ML20207G496
| ML20207G496 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/15/1988 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20207G494 | List: |
| References | |
| NUDOCS 8808240133 | |
| Download: ML20207G496 (259) | |
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e ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 DOCKET NO. 50-327 (TVA-SQN-TS-88-20)
LIST OF AFFECTED PACES Unit 1 3/4 5-4 v.
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g.o EMEkGENCY CORE COOLING SYSTEMS /ECCS) .
'5URVEILLANCE REOUIREMENTS (Continued)
- b. At least once.per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution valuee increase-of-greatan_than or equal to 1". of tank volume by
,, verifying the baron concentration of the solution in the water-filled accumulator. .
- c. At leut once per 18 months by:
- 1. Verifying that each acednulater isolation valve closes automa-tically when the water level in the watar-filled accumulator is .
91.0 '/.h./:? 0;.; 10.f, inches aho've tha tank. vancor working line/ 4Me.
- d;
- : S7.1 15.5 i; h:; when corrected for the mass R32 of cover gas. -
- 2. Yerifying that the total dissolved nitrogen and air in the water-filled accumu'lator is less than 80 SCF per 1800 cubic Yeat of water (equivalent to 5 x 10-5 pounds nitrogen per pounds water). . .
- d. At least once per 5 years by removing the membrane installed between i the wa.ter-filled and nitrogen bearing accumulators and verifying that tne removed membrane bursts at a differential pressure of 40 + 10 ps1. . . . . _ . . . _ . _ . . . _ . , . . . . . . . . _ . . . . . . . . . . . .
- May 3,1963 ,
SEQUOYAH - UNIT.1 3/4 5-4 Amendment 28 1 - .
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ENCLOSURE 2 -
PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT I DOCKET NO. 50-327 i (TVA-SQN-TS-88-20)
DESCRIPTION AND JUSTIFICATION FOR REVISING UHI LEVEL SWITCH SETPOINTS AND TOLERANCES f
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r ENCLOSURE 2 DE3CRIPT10N OF CHANGE Tennessee Valley Authority proposes to modify the Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications to revise the upper head injection (UHI) level switch setpoint and tolerances of surveillance requirement (SR) 4.S.I.2.c.1. This change reflects the relatio;. ship between instrument-sensed dif ferential pressure, UHI water accumulator icvel, and delivered UHI water volume. A high differential pressure is sensed at the instrument when the accumulator level is low, which correlates to the maximum injected water volume. Likewise, a low differential pressure is sensed for high accumulator levels and a minimum injected water volume.
REASON FOR CHANCE Condition Adverse to Quality Report (CAQR) SQP871644 documents that the '
level switches and setpoints currently used for unit 1 could allow more than the analytical limit of 1,130.5 cubic feet of UHI water to be injected during a postulated accident. Two changes in the design and configuration of the UHI system were pursued to correct this potential problem. First, the minimum delivered UHI water volume was reduced f rom 900 cubic feet to 850 cubic feet. This change is supported by Westinghouse Electric Corporation evaluations described in an August 10, 1988 letter to TVA (included as attachment 1). Second, a new model of level switch is being installed in the UHI system. The new switches are essentially the same as tho6e presently used, except for their span.
Because of the span differences, the switches also have different accuracy characteristics. Demonstrated Accuracy Calculation 1-LS-87-21 determined a new setpoint and tolerances based on the new instrument characteristics. These new values are being incorporated into SR 4.5.1.2.c.1 to ensure that the delivered UHI water volumes are bounded -
by the volumes assumed in the large-break, loss of coolant accident (LOCA) analyses. This in turn ensures that the offsite doses from a postulated LOCA are bounded by the analyses of the Final Safety Analysis Report (FSAR), Section 15.5.
JUSTIFICATION FOR CHA60E Delivered UHI Water Volure The UH1 system is designed to passively supply additional inventory to the reactor core during the blowdown phase of a postulated LOCA. The UHI system is described in FSAR section 6.3.2. As described in FSAR section 15.4.1.1.4, a broad spectrum of LOCA analyses has been performed to evaluate UHI performance. The various UllI performance analyses are categorized by the assumed discharge coefficient (CD) of the break and the presence or lack of UH1 water mixing in the upper head region of the vessel (perfect and imperfect mixing, respectively).
The limiting case break in the Ult 1 Evaluation Model emergency core cooling system (ECCS) analysis presented in the original SQN FSAR was the discharge coefficient C p=0.6 double-ended, cold-leg gulliotine (DECLC) break with imperfect mixing of UHI water assumed in the vessel upper head. Compliance with regulatory limits was achieved for this case by
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reducing the allowable core peaking factor (Fq) from 2.32 to 2.237. ,
Minimizing the volume of UHI water delivered ' maximizes PCT for imperfect mixing UHI LOCA cases. The lower bound value for UHI water volume delivery established in the original FSAR C =0.6 D DECLC imperfect mixing case is 900 cubic feet. This value also was employed in the imperfect mixing casea of the 10-peteent steam generator tube plugging (SCTP) analysis performed in the 1982-83 timeframe.
A complete spectrum of perfect mixing cases was analyzed for the original SQN FSAR. The limiting case with perfect mixing of UHI water assumed in the vessel upper head was the CD=0.6 DECLC; the calculated peak clad temperature (PCT) for this case is 2,1A1 degrees Fahrenheit (F) at an Fq of 2.32 with a UHI-delivered water volume of 1,053 cubic feet.
Using sensitivities appropriate to UHI plant perfect mixing cases, tradeoffs have previously been made among various input assumptions to justify increasing the maximum allowable UHI-delivered water volume to 1,130.5 cubic feet. Increasing the value of UHI water delivered maximizes PCT for perfect mixing UHI LOCA analyses. With the present technical specification Fq of 2.237 in force, 1,130.5 cubic feet is a valid maximum delivered water volume for the SQN UHI system becauso it results in a PCT of 2,163 degrees F.
It should be noted that separate safety evaluations performed for SQN have considered the impacts on PCT of guide tube flexure failures, increased feedwater isolation valve stroke time, reduced safety injection flow from a failed residual heat removal pump miniflow, and thimble tube filling during core reflood. For the perfect mixing cases, these scenarios do not impact PCT; and 2,163 degrees F remains the limit *ag PCT for perfect "
mixing cases.
The CD =0.8 and CD=0.6 DECLC imperfect mixing cases from the 1982-83 10-percent SCTP analysis have been reviewed to assess the PCT impact of reducing the delivered UHI water volume to 850 cubic feet. The calculated PCTs for the C D=0.8 and Cp=0.6 DECLC cases that comprise the current licensing basis for SQN ars 2,111 degrees F and 2,113 degrees F, respectively. Reducing the UHI water delivery in an imperfect mixing case will reduce the cooling of the fuel as the upper head drains during blowdown. During the core reflood phase, this hotter fuel will then expel more injection water as entrained liquid, producing a degraded flooding rate. Existing SQN imperfect mixing cases performed for the FSAR identify the penalty in core fuel heatup associated with decreasing UHI water delivery to 850 cubic feet, which reduces core inlet velocity by 7 percent for the licensing basis imperfect mixing cases.
The impact of degraded flooding rates upon hot rod eniculated PCT has been determined by WREFLOOD/LOCTA sensitivity runs for each licensing basis imperfect mixing case. The 10-percent SGTp licensing basis imporfect mixing cases are acceptable at an 8SO-cubic-foot-delivered UH1 water volume because the degraded reflood penalty only increases calculated PCT as fallows:
CD=0.8 DECLC PCT = 2,151 degrees F Cp=0.6 DECLC PCT = 2,166 degroos F
The PCT penalties imposed upon the imperfect mLxing cases aro 20 degroos F for postulated guide tube flexure failures and 12 degroes F for thimblo tube filling durint, core reflood. Because the not PCT for the limiting imperfect mixing Cp=0.6 DECLC case becomes 2,166 degrees F +
20 degrees F + 12 degrees F = 2,198 degrees F, compliance with the regulatory limit is maintained, Both the perfect and imperfect mixing case of the SQN large-break LOCA analysis remain in compliance with 10 CFR 50.46 if the UHI water-deliveced volume is within the bounds of 850-1,130.5 cubic feet.
Cateulation of Level Switch setpoints As described in FSAR section 6.3.2, four automatic hydraulic isolation valves are used to isolate the UH1 accumulators from the reactor coolant
- system (RCS) af ter UHI has injected. These valves receive &utomatle closure signals from level switches on the UHI water accumulator. The level switch setpoints are selected to ensure that the delivered UHI water volune is within the limits described above.
Demonstrated Accuracy calculation 1-LS-87-21, included as attachment 2 generates the level switch setpoint and tolerances that ensure that the delivered UHI water volume is between 850 and 1,130.5 cuble feet. As seen on page 6 of the calculation, a tank lovel of 95.3 inches (above the working line) equates to a delivered volume of 850 cubic foot; and a tank 19 vel of 85.1 inches equates to a delivered volume of 1,130.5 cubic feet.
The calculation then continues to establish setpoint and tolerance between 95.3 and 85.1 inches. Pages 7 through 23A are a compliation of the various inaccuracies aJsociated with the level switchee, including drif t characteristics. The limiting inaccuracies of +3.29 inchos and
-6.83 inches are calculated on page 22. Because of the nature of the drif t characteristics, a curve-fit program was utilized to dotormino the optitsmi sotpoint for the level switches. As described on page 22 of the calculation, the optimum setpoint in calculated to be 92 inches. This yieldo limiting level switch setpoints of 95.29 inchos to 85.17 inches, which are within the analytical limits described abovo.
The tolerances used in the revised SR of +2.6/-5.8 inchas represent the normal accuracy of the icvel switches excluding process variables that aro ur. measurable at the time of calibration (soo pages 3 and 24).
As calculated on page 22 and shown on page 23, the accuracy characteristles of the level switches necessitate calibration at least evnry ACd days. This lovel swltch calibration is independent of the level switch / isolation valve functional responso Lost required by SR 4.5.1.2.c.1. As such, the levol switch calibrations wLil be scheduled and tracked independently. This will also allow for the extension of the calibration intervals based on evaluation of the new levol switch performance. The calibration ovaluations are in accordance with our previous commitment made in responso to URC Uulletin 86-02. TVA will continuo to inonitor level swltch performance through the normal reporting process.
i ATTAcitMENT 1
- Technical Specification Change 88-20 k'estinghouse Letter Dated August 10, 1988 (B20 880811 010)
F R 0 rt ECW 482 374 3282 (THU)es.tl.'88 13:35 No.14 PAGE 2 l
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Westinghouse PowerSystems Nuc' m h M g EMctric, Corporation - 875*$ N$da
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. August 10, 1988 i TVA-88-746 0 Trudel NS-OPLS-OPL II-88-523'.
i Hr.'P.lhPr'ojectEhgineer Sequoya t
Ref.1) TVA,RD #428873
' Tennessee Valley Authority 2)WG(0.00-42680 Sequoydh Nu'elear Power Plant , DSC-A P. O. 2000 So'ddyDaisyl,TN37379 ~
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- l } lTDiNESSEE VALLEY AUTHCftITY SEQUOYAH UNITS 1 & 2
' ' ECREASED UHI VOLUME DELIVERY SAFETY EVALUATION
! (SECL-88-410 & 417)
Dear Hr,
. Trudel:
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. In) resp lonse decreasingthe ,, tominirun your request,, attached is the cafety evaluation 850 cubioaddressing UNI voline delivery from 900 to feet. ..
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- . ' Mis safety,' evaluation is pro lvided in the following docts.ents:
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ITEM SECL-88-410 TITLE .-
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I, ' ShL-88-410 Minimtn Required UNI Volume (Non-IDCA Accidents) i
, 2 SECL-88-417 Safety Evaluation For a 50 Cubic Feet Decrelase In -
, ;the UHI Accumulator kliverable Water Voluge (LOCA,
,SOTR, Post-LOCA Long Tem Core Cooling anc lbt Lcg lSwitchover Accidents) '
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FROM E C ') 412 374 3202 /fHU)es.11.*$$ a3836 H0.14 PAGE 3 E*A, -
j 3 TVA-88-746i* * *-
NS-OP@0PL-88-52'4 .
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If you have any comments or questions, please contact the undersigned. l
,. l' Very truly yours, - -
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WESTINGHOUSE ELECTRIC CORMRATION I
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' , . d. Lordi, Manager -
ESSDProjects
! , Mid-South Area L. V. Tomasic/tu
. At' tach 6ent i j l co': D. W. Wilson i ' R. W. Headows I
R. C.' Weir l .! 4
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' J. A.! Vogel ,
A R. G.! Davis
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SECL NO8_Er0L-88-417 Customer Reference No(s).
Westinghouse Ref. No. -
WEETINGHOUSE NUCLEAR SAFETY EVALUATION CHECK LIST
- 1) NUCLEAR PLANT (S) SEQUOYAH UNITS 1 AND 2 (TVA/ TEN)
- 2) CHECK LIST APPLICABLE TO SAFETY FVALUATION FOR A 50 CU.FT. DECREASE IN (subject of Change) THE UHI ACCUMULATOR DELIVERABLE WATER VOIfSiE_'~
- 3) The written safety evaluation of the revised procedure, design change or modification required by 10CFR50.59 has been prepared to the extent required and is attached. If a safety evaluation is not required'or is incomplete for any reason, explain on Page 2. ,.
Parts A and B of this Safety Evaluation Check List are to be completed only on the basis of the safety evaluation performed.
CHEbK LIST - PART A
, (3.1) Yes X No A change to the plant as dercribed in the FSAR?
(3.2) Yes No X A change to procedures as described in the FSAR?
(3.3) Yes No X A test or experiment not described in the FSAR?
(3.4) Yad X No A change to the plant technical specifications -
(Appendix A to the Operating License) ?
- 4) CHECK LIST - PART B (Justification for Part B answers must be ' "
included on Page 2.) ,
(4.1) Yes No X Will the probability of an accident previously evaluated in the FSAR be increased?
(4.2) Yes No X Will the consequences of an accident previously evaluated in the FSAR be increased?
, (4.3) Yes No X May the possibility of an accident which is different than any already evaluated in the FSAR be created?
(4.4) Yes No X Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
(4.5) Yes No X Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
(4.6) Yes No- X May the possibility of a malfunction of equipment important to safety different than any already evaluated'in the FSAR be created?
l (4.7) Yes- No X Will the margin of safety as defined in the bases j to any techn:. cal specification be reduced?
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SECL-88-417 If the answers to any of the above questions are unknown, indicate under 5) REMARXS and explain below.
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- - - If the answer to any of the above questions in 4) cannot be answered in the negative, based on written safety evaluation, the change cannot be approved without an application for license amendment submitted to NRC pursuant to 10CFR50.90. -
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- 5) REMAR.VJ5:
The following summarizes the justification upon the written safety evaluation, (1) for answers given in Part 3 of the Safety Evaluation Check List:
See the attachment (1) Reference to document (s) containing written safety evaluation:
NS-SAT-SAI-88-310 FOR FSAR UPDATE Section: Page(s):- Table (s) : 15. 4.1-9 _
Reason for/ Description of Change:
Chance Table lh 4.1-9 for UHI Accumulator water volume delivered to reflect 850 cu.rt. minimum volume evaluated in this safety evaluation and the associated footnoto.
- 6) APPROVAL LADDER (6.1) Prepa: cd by (Nuc1 car Safety): v t/M. ISAI) Da' e : 8 O!8e Reviewed by (Nuclear Safety)! N N A M N # (SAI) Date: Nh/l7 (6.2) Coordinated with Engineer (s)*' X U-L A fSATI) Date:_Y/67eES Coordinated with Engineer (s): MME/ (TSA) _Date: T-M
- 88 Coordinated with Engint'r(s): h M (COA) _ _ Date : Ph*/88 Coordinated with Engineer (s)N kd ' d ud W SAI) Date: bO- 65 (6.3) Coordinating Group Manager (s) 3 E (SATI)-Date:_ O,/IDI8 t#J[
Coordinating Group Manager (s): d'Ib h M (TSA) Date: DCdN Coordinating Group Manager (s): //8Yhd (COA) Date:_ fM*N _ __
(6.4) Nuclear Safety Group Manager: %bM 'ISAI) _Date: _ $//d[88 __
PAGE 2 OF 2
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WESTIN HOUSE PR3PRIETARY CLASS 2 ~
SECL-88-417 ,
SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A DECREASE IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUME BACKGROUND In order to accommodate relaxed UNI system tolerances at Sequoyah Units 1 and 2, Tennessee Valley Authority (TVA) has requested a widened set cf limits on the allowable UHI water delivered volume. Specifically, a decrease in the required minimum UHI delivered water volume considering uncertainty from 900 to 850 ft3 has been requested. The following presents the summaries of safety evaluations performed to assess tho effect of a 50 ft3 reduction in the minimum UHI delivered water volume on the LOCA-related analyses performed by Westinghouse for Sequoyah Units 1 and 2. .
3AS.ES.
LAF.GE BREAK LOCA - FSAR CHAPTER 15.4.1 In order to accommodate relaxed UHI system tolerances at Sequoyah Units 1 and 2, TVA has requested a widuned set of limits on the allowable UHI water delivered volume. To this end, the Sequoyah Large Break ECCS performance analysis has been reviewed to justify a decrease in the . . .
required 3 r.inimum UHI delivered water volume considering uncertainty to 850 ft .
The limiting case break in the UHI Evaluation Model ECCS analysis presented in the original sequoyah FSAR was the C =0.6 p DECLG break with imperfect mixing of UHI water assumed in the vessel upper head.
Compliance with regulatory limits was achieved for this case by reducing the allowable core peaking factor (Fg ) from 2.32 to 2.237.
Minimizing the volume of UHI water delivered is conservative for imperfect mixing UHI LOCA cases. The lower bound value for UHI water '
volume delivery established in the original FSAR C =0.6 D DECLG imperfect mixing case is 900 ft 3. This value also was employed in i
the imperfect mixing cases of the 10% steam generator tube plugging (SGTP) analysis performed in the 1982-83 timeframe and reported in i Reference 1.
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WESTINGHOUSE PROPRIETARY CLASS 2 SECL-88-417 .
SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A DECREASE IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUME A complete spectrum of perfect mixing cases was analyzed for the original Sequoyah FSAR. The limiting case with, perfect mixinq of UHI water assumed in the vessel upper head was the C =0.6 D DECLG; the calculated pcak clad temperature (PCT) for this case is 2111*F at an Fg of 2.32 wit h a UNI delivered water volume of 1053 ft3 . Using sensitivitie" :.)propriate to UH2 plant perfect mixing cases, trade-offs have previsusly been made among various input assumptions to justify increasingthemaximumallowableUHIdeliveredwatervolumeto 1130.5 ft . Maximizing the value of UHI water delivered is conservative for perfect mixing UHI LOCA anal ses. With a Technical Specification Fg of 2.237 in force, 1130.5 ft is a valid maximum delivered water volume for the Sequoyah UHI system the calculated PCT of the limiting C =0.6p DECI3 perfect mixing case at 1130.5 ft3 UHI water delivery is 2163*F.
The Cg=0.8 and Co=0.6 DECLG imperfect mixing casan from the 1982-83 104 SGTP analysis have been reviswed to assess t' ' ?? Impact of reducing the delivered UHI water volume to 850 1. . The calculated Reference 1 PCTs for the C =0.8 p and C =0.6 D DECLC cases which comprise the current licensing basis for Sequoyah are 2111'T and 2113*F, respectively. Reducing the UHI water delivery in an imperfect ..
mixing case will reduce the cooling of the fuel as the upper head drains during blowdown. Daring the core reflood phase, this hotter fuel will cause the expulsion of more injection water as entrained liquid, producing a degraded flooding rate. Existing Sequoyah imperfect mixing cases define the penalty in core fuel heat-up associated with decreasing UHI water delivery to 850 ft3 . Expressed as a flooding rate penalty, reducing UHI water delivery to 850 ft3 reduces core inlet velocity by 7% for the licensing basis imperfect mixing cases.
The effect of degraded flooding rates upon hot rod calculated PCT has been determined by WREFLOOD/LOCTA sensitivity runs. Expressed as an impe.rtect mixing cese PCT sensitivity relationship, a one ft3 decrease in UHI water delivery results in a l'F increase in calculated PCT. The 10% SGTP licensing basis imperfect mixing cases are ceceptable at an 850 ft3 delivered UHI water volume because the degraded reflood penalty only increases calculated PCT as followat
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I WESTINGHOUSE PR3PRIETARY CLASS 2
'. SECL-88-417 SAFETY EVALUATION FOR SEQUoYAH UNITS 1 AND 2 FOR A DECREASE IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUME ;
l C =0.8 DEC V, D PCT =2151'F C =0.6 DECV, D PCT =2166'T i
A separate safety evaluatfon performed for Sequoyah during November, 1986 considered the impact of a possible but unlikely scenario of guide tube flexure failures. The PCT penalties imposed upon perfect and l imperfect mixing cases under this scenario are O'T and 20*F, j respectively. The not PCT for the limiting imperfect mixing C D=0.6 ,
DECV, case therefore becomes 2166*F + 20*F = 2186'T ,
when postulated guide tube flexure failures are considered.
A further phenomenon which could impact the Sequoyah Plant calculated PCT values is filling of the instrumentation thimbles in the core during the reflood phase of a large break LOCA event. The thimble a volume which must be filled has not been explicitly treated in the :
l Sequoyah large break IACA analyses. Westinghouse had initially l 4
assumed that the thimble plugging devices would be sufficiently tight j to prevent the ingress of water into thimbles during reflood. However, ~
it was later identified that the plug clearances were sufficiently 1arge and the flows were sufficiently low during reflood to allow the thimbles to fill with water even with plugs installed. The impact which thimble filling will exert on the calculated PCT values has been assessed for Sequoyah, and the appropriate PCT penalties to be imposed l on the perfect and imperfect mixing cases are established as O'F and l 12'F. The not calculated PCT for the limiting imperfect mixing case i
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I 2186'T + 12'T = 2198'F l
so compliance with the regulatory limit is maintained. '
l l Both the perfect and imperfect mixing cases of the sequoyah large break 1 I4CA analysis remain in compliance with 10CFR50.46 if the UHI water
) delivered volume is set within the bounds 850 - 1130.5 ft 3 , with l l calculated PCT values of 2163*F and 2198'T respectively.
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WESTINGHOUSE PROPRIETARY CLASS 2 '
,, SECL-88-417 ,
SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A DECREASE
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IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUME SMALL BREAK LOCA - FSAR CHAPTER 15'.3.1 The current FSAR small break LOCA analysis for Sequoyah Units 1 and 2, was performed using the KRC-approved UMI Small Break LOCA ECCS Evaluation Model (Reference 2), which resulted in the most limiting FCT of 1486*F for a 8 inch equivalent diameter break (Reference 1). A ~
safety evaluation which considered the effect of charging /SI pump flow shortfall increased this result by 200'F, resulting in an overall licensing basis PCT of 1686'F.
The reason the 8 inch break is limiting and exhibits a low PCT value is because UHI provides enhanced safety injection capability relative to standard plant systems. Typically, 4 loop plants demonstrate the 3 or 4 inch break to be limiting at a higher calculated PCT than the Sequoyah value. Locause UHI injection is inherently beneficial for the evaluation model small break LOCA event, the FSAR analysis has assumed a conservativa value which is less than 850 ft3 for the minimum deliverable UHI water volume. Therefore, a decrease in the deliverable UNI water volume to 850 ft3 does not effect the FSAR small break LOCA results.
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ROD EJECTION MASS AND ENERGY RELEASE FOR DOSE CALCULATION - FSAR 1 CHAPTER 15.5.7 AND TABLE 15.5.7-1 i
similar to a small break LOCA, a rod ejection accident analysis is
, performed to provide primary and secondary mass and energy releases for l use in computing the radiological consequences of a rod ejection i Cccident as per Regulatory Guide 1.77. This analysis is a long term transient performed specifically to determine primary RCS mass and
- . onergy releases through the upper head break and secondary mass and
- cnergy releases via the secondary code safety valves. These mass and energy releases are then used to compute the radiological consequences cf a rod ejection accident. A reduction in the minimum deliverable UHI l water volume will result in an increase in the mass and energy releases of the primary coolant and a decrease in the secondary naas and energy c releases. However, for the Sequoyah Units, a conservative assumption was used regarding the primary mass and energy releases such that the net effect of a 50 ft3 reduction in the minimum deliverable UHI water Page 4 M
WESTINfMGUSE PROPRIETARY CLASS 2 SECL-88-417 ,
SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A DECREASE IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUME volume is a reduction in secondary mass and energy releases. Since a not reduction in necondary mass and energy releases would slightly reduce the computed doses, the current doses as reported in Table 15.5.7-2 of Reference 1 remain bounding.
CONTAINMENT INTEGRITY -(SHORT AND LONG TERM MASS AND ENERGY RELEASE)
FSAR CHAPTER 6.2 The containment analyses for the Seqcoyah Units are described in FSAR sections 6.2.1.3.3, 6.2.1.3.4, 6.2.1.3.6. and 6.2.1.3.11. These sections consider, respectively, containment pcessure transients for long and short term analyses, mass and energy releases for postulated LOCAs and containment subcompartments, and containment maximum temperature response following a main steamline break.
For the containment subcompartment analyses and the short term mass and energy release analyses no modelling of the UHI accumulator is included. Therefore, a 50 ft 3 reduction in the minimum deliverable water volume to 850 ft3 will have no effect on the current analyses.
The long term mass and energy release analysis is performed to
' calculate the maximum available releases which can enter the containment following a LOCA. Similar to the subcompartment analyses, no modelling of the UHI accumulator is included therefore, a minimum deliverable UHI water volume of 850 ft3 will not effect the long term mass and energy releases to containment.
'The evaluation for main steamline break concluded that there would be no change in the mass and energy releases to the containment for a reduction in minimum deliverable UHI water to less than 850 ft3 .
Therefore, the containment maximum temperature response following a main steamline break will not be effected. Hence, based upon the above information, the results of the current Chapter 6.2 Containment Integrity analyses continue to be valid.
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WESTINGHOUSE PROPRIETARY CLASS 2 '
... SECL-88-417 ,
SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A DECREASE IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUNE 4
STEAM GENERATOR TUBE RUPTURE - FSAR CHAPTER 15.4.3 ThesteamgeneratortuberuptureeventasanalykedintheSequoyahFSAR equilibrates in pressure;at a value which greatly exceeds the maximum l UHI nitrogen gas pressure of 1300 psia. Since the UHI system is not l actuated during a design basis steam generator tube rupture event, any !
change in UNI delivered water volume upon actuation is irrelevant to '
l this analysis.
