec. 4.1 on page 2 satisfactory performance criteria is based on: (1) Performed within 2.0% accuracy after being subjected to 5xlo6 gamma radiation dose. The accuracy after recalibra-tion was within +/-0.25% of the span. (2) Remained operable, within +/-0.25% accuracy when subjected to seismic disturbance of 3g level over a range of 5-100 Hz. (3) Performed within an accuracy better than 1/2% full scale after exposure to steam pressure environment. Question Nos. 8, 16 & 24 As shown in Figures 3 & 3A Rosemount conducted a steam pressure test for 50 hours (Sec. 5.5 of Ref. report no. 6) which envelops the required one hour plant HELB conditions. Hence the conducted test is considered more severe and the transmitters are qualified for HELB conditions. Question Nos. 9, 36 & 37 Rosemount conducted two cycles (100°-0°-200°-100°F) of eight hours each towards the thermal aging test. This is not enough to satisfy IEEE-323-1974. The vendor qualified these trans-mitters per IEEE-323-1971 in the past and is committed to conduct additional tests to qualify them per IEEE-323-1974 by the end of 1982. At this time even though we take credit for the extended steam pressure test we are unable to qualify these transmitters for more than 18 months (see the analysis below). Hence we recom-mend including these transmitters in an ongoing aging surveil-lancep::-ogram to extend the qualified life till Rosemount com-pletes the tests per IEEE-323-1974 and a new qualified life is established. NUS CORPORATION

ATTACHMENT #1 Question Nos. 9, 36 & 37 (Cont'd) Analysis for Qualified Life: Following tests were considered: Sheet 11 QDR-5437-201-01 Surry Unit 1 i) Thermal aging test: 2 cycles (100°-0°-200°-100°F; 2 hrs each,per Sec. 5.2 of Ref. #6) of 8 hrs each. Out of this test only four hours at 200°F are considered because other temperature values are lower than the plant ambient temp-erature. Applying Arrhenius equation: TL =Life@ ambient temperature= I00°F - 311°K 1 T = 4 hrs. @ 200°F = 366°K X Tl = 311°K T2 = 366°K 0 = 0.7 (See note below) Substituting the values and solving: T J = 203 hours. Ll ii) Credit from extended steam pressure test: In the following calculations the first one hour (See fig. 3) of the test which envelops the plant HELB condi~ tions is not considered. a) Test profile FG: Tl = 100°F = 311°K T2 = 303°F = 424°K T = 7 hrs. X TL = to be calculated 1 0 & K are same as in (i) NUS CORPORATION

ATTACHMENT #1 Sheet 12 QDR-5437-201-0l Surry Unit 1 Question Nos. 9, 36 & 37 (Cont'd) b) Substituting these values in Arrhenius equation and solving: TL = 7,386 hrs. 1 Test Profile HI: Tl = 100°F = 311°K T2 = 230°F = 383°K T = 42 hrs. X TL = to be calculated 2 (3 & K are sam.e Substituting these values in Arrhenius equation and solving: TL = 5,699 hrs. 2 Hence combining the results from (i) and (ii) above the total qualified life= 203 + 7,386 + 5,699 = 13288 hrs= 1.5 yrs. NOTE: 2nd Para, Page 83 of Rosemount Report No. 57820 in QDR-5437-13-01 reads as follows. The integrated circuit used is a linear device of mono-lithic bipolar construction; it is an LM308 device. An estimate of the activation energy is provided in a mili-tary technical report generated by the Air Force Rome Air Development Center (reference 9.7). In the conclus-ion of this document, it is stated that a range of activa-tion energies for microcircuit technology varies from 0.7 to 2.3 electron volts with no discernable correlation with microcircuit technologies, packages or manufacturer. Using the smallest value of this range gives the most conservative estimate of test time for thermal aging when used in conjunction with the Arrhenius equation. NUS CORPORATION

ATTACHMENT #1 Question No. 11 Sheet 13 QDR-5437-201-01 Surry Unit 1 Equipment Evaluation Worksheets indicates the transmitters may be exposed to the maximum radiation dose of 4.87xlo3 RADS 40 yrs (TID) plus 9. 3xlo5 RADS DBE. (Total lxlo6 RADS). Reference Report #6, page 5, section 5.3 indicates 1152 model transmitter was exposed to total of 5xlo6 RADS during radiation test, which equals the anticipated 40 yrs TID plus DBE dose. Question Nos. 27 and 39 Accuracy after recalibration remained sufficiently near to the specified value at all times except during the extreme conditions of the steam pressure test which were well above the plant service conditions. Since the accuracy returned to within 0.25% of specified following the steam pressure test, it is the judge-ment of NUS that this is not a detriment to qualification; Question No. 28 The test report does not define mounting details except for seismic testing. It is assumed that for both the manufacturer sponsored type testing and for installation in the plant that the manufacturer's mounting recommendations were followed. Question Nos. 29 and 30 The TME calibration dates are recorded in Appendix 1, page 28 of the test report. The traceability of calibration to NBS is not considered critical since generally the test facilities have a qualify control procedure which is recognized by the industry and which assures proper maintenance of calibration for the TME. NUS CORPORATION

e FIGURE 1 Sheet 14 QDR-5437-201-01 Surry Unit 1 Block Diagram for Qualification and Type Test Procedure fo~ Pressure Transmitter, Rosemount Model No. 1152 AP, DP, GP. Rosemount Report No. 117415,Rev. B, dated Sept. 24, 1975 (Ref. Report No. 6) BASELINE CHECK I THERMAL AGING SEC. 5.2 I FUNCTIONAL TESTING SEC. 5.2.2 I RADIATION AGING SEC. 5.3 I POST RAD. TEST SEC. 5.3.3 I SEISMIC AGING SEC. 5.4 I POST SEISMIC TEST SEC. 5.4.3 I STEAM - PRESSURE (MSLB)-SEC. 5.5 I POST MSLB TEST SEC. 5.5.3 I CONCLUSION SEC. 6.0 NUS CORPORATION