BIOUDOWN REACTOR VESSEL AND LOOP FORCES - FSAR CHAPTER 3.9 The blowdown hydraulic forcing functions resulting from a loss of l
coolant accident are considered in Section 3.9.1.5 (Analysis Methods l
Under LOCA Loadings), and Section 3.9.3.5 (Blowdown Forces Due to Cold and Hot Leg Break) of Volume 4 of the Sequoyah Units 1 and 2 FSAR. The decrease in the UHI accumulator water volume will have no effect on the LOCA blowdown hydraulic loads since the maximum loads are generated within the first few tenths of a second after break initiation. For this reason the ECCS, including the UHI accumulator, is not considered in the LOCA hydraulic forces modeling and thus the decrease in the UHI "
accumulator water volume will have no effect on the results of the LOCA i hydraulic forces calculations.
POST LOCA LONGTERM CORE COOLING SUBCRITICALITY REQUIREMENT; i i
WESTINGHOUSE LICENSING POSITION - FSAR CHAPTER 15.4.1 4 The Westinghouse licensing position for satisfying the requirements of 10CFR Part 50 Section 50.46 Paragraph (b) Item (5) "Long Tarn cooling" is defined in WCAP-833) (Reference 4,'pp. 4-22). The Westinghouco commitment is that the reactor will remain shutdown by borated ECCS water residing in the sump following a LOCA (Reference 5). Since '
credit for the control rods is not taken for large break LOCA, the borated ECCS water provided by the RWST and Accumulators nust have a concentration that, when mixed with other sources of water, will result in the reactor core remaining suberitical assuming all control rods out (ARO). The decrease in the minimum UHI water delivered volume of 50 ft 3 results in a reduction of approximately 1 ppm in the mixed Page 6
. i Od
,we--, --- - -, w e ,- ,--,,-,----,,-------w, , . , . , - - - - - - - . . , - , . , , - - - - - -
WESTINGHOUSE PROPRIETARY CLASS 2 SECL-88-417 .
SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A DECREASE IN THE UNI ACCUMULATOR DELIVERABLE WATER VOLUME mean sump boron concentration.
This reduction in the mixed mean sump boron concentration can be acconmadated within the existing margin for the current cycles of operation for Sequoyah Units 1 and 2.
i HOT LEG SWITCHOVER TO PREVENT POTENTIAL BORON PRECIPITATION - FSAR CHAPTER 6.3.2.2 The hot leg recirculation switchovar time analysis has been performed for Sequoyah Units 1 and 2 to determine the time following a LOCA that hot leg recirculation should be initiated. This analysis addresses the concern of bnron precipitation in the reactor vessel following a LOCA and has been performed to support the decrease of 50 cubic feet in the minimum UNI water volume to 850 cubic feet.
During a large break LOCA the plant switches to cold leg recirculation after the RWST switchover setpoint has been reached. If the break is in the cold leg there is a concern that thu cold leg injection water will f ail to artablish flow through the core. Safety injection entering the Arakan . loop alla spill out the break, while SI entering the intact cold legs will circulate around the downcomer and out the break. With no flow path established through the core the fluid in the ..
core remains stagnant. As steam is produced in the core from decay heat, the boron associated with the steam will remain in the vessel.
Thus, as water is boiled off with no circulation present in the core, the boric acid concentration increases. The boron concentration in the vessel vill increase until the solubility limit of the boric acid colution is reached, at which time boron will begin te precipitate. As the boron precipitaten, it may plate out on the fuel rods, which would cdversely affect their heat transfer characteristics.
The purpose of the hot leg recirculation switchover time analysis is to provide the tima at which hot leg recirculation must be established to prevent boron precipitation in the core.
An evaluation has been performed to determine the effect of the reduction the hot legofrecirculation the deliverable volume oftime.
switchover water in the UHI accumulator on This evaluation concluded that the time for hot leg switchover contained in the FSAR (15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />) is bounding. Therefore, the value in the FSAR need not be changed.
Page 7
~
WESTINGHOUSE PROPRIETARY CLASS 2
.. SECL-86-417 ,
SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A D"CREASE IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUME i CONCLUSIONS j
The effect on the LOCA related analyses for Sequoyah Units 1 snd 2 of a 1
50 ft3 reduction in the qinimum deliverable UNI water volume to 850 ft3 has been evaluated by Westinghouse. The potential effect of the change on the FSAR analysis results for each of the LOCA-relatnd ,
accidents was evaluated, and it was shown in all cases that the effect
)
' of the change did not result in exceeding any design or Regulatory limit.
Therefore, it is be concluded that the proposed decrease in the minimum deliverable UNI water to 850 ft3 for Sequoyah Units 1 and 2 is acceptable from the standpoint of the FSAR accident analyo.as discussed in this safety evaluation. Table 1 lists the effect of the change on the various accidents which are discussed here.
REFERENCES
- 1. Sequoyah Station (TVA/ TEN) FSAR - Updated 6/16/86 Amendment 3.
1
) (Non-Propriatary), Young, M.Y., et. al., "Westinghouse - . .
Emergency Core Cooling System Evaluation Model Application to i
Plants Equipped with Upper Head Injection", January 1975.
- 3. WCAP-9220-P-A i (Proprietary), WCAP-9221 (Non-Proprietary),
Eicheldinger, C., "Westinghouse ECCS Evaluation Model - 1981 Version", Revision 1, 1981.
j 4. WCAP-8339 (Non-Proprietary), Bordelon, F.M., et. al., -
1 "Westinghouse ECCS Evaluation Model - Summary", June 1974.
)
i 5. "Westinghouse Technical Bulletin NSID-TB-86-08, "Post-LOCA
! Long-Term Cooling: Boron Requirements", October 31, 1986.
I I
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i Page 8 l
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WESTINGHOUSE PROPRIETARY CLASS 2 SECL-88-417 -
SAFETY EVALUATION FOR SEQUoYAH UNITS 1 AND 2 FOR A DECREASE
-~ ~
IN THE UHI ACCUMUIATOR DELIVERABLE WATER VOLUME TABLE 1
@ CHAPTER ACCIDENT DESCRIPTION EFFECT ON RESUI;TS, 15.4.1 Large Break'LOCA
{eakcladtengerature w$k"$'kn$R maknta ad.
0.4 {1-kf 15.3.1 Small Break LOCA No effect on the FSAR
$$gdoxkNtgnormax onsf hafm$$ !dding yn hy rgon
$$ChR50N6b(kb$fma$n$aYneh.
15.5.7 Rod Ejection Accident Noadverseeffectonmgsand
$*b(0ChR$$$11$$m$ts" t
maintained.
6.2 Containment Integrity No adve'rse effect on short (Short and Long Term Mass and Energy Release) or lona tern mass and energy releas4s.
N$n[ta;, neb.onY$$$ts$bc! y 15.4.3 Steam Generator Tube No adverse effect on primary-Rupture to-a g g arg mgss f$m$ts maYntaknch g e g
3.9 Blowdows
Reactor Vessel No adverse effect on the and Loop Forces LOCA hydraulic forcing functions.
15.4.1 Post-LOCA Longterm Core 1 ppm decrease in the Cooling gott-LOCA g p boron v$h$ChR50'46bk$f makntakned.
6.3.2.2 Hot Le Switchover to FSAR nout-LOQA hot leg Preven Potential Boron switchove Precip tation bounding.r tine remains Page 9 e
O
,,F40} icy 41: 3*4 3284 (N4H)08.09.'tt 1815F HQ.31 pegg g i .
SECL NO. SEtt ta 410 Customer Reference No(s).
- Recuest from TVA-Westinghouse Refehace No(s).
TVA 87 896
. WESTINGHOUSE NUCLEAR SAFETY'.
.'SAF,ETY EVALUATION CHECX LIST
, 1.)NUCLEARPLANT(S): Seouova'h Unit 1 and 2 2c)FUBJECT(TITLE): , Minimum Reouired UHI_Volure
- m. . _ -
v 9, s 3.) The written safety evaluation of the revised procedure, design change or.
modification required by 10CFR50.59(b) has been prepared to the extent
- .
- requjred and is attached.. If a safety evaluation is not required or is ,
inco plate for any. reason, explain on Page 2.
.w .
.s.
Part on t eAbasis and.B of of thethis.
sa. Safety Evaluation Check List are to be completed only F fety' evaluation performed.
{'. CHEC LIST PART A 'l'CFR50.59(a) 0 (1) .
$' ' [. p Yes 1 No _ A change to the plant as described in the FSAR?
I( . p Yes- No 1 No 1 A change to procedures as described in the f5AR?
(J I Yes-Yes 1 A test or experiment not described in the FSAR?
_. No 1 A change to the plant technical specifications (SeeNoteonPage2) -
- 4) CHECK, LIST - must PART be incBa - 10CFR50.59(lu)de(d)on(Justification 2
Page2.) -
for (4.1) Yes No 1 Will the probability of an accident previously (4.2 l evaluated in the FSAR be increased?
Yes _. No 1 Will the consequences of an accident previously ,
(4.3) Yes evaluated in the FSAR be increased? !
No 1 May the possibility of an accident which is .
. different than any already evaluated in the (4.4 ) Yes FSAR be creattd?
No 1 Will the probability of a malfunction of
- vquipment important to safety previously (4.5 1 Yes evaluated in the FSAR be increased?
No 1 Will the consequences of a malfunction of equipment important to safety previously .
(4.6l Yes evaluated in the FSAR be increased?
No 1 May the possibility of a malfunction of equipment ireportant to safety different than any (4.7) Yes already evaluated in the FSAR be created?
i No 1 W111 the cargin of safety as described in the bases to any technical specification be reduced?
.a -
Page 1 of 5 '
-f '
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- FROM ECW 412 394 32's'2 , ( T HU)e s. ll . ' 8 9 13136
' MO.14 CAGE 4
] .-
' '.14
., l.
, ,,- )'*<i .
...y.,
. SECL 88 410, .
NOTES: .
t i ! ' '
.."1 '
. If the. answars to. any of th' -
5.) REMAPJ($ and explain beloW.s abovA questions are unknown, indicated un I
If the answer to any of the above questions in Part A cannotbe'ansstredinthenegaive,basedonwrittensa(3'4)orPart5 f ty evaluation, the change review would requtr an application for license amendment as requiredfy10CFR50.59(c)a,nd ub.mitted to ths NRC pursuant to 10CFR50.90, 5.)REMARXS: 1 The following'sumarizes the justification upon the written safety evaluatioh (1) fcr answers give'n in Part A (3.4) a:id Part B of this $ECL i' l Please ;
see the; attached evaluatl ion
- l i
1: i, .
(1) Reference to do,cument(s) containing written safety evaluations (
~
, { FOR FSAR UPDATE
' Sections;- I Page (s):---
(
Table (s) .
Figure (s):-
- Reason fo'r/ Des lcription of Change .
i* 1 1 1 o
fected by this evaluation.
[koHonLOCAF5ARsectionsarea
[
l* I 5 4 ,
3AFETY EVALUATION APPROYAL LADDER: - '
l Prepared by (Nuclear safety):I. MM I Date:-(!4
}Coord'inatedwnhEngineer(s):. . O A ce G 4- Date: 1/1/f Coordinati,'ngGoupManager(s): 1 M. Date -
- Nuclear Sa'fety' ;
Group Manager: -- M / J M A' d Dater /
i L.
j Page 2 of 5 -
1 I 1
i !
,i I
i
,seon gu 4i: s4 3:s4 <noioos.oe.'es 14 se no.2: Paar 4 I .
SECD 88-410 e .
SAITH LVALDATI0tt MntDLM RD;tJIFID QU VOLD2 9
FCR SD@YM{ UTITS 'l NiD 2 BAC2 G C W D:
Tabl, 15.4.1-9 "Plant Parareters used in loCA Analysis" of the Segacyah
,. thite the t 1 ard 2 TSAR specifies that the mininxn volmea of water delivered by '
been'yper Head Injecticg Accurulator for kttich the IccA transients have anal ed is 900 ft . Recently, TVA requested that a Safety Evalizati be perfezwed khich assesses the arount by which this value can be decreased while still satisfying the current licensirq basis IDCA and Nc MDCA analyses.
We purpose of this evaluation is to determine the mxinrn'a:!eunt by khich -
the yolu:e of the un acc2mlator can be decreased without having an '
irpact on the Segacryah Units 1 ard 2 licensirn basis Non-Ir/.A safety -
analyses. .
, 1.VALATIdh i i
Re peqacyah Units 1'ard 2 Liter Head Injection systems each censist of an accu;a11ator prescurized to between 1200 and 1300 pela khich prwides a f1ci/ of borated vatar directly into the uppr head khcn the reactor '
cxc1l ant pressure da:reases bolew the accumulator pressure. A r Wiev of the peqacyah licensity basis non-ItcA transients shcws that the LMI syste:n is only redellcd ard actuated in the follcwing stca:nline break amlyscs: ,,
I o Steamline Rrvak Miss/EnertJy Falcaco Inside Containrent (ITSAR Section 6.2.1.3) o Steamlira Drcak Core Responce (FSAR Sections 15.2.13 ard 15.4.2.1) '
I In oltler to detamird the minin2n volmo of deliverable water raded in the pII acetrallator so as not to have any irpet on the provicusly
' rent,ioncd dar amlyses, the am:unt of water actually injected by the ut! -
otAy' the transients was dotemined. Because the flow frcn the LWI is furction of the difforcrco in pressure betwoon the LHI accrulator ed the reactor coolant systcr4 the arount of water injected into the RCS by the LMI is raxinized in the stcanlino rupture event khich causes the -
RCS to depressurito the rect.
l ,
'Ibe evaluations khicN vure perfor:xd in order to detomino the irpet of 1cuc' ring the minirtra arcunt of water khich ray to delivertd by the utI are ,
se:srized en the follcuirrJ pges.
, Page 3 of 5 e
9 g Se g 4
paeg ,sev 4 : U4 *:8d snomios.oJ.'se istS9 H0 21 Past 3
, SEC!r48-410
,1 .
(
8 r
l~
I Stea-dine Dunhun hasanerw/ Rein $ne Inalde contaiment ji (MAR Section 6.2.1.M - !
I J r f
In orl der to detarz.ine if the minima volume o't deliverable un coald be decreased without impactig the mas / energy releases frca a stea611ne break inside contairment anal casen of this transient was performed yses, a ruvioW of the most limitirq f
. t t
' It was determined that a value less than 900 cubic feet of water would be f inje tad by.the UG durire the transient. he current analysis could !
support a enhaction of the minima deliverable water frca 900 cubic feet -
to 694 aabic feet. .
In sens mapport of this reduction, it should be noted that prwious relea$tivity studies have ahwn that the steadine break mass / energy
'[ !
( ses are insensitive to dhages in the amount of water injected by the !
UKI.l In fact, analyse's Wich have been perfomed to styport remwal of ,
. l j
the 1lHI in plants similar'to the Sequeyah units have shown that the ocrplete removal of the UC system has an insignificant inpact on the ,
l naas/ energy releases obtained. ,
i 3'
s+==-11ne Ruoture cere Wa IFsAR sections 15.2.n and is.4.2.1) l l
1 2e steamline break ekses Wich vers analyzed for Sections 15.2.13 and * ;
) 15.412.1 of the Sequoyah fur are listed belw .
1 1. Main staan11ne depressurization with offsite power available (for ,
l .
uniform and non-unifom . -
credible breaks). ,, ., ;
! +2. Main staan11ne rupture with offeita power availabit (for amptures upstream and. dwnstream of the steamline f1w restrictor). '
f t
1 l 3 d
I. Main staamline rupture without offsite power available (for tupturws upstrsam ard do nstream of the steamline flew f
i restrictor) . - .
} A reylew of these events showed that the rupture of a min steam pipe -
upstream of the flow restrictor with offsite pp'er available caused the l
- greatest WB depressurizaticri of the RCS and also prwided the most limitiM (
the ts. For this case, the a. cunt of water injected the u(I into
} l l ninihan required m.munt of 900 ftwas conservatively calculgted and detemincd to be esa it j and less than that injected durig - !
the ertae.line break mass / energy release insido contaimant analysis.
) -
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FR0;; gcu 41; IN **6*
sN0H)08.04.'48 19808 H0.21 Pagg 6 SECIr88-410 i
It is appurnt tJut dannasiry W'a. cant of water which can be delivered i
by the WI to the value governed by the aralysis discuuod above will have ro irpect en the stacnline break core response results ard the conclusions of the Ts.M for this transient will re ain valid.
catcwsIcts: ,
l . . .
Based upon the ary: en6s pasanted alwe, it can be oorcluded that the .
- taction of the mini:3.:n a cunt of water khich can be delivered b to a'value agaal to or grestar than 606 cubic ft will have no i@yact theenLHI the fass/anargy releasse or the staa.m.line break core . Thus, the conclusions presented in the Segaoyah TSAR for these yces f.n Section 6.2.1.3 and in Sections 15.2.13 and 15 4.2.1, respectisely, will remain valid
.s .
t t
t.
F Pago 5 of S
. ;i.. _ . -
E ATTACitMENT 2 Technical SpecificatLon Change 88-20 Detnonstrated Accuracy calculation 1-LS-87 21 (B25 880812 501) s se I
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TVA 10697 (DNE-0A-6-86)~
OslE CALCULAll0NS a ~
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/-t S -W7. '21 reparing Organization . i So N F / I S' 2. !i (fol Branch /Projectidentifiers
_f EEB-18C -
l key NOUNS (Consult RIMS Descriptors List) l 18C, INSTR, CAllBRAil0N,~5ETPolNT, ACCURACY
_. ti (Each time these calculatjons are issued, preparers must ensure that the
!i l
I~I T"D D l original (RO) RIMS accession nmoer is filled in. il l jRev (for RIMS' use) I i rims accession nmeer j I i I l
lApplicabitDesignDocment(s) 1 R0 i WO4/5606% 1 84'3 ,070 dor / God I l
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lSARSection(s) l UNID Systants) l l N /A l l I v/d l R __! 1 l Revision 0 __Ff#-N- RS ) R2 i R3 ISafety-related? Yes ( W" ho()
lECN ho. (or Indicate hot Applicable)l Dc426cBI 1 lStatenent of Problem l L6?s9 I A r, a CG I l
l Prepared l
$f.MgJd l
l l Determine the a: curacy of the subject l k A CA AICn if. :.6 l l 1 instrument loop (s) and der:enstrate that l Checked R /b 4AB4ETF l lgg l l the accuracy is adequate for the intended l l E.J. e3 % F
- I I lR; viewed \ purpose. Primary elsnents are located in '
l m4B / J. B. h'ursod l @M. l l l e envi_rorrnenL ITeceuL i 1 l Subject devices / /are / not part l
l Approved l l l l of PAM.
I* O' Nur*#N l l- h.Llk,llk I l l
l lDate l l 47-?? Iltyg(h Il I l l l
_l C'USE FORM l List all pages addedl #7*" ,3' TVA10534lbythisrevision l l l l
I . -, . u l I l llFMORE l List all pages deleted l W^a4_. ! l l
l SPACE lbythisrevision iis.ed. t , t3 Mll l
l I \
lREGUIRED l List all pages changed % * .r2 6,[ l l
l lby this revision 7N',N'I,Ydk l
-l l l l
l ABSTRACT [lhese calculations contain an unver'ified assumtion(s) that mustYes be( )verified later.
No % ) l l Calculations were performed to determine the accuracy of the subject instrwent loop (s). The determined / l
- l accuracies were ccr@ared to the required accuracies, setpoints, safety limits and/or operating limits and l
l the accuracy for the loop (s) listed below were dctnonstrated to be acceptable for the intended , fun l l the instrment loop (s). This calculation applies to the instrment loop (s) listed below:
l Is2-Ls- %i- 21, t , 2. - L. S 22, I, 2 - L s - L'7 2 3 , 1/2. - d. t 7- '2.@
l l rsa % eunn ec p]AL}L]_ .
P l
1 E It. -? V NlI l 1 l 1 1 I I I I l l 1 1 I I
... C i l % J( ) Microfilm and store calculations in RIMS Service Center Microf}lm and destroy. ()
l l ( ) Microfilm and return calculations to: +0 "u"= l cc: RIMS, SL 26 C.K Address: W8 Bill C-K l l DNEl - 254af I
l l
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- 57 1
' vA T tor 3 HONE 4 A6) 'W a 4
NE CALCULATIONS
$' $70d TITLE DEMONSTRATED ACCURACY CALCULATION PLANT / UNIT PHiPAHING ORGANIZATION
' \ l - l S - 8 *7- 21 So , ,p//v2 KEY NOUNS (Consuit BlMS DESCP.IPTORS LIST)
(. . )i El.' D- 16 C , I6C. INST 1. dALIBRAYION,'SETPOINT. ACC11 RACY BR ANCH/PROJEC7 IDENTIFIERS Eacti time ttiese calcuktions are samed, preparars must ortsure that the oreginal IRO) RIMS eccession
~
nutnbet is fil!*d ih.
Rev (for RIMS'uta
{g 7 m RIMS acceuion numt er 976V/c D 654 W D.2 m ni,n, ant
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UNIOSJYTE M(S)
/V/4 R 2. t Revision 0 ECN No. for indecete Not Appl + cable)
R1 'fC n Safety 4elat ed ?
Yes O No O f, / D e.R pf/p L. 635 9' NA i2 as us/g(>( p Statement of Problem Prepared A.9 "'^' &u R
- y. chudjcos Determine the ac.:uracy of the
'% /bk.ClQjkc h e{' subiect instrument loop (s) and Check ed n '?MT f.6 y demonstrate that the accuracy is
. .. .. TJ /.ru y 4 / '/.dd - adequate for the intended purpose.
/ . .u fD LU k0
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( List all pages added g a y by this revision.
I. f List all pages deleted lh o FEE ~ EeV e., c (J{
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l
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YS R CornPLIr\Md, fry $/f;l{t(}(,. .( ;g ,
l6' lhese calculations contain an unverified assumption (s) '
ttwt must be verif,od latar. Yes O Nog O OM Ob ' IN g '" ' R d' k -
f("6fN-
$cc 2 3 Q)
.p @
Calculations were performed to determine the accuracy of the subject instrument loop (s).
The determined accuracies were compared to the required accuracies, setpoints, safety limits and/or operating limits and the accuracy for the loop (s) listed below were demonstrated to be acceptable for the intended function of the instrument loop (s).
This calcularion applies to the instrument loop (s) listed below: ,
b 2 -L S- 6 7~ LI I> L - L S 2 3 lj 2 - L S - 6 7- 2 4 h 2. - L s - 8 7 - 2 2.
UA//7 2 c YCt. d 3 fr7 9p t ATS t UAVE A f4d/A L. 4t t ouj,4,ys:g yagin TN/G c Yct L c's/t. f ( A oM6S s G D 1H R1 O F 'T t' t S Rt SY 'tALCounTson) f'2.
SO This calculat pages and -b
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DEMONSTRATED ACCURACY CALCULATION REVISION LOG
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CALCULATION DESIG?/ VERIFICATION /(INDEPENDENT REVIEW) FORM i
~ 1-LS- 8 7- 2 l R3, Calculation No. Revisjon Method'of design-verification (independent review) used (check method used):
- 1. Design Review /
- 2. Alternate Calculation
- 3. Qualification Test Justification (explain below):
Method 1: In the design review method, justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc.).
Method 2: In the alternate calculation m9thod, identify the pages where the alternate calculation has been '.ncluded in the esiculation package and explain why this method is adequate.
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(, Muthod 3: In the qualification test method, identify the QA documented source (s) whore testing adequately demonstrates tae adequacy of this calculation and explain.
AS STATED I4 T4E REUlstood Lo6 , THE CALC ulAS REVIS E D To CHANGE THE CALF BR ATION GYC LE To ELIMATE TH E PROCESS ERRort PA RA/AETER AAJD REVISE VA LVE 5 TRok E TIM E . I HAVE REVIEW ED THE JUSTf FICA TION FOR TH ESE CH AM E c, AMO T>J IA'i 7UD6EMENT TH E JoSTI FICA TION A A>D CH A AJ6ES ARE TEO4 M I C A LLY ADGoOATE
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} \ FORM CALCULATION DESICp 'JERIFICATION/(INDEPE!! DENT REVIEW)
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/~~ L 5 -P 7 - Al ,$& !
Calculction No. Revission l
Method of design verification (independent review) used (check method used):
Design Roview W 1.
- 2. A1tornate Cal:ulation
- 3. Qualifiestion Test Justification (explain below):
Method 1: In the design review method, justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc.).
Method 2: In the alternato esiculation method, identify the pages where the alternate esiculation has been included in the calculation package and explain why this method is adequate.
Method 3: In tho qualification test method, identify the QA documented s
sourco(s) where testint, adequately demonstestes the adequacy of this calculation and explain.
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CALCULATIOli INDEPElJDENT REVIEW VERIFICATION FORM
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I-LS 1/ I Calculation llo. Revision Method of independent review used (check one or more):
- 1. Alternate calculation method
- 2. Testing method
- 3. Other method Justification (explain below):
Method 1: Identify the pages where the alternate calculation has been included in tha calculation package and explain why this method is adequate.
Method 2: Identify the QA documented source (s) where testing adequately demonstrates the adoquacy of this calculation and explain.
Method 3: Justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc.).
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2 UNVERIFIED ASSUMPTIONS ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ 2,_
DEFINITIONS & ABBREVIATIONS _____________,__,____ ___ __ _1 _
LOOP COMPONENT LIST _ ____,_,____ ___ _ _ _ _ ____ $_
COMPONENT DATA _.._______ _______ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ . _
COMPONENT NOTES _______ _ _ _ ,_
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____._______ b LOOP FUNCTIONS, REQUIREMENTS, & LIMITS ___ _ . _____ _____
___ d b LOOP DIAGRAM-- ______ ________ ___- ____________ _$
INSTRUMENT SENSING DIAGRAM __ _ __ _ _ _ __ ______________ld2, PROCESS UNCERTAINTY DISCUSSION / CALCULATION __,,_______ _j_2_A WATERLEG UNCERTAINTY DISCUSSION / CALCULATION _ __ ______,_,_____ [ /M ACCURACY DISCUSSION _________ _
_ __ d ACCURACY CALCULATION INDEX & CALCULATIONS ____ _____ _ _ = _ _ ___, f,20 7.3 A
SUMMARY
OF CALCULATED DATA _,____ ___..______,_____________ __ 3 24A
- 40 /
R2 C ON C L U S I ON S _ _ _ __ _,_, _ _ _ _ _ _ __ _,__ _ _ _,__ _ _ _ __ _, ___ _ _ __ _ _
_, _ _ _ _ _ _ _ c.; v .?'