Sheet 15 QDR-5437-201-01 Surry Unit 1 CLASS n: EQUIP. QUALIP', T':'PE TEST PROGRAM PER IEEE-32:l STANDARD 1974 Inspection to determine damage if any aubaequent to manufacture I Determination of data base for p.r!ormance under normal and IDQra atr*** condition* I Determination of baseline data for extremes operating performance and electrical characteristics given in equipment specs. (exclud-ing DBE and post DBE unless data are available from other tests on identical or essentially similar ~uipment I Equipment aging is a condition equipment to end (of useful life) qualified life condition. Simula-tion for degrading influences for thermal, radiation, vibration, electromechanical equipment shall be oper-ated to simulate the ex-pected mechanical wear and elect. contact degradation. Sampling aging times of less than 100 hrs. will not. be permitted. I !iged equipment subject to mechanical vibratior, as will be seen in service. This includes aeilllllic vibration (IEEE Std. 344-711 self induced vibration (aee 344-71) or vibration from other cause (such as might be seen by pipe-mounted equipment) J Equipment shall be oper-ated while exposed to the simulated post-Accident conditions. Those func-tions which must be performed following the si.lllulated DBE muat be monitored. Exposed ti.me must be an ho\\ll' or over I

l'h.e aged equipment operated while

~xposed to simulated DBE. Those fWlctions which must be perfor-med ~uring che simulated design basis t-----. event (DBE) must be monitored. I Diaaasemble necessary for ins?ec-tion of the status and condition of the.equipment &nd.record finding. Raalat1on: Mater1a~, or componen~~ which may be degraded to a degree of poorly performance due to radia-tion exposure w1ll be applied with a radiation dosage equivalent to --~~_. the expected service. The applied doaage will determine the qual1f1ec life service life and DBE condi-tions application. If service conditions encounter gamma (8) a.nd beta (B) radiation the equivalent gamma (8) may be utilized. Suggested factor to be applied to --- environments for type test~ng are, as followed ~

l.

Temp+ lSoP (8°C) When qualification testing is conducted under saturaccd steam condition - temp margin is such that test pressure won't exceed satura-ted steam2pressure by more 10 Lbf/in

2. *. + 10\\ of gauge, but2not more than 10 Lbf/in

3.

4.

s.

6.

7.

a.

Radiation+ 101 (on accident doae) Voltage+ 101 of rated value under otnerwise apecified Frequency+ 51 unlesa otherwise specified Time+ 101 of the period of time the equipment is required to be in ope~ation following the DBE Environmental transient: the initial transient and the Dwell at peak temp. shall be applied at least twice Vibration+ 101 added to the acceleration of the response spectr\\llll at the mounting point of equip. FIGURE 2

LOCA PROFILE [ Ref.: S&W Calculation ] No. 12846.44-US(B)-052-l for Zone for inside con-tainment NOTE: Required HELB conditions exist for one hour only. 01--~~o ACTUAL TEST PROFILE (Ref~ Section 5.5, Rosemount Report No. 117415, Rev. B dated 9/24/75) c~~~a HELB PROFILE (Ref. S&W Cale: 12846.44-PE-050-0 for Zone AB-13A) LOCA/HELB TEFlPERATURE TRANSIENT FIGURE 3 Sheet 16 QDR-5437-201-01 Surry Unit 1

-mL ::f_~i7 JCT ~~~t;: 3=fil=q~ :Jl 1fih ::g J:1 \\ -_ ? JT.f:J1~ff: -ilTI tr~ tfJ =~ It -: : :lJt!! jf "FI}~. "I~IE?F: TI:~. -: ~? *t iT:£ I~~: - 111 1oz 11J 10* I 10~

1 J05 10*.

(8 hrs) (SU hrs) Time After LOCA/HELB (seconds) LOCA PROFILE [Ref. : S&W Calculation ] No. 12846.44-US(B)-052-1 for Inside Containment o--.--o ACTUAL TEST PROFILE (Ref. Section. 5.5 Rosemount Report No. 117415, Rev. B dated 9/24/75) no---c HELB PROFILE (Ref. S&W Cale:' 12846. 44-PE-050-0 for Zone AB-13A) LOCA/HELB PRESSURE TRANSIENT FIGURE 3A Sheet 17 QDR-5437-201-01 Surry Unit 1

/~ ** l'acility: VEPCO, SURRY oni.t: 1 Docket:.: 50-281 SY'STBM: LBARAGE K>NITORI:NG IOQIPMBNT DBSC1UP'l'ION PLPJff ID RO. PT-LM-101A CDMPONEHT: Pressure Tranemitter MMIUl'ACTORER: Ro*eaount Inc. IODEL NOMBER: 1152AP7A22PB l'UNCTIOH l Poat-accident MOnitoring ACCURAC'l: Spec: ~.2s* of Span Demo: ~.251 of Span IDCATXON: AB -1 :s fJ (o) outside Contai11ment (AUX. Bldg.) SERVICE: Reactor Containment Pressure PLOOO LEVEL.ELBV: -21 1 11* ABOVE FLOOD LEVEL: X

Yes No Units OPER.