REFERENCES / ATTACHMENTS ____ ___,____, ,_ __,______,_____________ $dh
_ kMW.MM6ETS_____ __ __ _ __ ___ ______ _ _ _ ___ ___ N h i L l ___________________-____________-__--____------------------_-
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PURPCSE O P: \ .
C A L CUL/:47 I ON
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l The pur;;oce of this cciculation f s al to determine the ac:uracy of ani b) the instrumentation covered by this calculation, to dcocnctrate that the instrudentation is cufficiently at : urate to. per.Scra i ts intended f unction esi thout safety or ooirational limits being exccoded. !
UNUERI3:IED ASSUMPTIONS
\
This calculation contains no unverified assumptions.
The fallcuing unverified assumptions were used in the performance of this calculation.
further analynic and reevaluation. These assumptions require This calculation may require revisicn if the assumptions below are shown to be invalid.
PLANT / UNIT (S)MP (@
REV,.[ PREPAREDr$' h
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ti BRANCH }OJECTIDENTIFIER /-/S.97 '2/
DEMONSTRAT D\ ACCURACY CALCtJIJ. TION i
DESIGN INPUT l DATA A) DEFINITIONS & ABBREVIATIONS
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Aa ACCIDENT ACCURACY-ACCURACY OF DEVICE IN A HARSH ENVIRONMENT CAUSED BY AN ACCI ENT Aas COMBINED ACCIDENT ANb SEISMIC ACCURACY Ab ACCEPTANCE BA.iD-THE RANGE O VALUES AROLND TH1; CORRECT VALUE DETERMINED TO BE ACCEPTABLE WITHOUT RECALIBRATION AB AUXILIARY BOILER LINE BREAK AF AFW PUMP TURBINE STEAM SUPPLY LINE BREAK ;
An NORMAL ACCURACY-ACCURACY OF A DEVICE LOCATED IN A ENVIRONMENT NOT AFFECTED BY AN ACCIDENT OR PRIOR TO AN ACCIDENT As POST SEISMIC ACCURACY ffrijf /VdAMAl. MfAsadRd46 MeuRdey-SAmt 4s' Am 4xear spewofs g2.
Agoesss vssinws unes nas wmsssass.s or me rms oc catrasgrzoM CV CVCS LETDOWN LINE BREAK De DRIFT INACCURACY HELB HIGH ENERGY LINE BREAK IAD INTEGRATED ACCIDENT DOSE ICRe INPUT TEST INSTRUMENT READING INACCURACY ICTe 1NPUT TEST INSTRUMENT CALIBRATION INACCURACY INDRe INDICATOR READING ERROR ire INACCURACY DUE TO CABLE LEAKAGE L LOSS OF COOLANT ACCIDENT H MARGIN-THE DIFFERENCE DETWEEN THE SA7ETY LIMIT / OPERATING LIMIT AllD THE NORMAL / ACCIDENT ACCURACY (Mn= NORMAL MARGIN Ma= ACCIDENT MARGIN)
N/A NOT APPLICABLE OCRc OUTPUT TEST INSTRUMENT READING INACCURACY s Av dawn & G vn wt - satrezyr p & R'l REV 1 PREP vc DATE S.1t.9% CHECK % DATE <-t %$ SHEET 3 C/O M REV _ PREP DATE CHECK DATE SHEET C/ O_ _
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I PSEe INACCURACY CUE TO POWER SUPPLY VARIATIONS PV PROCESS VALitE (ACTUAL)
RADe INACCURACY DUE TO ACCIDENT RADIATION EXPOSURE Re REPEATABILITY INACCURACY RH RHR LINE 3REAK i
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WLe WATERLEG UNCERTAINTY WLHP WATERLEG HIGH POINT WLLP WATERLEG LOW POINT l
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( E) CCMPONENT DATA UOTZS \
I COMPONENT: '
I i NOTE ,, .
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Regression Output: ,, ., t Constant 0.039625 STAND AR D .cR Ao A oF y EstiM ATS Std Err of Y Mst R Squared 0.595909 0.560761 l gg g g qg.% ceNFJosNc6 )
No. of observations 390 . ( o, gg gg ) ( g.96 )
Degrees of Freedom 387 7 1 14 X Coefficient (s) 0.001842 1.233246 Std Err of Coef. 0.000256 0.131531 THf JNfeR m arJ0t) ON fe t t CUINfn l'Adt /S 9D\ THRU 7D'] HAT affM
+
cat eutar60 us rNG, Lotus 123 LIN w /?fdsat stred funerzed Y : \)< l )(R A M P ) + k 2. (SA PONff fM L ) V C h)MfA5 Y js 785 pygnN OF 7t/E ScrPozNT* D6vintroN of THE rES7ED J AlsrtumsNrs . 7HG DAYS dCa umM Is TMS N0* DF Ddy5 t'Asr THe~
CA L18 A A T10N DA TO- THE RAmis IS A suAsrJ7uff V/Lud fdA THf
,DA1S do4u m d. THIS 4]ILL /3 6 u.ss O JN THf dudV/ /~1f* fA061/AM grepusf 7HE eunvi F0R D/VJM TJod Vs. Days pppssgsD TD AE AM --
Es toNsarrA t of rue Fosm y: >< c i i W ). To use istus izs THIS VA L uf PIU51' Af S0857170760 IN. ~)*HE T JS 35, R t , No . of ppy9 f)AssgO QM L1/3AA 710 /U ' idTuS THE^I en :eu/ATES A cux yd*
fir of THE FC/M
- -Dng Y = [0 0012 U AYS ) + I. 28 5 (I - -< 4.o.ogyzC Tan funnoH ,9Ho 7as m,,a o, y ,g,y,,, agg ;,.gg,,,,.go og fdGtEC '7DI THau '7D9,
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- / + RAMP DEV ATION DAYS EXPoliENTIAL / CURVE FIT GUESS '
0 *'O O.039625-
-0.4 0.039625
-0.3 0 0
-0.3 0 0 l 0.039625
-0.2- 0 0 0.039625
-0.1 0 0 0.039625
-0.1 0 0 0.039625
-0.1 0 0 0.039625 0.0 0 0 0.039625 0.0 0 0 0.039625 0.0 0 0 0.039625 0.0 0 0 0.039625 0.0 0 0 0.039625 0.0 0 0 0.039625 O.1 0 0 0.039625 0.1 0 0 0.039625 0.1 0 0 0.039625 ,
0.1 0 0 0.039625 0.1 0 0 0.039625 0.2 0 0 0.039625 0.3 0 0 0.039625 0.1 1 0.028167 0.076205 0.076205
( 0.1 1 0.028167 0.028167 0.076205 0.2 0.2 1
1 1
0.028167 0.028167 0.076205 0.076205
[
0.2 0.1 2 0.055540 0.111806 0.1 2 0.055540 0.111806 t.
0.1 2 0.055540 0.111806 0.2 2 0.055540 0.111806 0.2 2 0.055540 0.111806 0.2 5 0.133122 0.213010 0.2 5 0.133122 0.213010 0.3 5 0.133122 0.213010 0.3 5 0.133122 0.213010 0.3 5 0.133122 0.213010
,0.0 6 0.157539 0.244965 0.2 6 0.157539 0.244965 0.3 6 0.157539 0.244965 0.3 6 0.157539 0.244965 0.4 6 0.157539 0.244965 0.0 7 0.181269 0.276072 0.3 7 0.181269 0.276072 0.3 7 0.181269 0.276072 0.3 7 0.181269 0.276072 0.3 7 0.181269 0.276072
-0.1 8 0.204330 0.306355 0.3 8 0.204330 0.306355 O.3 8 0..v4330 0.306355
~
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P .. .S t. % .._ 79.t...'!79.g.:.2__
t
.\
\ s C- ) .. EXPONENTI
\'/+ RAMP DEVIATION- DAYS EXPotENTIAL / CURVE FIT GUESS i 0.4 8 0.204330 O 306355 0.4 8 0.204330 0.306355
-0.3 9 0.226742 f 0.335836 0.3 9 0.226742 0.335836 0.3 9 0.226742 0.335836 0.4 9 0.226742 0.335336 0.5 9 0.226742' O.335836
-0.6 13 0.310251 0.446194 0.6 13 0.310251 0.446194 0.6 13 0.310251 0.446194 0.6 13 0.310251 0.446194 0.6 13 0.310231 0.446194
, 0.3 14 0.329679 C.471996 0.4 14 0.329679 0.471996 0.5 14 0.329679 0.471996 0.5 14 0.329679 0.471996 1.1 14 0.329679 0.471996
-0.6 20 0.435281 0.613284 0.6 20 0.435281 0.613284 0.7 20 0.435281 0.613284 0.7 20 0.435281 0.613284
( 0.7
-0.2 20 28 0.435281 0.550671 0.613284 0.770327 0.6 28 0.550671 0.770327 0.8 28 0.550671 0.770327 0.8 28 0.550671 0.770327 :-
0.8 28 0.550671 0.770327 0.9 28 0.550671 0.770327 0.9 28 0.550671 0.770327 1.0 28 0.550671 0.770327 1.1 28 0.550671 0.770327 1.1 28 0.550671 0.770327 1.3 28 0.550671 0.770327 1.3 23 0.550671 0.770327 1.3 28 0.550671 0.770327 1.4 28 0.550671 0.770327 1.5 28 0.550671 0.770327 0.4 57 0.803790 1.135916 1.2 57 0.803790 1.135916 1.2 57 0.803790 1.135916 1.3 57 0.803790 1.135916 1.4 5 '. 0.803790 1.135916 0.4 75 0.882680 1.266371 0.9 75 0.882680 1.266371 1.0 75 0.882680 1.266371 1.0 75 0.882680 1.266371 1.1 75 0.882680 1.266371
(, 1.1 75 0.882680 1.266371 THs s SHn! I s ifn eto di A/L ,_
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i . EXPONENTI
! + RAMP' DEVIATION DAYS EXPdNENTIAL / CURVE FIT GUESS ,
- .1 75 0.882680 1.266371 1.2 75 0.882680 g 1.266371 1.2 75 0.882680 ' 1.266371 1.3 75 0.882680 1.265371 1.3 75 0.882680 1.266371 1.4 75 0.882680 1.266371 1.4 75 0.882680 1.266371 1.4 75 0.882680 1.266371 1.4 75 0.882C80 1.266371 1.6 75 0.882680 1.266371 1.7 75 0.882680 1.266371 1.7 75 0.882680 1.266371 2.1 75 0.882680 1.266371 -
2.3 75 0.882680 1.266371 1.2 117 0.964664 1.444859 1.5 117 0.964664 1.444859 1.5 117 0.964664 1.444859 1.5 117 0.964664 1.444859 1.6 117 0.964664 1.444859 1.6 117 0.964664 1.444859 v 1.7 117 0.964664 1.444859 '
( 1.8 1.9 117 117 0.964664 0.964664 1.444859 1.444859 1.9 117 0.964664 1.444859 2.0 117 0.964664 1.444859 2.1 117 0.964664 1.444859 - **
2.1 117 0.964664 1.444859 2.1 117 0.964664 1.444859 <
2.2 117 0.964664 1.444859 2.3 117 0.964664 1,444859 2.5 117 0.964664 1.444859 4
2.5 117 0.964664 1.444859 i l 2.6 117 0.964664 1.444859 2.8 117 0.964664 1.444859 3'
0.5 152 0.987000 1.536891 O.8 152 0.987000 1.536891 1.0 152 0.987000 1.536891 l 1.0 152 0.987000 1.536891 '
1.2 152 0.987000 1.536891 1.3 152 0.987000 1.536891 1.3 152 0.987000 1.536891
, 1.4 152 0.987000 1.536891 1.4 152 0.987000 1.536891 1.5 152 0.987000 1.536891 1.6 152 0.987000 1.536891 1.6 152 0.987000 1.6 1.536891 152 0.987000
- ( 1.7 152 0.987000 1.536891 1.536891 7&n_ Swsr Js stMin 4/ //1 ~"
ve. .s n-se /-is.97 71 .
4
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' / + RAMP DEVIATION DAYS EXPOkENTIAL / CURVE FIT GUESS ,
1.7 152 0.987000 #
1.536891 1.7 152 0.987000 1.536891 1.8 152 0.987000 l 1.536891 2.2 152 0.987000 1.536891 2.5 152 0.987000 1.536891 2.6 152 0.987000 1.536891 0.3 180 0.994159 1.597307 0.6 180 0.994159 1.597307 0.9 180 0.994159 1.397307 1.0 180 0.994159 1.597307 1.2 180 0.994159 1.597307 1.2 180 0.994159 1.597307 1.3 180 0.994159 1.597307 1.4 180 0.994159 1.597307 1.4 180 0.994159 1.597307 1.4 180 0.994159 1.597307 1.5 180 0.994159 1.597307 1.6 180 0.394159 1.597307 1.6 180 0.994159 1.597307 1.7 180 0.994159 1.597307 1.7 180 0.994159 1.597307
( 1.8 1.8 180 180 0.994159 0.994159 1.597307 1.597307 2.2 180 0.994159 1.597307 2.2 180 0.994159 1.597307 2.5 180 0.994159 1.597307 -"
0.2 216 0.997911 1.668263 0.5 216 0.997911 1.668263 0.8 216 0 197911 1.668263 0.9 216 0.997911 1.668263 1.1 21t: 0.997911 1.668263 1.1 216 0.997911 1.668263 1.2 216 0.997911 1.668263 1.3 216 0.997911 1.668263 1.4 216 0.997911 1.668263 1.5 216 0.997911 1.668263 1.5 216 0.997911 1.668263 1.5 216 0.997911 1.668263 1.5 216 0.997911 1.668263 1.6 216 0.997911 1.668263 1.8 216 0.997911 1.668263 1.8 216 0.997911 1.668263 1.9 216 0.997911 1.668263 2.0 216 0.997911 1.668263 2.4 216 0.997911 1.668263 2.7 216 0.997911 1.668263 0.3 247 0.999138 1.726892 0.6 247 0.999138
( 1.726892
.pt, L7 Heft is Moro ($f $lL-
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' O.8 247 0.999'138 #
1.726892
'.0
. 247 0.999133 1.726892 1.1 247- C.999138 l 1.726892 1.2 247 0.999138 1.726892 1.3 247 0.999138 1.726892 1.5 247 0.999138 1.726892 1.6 247 0.999138 1.726892 1.6 247 0.999138 1.726892 1.8 247 0.999138 1.726892 1.8 247 0.999138 1.726892 1.8 247 0.999138 1.726892 1.8 247 0.999138 1.726892 1.8 247 0.999138 1.726892 1.9 247 0.999138 1.726892 2.2 247 0.999138 1.726892 2.2 247 0.999138 1.726892 2.7 247 0.999138 1.726892 2.9 247 0.999138 1.726892 0.4 279 0.999654 1.786486 0.7 279 0.999654 1.786486 0.8 279 0.999654 1.786486 279 i
( 0.9 1.2 1.3 279 279 0.999654 0.999654 0.999654 1.786486 1.786486 1.786486 1.4 279 0.999654 1.786486 1.6 279 0.999654 1.786486 _, ..
o 1.6 279 0.999654 1.786480 1.6 279 0.999654 1.786486 1.7 279 0.999654 1.786486 1.9 279 0.999654 1.786486 1.9 279 0.999654 1.786486 1.9 279 0.999654 1.786486 1.9 279 0.999654 1.786486 2.0 279 0.999654 2.786486 2.3 279 0.999654 1.786486 2.4 279 0.999654 1.786486 4-2.7 279 0.999654 1.786486
"~
2.9 279 0.999654 1.786486 0.6 303 0.999826 1.830916 4
0.7 303 0.999826 1.830916 0.8 303 0.999826 1.830916 0.8 303 0.999826 1.830916
] 1.4 303 0.999826 1.830916 1.6 303 0.999826 1.830916 l 1.6 303 0.999826 1.830916 1.6 303 0.999826 1.830916 j' 1.6 303 0.999826 1.830916
! ( 1.7 303 0.999826 1.830916 7*us r sur'er J t rinotr> bl RlL VC, Op .W /-4S #7 2/
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\~f +EXPONENTI RAMP DAYS EXPO'NENTIAL / CURVE FIT GU2SS 2.0 303 -/
0.999826 1.830916 2.0 303 0.999826 1.830916 2.0 l' 303 0.999826 1.830916 2.0 303 0.999826 1.830916 2.1 303 0.999826 1.830916 2.1 303 0.999826 1.830916 2.3 303 0.999826 1.830916 2.4 303 0.999826 1.830916 2.9 303 0.994826 1.830916 3.1 303 0.999826 1.830916 0.7 334 0.999928 1.888158 0.7 334 0.999928 1.888158 0.8 334 0.999923 1.888158 1.0 334 0.999928 1.888158 1.4 334 0.999928 1.888158 1.5 334 0.999928 1.888158 1.6 334 0.999928 1.888158 1.7 334 0.999928 1.888158 1.7 334 0.995928 1.888158 1.7 334 0.999928 1.888158 1.9 334 0.999928 1.888158
( 2.0 2.0 334 334 0.999928 0.999928 1.888158 1.888158 2.0 334 0.999928 1.888158 2.0 334 0.999928 1.888158 2.2 334 0.999928 1.G88158 "
2.2 334 0.999928 1.888158 2.5 334 0.999928 3.0 1.888158 334 0.999928 1.888158 3.1 3s4 0.999928 1.888158 !
0.5 362 0.999967 1.939795 0.6 362 0.999967 1.939795 0.8 362 0.999967 1.939795 0.9 362 0.999967 1.939795 l 1.3 362 0.999967 1.939795 1.4 362 0.999967 1.9397c 1.6 362 0.999967 1.939795 1.6 362 0.999967 1.939795 1.7 362 0.999967 1.939795 1.7 362 0.999967 1.939795 1.8 362 0.999967 1.939795 1.9 362 0.999967 1.939795 1.9 362 0.999967 1.939795 2.0 362 0.999967 2.0 1.939795 362 0.999967 1.939795 2.0 362 0.999967 2.2 1.939795 362 0.999967 1.939795
[ 2.3 362 0.999967 1.939795 3t n . w <t.r J s. A M.e 9 M E N . .. . ...... ......
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\ EXPONENTI
, + RAMP DEVIATION DAYS EXPO 4ENTIAL / CURVE FIT GUESS ,
.0 362 0.999967 1.939795
.0 362 0.999967 ; 1.939795 0.6 390 0.999985 '
1.991405 0.6 390 0.999985 1.991405 1.0 -390 0.999985 1.9914e5 1.1 390 0.999985 1.9914J5 1.4 390 0.999985 1.991405 1.4 390 0.999985 1.991405 1.7 390 0.999985 1.991405 1.8 390 0.999985 1.991405 1.8 390 0.999985 1.991405 1.8 390 0.999985 1.991405 1.9 390 0.999985 1.991405 i
- 1.9 390 0.999985 1.991405 2.0 390 0.999985 1.991405 2.0 390 0.999985 1.991405 2.1 390 0.999985 1.991405 2.3 390 0.999985 1.991405 '
2.4 390 0.999985 1.991405 2.5 390 0.999985 1.991405 3.0 390 0.999985 1.991405
( 3.1 0.8 0.9 390 419 419 0.999985 0.999993 0.999993 1.991405 2.044846 2.044846 e 1.5 419 0.999993 2.044846 1.6 419 0.999993 2.044846 ...
1.7 419 0.999993 2.044846 1.9 419 0.999993 2.044846 l 2.1 419 0.999993 2.044846 2.1 419 0.999993 2.044846 b 2.2 419 0.999993 2.044846 ;
2.2 419 0.999993 2.044846 2.2 419 0.999993 2.044846 2.2 419 0.999993 2.044846 2.3 419 0.999993 2.044846 2.4 419 0.999993 2.044846
'2. 4 419 0.999993 2.044846 2.6 419 0.999993 2.044846 !
2.8 419 0.999993 2.044846 !
3.0 419 0.999993 2.044846 3.5 419 0.999993 2.044846 (
1 3.6 419 0.999993 2.044846
- 0.7 453 0.999997 2.107493 1.1 !
453 0.999997 2.107493 j 1.5 453 0.999997 2.107493 ,
- 1.6 453 0.999997 2.107493 1.8 453 0.999997 2.107493 1.9 453 2 107493
{ 0.999997 l
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2.2 453 0.99'9'997 2.107493 2.2 453 0.999997 2.3 453 I' 2 107493 0.999997 2.107493 2.3 453 0.999997 2.4 453 2.107493 0.999997 2.107493 2.5 453 0.999997 2.5 453 2.107493 0.999997 2.107493 2.5- 453 0.999997 2.6 453 2.107493 2.8 0.999997 2.107493 453 0.999997 2.8 453 2.107493 0.999997 2.107493 3.1 453 0.909997 3.7 453 2.107493 3.7 0.999997 2.107493 453 0 999997 0.7 495 2.107493 1.1 0.999999 2.184878 495 0.999999 1.4 495 2.184878 1.5 0.999999 2.184878 495 0.999999 1.9 495 2.184878 :
2.0 0.999999 2.184878 l 495 0.999999 2.1 495 2.184878 i 0.999999
( 2.2 2.2 495 495 0.999999 0.999999 2 184878 2.184878 2.184878 2.4 495 0.999999 2.184878 2.4 495 0.999999 2.5 495 2.184878 '"
0.999999 2.5 495 2.184878 2.5 0.999999 2.184878 495 0.999999 2.6 495 2.184878 2.8 0.999999 2.184878 495 0.999999 2.8 495 2.184878 3.2 0.999999 2.104878 495 0.999999 3.6 495 2.184878 3.7 0.999999 2.184878 4?5 0.999999 0.9 525 2.184878 1.2 0.999999 2.240151 525 0.999999 1.4 525 2.240151 1.5 0.999999 2.240151 525 0.093999 2.0 525 2.240151 2.0 0.999999 2.240151 525 0.999999 2.1 525 2.240151 2.2 0.999999 2.240151 525 0.999999 2.3 525 2.240151 2.4 0.999999 2.240151 525 0.999999 2.5 525 2.240151 2.5 0.999999 2.240151 525 0.999999 2.6 525 2.240151
(, 2.6 0.999999 2.240151 l 525 0.999999 2.240151 7ee 1C, smos ouo + m...
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+ RAMP D2VIATION DAYS EXPONENTIAL / CURVE FIT 7 GUESS 2.7 525 0.999999 2.240151
'2.8 525 0.999999 2.8 525 l 2.240151 0.999999 '
2.240151 3.4 525 0.999999 3.7 525 2.240151 0.999999 2.240151 3.7 525- 0.999999 2.240151 NOT E :
I; THE tcTus /'g c ag p A M 15 usco Fo4 e t.y To suGg,6ST AN Ecu AttoN THAT Scsr F:TS'THE- ScR D A T A . TH G.
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(s/n-DATE 2364 06/08/87 0.70 07/06/87 0.60 08/03/87 0.60 09/01[87 Q.80 10/05/87 0.70 11/16/07 12/16/87 2365 1.7 1.7 0.70 0.90
1.8 ~ 2.1 2.2 2366 0.7 0.5 0.6 2.2 2.4 2367 0.9 1.1 1.1 1.2 1.4 1.3 1.4 l 1. 7 2368 1.9 1.9 1.9 2 1.8 2 2.2 2.5 2363 2 1.9 1.8 2.5 2.5 2369 2.1 2.4 2.4 2.1 1.5 1.4 1.4 1.9 1.8 2370 2.5 2.3 2.4 2 2 2371 2.8 2.8 2.8 2 2 2 2.8 2372 2.4 2.6 2.6 2.7 1.7 1.7 1.9 2362 2.2 2.3 2.4 2.5 2.2 2.2 2.3 2373 2.6 2.8 2.8 2.8 0.8 0.8 1 1.5 2374 1.7 1.5 1.5 1.5 2375 1.6 1.7 2.2 2.2 2.1 3.1 3 3.1 2.2 2376 3.6 3.7 3.7 3.7 3 3 3 2361 3.5 3.7 3.6 3.7 1 0.9 1.1 2377 1.6 1.6 1.6 1.4 1.4 2378 1.6 1.8 2.2 2.3 2.2 2.2 2 2.1 2.3 2379 2.4 2.5 2.5 2.6 2 1.9 1.9 2380 2.3 2.5 2.5 2.6 2 2 2.5 3 3.1 3.2 3.4
+
MEAN 1.7850 1.7100 1.8200 2.2000 2.3100 2.3050 2.3650 WIS fA G,6 AND THf NEx t 3
. f/?&ES Com/Ilf THE Divinizod $f .SETPo rd r~ FOR THE c:rro surs t xunnsR JNsrRumrNis 0^' THE day THAT THfy /Jdff CMfdKfD. 7//S t$p ribir? /rNfS THEN dst t euz A 7E THE /H f AA/ DEVJA TJ Orl 0F THE SETPor^'T3 f0R 7HE DA7 oktex 6D. Yk! !*1rsu Div1stred i
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- .*************** ********\-**********ww************* r DA'2E 2354 07/09/86 0.00 07/10/86 0.10 07/11/86 C.10 07/14/86 07/15/86 07/16/86 07/17/86 f
0.20 0.30 0.30 0.30 2335 0 0.2 0.2 0.3 0.2 0.3 2366 0.4 0 0.2 0.1 0.2 0 0 2367 -0.1 2368 0.1 0.1 0.1 l 0.3 0.3 0.3 0.3 0.1 0.2 0.2 0.3 0.4 0.3 2363 0.4
-0.3 2369 0 2370 -0.2 2371 0 2372 0.1 2362 -0.1 2373 -0.4 2374 ;
0 2375 0.3 2376 0.1 2361 -0.3 2377 -0.1 2378 0.1 2379 -0.1 2380 0.2 Kk (MEAN -0.0250 0.1600 0.1400 0.2600 0.2400 0.2400 0.2600
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2364 07/18/860.30 07/22/86 0.6 07/2J/86 07/29/$6 08/06/86 09/04/86 09/22/86 0'70 7 0.90 1.40 1.40 2365 0.3 0.6 **
.0.6 0.8 1.3 1.1 2366 - -0.3 -0.6 0.6 -0.2 0.4 0.4 2367 0.4 0.6 l 0.7 0.8. 1.2 1.1 2368 0.5 0.6 0.7 0.8 1.2 1.1 2363 0.4 1.6 2369 0.5 1.2 2370 1.1 2.3 2371 0.3 1.4 2372 0.5 1.4 2362 1 1.7 2373 0.6 0.9 2374 1.3 1.7 2375 1.5 1.4 2376 1.3 2.1 i 2361 0.9 1 2377 gp 1.1 1 4
2378 1.3 1.3
.2379 1.1 1.2 2380 1.4 1.3 DEAN 0.2400 0.3600 0.5600 0.4200 0.9733 1.1000 1.J300 i
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DA'IE. 11/03/86 12/08/86 01/05/87 02/10/87'03/13/87 04/14/87 05/08/87 23(4 1.90 1.50 '
1.40 0,90 0.30 0.70 C.70 2365 1.7 1.4 i.4 -1.1 1.3 1.4 1.6 2366 1.2 0.5 0.3 0.2 0.3 0.4 'O.6 2367 1.5 1 0.9 l 1.1 1.1 1.2 1.4 2368 1.8. 1.3 1.2 1.6 1.8 1.7 2 2363 2 1.6 1.5 1.5 1.8 1.9 2 2369 1.6 1.2 1.2 1.2 1.2 1.3 1.6 2370 2.8 2.2 2.2 2 2.2 2.4 2.4 2371: 2.1 1.8 1.8 1.8 1.8 1.9 2 2372 2.1 1.7 1.6 1.5 1.6 1.6 1.7 2362 2.2 1.7 1.7 1.5 1.9 2 2.1 2373 1.5 1 1 0P 1- 0.9 0.8 2374 2.3 1.6 1.6 1.3 1.6 1.6 1.6 2375- 2.5 2.6 2.5 2.7 2.9 2.9 3.1 2376 2.6 2.5 2.2 2.4 2.7 2.7 2.9 2361 2377 1.5 1.6 0.8 1.4 0.6 1.4 0.5 1.4 0.6 1.5 0.8 1.6 0.8 1.6 p
2378 2.5 1.7 1.8 1.9 2.2 2.3 2.3 2379 2.1 1.3 1.3 1.5 1.8 l'. 9 2.1 2380 1.9 1.6 1.7 1.8 1.8 1.9 2 MEAN 1.9700 1.5200' 1.4650 1.4350 1.5950 1.6550 1.7650 ktt..fW'.29,.dmD../$r.4l2- . . . . . . . . . . . . _
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lJAS JWPur 7D LOTU.S. THE ENhREk3JNd D/V' l MJoH 75 78f )WM/A$14d i fASElldS MJNUS TMC 224 1ASJN(f fffdwT. [All MIA AA6 IN IN' 500 )
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days from incrpasing increasing INCREASING s/n-
- m s/n date baseline
- sdt point baseline DEVIATION ;
2364 2364 07/09/86 60.7 !
l 2364 2364 07/09/86 0 60.7 0.00 2364 l -
2364 07/10/86 1 60.8 0.10 2364 2364 07/11/86 2 60.8 0'10 .