TIME PRESS. psia REL. HUM. I CHEM. SPRAY RAD. AGING SUB. SYST.&M ca,u>ONENT.EVALUATION WO.RR SHEET - .tiUPPLEMENT 3 Environment Documentation Reference Specification 120 days 11a. :SEE' Fl(,.3 A NR Cf-3 x,os-LOCA * ~x ~ -0 Yr* ~-S X 10* 4-~7 )I lo '.'.. tttr::~, ~ct1~11J 4{ y,:, NR Oualih.cation 7-~~~i, ai~* - :ratti.at.J.en ~ Specification Westinghouse Ref. Ltx. No. NS-SS-79287 NR M L11;: 't..,.\\ ..Hei1~ HR ~r.,./ c..o.Qc-**

12.,.,~b./.J!.i - PE-oS'r::, -c.

lllf 4 lllt"- £.N IJ. ?r:,NE; ..fa "I>F.:; d< I '1' 7Jo N A8- /3A Co) S&W Ca1c. ~38-M'- ff&-e-p i' Lj i~

Ll I./
UR ( B)

-C,l/3--0 ~ VE.PU). P. o "flO. ?/-j'3.1"c{. Dc0-i *,;.J..,,,J-. E.NV. 'iP NE.. - T.*E.SC.RIP 7Jr:, ~! A~ -1:.l'lir) Qualif. b, 17 Net.e 1 (.,7 /7 19- ~7 "* 17 ,ta= fo/R Not:a:o\\ b, 17 -G, 17 NR Method T;o;r;_ 7 (.:. T Nei!:e 1 f:-tl r,14 LY: 1::- TyPE, TE:ST -:nR.¢ AN*,C )'SIS TyPE TEST

1m4' ANA'Lj~I~

Tja.. Tc'ST N~ -Ila;" TyPE"i'Es.T ... 1 Tj~f. TeJr a~r4 ~~ibg) 1. ~ ? 0}\\.V"' (_::.r*.\\-is. NR e Ollt- &tanding Items "'ct-.'!' l!Me*"' None none Wone None .llata.,.. 1'1o/\\lt: .._. NcT,<: / None

m.

Not requi.red. All nwnbera written in Docwnentation Reference Qua1if1cation column a.re identified 1n Section 10.S.

lOTES:

1. Transmitter is qualified to the requirements of IEEE.-323-1971.

At present transmitters are being quaU.b.ed to -~Jn IO (I) ~ t:::J::, ~ ~ CD ~ I CD "< lJl rt requirements of IEBB-323-197Q. Tc, ,-~1-n*.... o .,ir)r-:-. C.;fc

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?OTES: 1. Transmitter is qualified to clle requirements of IEEE-323-1971. At present transmitters ~re being qualitie,,*ft*,.,.. 1*, /"

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SECTION #2 SPECIFICATIONS, PURCHASE ORDERS, VENDOR PROPOSAL NUS CORPORATION
e VEPCO P.O. NO. 39306 DATED JUNE 17, 1980 Page 2a
~ 156.SF GENERAL OFFICES
RICHMOND, VIRGINIA r
L ~.....JNT, INC. lGCO FC:U::ST AVE. RIOiMCNO., VA. 23229 )UBJECT TO CONDITIONS SPECIFIED BELOW 'ER QUOTATION
,

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ECIUISITICN NO, MATERIAL IIEQUIRE,C PROMISEC SHIP TO OROER NO. 6 39306 OUR PURCHASE ORDER NO.
ANO R!:OUISITION NO. MUST APPEAR ON ALL INVOICES. SHIPPING PAPERS,
PACK*
AGES, AND CORRESPOND* ENCES. VIRGINIA ELECTRIC AND POWER COMPANY 1 AT _J S~ PC'~R STATICH (SEE BEL.Oft) BILL TO VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND. VA. 23261 PA.ICE,..a.a. TEAMS b~ /o/!7/t(J I '; / \\." / CAT[ I I ZST/?
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SECTION,_ # 3 QUALIFICATION REPORTS NUS CORPORATIOr'-J
ROSEMOUNT REPORT NO. 117415, REV. B DATED SEPTEMBER 24, 1975 (REFERENCE NO. 6) Page 3a
e Written by Approved by Approved by Approved by e REFE-R.ENCI: N_t:. 6 Rosemount ROSEMOUNT INC., POST OFFICE BOX 35129 / MINNEAPOLIS MINNESOTA 55~35 i TEL. !E-12) 9.Cl-5560 TWX: 910-576*3103. TELEX 2S*Cl83 QUALIFICATION TESTS FOR ROSEMOUNT PRESSURE TRANSMITTER MODEL 1152 RMT Report No. 117415 Rev. E Date \\ ,. Jl'!. I 7 ~ r ~'ah g;~?T9
fign En~~g Date.q~ 2.