2364 2364 07/14/86 5 60.9 0.20 2364 2364 07/15/86 6 61 0.30 t
2364 2364 07/16/86 7- 61 0.30 2364 2364 07/17/86 8 61 0.30 2364 2364 07/18/86 9 61 0.30 2364 2364 07/22/86 13 61.3 0.60 2364 2364 07/29/86 20 61.4 0.70
, 2364 2364 08/06/86 28 61.6 0.90 2364 2364 09/04/86 57 62.1 1.40 2364 2364 09/22/86 75 62.1 1.40 2364 2364 11/03/86 117 62.6 2364 1.90 2364 12/08/86 152 62.2 1.50 2364 2364 01/05/87 180 62.1 2364 1.40 2364 02/10/87 216 61.6 0.90 2364 2364 03/13/87 247 61.5 0.80 2364 2364 04/14/87 279 61.4 2364 0.70 2364 05/09/87 303
( 61.4 0.70
. 2364 2364 06/08/87 334 61.4 2364 0.70 2364 07/06/87 362 61.3 2364 0.60 2364 08/03/87 390 61.3 2364 0.60 2364 09/01/87 419 61.5
-2364 0.80 2364 10/05/87 453 61.4 0.70 2364 2364 11/16/87 495 61.4 2364 0.70 2364 12/16/87 525 61.6 0.90 SY 2365 2365 07/09/86 61.2 2365 2365 07/09/86 0 61.2 2365 0 2365 07/10/86 1 61.4 2365 0.2 2365 07/11/86 2 61.4 2365 0.2 2365 07/14/86 5 61.5 2365 0.3 2365 07/15/86 6 61.4 2365 2365 0.2 07/16/86 7 61.5 0.3 2365 2365 07/17/86 8 Gl.6 4
2365 2365 0.4 2365 07/18/86 9 61.5 0.3 l 2365 07/22/86 13 61.8 2365 2365 0.6 l
2365 07/29/86 20 61.8 0.6 2365 08/06/86 28 62 23G5 2365 0.8 2365 09/04/86 57 62.5 1.3
} 2365 09/22/86 75 62.3 2365 2365 1.1 2365 11/03/86 117 62.9 1.7 2365 12/08/86 152 62.6 j 2365 2365 1.4 2365 01/05/87 180 62.6 1.4 i
( 2365 2365 2365 02/10/87 03/13/87 216 247 62.3 62.5 1.1 1.3 I VC , . 5 - 11 .9 9 * /* l S t.87 SL.
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( sor data sor data s/n s/n date days from increasing increasing INCREASING basel setpoint baseline
- ine *************************** DEVIATION
=***********;
2365 2365 04/14/87 279 2365 62.6 1.4 2365 05/08/87 303 62.8 2365 2365 06/08/87 334 1.6 2365 62.9 1.7 2365 07/06/87 362 62.9 2365 2365 08/03/87 390 1.7 63 2365 2365 09/01/87 419 1.8 63.3 2365 2365 10/05/87 453 2.1 2365 63.4 2.2 2365 11/16/87 495 63.4 1365 2365 12/16/87 525 2.2 63.6 2.4 2366 2366 07/09/86 .
2366 2366 63.6 2366 07/09/86 0 63.6 0 -
2366 07/10/86 1 63.8 2366 2366 07/11/86 2 0.2 2366 63.7 0.1 2366 07/14/86 0 63.8 2366 2366 07/15/86 6 0.2 2366 63.6 0 2366 07/16/86 7 63.6 2366 2366 07/17/86 8 0
2366 63.5 -0.1 2366 07/18/86 9 63.3 2366 2366 07/22/86 13
-0.3 2366 63 -0.6 2366 07/29/86 20
( 2366 2366 2366 2366 08/06/86 28 63 63.4
-0.6
-0.2 2366 09/04/86 57 64 2366 09/22/86 75 64 0.4 2366 2366 11/03/86 117 0.4 2366 64.8 1.2 "
2366 12/08/86 152 64.1 2366 2366 0.5 2366 01/05/87 180 63.9 2366 02/10/87 216 0.3 2366 63.8 2366 03/13/87 247 0.2 2366 63.9 2366 04/14/87 279 64 0.3 2366 2366 0.4 2366 05/03/87 303 64.2 2366 06/08/87 334 0.6 2366 2366 64.3 0.7 2366 07/06/87 362 64.1 bg 2366 08/03/87 390 0.5 3366 64.2 2366 09/01/87 419 0.6 2366 2366 64.5 0.9 2366 10/05/87 453 64.7 1.1 2366 11/16/87 495 64.7 23GG 2366 1.1 12/16/87 525 64.8 1.2 3367 2367 2367 2367 07/09/86 65.1 2367 07/09/86 0 65.2 2367 07/10/86 1 0.1 2367 2367 65.2 0.1 2367 07/11/86 2 65.2 2367 07/14/86 5 0.1 2367 2367 65.4 0.3 3367 07/15/86 6 65.4 2367 07/16/86 7 0.3 3367 2367 65.4 0.3
- k. 3367 07/17/86 8 65.4 ,
2367 07/18/86 9 0.3 65.5 0.4
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( sor data sor data days from increasing increasing INCREASING n/n s/n date baseline
.******************+********************** set point baseline DEVIATION 2367 2367 07/22/86 13 65.7 2367 0.6 2367 07/29/86 20 65.8 0.7 2367 2367 08/06/86 28 65.9 2367 0.8 2367 09/04/86 57 66.3 1.2 2367 2367 09/22/86 75 66.2 1.1 2367 2367 11/03/86 117 66.6 j
2367 1.5 2367 12/08/86 152 66.1 1 1
2367 2367 01/05/87 180 66
}
2367 0.9 1 2367 02/10/87 216 66.2 1.1 2367 2367 03/13/87 247 66.2 2367 1.1 2367 04/14/87 279 66.3 1.2 2367 2367 05/08/87 303 66.5 1.4 2367 2367 06/08/87 334 66.5 1.4 2367 2367 07/06/87 362 66.4 l 2367 1.3 2367 08/03/87 390 66.5 1.4 2367 2367 09/01/87 419 66.8 2367 1.7 2367 10/05/87 453 67 2367 2367 1.9 11/16/87 495 67 1.9 2367 2367 12/16/87 525 67.1 2 2368 2368 07/09/86 66.9
( 2368 2368 2368 2368 07/09/86 07/10/86 0
1 67.1 67 0.1 0.2 2368 2368 07/11/86 2 67.1 2368 0.2 2368 07/14/86 5 67.2 2368 0.3 2368 07/15/86 6 67.3 2368 2368 0.4 07/16/86 7 67.2 0.3 2368 2368 07/17/86 8 67.3 0.4 1368 2368 07/18/86 9 67.4 2368 2368 0.5 07/22/86 13 67.5 0.6 2368 2368 07/29/86 20 67.6 2368 2368 0.7 08/06/86 28 67.7 0.8 2368 2368 09/04/86 57 68.1 1.2
[h 2368 2368 09/22/86 75 68 2368 2368 1.1 11/03/86 117 68.7 1.8 2360 23.8 12/08/86 152 68.2 2368 2368 1.3 01/05/87 180 68.1 1.2 2368 2368 02/10/87 216 68.5 1.6 2368 2368 03/13/87 247 68.7 2368 2368 1.8 04/14/87 279 68.6 1.7 2368 2368 05/08/87 303 68.9 2368 2 2368 06/08/87 334 68.8 2368 1.9 2368 07/06/87 362 68.7 2368 1.8 2368 08/03/87 390 68.9 2 2368 2368 09/01/87 419 69.1 2368 2368 2.2 10/05/37 453 69.4 2.5 2368 2368 11/16/87 495 69.4 2.5 k_ 2368 2368 12/16/87 525 69.4 2.5 yc, s n-ss l L?. VI:.2.I.
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( sor data sor data '
days from increasing increasing INCREASING s/n s/n date baseline
- set point baseline DEVIATION 2363 2363 07/09/86 60 2363 2363 07/09/86 0 59.7 -0.3 2363 2363 07/23/86 14 60.4 0.4 2363 2363 09/22/86 75 61.6 1.6 2363 2363 11/03/86 117 62 2 2363 2363 12/08/86 152 61.6 1.6 2363 2363 01/05/87 180 61.5 1.5 2363 2363 02/10/87 216 61.5 1.5 2363 2363 03/13/87 247 61.8 1.8 2363 2363 04/14/87 279 61.9 1.9 2363 2363 05/08/87 303 62 2
- 2363 2363 06/08/87 334 62 2 2363 2363 07/06/87 362 61.9 1.9 2363 2363 08/03/87 390 61.8 1.8 2363 2363 09/01/8.7 419 62.1 2.1 2363 2363 10/05/87 453 62.4 2.4 2363 2363 11/16/37 495 62.4 2.4 2363 2363 12/16/87 525 62.1 2.1 2369 2369 07/09/86 61.4
( 2369 2369 2369 2369 07/09/86 07/23/86 0
14 61.4 61.9 0.5 0
2369 2369 gp r
09/22/86 75 62.6 1.2 B 2369 23d9 11/03/86 117 63 1.6 --
2369 2369 12/08/86 152 62.6 1.2 2369 2369 01/05/87 180 62.6 1.2 2369 2369 02/10/87 216 62.6 1.2 2369 2369 03/13/87 247 62.6 1.2 2369 2369 04/14/87 279 62.7 1.3 2369 2369 05/08/87 303 63 1.6 2369 2369 06/08/87 334 62.9 1.5 2369 2369 07/06/87 362 62.8 1.4 2369 2369 08/03/87 390 62.8 1.4 2369 2369 09/01/87 419 63.3 1.9 2369 2369 10/05/87 453 63.2 1.8 2369 2369 11/16/87 495 63.4 2 3369 2369 12/16/87 525 63.4 2 2370 2370 07/09/86 61.5 l 2370 2370 07/09/86 0 61.3 -0.2 l 2370 2370 07/23/86 14 62.6 *
.1 2370 2370 09/22/86 75 63.8 2.3 2370 2370 11/03/86 117 64.3 2.8 2370 2370 12/08/86 152 63.7 2.2 2370 2370 01/05/87 180 63.7 2.2 2370 2370 02/10/87 216 63.5 2
( 2370 2370 03/13/87 24/ 63.7 2.2
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c/n s/n date days from increasing increasing INCREASING basel setpoint baselino DEVIATION
- '****************************ine *********************************.*****'
237C 2370 04/14/87 279 63.9 2370 2370 2370 05/08/87 303 63.9 2.4 l 2.4 2370 06/08/87 334 64 2370 2370 07/06/87 362 63.8 2.5 l 2370 2370 2.3 4 2370 08/03/87 390 63.9 2.4 I 2370 09/01/87 419 2370 64.3 2.8 i 2370 10/05/87 453 64.3 2370 2370 2.8 11/16/87 495 64.3 2.8 2370 2370 12/16/87 525 64.3 2.8 i 2371 2371 07/09/86 1 2371 2371 64 i 07/09/86 0 64 2371 2371 07/23/86 14 64.3 0j 2371 2371 0.3 :
09/22/86 75 65.4 1.4 l 2371 2371 11/03/86 117 66.1 2.1 -
2371 2371 12/08/86 152 '
2371 65.8 1.8 2371 01/05/87 180 65 8 2371 2371 1.8 02/10/87 216 65.8 1.8 2371 2371 03/13/87 247 65.8 1.8 2371 2371 04/14/87 279 65.9 2371 2371 05/08/87 303 1.9 66
( 2371 2371 2371 2371 06/08/87 334 66 2
2 07/06/87 362 66 2371 2371 08/03/87 390 66 2
2371 2371 09/01/87 419 66.4 2
2371 2371 10/05/87 453 66.6 2.4 '
b 2371 2371 2.6 11/16/87 495 66.6 2.6 2371 2371 12/16/87 525 66.7 2.7 2372 2372 07/09/86 2372 2372 66.1 2372 07/09/86 0 66.2 0.1 2372 07/23/86 14 66.6 2372 2372 09/22/86 75 0.5 2372 67.5 1.4 2372 11/03/86 117 68.2 2372 2372 12/08/86 152 2.1 f /.8 2372 2372 01/05/87 180 1.7 2372 67.7 1.6 2372 02/10/87 216 67.6 2372 2372 03/13/87 247 1.5 67.7 2372 2372 04/14/87 279 1.6 2372 67.7 1.6 2372 05/08/87 303 67.8 2372 2372 06/08/87 334 1.7 67.8 2372 2372 07/06/87 362 1.7 2372 67.8 1.7 2372 08/03/87 390 68 2372 2372 09/01/87 419 1.9 2372 68.3 2.2 2372 10/05/87 453 68.4 2372 2372 11/16/87 495 2.3 2372 68.5 2.4 2372 12/16/d1 525 68.6 2.5 y C, 7 11 S ? . /.~ k', N--
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sor data sor data days from increasing increasing INCREASING s/n s/n date baseline s
- etpoint baseline DEVIATION 2362 2362 07/09/86 61.3 2362 2362 07/09/86 0 61.2 2362 2362 -0.1 08/06/86 28 62.3 1 2362 2362 09/22/86 75 63 2362 1.7 2362 11/03/86 117 63.5 2362 2362 2.2 12/08/86 152 63 1.7 2362 2362 01/05/87 180 63 2362 2362 1.7 02/10/87 216 62.8 1.5 2362 2362 03/13/87 247 63.2 2362 2362 1.9 04/14/87 279 63.3 2 2362 2362 05/08/87 303 63.4 2362 2362 2.1 06/08/87 334 63.5 2.2
- 2362 2362 07/06/87 362 63.6 2362 2362 2.2 08/03/87 390 63.6 2.3 2362 2362 09/01/87 419 63.9 2362 2.6 236? 10/05/87 453 64.1 3362 2362 2.8 11/16/87 495 64.1 2.8 2362 2362 12/16/87 525 64.1 2.8 2373 2373 07/09/86 61 2373 2373 07/09/86 0
( 2373 2373 2373 2373 08/06/86 09/22/86 28 75 60.6 61.6 61.9 0.4 0.6 2373 2373 0.9 11/03/86 117 62.5 1.5 2373 2373 12/08/86 152 62 - -
2373 1 2373 01/05/87 180 62 2373 1 2373 02/10/87 216 61.8 2373 2373 0.8 03/13/87 247 62 1 2373 2373 04/14/87 279 61.9 2373 2373 0.9 05/08/87 303 61.8 0.8 2373 2373 06/08/87 334 61.8 2373 2373 0.8 07/06/87 362 61.8 0.8 2373 2373 08/03/87 390 62 2373 1 2373 09/01/87 419 62.5 237: 2373 1.5 3
2373 10/05/87 453 62.5 1.5 2373 11/16/87 495 62.5 2373 2373 1.5 12/16/87 525 62.5 1.5 2374 2374 07/09/86 2374 62.6 2374 07/09/86 0 62.6 2374 2374 0 2374 08/06/86 28 63.9 1.3 2374 09/22/86 75 64.3 2374 2374 1.7 2374 11/03/86 117 64,9 2.3 2374 12/08/86 152 64.2 2374 2374 1.6 3374 01/05/87 180 64.2 1.6 2374 02/10/87 216 63.9 3374 2374 1.3 f
\ 3374 03/13/87 247 64.2 1.6 2374 04/14/87 279 64.2 1.6
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( sor data sor data days from increasing increasing INCRCASING s/n s/n date baseline sotpoint baselino DEVIATION 2374 2374 Ob/08/87 303 54.2 1.6 i 2374 2374 06/08/87 334 64.3 1.7 2374 2374 07/06/87 362 64.2 1.6 2374 2374 08/03/87 390 64.3 1.7 2374 2374 (
09/01/87 419 64.8 2.2 l 2374 2374 10/05/87 453 64.8 2.2 !
2374 2374 11/16/87 495 64.7 2.1 2374 2374 12/16/87 525 64.8 2.2 2375 2375 07/09/86 64.9 2375 2375 07/09/86 0 65.2 0.3 2375 2375 08/06/86 28 66.4 1.5 2375 2375 09/22/86 75 66.3 1.4 2375 2375 11/03/86 117 67.4 2.5 2375 2375 12/08/86 152 67.5 2.6 2375 2375 01/05/87 180 67.4 2.5 2375 2375 02/10/87 216 67.6 2.7 2375 2375 03/13/87 247 67.8 2.9 2375 2375 04/14/87 279 67.8 2.9 2375 2375 05/08/87 303 68 3.1 2375 2375 06/08/87 334 68
( 2375 2375 2375 2375 07/06/87 08/03/87 362 390 67.9 66 3.1 3 h 3.1 2375 2375 09/01/87 419 68.5 3.6 2375 2375 10/05/87 453 68.6 3.7 2375 2375 11/16/87 495 68.6 3.7 2375 2375 12/16/87 525 68.6 3.,
2376 2376 07/09/86 64.3 2376 2376 07/09/66 0 64.4 2376 0.1 2376 08/06/86 28 65.6 1.3 2376 2376 09/22/86 75 66.4 2376 2.1 2376 11/03/86 117 66.9 2.6 2376 2376 12/08/86 152 66.8 2376 2.5 2376 01/05/87 180 66.5 2.2 2376 2376 02/10/87 216 66.7 2376 2.4 2376 03/13/87 247 67 2376 2.7 2376 04/14/87 279 67 2,7 2376 2376 05/08/87 303 67.2 2376 2.9 2376 06/08/87 334 67.3 3 2376 2376 07/06/87 362 67.3 3 2376 2376 08/03/87 390 67.3 3 2376 2376 09/01/87 419 67.a 2376 3.5 2376 10/05/87 453 68 3.7 2376 2376 11/16/87 495 67.9 2376 3.6 2376 12/16/87 525 68 3.7 b 2361 2361 07/09/86 60.3
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- baseline DEVIATION 2361 2361 07/09/86 0 60 -0.3 2361 2361 08/06/86 28 61.2 2361 2361 0.9 4
09/22/86 75 61.3 1 2361 2361 11/03/86 117 61.8 2361 2361 1.5 l 12/08/86 152 61.1 0.8 2361 2361 01/05/87 180 60.9 2361 2361 0.6 02/10/87 216 60.8 0.5 2361 2361 03/13/87 247 1
60.9 0.6 2361 2361 04/14/87 279 61.1 2361 2361 0.8 05/08/87 303 61.1 0.8 j 2361 2361 06/08/87 334 2361 61.3 1 t
2361 07/06/87 362 61.2 2361 2361 0.9 j-2361 08/03/87 390 61.4 1.1 2361 09/01/87 419 61.9 2301 2361 1.6 2361 10/05/87 453 61.9 1.6 l 2361 11/16/87 495 61.7 2361 2361 1.4 12/16/87 525 61.7 1.4 i 2077 2377 07/09/86 i 2377 61.7
- 2377 07/09/86 0 61.6 i 2377 2377 -0.1 !
08/06/86 28 62.8
( 2377 2377 2377 2377 09/22/86 75 62.7 1.1 1
2377 11/03/86 117 63.3 1.6 ,
3 2377 12/08/86 152 63.1 a
2377 2377 01/05/87 180 1.4 2377 63.1 1.4 ~"
2377 02/10/87 216 63.1 2377 2377 1.4 2377 03/13/87 147 63.2 1.5 l
i 2377 04/14/87 279 63.3 ,
2377 2377 1.G >
2377 05/08/87 303 63.3 1.6
- 2377 06/08/87 334 63.3 i 2377 2377 07/06/87 362 1.6 i 1
2377 63.3 1.6 2377 08/03/87 390 63.5 j 2377 2377 09/01/87 419 1.8 %b i 2377 63.9 2.2 J' 2377 10/05/87 453 64 2377 2377 11/16/87 495 2.3 2377 63.9 '2.2 2377 12/16/87 525 64 2.3 i j 2378 2370 07/09/86 !
2378 2378 65.5 I 3378 07/09/86 0 65.6 0.1 2378 08/06/86 28 66.8 !
- 2378 2378 09/22/86 75 1.3 i 2378 66.8 1.3 2378 11/03/86 117 68 l
3378 2378 12/08/86 152 2.5 !
2378 67.2 1.7 2378 01/05/87 180 67.3 r 2378 2378 02/10/87 216 1.8 !
3378 67.4 1.9 2378 03/13/87 247 67.7 l 3378 2378 04/14/8 ' 279 2.2
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L 2378 67.8 2.3 2378 05/08/87 303 67.8 2.3 t vc, su.4% /,gs.g7 7 / i j
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2378 2378 06/08/87 334 67.7 2.2 2373 2378 07/06/87 362 67.5 2 2378 2373 08/03/87 390 67.6 2.1 2378 2378 09/01/87 419 67.9 2.4 2378 2378 10/05/87 453 68 2.5 2378 2378 11/16/87 495 68 3.5 2378 2378 12/16/87 525 68.1 2.6 2379 2379 07/09/86 66.7 2379 2379 07/09/86 0 66.6 -0.1 2379 2379 03/06/86 28 67.8 1.1 2379 2379 09/22/86 75 67.9 1.2
~
2379 2379 11/03/86 117 68.8 2.1 2379 2379 12/08/86 152 68 1.3 2379 2379 01/05/87 180 68 1.3 2379 2379 02/10/87 216 68.2 1.5 2379 2379 03/13/87 247 68.5 1.8 2379 2379 04/14/87 279 63.6 1.9 2379 2379 05/08/87 303 68.8 2.1 2379 2379 06/08/87 334 68.7 '2 2379 2379 07/06/87 362 68.6 1.9
( 2379 2379 2379 2379 08/03/87 09/01/87 370 419 68.6 69 1.9 2.3 2379 2379 10/05/87 453 69.2 2.5 2379 2379 11/16/87 495 69.2 2.5 2379 2379 12/16/87 525 69.3 2.6 2380 2380 07/09/86 64.7 2380 2380 07/09/86 0 64.9 0.2 2380 2380 08/06/86 28 66.1 1.4 a l' 2380 2380 09/22/86 75 66 1.3 D 2380 2380 11/03/86 117 66.6 1.9 2380 2380 12/08/86 152 66.3 1.6 2380 2380 01/05/87 180 66.4 1.7 2380 2380 02/10/87 216 66.5 1.8 2380 2380 03/13/87 247 66.5 1.8 2380 2380 04/14/87 279 66.6 1.9 2380 2380 05/08/87 303 66.7 2 2380 2380 06/08/87 334 66.7 2 2380 2380 07/06/87 362 66.7 2 2380 2380 08/03/87 390 67.2 2.5 2380 2380 09/01/87 419 67.7 3 2380 2380 10/05/87 453 67.8 3.1 2380 23F0 11/16/87 495 67.9 3.2 2380 23n0 12/16/87 525 68.1 3.4
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!I C0MPUTATIONS/ANALYBES ;
B) WATERLEG UNCERTAINTY DISCUSSION /CALCUIATION i
/ APPLICABLE TO ALL LOOPS LISTED ON SHEET 'T' . I APPLICABLE ONLY TO LOOPS:
t I
1 WATERLEG BECAUSE:
UNCERTAINTY IS NOT CONSIDERED FOR THE CALCULATION I NO WATERLEG EXISTS FOR THIS CALCULATION.
THE EFFECTS OF WATERLEG CHANGES ARE INSIGNIFICAllT.
SEE DISCUSSION / CALCULATION BELOW.
OTHER. SEE DISCUSSION / CALCULATION BELOW.
A WATERLEG UNCERTAINTY DOES EXIST FOR THIS LOOP. SEE i CALCULATION / DISCUSSION BGIAH+. ou ##1* M e,c V
SEE SENSING LINE DIAGRAM ON SHEET /0 OF THIS CALCULATION. i
~es
)
i l
I i
L REV R., PREP DATE _ _ Cl!ECK_ DATE SHEET _ C/O REV._L. PREPAA '
DATE,. 1 1y CHECK _(JA DATE /-it W_ SHEETjA C/0 4 REV_.2 PREP DATE CHECK DATE SHEET C/O
DRAlCH/ PROJECT IDEllTIFIER I-45 87 */
DE!'0!!STRATED ACCURACY CALCULATIC:1 Fro"thediscussiononpagoOb",Nho longest reference leg had af [3 preccuro of 305.4 I!!WC with an error of 2.3 I!iUC for a maximum pcoccuro of 307.9 IllWC . From drawing 47E225-10 rev 2 the tamperaturo extremos of the rcom is 40 to 110F with the normal rango from 70 to 92F. Attachment 23 shows the temperature history of the UHI room. This data gives assurance that the UHI room was between 65 and 85F when the sotpoint was dotormined.
Additionally, SI 606 requires that the temperature of the space be maintained between 75 and 85F. Corrective actions are to be taken to restore the room to this temperature range if ever found outsido of the rango. Therefore, the temperature induced errors will be based upon the criginal setpoint determination temperaturo betwoon 65 and 85F and the cperating temperature between 70 and 90F. Assuming that tho tank's temperature remains constant, the error caused by temperaturo variations is the density changes in the reference log.
Tho density of saturated water at:
65F = 62.3403 lbm/ft 70F = 62.3053 lbm/ft 85T = 62.1717 lbm/ft 90F = 62.1157 lbm/ft)
The waterleg egror, referenced to water at 60F,14.696 psia (62.316 lbm/ft ist 65 to 90F: [(62.3403 - 62.1157)/62.316)
- 307.9 = 1.1 IllWC '
85 TO 70F: [(62.3053 -
62.1717)/62.316)
- 307.9 = 0.66 IllWC ,
The error going from 65 to 90F represents a decrease in pressure on the reference leg. This requires a lower tank level to reach the instrument's differential pressuro setpoint. Viewing this change from an instrument accuracy perspectivo, this is equivalent to raising the instrument setpoint. This yicids a positivo error. .The change in temperature from 85 to 70F then reprenonts a negative error.
The waterleg error due to temperature variations is +1.1 / -0.7 I!iWC .
N'S O ' $ c u S} #0N #6 Fee T% h9 tT O C c t- d c u t.e u G C. F ao.u '
FM'ed i cr wi$ c A c-e m A Ti rM - TH E '00 5 I N'- lid'T I
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_ - . . _ - ~ + - -
s
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. l DRANCH/PROJECTIDENTIFIER__,l__L.$_'_b2_C.dL_______ l' DEMONSTRATED ACCURACY CALCULATION s
L. O O P DIAGRAM '
t LOOP IDENTIFIER:
I t ! '
APPLICADLE TO ALL LOOPS LISTED ON SHEET 1 APPLklADLEONLYTOLOOPS:
i N .
VALVE L S )- - - - - -- - l_ome r
I L
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L5 r PLANT /UN!T(S) M hTj'[th l REV.Q, PREPARED 4;'_lu__,,, CHECKED _[i.,';Cr_1 DATE -
_#_/_* /_'" SHEET 15 CeolG
i 8 BRANCH /PROJECTIDENTIFIER__.j_!_d_!_h_7_-h_b_______
DEMONSTRATED ACCURACY CALCULATION INSTRUMENT SENSING DIAGRAM LOOP IDENTIFIER:
APPLICABLE TO ALL LOOPS LISTED ON SHEET [.
APPLICABLE ONLY TO LOOPS:
. , . , , . , , A
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UH1 is e - -- - .
9fi' ,,, / a & #/ WATE R Nk
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ti - CHECKED Y*'-:
DATE i/_^ /f] SHEET [h C/0}7 w es. _
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BRANCH /PROJECTIDENTIFIER__,b'j__32O_7_Z2-d________
DEMONSTRATED ACCURACY CALCULATION f
I ACCUR ACY DISCUSSION
(
The accuracy of this instrument for normal ar.d post sei smic conditions will be determined by considering the parameters tabulated on sheet __ of this calculation. i i
The accu ~ racy calculation f or seismic (As) is bounding f or all seisaic events .
Accuracies calculated in this calculation will be determined by algebraically summing those factors which are not independent variables (i . e. , unidirectional temperature, waterleg uncertainty, seismic, etc.) with the results of the square root of the sum of the squares method f or those factors which are independent variables.
L/
The square root of the sum of the squares method shall be used in this alculation for calculating accuracy since the f actors af f ecting accuracy are independent variab1 r r..
V Bi-directional erro'r s and uni-directional errors will be combined in a manner such that the sum of the positive uni-directional errors will be added to the positive portion of the bi-directional error (obtained from the square root of the sum of the squares method), and the sum of the negative uni-directional errors will be added to tha negative portion of the bi-directional error.
This method is conservative and therefore it Etill this calculation. be used in -
Example:
110 = bi-directional error
+5 = first uni-directional er or
-2 = second uni-directional error Total Error = (+ 10 + 5) to ( 2)
= + 15 to - 12 others___________________________ ___________________
l
.9 -
PLANT / UNIT (S) _ _ .f_h l REV,Q, PREPARED Uj;__ CHECKED llD DATE $_/Z/f2 SHEET 2 C/0,lh t
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i* t BRANCH /PROJECTIDENTIFIER__l__h_$_~.h_2_~_h_b-----____
DEMONSTRATED ACCURACY CALCULATION tF ACCLJR ACY DISCUSSION (CONTIN,UED)
/
THE FOLLOWING DEVICES ARE CALIBRATED INDIVIDUALLY.
THEIR ACCEPTANCE BANDS ARE AS FOLLOWSt DEVICE ACCEPTANCE BAND REFERENCE 2 - LS- A7- 2 ' I /,D " H10 "IO f ,1 -L S -9 7- 2 "
~
- l . A " 42 0 , *S s 1 -L S - 6 7- 2.3 : I .h" H~D
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' THE FOLLOWING DEVICES ARE CALIBRATED TOGETHER.
THE ACCEPTANCE BAND FOR THE CONDINATION OF THESE DEVICES IS AS FOLLOWS DEVICE ACCEPTANCE BAND REFERENCE La PLANT / UNIT (S) SMP/Ltt REV O_ PREPARED ,,, '
,,,it_ CHECKED ;E-; l'g_ DATE __/__,/;3' SHEEY h C/0)f
i , I BRANCH / PROJECT IDENTIFIER __.l'~_h _~h2__d/___. ._
DElGNSTRATED ACCURACY CALCULATION C A C C t_J R A C Y C AL CUL. A T I ONS INDEX
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( /) INPUT1/JACCUR.ACY
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dRA$iCH/PROJECTIDENTIFIER T~'5~S7~2I DEMONS M TED ACCURACY CALCULAT:.ON
// COMPUTATIONS / ANALYSES D) ACCURACY CALCULATIONS
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{ REV._1 DATE 7 27 S3 CT.ECK/Y DATE C/O PREPR.C/ad DATE rih 415 7 CHECK Qh q C/0 2 t DATE '/I/'f/1) SHEET _ge REV Z PREPI DATE s.'#2 se C H E C X o-2. DATE 5-f 5-w SHEET,,__, C/O
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BRANCH / PROJECT IDENTIFIER /- Z S- F '/- 2 /,
DEMONSTRATED ACCtJRACY CALCUZ.ATION
{.
SUMMARY
OF RESULTS (BISTABLE-)
v APPLICABLE TO ALL LOOPS LISTED ON SHEET F .
. _ APPLICABLE ONLY TO LOOPS: k LTMIT 95 30 mg(,JAf g?. 0 / _
PV = SP + As PV = S P + An 95 24 SETPCINT (SP) 42 66 PV = SP - An Ps./3 l3/
PV = S P - A s _
PV = SP - Aa a /A MARGIN d,07 . .I SAFETY LIMIT FS./0 -Ig3 ALL VALUES SHOWN ARE _ JN. 0F AJA/ER AACVE VfArus /xxxtN6 leur
( REFER TO ACCURACY DISCUSSION, SHEET ir7 FOR CLARIFICATION OF ABOVE )
A V 9t,l g q 7b 96,23 - Aas M/4 . 3 31
.k REV O PREP ve DATE s12.w8 CHECK r' DATE T.(5-W SHEET 23A C/O_2//
l REV A PREP vc DATE 7.??, W CHECK /w DATE'VI./(t SHEET C/O REV 2 PREF, _ ,DATE CHECK DATE ' i~~ SHE'J T C/0
. ~ ........ .
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[ DEMONSTRATED ACCURCY CALCULATION REGu1RER78N75 '
TITLE: , '-/S- @7- 2 / REVISION: 2. # 57 POST-SEISMIC RECAL. /IS IS NOT h CALIBRATION FREQUENCY: 4TO DAYS REQUIRED N //t- h LOOP ANf: 4259 - 3. r/// JN, p4/2/ MODIFIER / INDICATOR ANf:
ANf INSTRUMENT ANf INSTRUMEhr I, 2 '- L S- t 7- 2 I t 2*C9l- f*99 .zN. /MTER t, 2 - A s E't- 22 I,7-12 23 l 2-45-87-24 i
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/- 4S 22 ~ 129.go p l-4S 23 W 129, 7G t - L S- 97
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DATE 7 3o B3 CHECK /Y DATE >/1,M _ SHEET C/O REV1 PREP, VC '
SHEET REV PREP DATE CHECK ' DATE,' C/O
( .
. I BRANCH / PROJECT IDi TIFIER /- LS - W- 2/
DEMONSTRATED ACCURAC." CALCULATION
- l
( CONCLU'SIONS V APPLICABLE TO ALL LOOPS LISTED ON SHEET 6.
APPLICABLE ONLY TO LOOPS:
7~MS Pf6SENT Sf7P0]N7' 2S NOT A/)ffod76 70 SupAr#7
/* // t/
.7"H E A?NALY778 L2/Y)1?T f SS* / 70 ff. ;' tJ d/fA* s/MSV! TMS
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l 74 f REV F2 PREP ye DATE g.//. 9 5* CHECK b DATE 4-r 1-5 b SHEETW/l C/024'.3 REV't3 PREP DATE, CHECK DATE SHEET C/O REV_,7md PREP DATE CHECX DATE SHEET C/O
BRANC. H/ PROJECT I DENT I F I ER __'[_-4_3__(3_7__ _2_d-------_ _ _
DEMONSTRATED ACCURACY CALCULATION REF ERENCES / ATTACHMENTS ~
NUMBER ---=- --- -
REFERENCE (RIMS #)------- -----------
_ w m x m .a _ _ - _ - _ s. m .ua w .or< 2: _ u _< w _ ,_ - _ _ _ /s n - a , , , . , , _ ~
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N PLANT / UNIT (S) _MUf]IP.__
REV_j._ PREPARED ['_ 3_ CHECKED _TM_____ DATE [_/_2k d SHEET 2d[C/O_2_h II)14 } H
i- :
BRANCH / PROJECT IDENTIFIER __/_d 3_~_ N -'81___ _ __
DEMONSTRATED ACCURACY CALCULATION REFERENCES / ATTACHMENTS N JMBER -----------------R E F E R E N C E ( R I N S # ) -------------------
_._9__ .' . __.2nas w,_2esmuz.v_n._&h__kise_scitr_ix_ _______
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L13 PLANT / UNIT (S)(( k / h REV O_ PR EP AR E D '_ _.' _ _ .__ CHECKE D _~_ _~ N _ ' _ aD AT E _'_"/ _ _
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DEMONSTRATED ACCURACY CALCULATION REFERENCES / ATTACHMENTS NUMBER ----------------R EFER E N bE ( R I MS # ) ------------------
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REF ATT REFERENCE (RIMS #)
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- Loop #/tdcritifier 1 -LS-R7-21 *
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l Example: 103AS-EFN2-NS-C1A-YY (1st & 4th places in Model Number) say sweted eor a venefy of proceee and hydreutic appacates eanging from s.mpie
- see. r c.=nt poeanc. wen u,oer w.ee,y .arymo system operata ve s.
arro-do.d b.ndi wa aecept u r .rw om. and i.e s.ee veswei .m earn.,e 2.,wes e.n to me,on w. e,itm are ewed DEAD BAND 8 ERA PROOF (Maalmum) PRESSURE PRESSURE palfkswc) ter(mt.ar) poi der pe4 ber -
'1.0 2.0) (2.5 - 2.0) 1500 103 1500 103
'1.5 8.0) (4.0 20) 6.0 50) 3000* 207' 5000* 345' (15 -125) 13 (69 206) 1.5 - 5 (103 345) 1.5 6 (103 414) .1 r
2 - 10 (138 690) 30g 207 5000 345 4 20 .3 1.4 P .
5 30 .3 - 2.0 10 - 40 .72.8 35 - 150 2.4 10.3 a Oweange Presswe e the masevapresswre retcaa becontevousy acce+d to tre pesswre seesor assemedy wcout permawat'y aaenng as coe'ateg -
charscienstes 9 e Set Pont, Deas Bano) or cawsq iosaage or pe sacai r
damage 5 Proof Pressure The maseum presswee inst tai be coetevows4 4096ed to lhe pressure seesor asseetdy =4*oA causag 44aage howeve'. per*aNet --
change m ope *a'eg creracismst4s may occur or the estrweeni es, be readered rooerti've e Nymgers ag.a s'e mase e wpressw esr Maam mwc.a <e%s! p'essw ee es 1500 ps410) tae e
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SWITCHING ELEWE NT DESIONATORS MULTIPUER
'L e K, W, N i.o
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.aws omaa' E, B, Y, EF, VF i.5 A,KK,EE,YY ts AF, RF, EG, VG G, L, AA, BB 3.o
-m C, S, GG, LL, AG, RG 4.s Emunple: Model 13 93 05.N4.F1 A Masenum stavard Dead Band 6 to 12 psi G.S*,tchng Elo neot mu't'ph.r - 3 Corrected uammum Deed Band 6 (3) to 12 (3) = 18-36 psi Accroseate uamenum Dead Band at 200 ps,d set Po nt - 27 psi C
Attechment No. 3 Sheetl_cf.1_ /
Loop f/fdentifier I-l E - A7-21
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Temperature - Remote Bulb 40 - 225 F 203T A-B125-JJ TTX6 p Note 4a 203N6-B125-JJTTX6 203T A-B B125-J JTTX6 203N6-BB125-JJTTX6 40 - 225 F 20 X T A-B 125-J J TT X 6 Note 5 20X N6-B125-J J TT X6 20XTA-BB125-JJTTX6 20XN6-BB125-JJTTX6 High Static Working Pressure - Differential Pressure for Accident Conditions to 325 F/25 psi (less margin) Range Max Working Pressure Notes 5-35" w.c. 1500 psi 103 AS-8 202-N X-JJ TTX6 (7 & 11) 1850 psi (7, 8 & 12) 7-100" w.c.
103 AS-8 212-N X-J JTTX6 10-100" w.c. 1850 psi 103 AS-8 8 212-N X-J J TT X 6 (8) 1850 psi (9 or 13)20-200" w.c.
103AS-8203-NX-JJTTX6 30-200" w.c. 1850 psi 103 AS-B B 203-N X-J J T T X 6 9) 3000 psi
'1
- 3-60 psid 103 AS-8903-N X-J J TT X 6 5-60 psid 3000 psi 103 AS-B B 903-N X-J J TTX6 50-300 psid 3000 psi 102 AS-8 405-N X-J J TTX6 ( (0) 3000 psi (9 6 0) 50-300 psid 102 AS-B B 405-N X-J J TT X 6 100-500 psid 3000 psi 102 AS-B 305-N X-J J TT X 6 (9 & 10) 3000 psi (9 6 10) 100-500 psid 102 AS-B B 305-NX-J JTTX6 For availability of other ranges, please consult the factory.
Notes .
1 Test Conditions: 227*F/7 psig Acton 17 344-82 N-D /18441 -83 N 2a Test Conditions: 4350F/115 psi 5 spray Acton 17344-82N-C 26 Test Conditions: 350cF/115 psi & spray & Irradiation Sandia 83-2652 2c Test Conditions: 380 F/48 psi Acton 18577-83N 2d Test Conditions: 325 F/25 psi Acton 18878-84N-2 -
3 Formerly 8 4a Acton Report 18878-84N-4 4b Acton Report 18441-83N 5 By analysis - armored capillaries longer than 6 ft. If supported each 2 feet 6 Wall mount or direct mount 7 Evaluate chatter at set point for service 8
Anodized aluminum diaphragm plates in air service 9 By analysis - higher natural frequency 10 By analysis - o-ring sealed piston vs. diaphragm 11 Acton Test Report 18878-84N-1 12 Acton Test Report 18878-84N-3 13 Wyle Test Report (currently CECO property)
Attoctwnent No. 3 Sheet 7 of 3
% f/fdentifitt - ( ~ l- $ - R4 - t. l
I SCR QUALIFIED SWITCH LIST b TABLE 1 F ar accident temperatures to Adjustment For accident temperature 2'20F and 5 psi (Note 1) Range to 350oF and 115 psi and spray (Note 2)
Note 1 12N6-B4-NX-C1 A-JJTTX6 .5 - 6 psi (Note 2a) 12TA-84-NX-C1 A-JJTTX6 12N6-BB4-NX-C1 A-JJTTX6 (Note 2d) 12TA-BB4-NX-C1 A-JJTTX6 12N6-B5-NX-C1 A-JJTTX6 .75 - 12 psi 12TA-8 5-NX-C1 A-JJTTX6 12N6-BBS-NX-C1 A-JJTTX6 12TA-8 85-N X-C1 A-JJTTX6 1 N6-B45-NX-C1 A-JJTTX6 1 - i6 psi 12TA-845-NX-C1 A-JJTTX6 1?N6-BBuS-NX-C1 A-JJTTX6 12TA-BB45-NX-C1 A-JJTTX6 ON6-84-NX-C; A-JJTTX6 2 - 25 psi 4TA-B4-NX-C1 A-JJTTX6 4N6-BB4-NX-CI A-JJTTX6 4T A-BB4-NX-CI A-JJTTX6 4N6-85-NX-C1 A-JJTTX6 3 - 50 psi 4TA-BS-NX-CI A-JJTTX6 4N6-BB5-N X-C1 A-JJTTX6 4TA-BBS-NX-C1 A-JJTTX6 4 N6-B45-NX-CI A-JJTTX6 4 - 75 psi (Note 2b) 4T A-845-NX-CI A-JJTTX6 4N6-BB45-NX-C1 A-JJTTX6 4TA-BB45-NX-C1 A-JJTTX6 GN6-B3-NX-C1 A-JJTTX6 12 - 100 psi 6TA-83-NX-C1 A-JJTTX6 6N6-BB3-NX-C1 A-JJTTX6 6TA-BB3-NX-CI A-JJTTX6 6 N6-85-NX-C1 A-JJTTX6 20 - 180 psi e 6TA-BS-NX-C1 A-JJTTX6 6N6-BB5-NX-C1 A-JJTTX6 6TA-BB5-NX-C1 A-JJTTX6 6N6-B45-NX-C1 A-JJTTX6 25 - 275 psi 6TA-B45-NX-CI A-JJTTX6 6N6-BB45-NX-C1 A-JJTTX6 6TA-8845-NX-CI A-JJTTX6 5N6-83-NX-C1 A-JJTTX6 25 - 240 psi STA-83-NX-C1 A-JJTTX6 b SN6-BB3-NX-CI A-JJTTX6 STA-BB3-NX-C1 A-JJTTX6 SN6-BS-NX-C1 A-JJTTX6 35 - 375 psi STA-85-NX-C1 A-JJTTX6 SN6-B B5-NX-C1 A-JJTTX6 STA-BBS-N X-CI A-JJTTX6 SN6-B45-NX-C1 A-JJTTX6 45 - 550 psi STA-845-NX-C1 A-JJTTX6 SN6-8845-NX-CI A-JJTTX6 ST A-B B45-NX-C1 A-JJTTX6 Note 3 9N6-84-NX-C1 A-JJTTX6 100 - 500 psi 9TA-84-NX-C1 A-JJTTX6 Note 3 9N6-BB4-N X-Ci A-J ITTX6 9TA-BB4-NX-C1 A-JJTTX6 Note 3 9N6-BS-NX-CI A-JJTTX6 200 - 1000 psi 9TA-85-NX-C1 A-JJTTX6 Note 3 9N6-885-NX-CI A-JJTTX6 9TA-B BS-NX-C1 A-JJTTX6 Nota 3 9NS-B45-N X-CI A-JJTTX6 200 - 1750 psi 9TA-845-NX-C1 A-JJTTX6 Note 3 9N6-BB45-NX-C1 A-JJTTX6 9TA-BB45-NX-C1 A-JJTTX6 I N6-845-NX-C1 A-JJ TTX6 500 - 4000 psi IT A-845-NX-C1 A-JJTTX6 1N6-8845-NX-C1 A-JJTTX6 I T A-B B45-N X-CI A-J JTTX6 3N6-845-NX-C1 A-JJTTX6 1000 - 7000 psi 3TA-845-NX-C1 A-JJTTX6 3N6-BB45-NX-CI A-JJTTX6 3TA-BB45-NX-CI A-JJTTX6 Vacuum Cage ,
54N6-B118-NX-C1 A-JJTTX6 30" HgV to +.5 psi 54TA-B118-NX-CI A-JJTTX6 54N6-BB118-NX-C1 A-JJTTX6 54TA-BB118-NX-C1 A-JJTTX6 Tempe. ature - Direct Y.ount 201 N 6- B 125-J J T T X 6 40 - 2250F Note 4a/b 201 TA-B125-J J TT X 6 Note 6 201 N 6-8 0125-J J T TX 6 201 TA-B B 125-J J T T X 6 P
A*sachment NoJ Shut 3_o1 tsw Hldentifier /- t- s -S 1 z 1
e - - -
- 3. G CFECIFICATIONG .
Pow e r- Requirements:
115 VAC +/-10%, 60 H-e Control Ranges available:
DCVM/D-1:
0.5 to 100 PGIO full scale at up to 1000 PSIG line peasr,ur'e.
DCVM/D-2: 0.5 scale at upto to300 2400FSID PSIGfull line pesssure.
Me a su r en.en t Ranges:
Full scal e ranges consistent with the control customer spectf edranges,
' Li n e Pe er.y ehgineering units.
sur arc. Pa * '*
e Accorscy: ,
+/-0.1% Full Sc al es
~%
Da f f orents al Accuracy: (+/-0.05% Full Scale optionst)
+/-0.1% Full Scele 16 0
(+/-0 05% Full Scale optiona at At line atmospheric line pressur e.l) ,
pressure abnve g g hayrp
, atmQ5pheriC. add A calibration 'h uncertainty of +/-0.1 inch
.rst Media: water (0.004 PSI) of]
In s t r uinen t air or nitrog9n ..
(Separotor u muht be used on li qui d-filled sywrems)
Inlet Frensorse Requiromcist s:
110% of ma n i thum l i ne pr es.oure.
Pressure A w.a.fout :
Inlet Gauge : Digital 5-dtgit 1.ED dispicy.
Dimon. tons:
1-1/2" dial.
H-3/4"H x 16-1/4"W .8 10-1/4"D (19" rack mount avatloble=>
F'ressur
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FINAL. TEST CERTIFICATE FOR DIFFEREilYlAL . PRESSURE SWITCH
- Mtow ~
/i'2i G 3 M R W ITd F. l f.
} Yi '
';}:Q:'Edy($CLSR CI mT*
Custemor P.O. sptt.g37g
!O -
Salos Order No. Ca s ;*nL s:
ltom No. __ l t.w wece FINAL TEST AND CA!.lBRATION DATA lovs- eams-tux-JJrns j Saet:I numoae m 9g. 9..ry yi g.ygg i
i - .g numnu 3.w >3 .rf -).3,i,g r . _ _ _ .,. u . g r. y
] Itydroc*at!: T:sst per L or _H_ C 2.a.n .n.._ 1 u n . ?. s a u n. v tG 830t-MS 'hv. ~ / &d M- N .
Prm urY R:sults
/r n a l W e/ /fJ N ANGU > IQ.
pg, ., l ,r o,.y / W @ '*i p '
tw -
SOR U3uga Humbst rwt-
\
),f-}]*lE
- 3. ~t 1 f ,
ll%
SET POINT Call 0 RATION 4
"'lRST CYCM Set Ft., increasing '
L'1 4@-
97 g% 4 ,f f ,*
Set Pt. . Dicreasing g t/ *Q l., ff.$yffg ,.
g7,7"a Dead B:nd g 7,j % f), / % f');75e.N
/4. J ' . /# ,Yb 9, 7 b /8, D e "
SECONO CYCtj ,2 6.
Sot ?t. , incrocsIng h 9 7, Q 9 7,f"' < 9p;,
>rs L1s.y $w Ouaniy Assurance./g[M M+ ,, c, it Date 7-i' r-d A _ 'Q M _ ,M , h CAUGRA TION ('CR TlFICA TF % 4185-030 l ,p,,, ,{... .. . ....~...... n,... , ,,....i e sr e'e e un m , , P.O. BOX $91 ti705 ILACXK4 ean { y ' ~ mN& W1 S /CorWC DeWCes FINAL TEST CERTIFICATE FOR DIFFERENTIAL PRESSURE SWITCH n a LA r Customer 7"g.yN p t/Atity hwerfy Customer P.O. Mpf_C.- a574dl y SSP 11wM4 MtYlCAR PIANT" ' j' Sales Ordar No. GWt_ 9 0 0 0 c' m item No. I g FINAL TEST AND CAllBRATION OATA Model Number I g g p,y g .g. y g S*rf*I NUmDer fS* 7- J'l7f X-7-3 Y7f' C Tag Number Hydrost.atic Test ,.34,,g y ,3 y 40 9 37.gy.g ) h 8305-056 Rev. [per 4Pressurf or H_CF //N g 40 //ft 4:r' 4 *- *c Results pgy pg . < e,+ . a :- y.
- M: ; j '
SOR Caug's Number pepf - 2 7. ) . ..x. ;k.: K +=* SET PolHT CAllBRATION FIRST CYCLE
- g
- , Set Pt. , increastng 4g g' ;;
9 7, gu , , ,.Q3,; Q ,, Set Pt. , Decreasing y7,j"n g 7, , *y . Dead Band (, C /d ,7 % _. .. SECOND CYCLE *. as Set Pt. . Increasing ~ 9g ( y7pg g Set Pt. , Decreasing py,y n,g gy, ; n,,,, , , , _ Q g. ' W Dead Band,,
- __ t, _(' t, jg, 7 " e . M ' . f,L'M
.y . - , . ~ SOR Cauge Humber ,,. N'h% f'/# .
- U ..pyyM
- x ll' TEST PROCEDURE 1)
- 2) Verity that gauge has been calibrated and recorded in Q' A callbratkm log.
Connect pressure source to high sida process connection and vent low side process connection to atmosphere. 3) 4) Increase pressur.a from zero psig to increasing sat point and record. Decrease presrure to decreasing set point and racord.