,, /'l"?S-
. p..). v,.,,( ~ Project Engineer
j. -A. -~ Date S-e.-1v/* -2~, L q_ 75-Engineering Supervisor
~ 0-v-QQ,u~ *;&:e-.,,' Date Se..,,c ~c" 19 Z.{"' --. " - /-, v *-qua l kY~ssuranc..e' J I
Form No. 16215A e REVISION STATUS Para-EngT QC Rev. Page graph Change Description App App Date A Recollated Appendix, Delete Report 2758
1 /,'
S"&/7, add summary page 37, add page 38 to
..}~,'.) y.,....._r-Appendix; Change para. 4.1, 5.~.2; LL reference and spec. deleted.
8 1 Changed reference date of IEEE 323 I -** ~ 10(,_, . --:. 'j ..-,,.o to 1971.
TABLE OF CONTENTS -.e SECTION TITLE PAGE 1.-0 SCOPE l
2.0 INTRODUCTION
l 3.0 REFERENCE DOCUMENTS l 4.0 TEST PROGRAM 2
4. 1 Performance Criteria 2
5.0 QUALIFICATION TEST 3
5. 1 Test Sequence 3
5.2 Aging 3 5.3 Radiation 5 5.4 Seismic Vibration Test 6 r 5.5 Steam Pressure 9 ~
6.0 CONCLUSION
11 7.0 APPENDIX I 12
7. 1
Radiation Graph 13 7.2 Seis~ic Vibration Data 14 7.3 Steam-Pressure Data 24 7.4 Equipment Lists 28 8.0 APPENDIX II 30
8. 1 Pressure Transmitter Specification Drawings 31 8.2 Report 2758 Summarized 37 8.3 Report 127516 Summarized 38
e 1.0 SCOPE QUALIFICATIQN TESTS FOR ROSEMOUNT PRESSURE TRANSMITTER MODEL 1152 RMT Report No. 117145 The objective of this document is to verify performance of Rosemount Model.1152.pressure transmitter under normal operating conditions; during and after radiation exposure, seismic events and a loss-of-coolant accident (LOCA). The unit was subjected to a series of independent tests in accordance with IEEE 323 (1971) and IEEE 344 (1975), which includes aging, radiation, seismic vibration and steam-pressure tests. Performance of the transmitter durina the test program is described in Section 4.1.
2.0 INTRODUCTION
The 1152 differential pressure transmitter is intended for use in nuclear power stations and other applications where stringent quality control of pressure retaining material and cleanliness are necessary to insure high reliability over an extended service life. Typical applications for the pressure transmitters are where equipment failure can result in the release of radioactive materials. (See specification drawings in Appendix IO. This report covers procedures, testing and results for exposure to radiation, seismic vibration and steam-pressure conditions performed on a test unit, Model 1152DPIA22, serial number 090. Qualification testing of the 1152 pressure transmitter, serial number 090, began on January 13, 1975, and was completed on April 9, 1975. 3.0 REFERENCE DOCUMENTS 3.1 IEEE 323 (1971} - IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations. 3.2 IEEE 344 (1975) - IEEE Recommended practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations. 3.3 Rosemount Report 2758 - Seismic Qualification Test for 1151/1152 Pressure .e' Transmitter with Stainless Steel Electronic Housing; by Ismail Ismail 3.4 11520P specification drawing for differential pressure transmitters. ll52AP specification drawing for absolute pressure transmitters. ll52HP specification drawing for high line pressure transmitters 1152 GP specification drawing for gage pressure transmitters. 4.0 TEST PROGRAM The test unit was first subjected to thermal aging followed by radiation exposure of 5.0 x 106 Rads total integrated dose of gamma radiation. The unit v,as recalibrated and then subjected to seismic vibration in each of the three major axes independently, while it was pressurized at 60% of full scale. Vibration testing was ~erformed with and without the mounting bracket at the.3" double amplitude or 3g level, over a frequency range of 5-100 Hz. Finally, the unit was subjected to sequential pressures of 60 psig, 350°F 1 dry heat environment for 10 minutes; 70 psig 316°F. saturated steam environment for l hour; 55.4 psig, 303°F, saturated steam environment for 7 hours; and 6 psig, 230°F 1 saturated steam environment for 42 hours.
Calibration data was recorded before, durin~ and after each major portion of the qualification tests.
4.1 PERFORMANCE.CRITERIA The 1152 pressure transmitter performed to within 2.0~ accuracy after being subjected to 5 x 106 Rads total integrated dose of galTITla radiation. The accuracy after recalibration was within.:!:. 0.25% of the span. Additionally, the transmitter remained operable, within the specified accuracy of +0.25%, during and after a seismic
disturbance in each of the three major axes at the.3 11 double amplitude or 3g level over a frequency range of 5-100 Hz, with and without the panel mounting bracket.
Finally, the test unit was exposed to a steam-pressure environment. tn outout drift of 12% of ~p6n occurred during sequential exposure to 60 psig. 350°F for 10 minutes; 70 psig, 316°F for l hour; 55.4 psig, 303°F for 7 hours; and 6 psig 230°F for 42 hours. These temperatures are far in excess of the normal operating limit of the model 1152 {200 Degrees F ) so no performance limit was set. Data was taken during the simulated accident temperatures for information only, and are proffered fn Figure 6. RMT Report 117415 After exposure to the steam-pressure environment, the unit perfonned within an ~ accuracy better than 1/2% Full Scale. 5.0 QUALIFICATION TEST Type testing of the actual equipment using simulated service conditions is the preferred method of the IEEE standards and the procedure used for qualifi-cation requirements of the Rosemount Model 1152 pressure transmitters. Qualification is satisfied if the equipment to be tested is aged, subjected to environmental in-fluences, and operated under post-event conditions to provide assurance that all such equipment will be able to perform their intended function for the required operating time. The type test for qualification of the 1152 was a planned sequence of test conditions that met or exceeded the expected or specified service conditions and took into account both normal and abnormal operation. 5.*1 TEST SEQUENCE The test unit was subjected to the following sequence of tests: Thermal Aging (Section 5.2) Radiation Exposure (Section 5.3) Seismic Vibration (Section 5.4) Steam-pressure Environment (Section 5.5) 5.2 AGING The transmitter was subjected to two complete thermal cycles from 100-0-200-100°F, both as a preliminary aging and as an initial bench mark to compare with all future test data. 5.2.1 Test Procedure The aging test was performed on the transmitter at Rosemount Inc., Mpls. The tra*nsmitter was subjected to two complete temperature cycles of 100°F, 0°F, 200°F and 100°F. All temperatures were sustained for a minimum of one hour before readings were recorded to assure *that the transmitter was stabilized at that temperature. RMT Report 117415 .~ 5.2.2 Test Data Table 1: 1st Calibration Data for Aging (Duration of the test was approximately 8 hours) % Full Temperature Scale 100°F 0°F 200°F 100°F 0
1. 997 2.003