- 5) Reduce pressuro to zero psig.
g }_ 6) 7) Repeat Steps 2, 3 and 4, gauge at set point immediatsly after each series of 4 Check tests andcalibration record in of,QA callbration log g - . If the gauge varies more than .1% of full scale, all pressure switches tested on the gauge since last calibration must be retested per this procedure. , , g .{~g ,. -"] Test By _..._f27,k,.. ,1. A,W ~ Dstte: n? 2 7.! ff' !~/ 6 ~tVl ~- E-l---- .. Qu a li t y A s s u r.a n c e--M . 5-+[M. u cw_ _ J - Oate 7-29 M b w e.vu a' C A t.inRATION CFRTIFIC ATF g,g 7;W 6 * ,', ' { u 6est es esos-ess see i y -s* D9'Cov.a1Nvg <?[., & Oste 10- 15-97 x- Q -[lt t TTA - 4 FE0 JECT 6 r a, ._ ;; r ld' CCMT21.CT I"7' ' 73G 533 1 Tl!LE b@,- Ph. Sc4724 . i ....y /c a t ; 'vrt Me,_.13.8dl - -je ;rp,q:n _ 49 ' - 1 My 1 - 9/25/34 5 LgJg .r.,,, APPE!'. DICES A - G GS0328T0418 @ B72 '86 0324 !l00 i . I I ihi,nu d Or. . .dest j FC3 1 l Ct'ALIFICATICni TE5flui CF g
- CLASS 1E ELECITtlCAL EQUIrMENT -
g i:: .*.CCC.10.t'CE UITH IEEE STD. 323-1974 IEEE STo r 3 Am nas2c588 . .,,, ~ Mo o "i U 5 f m =v.;;;a= : son, snc. y P.O. DOI 591 ; em ,,0't ' 11705 ELAC3308 RCAO l 9* m l f OLATitE. KS 66061 ! meesu wury M.,5=<nv g , w o u CLZ2 . .... _ . EQUlittEMT QUAT!FIED: .- SCR, Inc. O!FFERENTIAL FRE55tfiE Sv!TCHES: H00EL 10MS-8212.NI-JJTTI6 AND 'l> * ., s MODEL 103AS-3B903-HI-JJTTI6 ei' *
- ,e.
33 60's e A Purettsee creu tsa. 6951 \ .-w . 5 / ' Propww by: - - /[ M Dat w 2M Nk 8. Cox, Seniori.E.Q. Scientist / HTS /Acton [N 533 Main Street. Acton. HA 0!720 Rwlawed & 'y( ( $ Apptcved by: ./)' > f~ , . DataI,73,gi \ 4 Q ' .) h u. . ton /redkin, Jr., N.E.Q. Manager 1, $ JBC/rla:203 '. ^th*'"'No- 5 RIM % 9 ?^ C M(~ ~' _ ssect_ f._cr f r \ Lc0 / ~ LS ~ 67 '2) \ N ... - . .. p d/ldentifier .- . . . . . . . . . -....-..\ , 4p 63 % : -) i ? i i O Test Report No. 18878-84N-3 i Page 6-z I TABLE I: SUPmARY OF FUNCTIONAL TEST DATA - DIFiERENTIAL PRESSURE SWITCHE . ? - t INIT*AL ggg _ POST-IRRADIATION POST-SEISMIC { INCREASE _ DECREASE
- _ INCREASE . DECREASE _ INCREASE DECREASE 9
SETPOINT: 103AS-B212 14.76* H 2O 10.43" H 2O 14.76* H 2O 103AS-BB903 33.5 PSIG 31.0 PSIG 10.56" H 2O 15, 3" H 0 11.26" H 0 35.0 PSIG 31.5 PSla 35.0PStk 31.0 PSla3 AYERAGE DEADBAND: NI 103AS-8212 $s %.- .Y. 103AS-BB903 4.33' H 2O 2.5 PSIG 4.20" H90 3.5 PSIC 3.87" H-0 b3 4.0PS!b i INSULATION [$ RESISTANCE: Ez 103AS-8212 >100 Gohns g { 103AS-BB903 >10 Cohns >100 Cohns >400 %has >10 Gohns N > 10 Gohes DIELECTRIC W.V. 3 l.!l LEAKAGE CURRENT: l 1 N 103AS-8212 <1 mA i . ? 103AS-BB903 <1 mA <1 mA 's 2 <1 mA <1 mA D <1 mA 9 Note: l . flo No adjust:aents to the factory setpoint were made to either test unit throughout the test program. , u' } ? i p.o. K M Set 017S3 .v.cxx:3 Ac.m li %- _ l_ ,l-) t cvM. ".w.s So0M k{L , _ ] r_%&_ _ I , , , gg T'IST REPonT FOR BASELINE AND AGING TESTS AT SOR. INC. / FOR ACTON *NVIRONMENTAL TESTIhG CORPORATION TEST PROCEDURE NO. 18870-84N 5 SPECIMEN: ' HIGH STATIC PRESSURE - LOW DIFFERENTIAL PRES 5URE SYllTCH A FOR MODELS i . CMS-D212-NX-JJTTX6 (S/N M-5-357::) , l , 103AS-3B903-NX-JJTTX6 (S/N 3r.-5-3079) , 1.0 PURPOSE - To determina the influence of: "I 1.1 Set ' point on dead band
- 1.2 Static pressure on set point (
1.3 Temperature change on ses point 4 1.1 Temperature agi j anci cycle aging per Paragraph 7.2 of Acton g i Environm2ntal Testirig Corporation Test .:rc<:edure No. 18878-84N. ( j . 2.0 PROCEDURE 7~1 52t Point influence on Dead Band ,( ' i 2.1.1. Utthed - The switch was cailbretad it 10 nrid 100 inches . l w.c. using water column manometers for readout.
- 2.1.2 Results 4 2.1.2.1 S/N 84-S-3573 (
Set Point 10.od w :. 100" w.c. 64 Ocad Sand 3. 6" w , '. 7.7" W.c. ( 2.1.2.2 S/N 84-5-3579 (using pressure.gaugos for re.adout) j Set Point 5 psi 30 psi 60 psi P Dead Band 1.0 psi 3.6 psi 4.1 psi g 2.2 Static Pressure influence on Set Point (
2.2.1 Method
The switch high pressure port was manifolded to the high pressure port of a Leeds & Northrup Model a70 ~ (
differential pressure transmitter. The low pressure port was manifolded to the tranrmitter low pressure port. I Supply, equallre, and vent valves were in the rnanifold. ,
The static pressure was applied with the equalize open ind in the transmitter zero was confirmad at each static after the d supply valve was closed. The differential was then slowly changed by cracking the supp'y valve to increase and the equalize valve to decrease.
2.2.2 Results 2.2.2.1 S/N 8t 5-3578: 2.2" w.c. changi to 1G00 psi
)0 static.
2.2.2.2 S/N C4-5-3579: 1.9 psl change to 1500 psi static.
G 5 2.3 Temperature Change influence on Set Point
$ 2.3.1 Method: The switch was place in an oven. Temperature war monitored by a thermocouple placec on the switch 4 body. Pressure was read out using a manometer with th-
?-
pressure applied to the high pressure side and with the low pressure port vented to atmosphere.
F-I Atto:hment No- T gggg ;
d , 1.00 #/tdentiher I ~ LJ;-py g y
- l 4/i; '
'u ACTON TEST PROCEDURE FOR 8215-710 i U !?yS-y,s2;.Np,-y>,55L :n. .. .i I,= =. -
s t
"O' # h Sm'O% /coreido.*.e 1 -
$ 2.3.2 Results from a 0 to full scare applied pressure cycle are
. shown below:
' 1 2.3.2.1 S/N 04-5-3578:
, Set Point Set Point Temperature _I_ncrea s e Decrease 284*F 13.9" w.c. 10.2" w.c. T 70'F 13.7" w.c. 10.6" w.c. g 2.3.2.2 S/N 84-5-3579: *
"et Point Set Point E Temperature 284'F 70*F increase 31.7 psid 33.4 psid Decrease 29.2 psid ].
28.8 psid [
, 2.4 Temperature and Cycle Aging l
2.4.1 Method
With the switch in the oven, temperature was >
monitored by a thermocouple placed on the switch body. t0, Pressure was cycled using the cycling apparatus of Figure
- 2. The switch contact bad was 15 watts except one contar.t ***
was 5 amps 120 VAC on S/N 84-5-3579. G 2.4.2 Results 4
~,
" 2.4.2.1 34,674 cycles were recorded on the counter y*
/ operated by the switch contacts on S/N 845-5-3578
( and 34,674 cycles on 84-5-3579. g 2.4.2.2 A temperature 200/282'F was maintained for 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />. Using the Arrhenius equation the E equivalent 150' time g
_ 1.24 I 1 K
2
= (120.8) exp .8617 x 10' M ~ iiTTT h
= 209,022 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> Where:
exp = 2.71828
.8617 x 10" eV/*K = Boltzmann's Constant
=
1.24 eV = Lowest activation energy on switch d materials .
338.89'K = 150'F 411.11'K e 280*F ' -
l This corresponds to 23.74 yea r.= of service at l 150*F without margin. 21.58 years at 150'F with 10% margin, and 40 years at 141'F with 10%
margin.
l Q.
3.0 Data - Attached Attochment No. 6 Sheet A of 4 -
t
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Loop #/identificr / - M ~@~ b
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ACTON TEST PROCEDURE FOR WMV 8215-710 f
- 103 AS- 8212-N X-JJ TTX 6 ~.--> . r *r i l
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1 i A special test. (SQ.STRAR, INff=4)=13) wee perf ereed en the the stat 14 [
"0" ring switch Medel 103A. The switch was installed La parraist with , e, i '- ces of the Eartoe level switches and calibration was checked for a sis month period of time et 30 day intervals. The switch did set require ,
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In addition, a nattaa service representative was centracted to perform igi s
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' This helped, but still eid not prevent the evitch drif t probles totally.
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- t. Will enett shetdown be twired or startup be () (g )';.' .+ l pesvested witheet this modificatiest !! se, ..
state wy. ,
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!!!. Is this modificattee necessitated by a () ( g)' b i consitment to se esters 41 asesey or orgaattattent i,egj'.
A. Te vboe was coenitment madet $ ,,
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- 3. Attach commitment source documentaties.
[ff C. Required implementatten datet if se, h l state and attack source docusestation. 4' I D. ty whoe sad whyt D).
.3-E. Can coasttment be deferred?
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F. Ceasequences of deferring. -[
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Is this modification necessitated try A1AAAf () (x ) , k/-
B. Mig h' 1. Actmal dose rate esp riescod.
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- 1. Lapected dose rats expertesced.
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[ 1 3. A hasard analysis must be performed. (Attach results). //s /
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+: v Vill major equipment f ailure occur froe () ( g) , ,% j ;
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' act implementing this modificatient '?hy '
- 1. Cost of replacement egl i cant.
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h 3. Required saa bours to replace. (l.ist by craft and *> gt~' '
W teclude engineering and Operations support aan hours). ,
- 6. Consequences of having this equipment out of service, l:Vk, l w:.;
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Le W& OW Vill this swodification eliste. ate a (1 ) ()
D.
significant aanpower expenditure? P[64[jv);
- 1. Detail method or present procedure and shew can he,urs51 196 6 194 2 each 30 days 9%* v1 ,
erpended for each major segeent. Performance of b '. .W) requirea 8 hrs. f or instrument se 2.
tER 8 2 13 5 6 L37. P e r f orman c e f or e a : h un it Detail revised method et procedure as in ites I above.& 1 hr.pach. prep.6 revt '-hdM Jc i Replace switches with a more reliable one and return perf. of $! 196 6 196.2 to 18 hour intervale.
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- 3. State man-hours saved, mes.or. ..veo per is .onth inierv.t. <in.iead of 30 de, intervei.) t.
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?,! ESSURE, TEMPERATURE AND O!?FERENTI At PFifiduiEi j ,
SYliTCHES QUALIFIED TO lEEE '
323-197'i and 34A 10% l.~."{._C gd u.c. Oier: - t - r- -
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D continued we are enclusir,9 ei' ortantoupdated provide qualified "Abstract products of Tests"* to th{etmHAareh-h.jttear_':597Cnd .
u r .! witch testing qualified to IEEE. This abstract offers: e --
.n -
-e A det.-ile d listing of qualifi;.d pressure, temperature and differential pressure switch models available. ,
7i Concise information on the additional testing parfoimed at Acuin Environmentai Testing Corporation.
;; A synopsis of the different types of switches testoc.
H Sample dimensional drawings of IEEE qualified mo.iels.
es. applications not covered by this abstract, please contsc'. the factory for
.a, r ec< nt testing information.
T: n .4 you for your time and interest ano should you have en) ques'.lons or if ..c c.cn be of assistance, please contact.. .
- SOR, INC.
PO BOX 591 Olathe, KS 66061 Attn: Ms. Jane Peterna!
Telephone: 913-7684-2630 R 3a ds,
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. .. .O.)4.4 c. v L< d -
J d. ': Patern a.1 Nu .ca ir CMrdinator Attachment No._ 9 Sheet / oL M p,.g Loop #/ldentifier /~ 5 '
ff;;.M -05 E. P.!Jsure 4/15/85 - FWC: Mil c P. O. DesMarais Co. cc: P.IMS , SL26 C-K, , v/ attach =ents 4 513 Po 03 W 1173 E . A".< BOB AOAO CLA'"i K ANS A% 65061 9'3 764 2833 THE GAE ATER K ANSAS CITY AAC A CAB . E Sen tNO TEt.Er 42 8130 502 690 sis-: C Aa CONT AOL OFViOE L INTE ANAfsO*dAL TELEX NUMBE A 493 2783 5CA Ut M
ABSTRACT OF TESTS SOR has qualified the gage pressure, vacuum gage, high static working pressure-differential pressure and temperature switches listed. in Table 1 to IEEE 323-1974, IEEE 344-1975 and NUREG 0588.
The switches have been thermally aged to a 20-year life at 1500F service temperature (40 years at 140 F); electro-mechanically aged to 33,000 cycles, 5 amps, 250 VAC; irradiated to 33 mega* ads (LOCA unit to 223 megarads); vibration aged .75 g for 90 minutes each axis over the range of 5 to 200 Hz, OBE aged 3g 2-35 Hz sine sweep 17 minutes each axis (except reports 18878-84N-3 & 4 used five 30-second, multi-frequency shakes at S/9 SSE each axis), SSE tested at 25g over the range of 4 to 30 Hz at 1% of critical damping (Reports 18878-84N-1, 2, 3&4 included 4.59 sine beat testing). See Figure 7 for a typical TRS.
Accident testing varied according to the housing used:
Housing Test Conditions (Max) Report Reference N6 227 F/ 7 psi per Acton 17344-82N-D/18441-83N TA 435 F/115 psi / Spray per Acton 17344-82N-C 350$F/115 psi / Spray per Sandia 83-2652 3800F/ 48 psi per Acton 18577-83 N 325'F/ '25 psi per Acton 18878-84N-2 103 AS 325 F/ 25 psi per Acton 18878-84N-1 A summary of the test results is shown in Table 2.
CONSTRUCTION - These switches have a compression-set leak-resistant design for the o-rings in pressure ports (new in SOR's nuclear-qualified switches). . . .
The materials of construction are:
316 Stainless Steel Pressure Ports - 1 NPT Kapton Polyimide Diaphragms Cast iron Switch Housings -
Steel Bodies EPR or Fluorocarbon 0-Rings and Gaskets Glass-to-Metal Electrical Entry Seal with Epoxy Wire Support Silicone Rubber (Glass Braid impregnated Wire Insulation)
Silicone Rubber (Secondary Diaphragm)
Honeywell 11SM244 high temperature micro switch ANALYSIS divided by -piston On the basis of higher natural frequencies computed from spring rate mass, identical materials , mechanical construction features and equal or lower tctal weight the untested switches listed in Table 1 are also qualified.
SEE MOUNTING FIGURE
_ Pressure Switches N6 Housing {-20 Screws - 2 at 14 ft-lbs 1 TA Housing 1-20 U-Bolts - 3 3 Ano:hmer.t No. Y L#
- Loop #/ider.tifier I ~ O "'
~
SEE M O U N Y i4G FIGURE T.u. .x n wre Switches
.. - mng ;-PJ u ms - 2 at 85 in-lbs plu; .up,: ort armored
- 41: uch 2 ft '2 .
.c, .n :. 791ts - 3 4
. n.ng . .c_ '.launt on Thermowell 's D -r e ! Pressure Switenes to n Housing with Teismic Bracket 7" Bolt circle to match Barton 1 - 20 Grade 5 bolts - 4 at 85 in-lbs 5 1 e., .W: sing with Base Plate 5
. >a d - Replace the cover gasket each tima the cover is removed (exct,'t
, . i.n dju s tmen t ) . Calibration frequency is not reccmmended by SOR as r1 4 , main ging and calibration changa re.sults.
's5T!TUTIONS - For oli sarvica, flu,,Gct.chan < . h.9 s e..Ly Le ut.ed .f
.- O- EPR is not comnatible with hydrocarbcns. Monal pra::su ra ports
-"" al:chos only) and longer leads are available.
Ji 1.'G'ilS AND PROBLEMS OF THE TEST PROGRAM.
12tr.arorcof Pressure - The 12N6-84 in Test 17344-82N-D was not operated during IIDimidity test so addendum tests were run on this unit in 18441-33N at 227 F/7 p a tt. the lead wires external to the seal exposed to the steam. The pressure in the enclosed housing caused by the thermal expansion of the air is shown on Page o 0: ...a .:ddendum report to reach 5.8 psi and is the cause of the increase in cet
,. . . , .y 3. 3 psi .
T am.w rc ture Ya h 2 F. T A- B 12 5 was irradiated as part of 18441-83N to determine the radiation' ~ "
- if:ct on Freon 12. Since there was none and the 201 T A-B 125 is a 5T A-B 45 prescure s wi'.c h with a temperature bulb charged with Freon 13 attached, the pressure switch qualification applies. In 18878-84N-4 both local and remote bulb temperature switches were te M.ed through seismic, including sine beats. The operability requirements during seismic tests are shown by the similarity of .the pressure switches in Reports 17344 and 18878-84N-2 which were operated during seismic.
Differential Pressure tee I C 3 AS-8 202 of' Report 18878-84N-1 when subjected to the 39, 2 to 35 Hz sinucoidal OBE aging was being~ pressure cycled by its own contacts operating alternating current solenoids, and contact chatter input resistors. -The interaction of vibratic,n and induced voltages from the solenoid coils "painted" the chart. For the SSE tests, the pressure was cyc;ed using a timer to drive the soienoids and a DC chatter monitor circuit for the visicorder; also equal water legs were added to the differential pressure input to provide damping.
We obs2rved Commonwealth Edison's test of a Model 103 AS-B203-NX .U TTX6 on Wyle's triaxial table and can report that no chatter occurred during SSE's with water legs or the SSE after draining the water out. This model uses a simple base mounting plate instead of the bracket designed to match with Barton's 7" bolt circle
- mounting holes as tested at Acton, i The soppicmental tests of 18878-84N-3 were run to determine the seismic influence switches.ghtly higher range and higher natural frequency different al pressure on a sli The test showed if there was chatter (oneA:P:h o?-JeusSE-e t!<. runi S--anti
. tF{1WCA
.... l-l.s-8 7- 21. . -
-.-. .. . .~c 1
. sine beat frequencies and orientations on the 1AS-B212 only) it occurred between the increasing and decreasing set points near one of the et points. These tests were run with air on the diaphragms (no water legs).
The .7 megohm insulation resistance reading during the HELB shown on Page 7-49 of Report 1887B-84N-1 is addressed in the conclusions.
H!GH TEMPERATURE PRESSURE AND LOCA The 12TA-B4 of Report 17344-82N-C operated through the first cycle of the LOCA test exhibiting similar increases in set point due to thermal expansion of the air trapped in the housing as was observed in the Sandia t>nt (Test Report SAND 83-2652) on two of Model 4TA-845. However, in the second cycle (See Figurn 2 and Table 3) operating pressures were close to external ambient pressure because the Loctite in the through-tapped hole blew cut at 430 /115 psi. The Loctite did not blow out at 350cF/115 psi in the Sandia test. (The Switch operated in spite of the steam in the housing. ) The corrective act.'on was to bottom tap the holes in the casting and test the housing seal integrity in Addendum Report 18577-83N.
- The pressure buildup in the sealed housing is offset by the natural temperature influence on a vented pressure switch approximated by the equation.
Sealed Natural Housing Temperature Effect In0uence Change in Set Point = .04 psi -
.0003 x SP oF GF *F ,
For example, for a 100*F increase in temperature and a 200 psi set point
.04 x 1000F .0003 x 100oF x 200 pri = 4 - 6 = -2 psi in 18878-84N-2, the OBE data was interfered with by the differential -
pressure test rig. Since OBE is for aging and the SSE and sine beat data were good, the OBE data was not rerun.
For further in formation , please contact SOR, Inc., PO Box 591, .Olathe, Kansas ,
66061 (Phone: 913/7.64-2630). Direct your inquiries to Ms. Jane Peternel.
Abbreviating IEEE Institute of Electrical and Electronic Engineers NUREG Nuclear Regulatory VAC Volts alternating current
! LOCA !oss of cootpnt accident g 32.2 ft/sec = acceleration of gravity
[ Hz Hertz = cycles per second OBE operational basis earthquake SSE safe shutdown earthquake ,,.
j TRS Test Response Spectrum (Scismic) ~
EPR ethylene propylene rubber DC direct current HELO high energy line break accident SP t int - - " - - ~ ' - ~ ~ ~
psi ounds per square inch ! Attochment No.
9 Sheet + cilS-l "wc inches of water column (differential) Lxp #/ identifier /M~@$
'Hg inches of mercury column (vacuum)
I
SOR QUALIFIED SWITCH LIST TABLE 1 Foi s ;. at temp cm m to Adjustment W. mc ?or a dmt temparature
. :sl (Moto 1) Range :.; .4505F .nd
- 15 psi and t.y ,; ote 2)
.. 7.- n +.': A -JJTTX6 .5 - G psi (Note 2a) 12 TA-34-NX-C1 A-JJ TTX6
:i:-SS4-NX-C1 A-JJTTXS (Note 2d) 12TA-GB4- X-C1 A-JJTTX6
' ~> MS-3 5-UX-C1 A-JJTTX6 .75 - 12 psi 12TA-65-NX-CI A-JJTTX6
!!N6-BBS-NX-C1 A-JJTTX6 12TA-a B5-NX-C1 A-))TTX6
"?
5-945-NX-C1 A-))TTX6 1 - IC ai 1 EiA-345-N X-CI A-J JTTX6 7 Bus-MX-C1 A-JJTTX6 12TA-CBir.,-N X-C e A-) s iTX6
-:c -NX-CI A-JJTTX6 2 - 25 psi 4 *f A- B U-N X-C 1/v .' .i T T X 4
^ /,- N %-C1 A-JJTT X 6 iTA-i304 ilX-Cle.)T TX6
HY -C1 A-JJTTX5 3 - 50 p31 6" A-3 5 ilX-C1 s . J TTX6
' 35 *4Y-CI A-JJTTX6 .TA SL5-W:-CleJJ (TX6
'm-B45-NX-C1 A-JJTTX6 4 - 75 psi (Note 2b) 4T A-3 4 5-NX-C1 A-J JTTX6 m 3 345-NX-C1 A-JJTTX6 'iTA- B B 45-N X-C 1 h-JJ TT X 6 m
9 9 3-NX-C1 A-JJTTX6 12 - 100 psi 6TA-83-NX-C1 A-JJTTX6
- !5-3B3-NX-C1 A-))TTX6 6TA-8 B3-NX-C1 A->JTTX6 S NS-8 5-NX-C1 A-JJTTX6 20 - 100 psi 6TA-B5-NX-C1 A-JJTTX6
' ' M-B B S-NX-C1 A-JJTTX6 6TA-B85-NX-C1 A-JJTTX6 G T16-8 45-NX-C1 A-JJTTX6 25 - 275 psi 6TA-Bri5-NX-CI A-JJTTX6 SN6-BB45-NX-C1 A-JJTTX6 STA-DS45-NX-CI A-JJTTX6
~ "5-33-NX-C1 A-JJTTX6 25 - 240 psi STA-83-NX-C1 A-JJTTX6 SN6-BB3-NX-C1 A-J)TTX6 STA-BB3-i4X-C1 A-JJTTX6 5 N5-85-NX-C1 A-JJTTX6 35 - 375 psi ST A-85-NX-C1 A-JJTTX6 ---
SN6-B B5-NX-CI A-JJTTX6 S TA-BB5-WX-C1 A-JJTTX6 SNS-0 45-NX-C1 A-JJTTX6 45 - 550 psi STA-B45-NX-C1 A-JJTTX6 5N6-BB45-NX-CI A-JJTTX6 STA-UB45-NX-CI A-JJTTX6 Note 3 9N6-8 4-N X-C1 A-JJ TTX6 100 - 500 psi 9TA-84-NX-C1 A-ljTTX6 Note 3 'JN6-B B4-NX-C1 A-JJTTX6 a 9TA-BB4-NX-C1 A-JJTTX6 Note 3 9 N6-B S-NX-CI A-JJTTX6 200 - 1000 psi ~
9TA-85-NX-CI A-JJTTX6 Note 3 DN6-BBS-NX-CI A-JJTTX6 9TA-BB5-NX-C1 A-JJTTX6 Note 3 9N6-845-NX-CI A-JJTTX6 200 - 1750 psi 9T A-845-NX-C1 A-JJTT X6 Note 3 9N6-B B45-NX-CI A-JJTTX6 9TA-BB45-NX-C1 A JJTTX6 1 N6-845-NX-C1 A-JJTTX6 500 - 4000 psi 1TA-B45-NX-C1 A-JJTTX6 1 N6-BB45-NX-C1 A-JJTTX 6 I TA-BB45-NX-CI A-JJTTX6 3N6-B45-NX-C1 A-JJTTX6 1000 - 7000 psi 3TA-845-NX-C1 A-JJTTX6 3NS-BB45-NX-C1 A-J)TTX6 3TA-BB45-NX-C1 A-JJTTX6 Vacuum Gage 54N6-0118-NX-C1 A-JJTTX6 30" HgV to +.5 psi 54TA-B118-NX-CI A-JJTTX6 54N6-BB118-NX-C1 A-JJTTX6 54TA-B B113-NX-CI A-JJTTX6 Temperatura - Direct Mount 201 N S-B125-JJ T T X 6 40 - 225 F Note 4a/b 201 TA- B 125-JJ TTX6 Note 6 201 N 6- B B 125-JJT T X 6 201 TA-B B 125-J JT T X 6 l Atto:hma.t N;. T EM 5._e .m Loep/ ,' /lden*ific.-IND
Temperature - Remote Bulb Note 4a 203N6-B125-JJTTX6 40 - 225'F 203TA-B125-JJTTX6 203N6-BB125-JJTTX6 203TA-BB125-JJTTX6 Note 5 20X N6* B125-JJ TT X6 40 - 225'F 20XTA-B125-JJTTX6 20XN6-BB125-JJTTX6 20XTA-BB125-JJTTX6 High Static Working Pressure - Differential Pressure for Accident Conditions to 325'F/25 psi (less margin)
No,tes Range Max Working Pressure 103 AS-B 202-N X-JJTT X6 (7 & 11) 5-35" w.c. 1500 psi 103 AS-8212- N X-JJTTX6 (7, 8 & 12) 7-100" w.c. . 1850 psi 103AS-BB212-NX-JJTTX6 (8) 10-100d w.c. 1850 psi 103AS-8203-NX-JJTTX6 (9 or 13) 20-200" w.c. 1850 psi =
103AS 3B203-NX-JJTTX6 (9) 30-200" w.c. 1850 psi 103 A'.-8903-N X-J J TT X 6 3-60 psid 3000 psi 103 AS-B B903-N X-JJTTX 6 (12) 5-60 psid 3000 pal 102 AS-B 405-N X-JJ TT X6 (9 & 10) 50-300 psid 3000 psi 102AS-BB405-NX-JJTTX6 (9 s 10) 50-300 psid 3000 psi 102 AS-0305-N X-JJTT X 6 (9 L 10) 100-500 psid 3000 psi 102 AS-B B 305-N X-JJTT X 6 (9 f, 10) 100-500 psid 3000 psi For availability of other ranges, please consult the factory.
Notes 1 Test Cor.ditions: 227'F/7 psig Acton 17344-82N-D/18441-83N '
2a Test Conditions: 435*F/115 psi 6 spray Acton 17344-82N-C 2b Test Conditions: 350*F/115 psi s spray s irradiation Sandia 83-2652 2c Test Conditions: 380*F/48 psi Acton 18577-83N 2d Test Conditions: 325*F/25 psl Acton 18878-84N-2 3 Formerly 8 4a Acton Report 18878-84N-4 4b Acton Report 18441-83 N 5 By analysis - armored capillaries longer than 6 ft. If supp,orted each 2 feet 6 Wall mount or direct mount 7 Evaluate chatter at set point for service 8 Anodized aluminum diaphragm plates in air service 9 Dy analysis - higher natural freque.7cy 10 By analysic - o-ring sealed piston vs. diaphragm 11 Acton Test Report 18878-84N-1 12 Acton Test Report 18878-84 N-3 13 Wyle Test Report (currently CECO property)
Attochment No.-- 9 Shect fELof /_f2.
Loop #/ldentiflor _/ -/ S ->97- 21 s
.w-o
-6 -
. TABLE 2 Model 3 . Post Post Post Serial # Report initial Radirtion Seismic Accident 171 c.. H ri a 17344-D 7.5 psi 2.7 psi 2.6 psi- 2.5 psi to . , 17 (.'/ 18441- 2.86 psi none none 3.0 psi
) Ti A -i q l'/344 C. 2.5 psi 2.9 psi 2.56 psi 66.0 psi Note 1 82 b-304 12TA Ott 18577 3.05 psi 3.20 psi a'c f 7e'/ 8 m6 B1311 18878 2 3.0 psi none 3.0 ps! 3.1 psi cs . u . y,) 3 ,
sti/ ta! 5ANI)lA 38.0 psi Simo w/LOCA 38 0 p:tl 38.0 psi s'/ 5 1b49 R 83-2652
.:J1T A Hi>5 18441 182.SoF 178.3*F S3-t 3530 201 T A-B 125 18878-4 45.3 'F 41.5 'F 46.8 'F 0'l i. 2440 703f46 Il125 18878-4 42.0 *F 37.4 'F 39.7 'F 84-S ?440 103A5 H207 18878-1 7.48" wc 6.45" we 7.16" wc- 7.10" we 83-9-3610 103A5-D212 18878-3 10.43" wc 10.56" wc 11.26" we 84-5-3578 103AS-BB903 18878-3 31.'0 psid 31.5 psid '31.0 paid 84-b-3579 4 Nnt No readjustments of calibration were made during test program.
Note 1 Page 7-43 of 17344-C report shows operation OK thru 700 hours but steam leaked in. See Test 18577 for corrective action on leak.
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k-f SQNP SI-196 Page 9 APPENDIX A Revision 9 Page. 2 of 19
'LNIT _
Date --
- 7 511TN.i si? ' Jill LE/SL SWITCH LS-87-21 (continued)
'.7
.1cinatall the vent plugs and connect a calibration pressure source to the high aida of the water box.
IM h"/
k 1.3 Ccnnect a continunity tester across the ~
- stninals 11A and 1106VG in JB 1612 (U-1)
;r tccminals 21A and 2106VG in JB 2164
(,*)
(C-2).
O 1,9 IM CJsuly increase the pressure to the high side of the switch'(water box) until
- ntact closure occurs. Repeat two times to en:ure repeatability. Record the "As Tcund" values below.
d
?jo E: Unit 1 and 2 have different setpoints.
E' Select the unit being tested and N/A the unit not being tested.
Desired TS Allowable As Found As Left 1-LS-87-21 122.02 1" H 0 e 2.0" H2O 2-LS-37-21 129.18 = 1" H 0 m 2.0" H:0
/
gg IM Date 1.10 If the "As Found" values are within the -
desired tolerance, record the "As Left" values.
1.11 If the switch is out of TS allowable tolerance, notify the SIMF. N/A if not g applicable, y
l
- IM
- 1.12 If recalibraton is required, recalibrate and record the "As Left" values.
Attochrnent No. 10 Shect10 Loop f/ldentif;er j - t c;- 8 7- 2 L_.
9 0139R/n1t
- WB
- ()i I
E s
Pg SGMP
- h. .
SI-196.
Page 23 APPENDIX B Dago 2 of 18_ .70Vicion 9 UNIT Date
". 1.0
=
CALIBRATION OF UHI T2 VEL SNITCH LS-87-22 (continued).
1.7 Reinstall the vent plugs and connect a 1 -
calibration pressure source to tho high side of the watar box.
1.8 Connect a continunity tester across IM .
terminals 12A and 1206VG in JB 1613 (U-1) or terminals 22A and 2206VG in J3 2165 (U-2).
IM
' f".
- 1. 9 - Slowly increase the. pressure to the high side of the switch (water box) until contact closura occurs. Repeat two times to ensure repeatability. Record the "As Found" values below. '
y NOTE: Unit 1 and 2 have difforent g setpoints. Select the unit balng tested and N/A the unit not balng tested. -t-Desired TS Allowable As Found As '. aft Q 1-LS-87-22 124.02 = 1" !!:0 e 2.0" Il:0 *
.3 ,
2-LS-87-22 125.98 2 1" H 0 x 2.0" H2O I
IM Date
'g 1.10 If the "As Found" values are within the desired tolerance, record the "As Left" values.
1.11 If the switch is out of TS allowable '
tolerance, notify tne SIMP. N/A if not required.
IM 1.12 If recalibraton is required, recalibrate and record the "As Left" values.
A*to& ment No. /O Shee L&__cf.d"
- 0142R/mit
; L v t/ldentif; r /7_ l S '87'._Al_
l l
I-3QNP h SI-196 Page 46 APPENDIX C Revision 9 Page 2 of 18 UNIT Date
, *J c;.LIBRATICl! Oh' UHI I2/EL SMITQt LS-87-23 (continn!)
- 1. ~l loinstall the vent plugs and connect a calibration pressure source to the high side of the water box.
~
,IH
- 8 .
.act a centinunity tester across terminals 13A and 1306VG in JB 1614 (U-1) a.- arninale 20A and 2205VG in J3 2166
(!!- 7. ) '.
s IM 1.0 Slowly increase the pressure to the high side of the switch (water box) until y contact closure occurs. Repeat two times to ensure repeatability. Record the "As .
round" values below.
!!OTE: Unit 1 and 2 have difference setpoints. Select the unit being tested and N/A the unit not being tested.
Desired TS Allowable As Found As Left 1-LS-87-23 122.02 1" H 0 e 2.0" H 0 2-LS-87-23 129.18 1" H 0 m 2.0" H 0
~
/
IM Date
-1.10 If the "As Found" values are within the desired tolerance, record the "As Left" values.
1.11 If the switch is out of TS allowable
- tolorance, notify the SIHF. N/A if not I required.
- IM 1.12 If recalibraton is required, recalibrate -
and record the "As Left" values.
i
' Attechment No._ / h Shect h CI b Loop #tdentifier / ~$3'b7~21" .
w
- l2 SQ!!P SI-196 Page 64 (0
- APPDIDIX D Revision 9 Page 2 of 18 UNIT Date 1.0
__ CALIBRATION OF UHI LEVEL SWITCH LS-87-24 (continued)
L 1.7 Reinstall the vent plugs and connect a calibration pressure source to the high side of the water box. .
IM
. 1.8 Connect a continuity tester across
' terminals 14A and 1106VG in JB 1615 (U-1) or terminals 24A and 2406VG in JB 2167 (U-2).
IM
- g. 1.9 Slowly increase the pressure to the high
*~ side of the switch (water box) until contact closure occurs. Repeat two times to ensure repeatsbility. Record the "As
'Found" values below.
FIOTE: Unit 1 and 2.bave difference setpointili:' ' Select 'thb"On1t baing tested and Fl/A the unit not being tested. "
Desired TS Allowable As Found As Left 1-LS-87-24 124.02 m 1" H2O 2 2.0" H2O 2-LS-87-24 125.98 s 1" H 0 e 2.0" H 0 -
H '
IM Date 1.10 If the "As Found" values are within the g desired tolerance, record the "As Left" u values.
Q 1.11 If the switch is out of TS allowable 3 tolerance, notify the SIMF. ~
tJ/A if not required. IM 1.12 If recalibraton is required, recalibrate and record the "As Left" values.
At:::hment fJo- 1 onticLA*
, ,y_y _$
Lenp g/tdentificr 0144R/mit o . -
( . Rec orde<
.,- Bot Recordec V , Distributeo NUCLEAR EMINEERIM OIRECTOR'S CF,FICE FtXJilNG/0!SinitwilCN 6 .Fi RIMS 10, 8 db d k 7 DATE RECEIVED7 .2-85 OAi; OF MCUMENT [ ~]o "Ib Ffu0l!K. CtJE CATE / /
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OlPECTC4'S OFFICE ROUilf/;
ROUTE I folE0 CCUEN TS .
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_ RIMS VERIFICATKW FIL E -
C'.'E IXY2K!!4 F ILE I (TOSS AFTER ROUTIE PEN 0lM DUE DATE / / /
COPY DISTRIBUllON /_
COPY / CCPY H. Pwkner, W C155 C-K R. O. Barnet t, W9 D224 C If K. T. Myers, Wil 819 C-K W. D. Hall, Wl? C62 C-K C. A. Chandley, H7 Cl26 CIK C . L . O' De l l , W5 C99 C-K R. R. Hoes t y, 9-li s $8.K J. P. Fenton, W5 Dl?6 C-d S. A. Shitmin, W4 0224 C-l C. W. Kiloore, W12 0151 C-K M. L. Rayfield, P-104 SB-K
(- W. S. Raughley, W8 Cl26 C(K J.T Ta'uIston,' WTo TIFc!K J. P. Stapleton. A10-8FN EM i. W. Roberts W5 0181 C-K l . Tumel, Wil Cf;8 C-K J. P. Vineyard, Wl2 C61 C-K C. E. Cantrell, LP SS 85E-C D. W. Wilson, DNE, OSC-A, SW t. W. lau, W10 0??0 C-K J. N. McGriff, BR SN 75A-C J. H. Miller, LP $5 1500-C RIMS, SL 26 C-K WOTE: /-Inform 3 tion H - Handle R.- Reply ', " , or (1), etc. - See notes Affachrnent No. // Shee t_/_o f_f_,
Loop #/ldentifier _l-LS-R7-? I 0967A (Use other sida for additier.al notes)
,( 45 L k\*
s.a e c ~ L28 860630- 997-TO : J.
Br . McCrif ch,, BR SNf, Chief, 15A-C Electrical and Instrument and Controls Services 7 ROM i F.BRH.SSoiler, 59A-C Supervisor, Instrument end Controls Enginearing Section, JUN 3 01986
SUBJECT:
SEQUOYAH (SQN), BROUNS FERRY (BFll), AND WATTS BAR (UDN) UUCLEAR PLANTS - MEETINC PRESSURE SWITCHESHIlTUTES - ERRATIC BEHAVIOR OF STATIC-O-RIUCS (SOR) DIFF 1.0 Dato and Place of Meeting The r.eeting was conducted on' June 12, 1986, at the Nucicar Regulatory Commission (NRC) of fices in Dethesda, !!aryland. Attachment I documents the meetin5 aSonda. 2.0 Attendanec 2.1 Attachment 2 is a complete list of the attendees. . 2.2 TVA attendecs: W. C. Ludwig. Nuclear Safety and Licensing Staff F. H. Siler Instrumont and Controls En51neering Section ,,, J. D. Thompson, Instrument Maintenanco Section DFN J. D. Wolcott, Licensing Staff, DFN 3.0 Cornents 3.1 In openin5 comments, Cary Holahan of URC stated'that the meeting was called so Nnc could determine if directives should be issued to utilitics as a result of SOR instrument failurcs at LaSalle Generating Station. He stated that representatives from LaSa11c and Oyster Crcok Nuclear Ceneratin5 Stations would describe testing which they are conducting on SOR differential pressure switches and asked all other utilities pecsent to describe their use of SOR differential pressure switches and to provido any testing history available. 3.2 TVA responded that the only SOR differential pressuro switches installed at SQN had bee, in service only a short perio d of time prior to the LaSailo v'ent; c-dy the initial instrument calibration following installation had been performed. However, a calibration was performed as a result of the LaSalle i Atte ener II ShM' L CI Y-- y p. _]-l % 97-2I r ' " ~ "
2 J. !!. McGriff SEQUOYAH (SQN). UROWNS FERRY (BFN). AND WATTS BAR (UDN) UUCLEAR PL MEETING MINUTES - ERRATIC DEHAVIOR OF STATIC-0-RING (SOR) DIFFEREN
' RESSURE, SWITCliES C
event. All SOR switches were within their Technical Specification limits. TVA described the special test conducted on one SOR differential pressure switch prior to its installation. ?tRC cnly notcd that ua hcd positivo results and did not ask for copies al the tas. dets. TVA stated that we were in the peciaas of installing SOR differential pressure switches at 3rN fer residual heal removal (AHR) miniflow valve actuation. This mcdification his been put un hoic. No utility present, other than LaSalle and oyster Creek, has had an SOR dif ferential pressure switch installed long enough to gather periodic calib. ration data. 3.3 Oyster Creek installed SOR differential pressure switches for both low and low-low level scram and safeguards actuation service. The model switch used for low icvel had one micro switch while the model switch used for low-Icw icvol had two micro switches. Otherwise, the switches were physically identical. At the first 30-day surveillance interval, one of ,, the low level switches was out of tolerance. At the next surveillance interval, a different low level switch was out of tolerance. The frequency of testing was increased to overy two weeks. Switches continued to be discovered out of tolerance with no recognizable pattern. During this period, the low-low *
- level switches remained within tolerance. '
The low icvel switches were installed with the instrument sense line connected to the upper tap.
, be used for liquid service. SinceSOR recommended the lower tap the lower the level, the greater the differential pressure, the setpoint for low-low level was in the upper part of the instrument span while the low level setpoint was in the lower portion of the span.
Although extensive testing by Oyster Creek and SOR could not determine why the low-low level switches performed bettse. Oyster Creek is replacing the low level switches with the same model SOR switch as is used on low-low icvel application. They are also installing them in the same instrument configuration. 1 4 A
- f 7 ;' M' .' a .' ' .'T I
I.L:.p 'l,. M ;! n m l - b 3__~ b 7 ' 2d . I
'l 3
J. M. McCriff . SEQUOYAH (SQN), BRO'. INS FERRY (UPN), AND 1/ATTS DAR (t/DN) ;MCLEAR PLANTS - MEETING !!INUTES - IRRATIC 3EHAVIOR OF STATIC-O-RINC (SOR) DIFFERENTI PRESSURS, SWITCHES 3.4 Af ter the June 1,1986, cvont, LaSallo Nuclasr Station initiated a testing program on all installed SOR switches. Preliminary conclusions are that the dif ferential pressure cwitches have a definite shift
.. hen calibrIIec at atmosphora pressuro and subsequently
.mbjected to system operating pressure of over 900 psig. The amount of shift is not consistent from switch-to-switch. This phenomena suggests that calibration chould be pcrformed at the system operating pressure.
The switches also exhibited a definito setpoint difference between the first actuation af ter a prolonged period of inactivity cnd successive actuations. LaSalle believes with enough test data they can nodify their testing / calibration procedures and/or system setpoints to assure themselves and URC that the unit will be sofs to operate. However, they are also looking at other contingencies such as installing en analog trip system (ATS). 3.5 General Electric Company (CE) representatives gave a short presentation on the safety significance for boiling water _ reactors of the failure of the reactor to scram at the low reactor watcr level setpoint as experienced at LaSalle. According to CE, tha safety significance was very low if the reactor water low lovel scram did not occur at the plant Technical Specification setpoint. In-response to an NRC question as to why the Technical Specifications were so rigid, CE stated it was believed the instrumentation used would meet these limits; thoroforo, these setpoints were put in the Technical Specifications. LaSalle has contracted CE to conduct a new safety analysis to determine more appropriate and realistic limits on water level actuation setpoints. 3.6 So J made a icngthy procentation on the design and operation of the SOR dif ferential pressure switches. They conceded that testine. has determined approximately 2" H9 0 dit terence in-setpoint on first actuation and successivo actuations after a switch has been subjected to operating pressure. Subj ecting?
'the switch to system operating pecscure hardens tho two "O" rings in which a shaft must rotate approximately one degree to actuate the Af tc;hment No._ ll Shest & of T l
_locp A/ldentihcr _ l ~ /S-87-3 ) l
4 J.11. licCrif f SEQUOYAH (SQU), BROWNS FERRY (BFN), AND WATTC BAR (WEN) UUCLEAR PLANTS - IIEETING MINUTES - ERRATIC DERAVIOR CF STisTIC-0 9100 - (Sca) DIFFERENTIAL PRESSURE, SWITCHES micro switch. This adds to the backforce used to determine the actpoint. SOR stated that they are conducting a test program designed to give more data about switch performance at operating pressures typical of r.hoso 00en in power plants. SOR plans to issua e.are detailed cali*uration procecures based on the results of these tests. 3.7 Concluding remarks by NRC were that chay 5.o no need at this time to issue any directives to tha sit'.litita. They ulll be looking closely at the results of te: ting at LaSalle, Oyster Crack, and 3EE 4.0 conclusions 4.1 BFN does not use SOR differential pressure switches for low reactor water level scram functions. However, we do have plans to install them to control the RER miniflow valve actuation. 4.2 SQM uses SOR differential pressuro switches for upper head injection valve closure. We have limited operating axperience with these switches but have not seen similar problems in this .. application. 4.3 URC decided there was no need for regulatory action at this time. 4.4 BothSQNandBFNshouldreviewtheircalibr$tionproceduresto verify that they are adequate and take into account the difference in setpoint at operating pressure as well as different setpoint for first-time operation. 4.5 In light of the statements by CE, one should take a new look at the values used in determining setpoints for the ATS modification channels. Some of the setpoints were difficult to meet when based strictly on plant Technical Specification values.
/Y . ./
'r' F. H. Siler NTH:FMS:MRH Attach:.ents
***
- P'8 ' A' Wh r u ' t ,' .' // D., u 5 g '/ l tc:p c/Leriiher - /~&M4 l 8** 08 M 1)Id 5'*g8 d* %'10 8." 3 N % Ma, w as es *M M e me
J. H. McCriff SEQUOYAH (SQN), BRO',nIS 72RRY (BFN), AND UATTS DAR (UDU) MICLSAR PLANTS - P?.ETING HItNTES - 2RRATIC 32HAVIOR OF STATIC-O-RIt!G - DIFFERENTIAL (003) PRESSURE, SWITCHES cc (Attachments): / RIMS, HR 4H 72A-C- # C. R. Brimer, OES. Sequoyah ! R. E. Durms, I!!S, Drowns Ferry F. E. Dicola,1112 A6 C-K H. D. Stkins, IRS, Sequoyan H. L. nayfield, Untta Dar J. P. Stapleton, Browns Ferry D. W. Wilson, Sequoyah o337C .w, : .
, . - _. ~ . -
l / n n :e t:. II , .. f}~qm j i : 4.'!Jer r: : .J 87- N
,.~. -
l Attachment 1 STATIC "O" RING DIFFERENTIAL PRESSU;1E' SWITCHES MEETIt!C ACENDA
, JUNE 12, 1986 -
- 1. h'elcoma and opening Comments -
Holahan/ Jordan
- 2. Sutxnaries of Operating & Haintenance Utilities 3:Geriences -
- Lt.0alle
- Oyster Creek
- Browns Terry
- Coquoyah
- Othces
- 3. Sat'ety Significance for BWRs (Design / CE Licensing Basis) -
- Rx Water Level
- Other Applications
- 4. Design and Operation of SOR dP Switches - SOR. Inc.
- 5. Discussion of Possible Future Actions - Open
- Reporting
- Testing
- Calibration
- Potential Replacement or Modification . . . .
6 Concluding Remarks Holahan/ Jordan
~
AttachmeAt No. II b of-Loop #/ldentifier 1 -LS - 82OI -
Attacluent 2 Attendees Wayno A. Priest Rosa E. Johnson SOR. Inc. Harry P. Hartman SOR, Inc. Chief Dasi;',n Engineer ltus2011 C. Engel SOR. Inc. Exec. Vice President COR. Inc. Manager, QA rom H. Crawford tenn;th R. Eibon Houston Lightn.& Power Uuclear Sales Manager fom H ctson CPU-Nuclear Ctaff Engineer ~IIhn R'.gers CPU-Nuclear I&C Engineer TC2k Donshew GPU-Nuclear Project Engineer
- Crry Nicholson NRC Licensing Engineer Ib Samworth NRC Project Manager NRC-HFO negion II smont E. Youngborg CE
. C. PfGfferlen Sr. Reactor Sys. Engr. >b Picrson CE Principal Engineer NRC Manager, IE, PAT BWR Licens. Prog. , Cr t nhuis -
o H21cnich NRC
'J. Kanyon NRC Projttet Manager J. Feccman NRC Project Manager _,
rjcrio Widmeyer UPPSS Project Manager ' n McCtw WPPSS Technica1 Staff ivell Porter SCE Technical Staff in C. Bradfule WPPSS Licensing Engineer B. Vcssallo NRC Engineering _ r. , cs J. Shea NRC Project Manager -
,ccnt D. Thomas NRC Chief, FOB /NRR W. Domenick NRC Project Manager, MP-1 NHC IE/ECCR n311u3 T. Coddington IE/ECCR X. Tr;hin PA Power & Light,. Co.
soiro C. Daldiaz NRC Senior Project Engineer EICSD/DDL tin C. Santic PA Power & Light. Co. I&C/C Supervisor m is S. Abel Commonwealth Edison I6C Supervisor ' eth L. Craesson Commonwealth Edison Energy Manager col S. Turbak Cor.unonwealth Edison Div. J.P. Nue. Sta,
.k H. Siler Commonwealth Edison C. Ludwig TVA Nuclear Licensing Lynch TVA ICC Enge. Sec. Supervisor anco H. Root NRC Nuc. Safety & Licensing * . Ab31afia INPO NRR/DDL/PD 03 W . Th:mPson Northeast Utiliti;s A&E Division Wolcutt TVA .
Nuclear Operations
'iniv stn TVA 16C, Browns Ferry dg;s NRC Licencing, Browns Ferry llins NRC NRC/DDL/EICSB DDL/RSB rsilo NRC '
NRC DDL/RSB Chief, BWR Assessment Br. Attochmer.t No I __._._ .' x cf b L Jc* "'*"2_.lib?:M=EI.3 .
1 o
-2 E. daker . URC 2a:cond 7. Scholl' !EC Chief. React. Inspec.
- j
; lt.hnal P. uurphy OMS / %'R TSO/SMA.Inc. Consultant,Oper. Engr. Asses.
Danial n. l'uller Imc DdL/PD #2 Donald J. Florek URO Jim Proll RI/DRS/OS URC RI/DRS/OB Bob 12ewlin NRC OPA Sholden .L ::chwartz imC IE thri-Jo Ca ocGnone NRC D3L E. L. Jordan NRC G. C. Vright IE Dept. NRC
- 0. Allison IIRC RIII-AIT Loader R. Woodruf f I&E IIRC IGE J. T. Jeard NRC C. Holahan ORaS/PWR liRC ORAS FHS:HRH '
0337C
'. O E
e l A: &.v.m t.!: .. ll_D*.n 9 a.$-
. /- LS-2 7--2) -
TVA SEQUOYAH WESTINGHOUSE PROPRIETARY CLASS 2 DESIGN CRITERIA UPPER HEAD INJECTION SYSTEM - A Table 3.5-3 UH! Instrument Setpoints TVA Westinghouse Instrument instrument Setcoint Number Number Descriotion Function Setooint LS-87-21 1-LS-900 Accumulator Water Level Trip valves 103.0 inches (above tank LS-87-22 1-LS-901 Valve Control Closed d g working line) LS-87-23 1-LS-902 J LS-87-24 1-LS-903
~~
LA 87-1 1-LIA-904 Surge Tank Water Level Hi alarm *15 Inches LA-87-4 1-LIA-905 Lo alarm 2.3 Inches PA-87-2 1-PJ A-908 Accumuistor Gas 40)W alarm 1209 lb/in2g t-M-99 Hi s/ don '
/?b/ IDhn'g LS-87-30 1-LS-910 Hembrano Leak Detector Detect (Set in field water in gas line to detect water leve.1 N ,
above mernbrane (Hydraulic service system settings) 2 Hydraulic Accumulator Normal 3200 lb/ir 9 Gas Pressuro Lo alarm 2800 lb/in 2g_ Hydraulic Accumulator Normal 24# Fu.o uruct+T m ala r m 24,n Me: bled - .Ma-Hydraulic System to alarm factory set Fluid Reservoir level -
- Level setpoints are referenced to the lower level tap.