1. 984 1.992 20 3.590 3.616 3.557 3.585 40

5. 185 5.222

5. 131

5. 180 60 6.784 6.828 6.717

6. 778 80 8.365 8.421 8.281 8.360 100 9.985 10.044 9.882 9.978 Span 7.988 8.041 7.898 7.986 Table 2:
Calibration Check Between Aging Cycles (at 75°F) % Full Sea 1 e ( Output 0% 20% 40% 60% 80% 100% I *:* Vo 1 tage ( VDC). 2.001 3.598
5. 195 6.795 8.380 10.001 Table 3:
2nd Calibration Data for Aging (Duration of the test was approximately 8 hours) % Full Temperature Scale 100°F 0°F 200°F 100°F 0 2.000 2.014 2.000 2.005 20 3.592 3.622 3.570
3. 596 40

5. 185

5. 231

5. 142

5. 190 60 6.783 6.835 6.725 6.789 80 8.364 8.425 8.287 8.370 100 9.984 10.050 9.889 9.990 Span 7.984 8.036 7.889 7.985 RMT Report 117415
/ 5.2.3 Discussion of Aging Results e
The transmitter exhibited no significant change at any *temperature an~
performed satisfactorily within the specification limit during and following approxi-rr~te1y sixteen hours of thermal aging. 5.3 RADIATION Radiation testing was performed at Isomedix Inc. to find the effects of 5.0 x 106 Rads total integrated dose of gamma radiation on the performance of the 1152 pressure transmitter. 5.3.1 Pre-test Table 4: Calibration Data Recorded at Isomedix Inc. Before Exposure to Radiation (Room Temperature-in Radiation Cell, 70°F) 0/ Full Sea 1 e 1152 Output ( VDC) IC 0 2.003 25 3.99'2 50 5.991 75 7.970 100 9.990 Span 7.987 5.3.2 Test Procedure The test unit was exposed to radiation from cobalt 60, a source of gamma rays. Dose rate was 1.0 x 106 Rads per hour for five hours with data recorded every hour during radiation exposure. The test was performed in a radiation chamber, in air at ambient temperature (70°F) and a slight negative pressure (1/4" water). Table 5: Data Recorded During Radiation Test at Isomedix ., Full Hours of Exeosure IO Scale 1 2 3 4 5 0
1. 941 1.930 1.930 1.932 1.936 25 3.926 3.918 3.917 3.920 3.925 50 5.930 5.920 5.920 5.925 5.931 75 7.911 7.900 7.905 7.909 7.914 100 9.934 9.924 9.927 9.933 9.937 Span 7.993 7.994 7.997 8.001 8.001 RMT Report 117415
'*e 5.3.3 Post-test Table 6: Calibration Data after Return to Rosemount following the Radiation Test % Full Temperature Scale 100°F. 0°F 200°F 100°F
0.
1.916
1. 927 1.944 1..943 20 3.512 3.540 3.515 3.535 40

5. l 09

5. 152 5.090

5. 132 60 6.710 6.760 6.675 6.731 80 8.295 8.355 8.240 8.314 100 9.918 9.985 9.843 9.933 Span 8.002 8.058 7.899 7.990 5.3.4 Discussion of Radiation Exposure Results The test unit received a total of 5 x 106 Rads total integrated dose of garrma radiation over a period of five hours.
Maximum changes in output, before (Table 3) after (Table 6) and during (Table 5) radiation exposure are as follows: Pre to Post During Zero Pressure Shift -84mv (1.05%) -73mv (0.9t) max. Span Shi ft +18mv (0.23%) +14mv (0.2%) max. Lineadty +lmv (0.01%) -3mv (0.04%) max. (0°F-200°F) Zero Temp Coefficient +3lmv (0.4%) (0°F-200°F) Span Temp Coefficient -1 2mv ( 0. 15%). From the results, we see that the maximum change was zero shift of 1.05% of full scale. This shift is within the performance specification of the. trans-mitter, (See Appendix II). Next, the transmitter was recalibrated to the original output accuracy with the span and zero adjustments provided on the Model 1152. This allows for easy maintenance during the projected operating life (40 years) of the transmitter. 5.4 SEISMIC TEST Seismic vibration was performed at Rosemount Inc., Mpls., to simulate an earthquake disturbance. A frequency range of 5-14 Hz was covered at.3" D.A. level and 14-100 Hz at the 3 g level. The test was performed in three major axes independently; vertical, horizontal and 90° to horizontal, mounted with and without the panel bracket. (See Drawing #1 "Three Axes Orientation and Panel Mounting Bracket). RMT Report 117415 e e 5.4.1 Pre-test Table 7: Calibration after Radiation and Recalibration (Taken at Room Temperature) % Full Scale oi 20t
40%
soi 80% 100% Output Voltage up scale 1.999 3.596
5. 195 6.796 8.381 9.997 (VDC) down scale 2.000 3.597

5. 196 6.798 8.383 5.4.2 Test Procedure The same transmitter tested previously in radiation was subjected to seismic vibration. The unit was pressurized at 60% of full scale (90 inches H20) during vibration and a resonant search over a frequency range of 5-14Hz was performed at a.3 11 input and 14-100 Hz at 3 g level.
(Frequencies lower than 5 Hz 1-Jere not covered because of the testing machine capability.) A dwell for a period of 30 seconds was performed at each resonant point. If no resonance was found, then dwelling was done at frequencies of 10, 20 and 30 Hz. Table 8: Hard Mount - No mounting bracket (see Figure 1 in Appendix I ). Axis Vertical Horizontal 90° To Horizontal Frequency (Hz) 10 20 30 10 20 30 10 20 30 RMT Report 117415 Dwell (Sec) 30 30 30 30 30 30 30 30 30 Double Amplitude or G Level
311 3g 3g

311 3g 3g

3" 3g 3g Output (VDC) 6.798 6.797 6.798 6.845 6.845 6.845 6.795 6.795 6.795 Graph
1

1

1

2

2

2

3

3

3
i **e Table 9: Transmitter Mounted with Panel Bracket (See Figure 2, 3 and 4 in Appendix I ) Resonance Double Frequency Dwell Amplitude or Output Axis (Hz) (Sec} G Level {VDC} GraEh Vertical 68 30 3g
6. 797 Horizontal 78 30 3g 6.747

24 30 3g
6. 749
90° to 69 30 3g 6.797 Horizontal 61 30 3g
) 6.797 (outside 22 30 3g 6.797 bracket) 90° to 52 30 3g 6.797 Horizontal 26 30 3g 6.797 (inside bracket) (refer to pictures and graphs in Appendix I )
Static head effect 5.4.3 Post-test Table 10: Calibration at Room Temperature After Vibration
% Full Scale 0% 20% 40% 60% 80% Output Voltage up scale
1. 999 3.595

5. 196 6.801 8.385 (VDC) down scale 2.001 3.597 5.202 6.802 8.388 5.4.4 Discussion of Seismic Vibration Results
4

5

5

6

6

6

7

7 100:
10.000 There was no resonance at any frequency in the range of 5-100 Hz at the .3" double amplitude or 3g level when the transmitter was hard mounted (no moun.ting bracket) in the vertical, horizontal and 90° to the horizontal positions. On the other hand, there was resonance when the panel mounting bracket was used in the positions mentioned above. All resonances were dwelled at for 30 seconds with no significant change in the transmitter readings. Strip chart records demon-strated that there was no shift during seismic vibration and the data in Tables 7 and 10 shows there was a negligible calibration change from before to after seismic testing. RMT Report 117415 The 92 option (stainless steel electronics housing rather than aluminum) was ~vibration tested as documented in RMT Report 2758 and ~ummarized in Appendix II. Subse-quent to this Qualification Report, A random multi-frequency test was successfully conducted at Wyle Laboratories on a different 1152 test unit. One is referred to RMT Report 127516 for details of this testing; a brief summary appears in Appendix 'lI. 5.5 STEAM PRESSURE Steam pressure testing was performed at Rosemount, Inc., Minneapolis. The test demonstrated that the test unit is capable of operating in the steam-pressure environment of a simulated loss-of-coolant accident and will continue to operate in the post accident period.
5. 5. l 5.5.2 Pre-test Table II: Calibration Check (unit installed in steam chamber) 0%
Output Voltage up scale 1.998 (VDC) down scale 2.002 Test Procedure Before Steam-Pressure Test % Full Scale 20% 40% 60% 80% 3.598 3.599 5.198
5. 199

6. 798 6.800 8.384 8.385 100%

10. 001 Tested the same transmitter that*was exposed to radiation and seismic tests.
The transmitter was installed in a steam autoclave with a pressure input line connected to the high side of the 1152 and the low side vented to the outside atmosphere. (Refer to Figure 5 in the Appendix I. The electrical wiring was connected to the signal terminals of the housing and a pressure tight conduit connection from the housing through the autoclave wall was used to prevent the terminal side from filling with condensed water. The steam generator used can only provide saturated steam. Thus, because of the dift'ic:ulty in supplying super heated steam at 60 psig, auxiliary heaters and dry air were used to raise the chamber temperature to 350°F in five minutes. The following sequence was then followed: RMT REPORT 117415 Temperature 350°F 316°F 303°F 230°F Pressure 60 psig 70 psig 55.4 psig 6 psig Hold Time l O minutes l hour 7 hours 42 hours Steam Environment Dry Saturated Saturated Saturated
e \\, __ 'e 5.5.3 (Refer to Figure 6 in Appendix I, 1152 Steam-pressure: Output vs Time). Table 12: Calibration Check during Steam-pressure Test (at 230°F) (Data was recorded 40.5 hours after the start of the 50 hour steam~pressure test) % Full Scale 0% 20% 40% 60% 80% 100% Output Voltage
2. l 01 3.662 5.220 6.783 8.314 9.782 (VDC)
Post Test Table 13: 1st Calibration Data After Steam-Pressure Test Unit at> 200°F (5 minutes after test). % Full Scale 0% 20% 40% soi 80% l 00% Output Voltage 2.117 3.650 5.220 6.784 8.293 9.872 (VDC) Table 14: 2nd Calibration Data after Steam-Pressure Test (Data taken after return to room temperature, 75°F) % Full Scale 0% 20% 40% 60% 80% 100% Output Voltage up scale 2.041 3.639 5.240 6.843 8.430 10.036 (VDC) down scale 2.043 3.640 5.240 6.847 8.431 Iab] e l 5: 3rd Cal ibr'ation check after Steam-pressure % Full TemQeratur~ {°F) Scale Room Temp 100° ao 200° 100° 0 2.045 2.047 2.075 2.060 2.044 20 3.644 3.642 3.676 3.630 3.639 40 5.245 5.238 5.276 5.203 5.236 60 6.846 6.838 6.875 6.788 6.836 80 8.431 8.421 8.461 8.349 8.418 100 10.038 10.026 10.060 9.939 10.022 Span 7.993 7.979 7.985 7.879 7.978 RMT Report 117415 I
e ( ' **e .'9 -5.5.4 Discussion of Steam-Pressure Test Results Comparison of data before and after steam testing shows an increase* shift at all pressures. However, the shift was 1/2% full scale between the readings on tables 11 and 15 at room temperature.
6.0 CONCLUSION
All qualification tests for radiation, seismic vibration, and steam-pressure were passed by the 1152DP test transmitter. The 1152DP (differential pressure) is representative of the other models of pressure transmitters AP (absolute), GP (gage) and HP (highline) in mechanical and electrical features. The only differences in the varios models is the input (pressure) and output (electrical) relationships. These are primarily calibration differences; not influencing qualification capability. The output option D differs physically from the A option by a slightly different amplifier printed wire board assembly. The D option amplifier board was tested independently in radiation and has passed the same levels as described in Section 5.3. Similarly, the 1152 transmitter is mechanically identical to the 1151 model. The 1152 has the requirements of material traceability of pressure retaining parts and the use of non-Teflon wire in its assembly. The 1151 also has DP, AP, GP,. HP and pressure transmitters that are qualified by similarity to the 1152 DP test transmitter, except for radiation levels. RMT Report 117415 e 7.0 APPENDIX I
e RMT Report 117415
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)( M -0 no lO ro N 00 ITEM 1 2 J 4 5 6 7 8 9 10 11 12 13 14 15 16 17 DESCRIPTION Digital Multimeter Power Supply Vacuum Tube Voltmeter Logarithmic Converter Vibration System X-Y Recorder Resistance Box Digital Multimeter Pressure Tester Signal Cond. Amplifier Tracking Filter Charge Amplifier Fixture Power Supply Potentiometer Triple Beam Balance Speedomax Recorder-Azar EQUIPMENT LIST Serial CAUBe Number FREQ* MFGR MODEL RANGE ACCURACY (MOS.) !>ystron U-lOOOVOC; U-lUUUVAC +/-.UL% l<dg; +/-1:.t l<dg Donner 7205 0- lOMri; 0- lAmp +/-lX Rdg 3 __ VJBilAll 1~1 n~ T rnm Pt-ENI. I I SI Kepco 0-40V As used HP 001-33143 lmv-300V RMS +/-2% 3 .uul to lV Al.,.uuJlb HP 561 to 3.16 DC +/-0.5db 6 unno,tz Dickie NA 10 10 1 HP 806-03398 0-50 V/inch 0.2% of full scale 6 ~uuri + REC NA soon .01% 12 Fluke 51412 0-lOOOV DC +/-.03% of range 3 Mansnela & Green 67818 0-831" H?O 0.025% 12 unno1tz Dickie 340 2Hz to JOKHz +/-5% 3 unno1tz Dickie 239 5Hz-5KHz +/-.5013 +/-.3%FS 3 Unholtz Dickie 390 20Hz to lOOHz 10 6 RMT SJfJ\\M::P_R[S.SURLE( UJPMENT _USJ Set for 30V As used L & N 1606954 -11 lOlMV +/-.05% 4 0-10 gr; -.2 gram Chaus None 0-2610 grams 10-2610 qr; +/-1 qr. 3 L & N 68-58144-1-1 0-lOOMV (IO) 6
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)( H -0 DI lO ro N '.O ITEM DESCRIPTION 10 Recorder 19 Pressure Tester 20 Digital Voltmeter 21 Pressure Gaqe 400# 22 Resistance Box 23 Type K ThernDcouple TABLE EQUIPMENT LIST MFGR MODEL RANGE HP 903A08223 10 anst1e1<1 & Green 67818 0-831" H20 U-lUUUV Ul.; 1-lUK.U Fluke 77420 0-300V AC u.s. Ga<1e 5 to 400fl 200 ohms RMT NA 500 ohms RADIATION EQI IPMENT LIST Power and r ressure S0urc1 in console built by Ro* Power Suppl y set for 30, DC. Load Resist or 500 ohm ( c, librated at 500.08 ohm) Pressure fr om six inch b !llows. Calibrated model 1151 DP A24, cell Seri a 1 No. 44 CALIBe FREQ* ACCURACY (MOS.) 10 6 0.025% 12 +/-.un Kag Ul.i,+/-.UJ~Kagu +/-1% Rdg AC 3 +5# 12 +/-.02% 2 emount. 39755. I
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'*e SEISMIC TESTING 1151/1152 TRANSMITTER WITH STAINLESS STEEL ELECTRONIC HOUSING (Summary of Report 2758) The testing consisted of six separate test configurations: rigidly mounted and panel bracket (PB option) mounted in each of three orthogonal axes. The manner of test was to perform sinusoidal frequency sweeps from.5 - 70 Hz for each configuration at levels of.5, 1, 3, and 4 g's. These frequency sweeps were for a duration of approximately 4 minutes each. If resonance was found, the frequency of ma~imum resonance was dwelled at for an additional thirty seconds. Following these series of frequency sweeps, each configuration was vibrated for 2 minutes at 10 Hz and 4 g's for fragility investigation. During the frequency sweeps at various g-levels the test specimen demonstrated sufficient integrity to withstand without comprimise of structure or electrical function the described environment. However, during the 2 minute dwell at 4 g'.s in the X-axis configuration (after 4 g/2minute dwell in the Z-axis) a crack started to show in the panel bracket. Because of this, a fragility limit of 3 g's is established for the transmitter/bracket assembly. In the case of the panel mounting configuration, resonance was found at 25, 50, and 29 Hertz for the x, y, and z axis, respectively. RMT Report 117415 _ 37 _
RANDOM MULTI-FREQUENCY SEISMIC TESTING (SulTITlary of Report 127516) Two DP transmitters with aluminum housing were tested by Wyle Laboratories. Each was submitted to two different test series. The first was a biaxial test series and the second was a psuedo-biaxial "fagility" test series. All vibration was random multi-frequency input mot,on. One transmitter was a model 1151 the other was a model 1152; mechanical features of the two are identical for seismic considerations. The test units were powered continuously and were pressurized at approximately 50% full scale. During the biaxial testing, the test specimens were subjected to horizontal/vertical and lateral/vertical phase incoherent inputs of random motion; consisting of frequencies spaced one-third octave apart over the frequency range of 1 Hz to 31.6 Hz. A minimum of five biaxial tests at one-half level followed by a full level test, each of 30 seconds duration, \\oJas performed in both the horizontal/vertical and lateral/vertical orientations. The full level test exceeded a response spectrum defined by the following, at three per-cent damping: 1 Hz,.5 g; 3 Hz, l.5 g; 3.5 to 6 Hz, 2.7 g; 10 Hz, 1 g; 30 Hz,.5 g. Both transmitters were mounted with the Rosemount panel bracket (PB option). . ~ Fragility testing was done on a long stroke single axis machine inclined 45° to the ',-horizontal. One transmitter, the model 1151, was mounted using the panel bracket (PB); the other, model 1152, was rigidly mounted. The specimens were mounted with their longi-tudinal axis parallel to the horizontal and the input motion was inclined at 45° to the horizontal. The specimens were tested in the vertical and first horizontal axis simul-taneously, and then the fixturing was rotated 90° and the test repeated for the vertical and second horizontal axis. This was repeated until all four principle horizontal direc-tions were tested. Input motion along the 45° inclined axis was analyzed at a 5~ damping value. The response spectrum for this table motion exceeds a curve defined by the follow-ing: 3 g, l Hz; 15 g, 3 Hz to 40 Hz. Horizontal and vertical components can be determined by dividing by the square root of 2. It was demonstrated that models 1151 and 1152 possessed sufficient integrity to withstand, without comprimise of structures or electrical functions, the described simulated seismic environment. And, although a slight amplification did occur at three Hertz durina the biaxial testing, no significant resonance was found below 5 Hertz. This is additionally demonstrated by the fragility test data. RMT Report 117415
SECTION #4 CONCLUSION SECTION & REFERENCE SECTION NUS CORPORATION
I *-e* i ' \\ __ -Ce YE-VMS-100C-1 YE-vMS-lOOC-2 YE-VMS-101A-1 YE-vMS-101A-2 YE-W..S-101B-1 YE-VMS-10 lB-2 CONCLUSION SECTION 2273AM20 2273AM.20 2273AM20 2273AM20 2273AM20 2273AM20 10.. 3.-13 10.. 3-14 10.3-15 10.. 3-16 10.. 3-11 10.. 3-18 The monitoring equipment is currently in the process of being qualified to the requirements of IEEE 323-1974.. The intormation on the worksheets is the levels to which the equii;:men:t will be tested.. 4.. Endevco Supplied Cable - Acoustical Monitoring Equipment Plant ID No.. Model Worksheet Page No. Low Noise Cable 307SM6 10.. 3-19 I I 3 The cable is currently in the process of being qualified to the I requirements of IEEE 323-1974.. The information an the worksheet I reflects the levels to which the equipment will be tested. -r-------------------------~--- 5.. Rosemount Inc. - Pressure Transmitters ! l Plant ID No. Model Worksheet Paqe No~ PT-LM-101A 1152AP7A22PB 10.. 3-1 3 PT-LM-101B 1152AP7A22PB 10.3-2 Transmitters test documentation is presently being upgraded tron: IEEE 323-1971 to IE&E 323-1974. -*----*-*--~.-. *-
6.
Valcor - Solenoid Operated Valves Plant ID No. Model Worksheet Paoe No. TV'-SS-102A V526-5683-19 ,o.3-32 TV'-SS-102B V526-5683-19 10.3-33 TV-SS-106A V526-5683-19 10.3-34 TV-SS-10bB V526-5683-19 10.3-35 HCV-SS-101D V526-5683-19 10.3-36 HCV-S5-102A V526-5683-19 10.3-37 HCV-SS-100A V526-568 3-19 10.3-38 HCV-SS-100B V526-5683-19 10.3-39 TV-SS-103A V526-Sb83-19 10.3-40 TV-SS-103B V526-5683-19 10.3-41 S1-XCV-1401A V526-5683-19 10.3-t)2 S1-XC.V-1401B V526-5683-19 10.3-63 S 1-XCV-1&i 22A V526-5683-19 10.3-t,4 S1-XCV-1422B VS26-5b83-19 10.3-65 TV-GW-100 V526-5695-31 10.3-76 TV-GW-101 V526-5695-31 10.3-77* S1 10.4-2 Supplement 3 February 1, 1981

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1.

2.

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4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.
16
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18.
SECTION 10.5 REFERtNCES Automatic Switch Co. - Test Report No. AQS21678/TR, Rev. A. Cleveland Development Co. - Qualification of NAMCO Controls Limit Switch Model EA-180 to IEEE Standards 344 (1975), 323 (1974) and 382 (1972), March 3, 1980. Babcock & Wilcox Transmittal 86-1119091-00. Comsip Delphi Test Report No. 1035-1 dated 12-1980 for Delphi KIII-KIV Hydrogen Analyzer. VALCOR IEEE Qualification Letter SK-10616. Qualification Tests for Rosemount Pressure Transmitter Model.1152, Rosemount Report No. 117415, Rev. B dated September 24, 1975. VALCOR Qualification Report QR-52600-515, dated NAMCO Controls Report on switches EA-180 - nEstimation of Qualified Life of Nuclear Switches" Rev. dated April 26, 1979. QDR-5437-212-01. QDR-5437-205-01. QDR-5437-201-01. QDR-5437-211-01.}}

ML18139C258

Contents

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Subject:

Dear Mr. Parrish:

2.0 INTRODUCTION

6.0 CONCLUSION

2.0 INTRODUCTION

6.0 CONCLUSION

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ML18139C258

Text

Subject:

Dear Mr. Parrish:

2.0 INTRODUCTION

6.0 CONCLUSION

2.0 INTRODUCTION

6.0 CONCLUSION

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