' " 'p.t :' t9 ei s- 4 a -- 8 : dh;b!cd by ; TACI a d k--te be e6
??- i-~~t p;. [CN 00'7.
pr 5"" 0 Atto:hment N1- - toop (:/ld:ntifi:r _-- l-4.5 -8 7 - 21 __ 97090:10/071785 64
- ,.....a
WESTINGHOUSE PROPRIETARY CLUS 2 TVA SECVOYAH DESIGN CRITERIA ! UPPER HEAD INJECTION SYSTEM TABLE 3,7-4 f-UH1 ACCUMULATOR TANK PARAMETERS I 2 iceber Stainless stael elsd carbon steel Astorial ,. 2 1800 I Design Pressure, Ib/in g > 300 Design Torneerature, 'F ,. 70'- 100-
~~'
- A Operating Temperature, 'F 2 ,?
1255
'Anximu. h erating Pressure, Ib/in2g 1185 Mini:nu-i Operating Pressure, Ib/in g 3 1800 Each Total Volume, ft ,
1805 s 3
" Water Velu .e, f t Gas, ft 3
_1800 ~ ~
'~
Voltm N2 2100 Boron Concentration, ppm ream \ . ppm min 1900 - Y '* & ' 2 : 1800 Relief Valve Set Point, Ib/in g
'I' #
ASME Section !!!, Class 2
. Code 7,. " j g s :- n-
.l' i.
V'E t id I
,., [] .46b O Atto: 5 e.t Na3 Sh: '-@ ' - -
te3p / /ume;ii:r / ~ LS~87 - ?d _,; 69 97090:10/071785 k
% emo -
EMERGENCY CORE COOLING SYSTEMS (ECCS) ~ UPPER HEAD INJECTION ACCU'iULATORS LIMITING CONDITION FOR OPERATION
- 3. 5.1. 2 Each upper head injection accumulator system shall be OPERABLE with:
- a. The isolation valves open, \ 4~~
- b. The water-filled accumulator containing between '1805 and 1851 cubic feet of borated water having a concentration of between '19p and 2100 ppm of boron, and
- c. The nitrogen bearing accumulator pressurized to between 1185 and 1285 psig.
APPLICABILITY: H0 DES 1, 2 and 3.* ACTION:
- a. With the upper head injection accumulator system inoperable, except as a result of a closed isolation valve (s), restore the upper head injection accumulator system to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours lind in HOT SHUTOOWN within the following 6 hours,
- b. With the upper head injection accumulator system inoperable due to the isolation valve (s) being closed, either immediately open the . . ,
~
isolation valve (s) or be in HOT STAND 8Y within one hour and be in HOT SHUT 00WN within the next 12 hours. SURVEILLANCE REQUIREMENTS , s..
- 4. 5.1. 2 Each upper head injection accumulator system shall be demonstrated OPERABLE:
- a. At least once per 12 hours by:
- 1. Verifying the contained borated water volume and nitrogs..
pressure in the accumulators, and
- 2. Verifying that each accumulator isolation valve is open.
~~.
- M
. phi._ l- }
"Pressurizer Pressure above 1900 psig._
Attos'2 ' hh8 Loop pig & ut.cr M b L-SEQUOYAH - UNIT 1 3/4 5-3
.- .. . . ~ -.
a EMERGENCY CORE CCOLING SYSTEMS (ECCS) SU '.VEILLANCE REOUIREMENTS (Continued) .
- _ At least on:e per 31 days and within 6 hours after cach solution b.
volume increase-of-greaten than or equal to 1% of tank volume by
, verifying the boron concentration of the solution in the water-filled accumulator.
- c. At least once per 18 months by:
- 1. Verifying that each accu'mulator isolation valve closes automa-tically when the water level in the water filled accumulator is 82.1 +5.6 inches above the tank vendor working line. This corresponds to 87.1 +5.6 inches when corrected for the mass R32 of cover gas. *
- 2. Verifying that the total dissolved nitrogen and air in the water-filled accumulator is less than 80 SCF per 1800 cubic feet of water (equivalent to 5 x 10 -5 pounds nitrogen per pounds water). -
- d. At least once per 5 years by removing the mer.brane installed between the water-filled and nitrogen bearing accur:ulators and verifying that the removed membrane bursts at a differential pressure of 40 + 10 psi.
. o -
May 3, 1983 3/4 5 4 Amendment 28 SEQUOYAH - UNIT 1 e N:c:i n : .t iso _l3_ ! .:n 1_cE_3.' Lew :::k. .s.:- I -LS ~f 7-2l _ *
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-. 913 704 2630 TELEX.M9 2783 SO4 UI '87 04 09 DaU4 5 Date: 2/11/87 & $?.5'?
I To: Ms. Kelly Crato __ _ Tennessee Valley Autheeltv
. ,' / ,
FAX: 615-63 2-r,803 .
,j "
t From: _
. Sherry Burns a SOR, Inc."- Olathe, Kanses PAX: (913) 764-9148 This fax consists of . - pages plus cover sheet.
MESSACE: Daar Ms. Cralg: This letter serves to confirm our telephone conversellun on this date concerning the qutillfication of SOR differential pressure switch models 103AS-BB203-NX-JJTTX6 and 103AS-B203-NX-JJTTX6. The following test reports are used to qualify SOR series 102/103 [ differential pressure switches, which includes the two models mentioned eboves 8, $ ' ". . AET'C Test Report 18878-84N-1, Rev. 1 . . .
- . " - --.v.w l2 0 AETC Test Report 18878-84N-3, Rev. 1 i , gi ta ,g e
if you have any questions, pleaso let us know. . Regards, . . . . . . . . , n v. k Sherry B ns ~
. . . . 4,,
I -- . a - 1 -r- ;; Nuclear Coordinator 7, , **! l~ , , M
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- 87 03/11 13:02 R.002 i
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March 11,1987 Ms. Kelly Craig TENNESSEE VALLEY AUTHORITY ~- Telecepy: 615-632-6893
SUBJECT:
SOR DIFFERENTIAL PRESSURE SWITCH MODEL 103AC-BB203-NX-J)TTX6
Reference:
Tennessee Valley Authority Contract 85PLC-837609, Change #2 SOR Orders 0065086RA, RB and RC Sequoyah Nuclear Plant
Dear Ms. Cralg:
This letter serves to confirm that the differential preart're switches of the wgg;) . ubject model number which were supplied on the referenced order have a ,, reoestability of 1% and _ drift of 1%. These values are currently being reviewed In~ ,.ght of some additional data. Please note the figure for repeatability le based on the ANSl/ISA 551.1 definition.
~ ~' - The mutmum static shift you should expect for the decreasin'g set point is 6"we in the downward direction.
If you have any further questions, please let us know. Regards, U -0% Bob Davidson Project Engineer BD:sb 031187-01 l Atted. Tent No.- /R _ S,seet l ep h LOOP f/ifentifie,- / -L S -8 7-- 2 / re. es ::; .uv. s.. Aw m. nw e- u% o x o sie n. .esu vi. sacces sa% .a . c..tv a am a t as .g .w .s . a as .:4. sa a '%v g 's,-.. A ". :s , e g
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,f in a Radiation Environment of :C 5I10 RADS
' ensPAmihu onGANizAfsoN , All Nu:: lear Plante ,
FFA T A f* KEY NOUNS (Consult RIMS DESCRiirTORS t.13T) .
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Revsion 0 at H2 B3 Ecss sea lor ind. case Not Aaadacuesel ssfety ettsted ? Yes 7 No O NA 2221stront cf PreWorn Y79feMs.O9.nn " Diested To document the engineering basis A/MdY8 dw l>f/Ht > for classifying the accident Reviewed V T~ environment for this device (s) as (essentially) mild in AMm8 accordance with 10CTR50.49 paragraph (c). This calculation Dete vill be used in the justification basis for instrument demonstrated urt oli pages sodd accuracy calculations. 1 by this re= Won. g}j ' Ust all peges deleted by this revision. j Urt all peges chenpd by this rerwon. Abseract Ties alcutetioes contain en unvwif ad cuumption(s) that must be wrified Letar. Yes O tu Y - A reviev was made of a pertinent sognent of available literature on radiation effects on electronic components, both fros the perspective of the individual cotsponent and of the cocponent anocably. Based on this review, an argu=ent is presented that typicel, nonnelected electronic co=ponenta used in nuclear plantswill,withcertainnotableexceptions,tolerateatogalradiationdose (total 40 years integrated dooc plus accident dose) of 5K10 rada or less without significant degradation in their performance. Consequently, with respect to the radiation enviretrient, the oubject ce:ponents, or assemblies comprised of these components, are in a mild enviroc2cnt sa defined in 10CTR50.49(c). ., Attochment No.j,9 Skeet / ol gj . Loop 4/tdentifier - D o - - ,, - i .
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'jy fistsresce 9 (see Table 1 la snbsectica 5.1.3 :0ne) ledicctJs that j f
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; se, tastas spos tr.e at. eve taf ormasles, it is tocelnjsd t1st F3e, ld w esalodla4 fluern arbees fraa their coastr:<tist, tu tainate at Q']
A *r: Ic4st i 1E05 reds (Cerwel redletloa fa4 :/lt':4t alpificut ..T j
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5.10 Mhtlee rffuts e reitts en otettu ; , l y[ Daelser radiation affects enlays tod strite'sas grk:.arily ky drage 4 sidW' t, tt4 crsaale lassistlos and constr24tles nat4rlais. Trple.:1 Q tahatter of relays sad switches la a rHistles cavirte:: set is isonen p% 4 IQ i,W.S.T in Tabis 34 (pages 194-199) la refereste 1. P hja i A review of Table 34 Indicates that, far all sott!Os tre e,srae # , [f;7l ' redletloe data is gives, the total dise esceo.'ad 1X103 rses arsept for see, i.e., 8.8D 04 rods for the Les44 Cwyeratio2 typs . & 9410,12SC10604031 (fened es pale 194 et reference 1). ;ho %}$ g statanest was snee la the table (coccarsias this critry) that tts g j 'E g(j &avice worked satisfacterfly at least up to C.C 104 tcda, ne 'l i C indicatlee is that the device was att tested hyttd ft.f2104 1. l reds. Caesessentir. Table 36 e ntelms ao evi6sw o of reine__*r N, . AN
, 3 evitch malftactica for go,ana deses of 1710* reis er loss. 'f 'c. , '
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,f Reforesco 3, ;ege 661, ladicates that so:4 nicro-switeles estfw 4 demage to the plastic cases ara artssters at str:4. ray czpec2res et fl *-
i9] f low a 4 to &D06 rada (C) or satelrated sestren fittee at 1015 aca*g.
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l y Esference 9 (see Table 1 la subsectica 5.1.3 atevel reports both panel-speested and PCS-counted relays esposed to a radiatios dose as h, l high as 1D06 rods (gttsa) without failure. h#
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; MODEL 103AS-8212-NX-51 A-JJTTX6 TEST REPORT 8601-042 1
Prepared for: I Ceneral Distribution to the Nuclear Power Industry
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Prepared by: SOR, INC. 11705 Blackbob Road Olathe, Kansas 66061 p - (913) 76;-2630 ' Atta:hment No- 4 > _ Sheet.L_efS.d 1 Loop h/ldentifier /~ AE'874/ .. COPYRIGHT @ 1987 March, 1987
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j s. Differential Pressure Switch Test Data Sheet 7301-105 Model: 103AS-8212-NX-JJTTX6 S/N: 86-6-2364 By: DCK Date: 7-8-86' f Diff'l Pressure Cauge: Rosemount Pressure Cauge: 3D . Scale: 150 in w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy:'10.25% Graduations: 0.1 in, w.c. Graduations: 10 psi Daily: "A" Set Point Shift Static Reference Increasing Maximum Decreasing Reset Date Time Each Side Delta-P Set Point Delta-P Set Point Value Inc. Dec. (psig) (in. w.c.) (in w.c.) (in w.c.) (in. w.c. ) (in.w.c. ) 7- 9-86 6:00 am 1000 47.6/ 1 min + 60.7 60.8 51.8 8.9 Baseline Data 7- 9-86 10:30 am 1000 47.6/ 1 adn + 60.7 60.7 51.8 8.9 1 0.0 1 0.0 7-10-86 8:00 am 1000 47.6/ 1 min + 60.8 60.8 52.0 8.8 + 0.1 + 0.2 7-11 8:00 am 1000 47.6/ 1 min + 60.8 60.9 52.0 8.8 1 0.0 1 0.0 7-14-86 8:00 am 1000 47.6/ 1 min + 60,9 61.0 52.1 8.8 + 0.1 . + 0.1 7-15-86 8:00 am 1000 47.6/ 1 min + 61.0 61.0 52.1 8.9 + 0.1 1 0.0 7-16-86 7:50 am 1000 47.61 1 min + 61.0 61.1 52.2 , 8.8 1 0.0 + 0.1 7-17-86 7:40 am 1000 47.6/ 1 min + 61.0 61.1 .52.2 8.8 1 0.0 1 0.0
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7-18-86 8:05 am 1000 47.61 1 min + 61.0 61.0 51.9 9.1
- 1 0.0 - 0.3 7-22-86 8:10 am 1000 47.6/ 1 min + 61.3 61.3 52.2 , 9.1 + 0.3 + 0.3
' + 0.1 + 0.1 7-29-86 12:45 pm 996 47.6/ 1 win + 61.4 61.5 52.3 9.1 8- 6-86 12:40 pm 1000 47.6/ 1 sin + 61.6 . 61.6 52.5 9.1 + 0.2 + 0.2 9- 4-86 12:30 pm 1000 47.6/ 1 min + 62.1 62.1 52.8 9.3 + 0.5 + 0.3 9-22-86 12:55 pm 997 47.61 1 min + 62.1 62.1 52.8 9.3 1 0.0 1 0.0 11-3-86 9:15 am 960 47.6/ 1 pin + 62.6 62.6 53.3- 9.3 + 0.5 + 0.5 12-8-86 10:55 am 1000 47.6/ 1 w_n + 62.2 62.3 53.1 9.1 - 0.4 - 0.2 9.2 1- 5-87 8:20 am 1000 47.6/ 1 min + 62.1 62.1 52.3 - 0.1 - 0.2
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2-10-87 10:45 am 995 47.61 1 min + 61.6 , 61.6 52.5 9.1 - 0.5 - 0.4 3-13-87 10:35 am 1000 47.6/ 1 min + 61.5 61.6* 50.7 10.8 - 0.1 - 1.8 4-14-87 3:20 pm 1000 47.6/ 1 min + 61.4 ' 61.4 50.5 10.9 - 0.1 - 0.2 5- 8-87 10:40 am 1000 47.6/ 1 min + 61.4 61.4 49.9 11.5 1 0.0 - 0.6 6- 8-87 3:10 pm 1002 47.6/ 1 min + 61.4 61.4 49.7 11.7 1 0.0 - 0.2 7- 6-87 1:35pm 1009 47.6/ 1 min + 61.3 61.3 49.7 11.6 - ' 0.1 1 0.0 8- 3-87 12:30 pm 1003 47.61 1 imin + 61.3 61.3 49.8 11.5 i O.0 + 0.1 9- 1-87 7:45 am 985 47.61 1 min + 61.5 61.4 49.9 11.6 + 0.2 + 0.1 10- 5-87 10:00 am 990 47.6/ 1 min + 61.4 61.5 50.0 11.4 - 0.1 + 0.1
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Y t Differential Pressure Switch Test Data Sheet 7301-105 - M ciel: 103 AS-B2 I 2-NX-JJTTX6 S/N: 86-6-2364 By: DCK Date: 7-B-86 L; I Pressure Cauge: Rosemount Pressure Cauge: 3D , Sc -le: 150 in. w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy: .10.251 Graduations: 0.1 in, w.c. Graduations: 10 psi Daily: 'A" Static Reference increasing Maximum Decreasing Reset Set Point Shift Date Time Each Side Delta-P Set Point Delta-P Set Point Value loc. Dec. (psig) (in. w.c.) (in. w.c. ) (in. w.c.) (in, w.c.) (in.w.c. ) 47.61 1 min + 61.4 61.4 50.1 11.3 1 0.0 + 0.1 11-16-87 9:40 am 995 12-16-87 12:30 pm 987 47.6/ 1 min + 61.6 61.6 50.3 11.3 + 0.2 + 0.2 9 1
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1 Differential Pressure Switch Test Data Sheet 7301-105 , Model: 103AS-B212-N X-JJTTX6 S/N: 86-6-2365 By: DCK Date: 7-8-86 Diff'l Pressure Cauge: Rosemount Pressure Gauge: 3D . I Scale: 150 in. w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy: 10.25% Graduations: 0.1 in. w.c.
- Graduations: 10 ps!
Daily: "B" . . Static Reference Increasing Maximum Decreasing Reset Set Point _ Shift Date Tima Each Side Delta-P Set Point Delta-P Set Point Value Inc. Dec. (psig) (in. w.c. ) (in. w.c. ) (In. w.c. ) (in. w.c. ) (in.w.c. ) 7- 9-86 6:00 am 1000 47.6/ 1 min + 61.2 61.4 53.9 7.3 B~aseline Data 7- 9-86 10:30 am 1000 47.6/ 1 min + 61.2 61.2 53.9 7.3 1 0.0 1 0.0 7-10-86 8:00 am 1000 47.6/ 1 min + 61.4 61.4 54.2 7.2 + 0.2 + 0.3 7-11-86 8:00 am 1000 47.6/ 1 min + 61.4 61.5 54.2 7.2 1 0.0 - 1 0.0 7-14-86 S:00 am 1000 47.6/ 1 min + 61.5 61.6 54.5 .7.0 + 0.1 + 0.3 7-15-86 H00 am 1000 47.6/ 1 min + 61.4 61.5 54.4 7.0 - 0.1 - 0.1 7-16-86 7:50 am 1000 47.6/ 1 min + 61.5 61.6 254.4 7.1 + 0.1 2, 0.0 7-17-86 7:40 am 1000 47.6/ 1 min + 61.6 61.6 54.4 7.2 ' + 0.1 1 0.0 7-18-86 8:05 am 1000 47.6/ 1 min + 61.5 61.6 54.4 f 7.1 - 0.1 1 0.0 7-22-86 8:10 am 1000 47.6/ 1 min + 61.8 61.8 54.5 ' 7.3 + 0.3 + 0.1 7-29-86 12:45 pm 996 47.6/ 1, min + 61.8 . 61.9 54.6 7.2 + 0.1 + 0.1 8- 6-86 12:40 pm 1000 47.6/ 1. min + 62.0 62.0 54.8 7.2 + 0.2 + 0.2 9- 4-86 12:30 pm 1000 47.6/ 1 min + 62.5 62.5 55.1 7.4 + 0.5 + 0.3 9-22-86 12:55 pm 997 47.6/ 1 min + 62.3 62.3 54.8:- 7.5 - 0.2 - 0.3 11- 3-86 9:15 am 960 47.6/ 1 min + 62.9 62.9 55.2' 7.7 + 0.6 + 0.4 12- 8-86 10:55 am 1000 47.61 1 min + 62.6 62.6 55.1' 7.5 - 0.3 - 0.1 1- 5-87 8:20 am 1000 47.6/ 1 min + 62.6 . 62.6 55.1 7.5 1 0.0 1 0.0 2-10-87 10:45 am 995 47.6/ 1 min + 62.3 62.3 54.8 7.5 - 0.3 - 0.3 3-13-87 10:35 am 1000 47.61 1 min + 62.5 62.5 55.1 7.4 + 0.2 + 0.3 4-14-87 3:20 pm 1000 47.61 1 min + 62.6 - 62.6 55.4 7.2 + 0.1 + 0.3 5- 8-87 10:40 am 1000 47.6/ 1 min + 62.8 62.8* 54.7 8.1 + 0.2 - 0.7 6- 8-87 3:10 pm 1002 47.6/ 1 min + 62.9 62.9 55.4 7.5 + 0.1 + 0.7 7- 6-87 1:35 pm 1009 '47.6/ 1 min + 62.9 62.9 55.6 7.3 1 0.0 + 0.2 8- 3-87 12:30 pm 1003 47.6/ 1 min + 63.0 63.0 55.8 7.2 + 0.1 + 0.2 9- 1-87 7:45 am 985 47.61 1 min + 63.3 63.3 56.0 7.3 + 0.3 + 0.2 10- 5-87 10:00 am 990 47.61 1 min + 63.4 63.4 56.2 7.2 + 0.1 + 0.2
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s Differential Pressure Switch Test Data Sheet 7301-105 ' Model: 103 AS-D 212-N X-JJ TTX6 SIN: 86-6-2365 By: DCK Date: 7-8-36 DifI'l Pressure Gauge: Rosemount Pressure Gauge: 3D I Scale: 150 in, w.c. Accuracy: 0.2% Scale: 3000 psi Accuracy: 10.25V. Graduations: 0.1 in, w.c.
- Craduations: 10 psi '
Daily: "B" Static Reference Increasing Maximum Decreasing Reset Set Point Shift Date Time Each Side Delta-P Set Point Delta-P Set Point Value Inc. Dec. (psig) (in. w.c. ) (in w.c. ) (in. w.c. ) (in. w.c. ) (In. w. c. ) 11-16-87 9:40 am 995 47.6/ 1 min + 63.4 63.4 56.1 7.3 1 0.0 - 0.1 12-16-87 12:30 pm , 937 47.6/ 1 min + 63.6 63.6 56.4 7.2 + 0.2 + 0.3 7 O
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Differential Pressure Switch Test Data Sheet 7301- 05 Model: 103AS-B 212-NX-JJTTX6 S/N: 86-6-2366 By: DCK Date: 7-8-86 9 z Diff'l Pressure Gauge: Rosemount Pressure Gauge: 3D ' Scale: 150 in w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy: 10.25% Graduations: 0.1 In w.c.
- Graduations: 10 psi Daily: "C" .
Static Reference Increasing Maximum Decreasing Reset Set Point Shift Date Time Each Side Delta-P; Set Point Delta-P Set Point Value Inc. Dec. (psig) (in. w.c.) (in. w.c.) (in. w.c.) (in. w.c. ) (in.w.c.) 7- 9-86 6:00 am 1000 47.61 1 min + 63.6 63.9 55.6 7- 9-86 10:30 arn 8.0 daseline Data 1000 47.6/ 1 min + 63.6 63.7 55.7 7.9 1 0.0 + 0.1 7-10-86 8:00 am 1000 47.6/ 1 min + 63.8 63.8 7-11-86 55.8 8.0 + 0.2 + 0.1 8:00 am 1000 47.6/ 1 min + 63.7 63.7 55.8 7.9 - 0.1 1 0.0 7-14-86 8:00 am 1000 47.6/ 1 min + 63.8 63.9 7-15-86 55.8 8.0 + 0.1 1 0.0 8:00 am 1000 47.6/ 1 min + 63.6 63.6 55.7 7-16-86 7:50 am 7.9 - 0.2 - 0.1 1000 47.6/ 1 min + 63.6 63.6 . 55.5 8.1 . 1 0.0 - 0.2 7-17-86 7:40 am 1000 47.6/ 1 min + 63.5 63.5 7-18-86 55.4 8.1 - 0.1 - 0.1 8:05 am 1000 47.6/ 1 min + 63.3 63.3 7-22-86 8:10 am 1000 47.6/ 1 min + 63.0 55.2 .(- 8.1 - 0.2 - 0.2 63.1 55.2 7.8 - 0.3 1 0.0 7-29-86 12:45 pm 996 47.6/ 1 min + 63.0 63.0 55.2 8- 6-86 12:40 pm 7.8 1 0.0 1 0.0 1000 47.6/ 1 min + 63.4 63.4 55.6 7.8 + 0.4 + 0.4 9- 4-86 12:30 pm 1000 47.6/ 1 min + 64.0 64.0 56.1 7.9 + 0.6 + 0.5 9-22-86 12:55 pm 997 47.6/ 1 min + 64.0 64.0 56.01 ' 9:15 am 8.0 1 0.0 - 0.1 11- 3-86 960 47.6/ 1 min + 64.8 64.8 56.5 8.3 + 0.8 + 0.5 12- 8-86 10:55 am 1000 47.6/ 1 min + 64.! 64.2 56.0 8:20 am 8.1 - 0.7 - 0.5 1- 5-86 1000 47.6/ 1 min + 63.9 . 64.0 55.8 8.1 - 0.2 2-10-87 10:45 am 995 47.6/ 1 min + 63.8
- 0.2 3-13-87 63.8 55.7 8.1 - 0.1 - 0.1 10:35 am 1003 47.6/ 1 min + 63.9 63.9 55.8 4-14-87 3:20 pm 8.1 + 0.1 + 0.1 1003 47.6/ 1 min + 64.0 , 64.1 55.8 8.2 + 0.1 1 0.0 5- 5-87 10:40 am 1003 47.6/ 1 min + - 64.2 64.2 6- 8-87 3:10 pm 55.9 8.3 + 0.2 + 0.1 1002 47.6/ 1 min + 64.3 64.3 56.1 8.2 + 0.1 7- 6-87 1:35 pm 1003 47.6/ 1 min + + 0.2-64.1 64.1 56.1 8.0 8- 3-87 12:30 pm 1003 47.6/ 1 min + - 0.2 1 0.0 64.2 64.2 56.2 8.0 + 0.1 + 0.1 9- 1-87 7:45 am 985 47.61 1 min + 64.5 64.5 10- 5-87 10:00 am 56.3 8.2 + 0.3 + 0.1 990 47.6/ 1 min + 64.7 64.7 56.6 8.1 + 0.2 + 0.3 .
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. Differential Pressure Switch Test Data7331-105 Sheet i
Model: - 103AS-D212-NX-JJTTX6 S/N: 86-6-2366 By: DCK Diff'l Pressure Cauge: Ros mount Date: 7-3-86 Scale: 150 in w.c. Accuracy: 10.2% Graduations: 0.1 in, w.c. Pressure Gauge: 3D '
- Scale: 3000 psi Daily: "C" Graduations: 10 psi Accuracy: 0.251 Date Static Reference Time Each Side Increasing Maximum Delta-P Set Point Decreasing Reset (psig) - (in. w.c. ) Delta-P Set Point Value Set Point Shift 11-16-87 (in. w.c. ) (in. w.c. ) (in. w.c.) 'Inc. 07c.
9:40 am 995 (In. w.c. )
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12-16-87 12:30 pm 47.61 1 min + 64.7
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Differential Pressure Switch Test Data Sheet 7301-105 . Mode!: 103 AS-8212-14X-JJTTX6 S/ti: 86-6-2367 By: DCK Date: 7-8-86 1 Diff'l Pressure Gauge: Rosemount Pressure Cauge: 3D 4 Scale: 150 in. w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy: 10.25% Craduations: 0.1 in w.c.
- Graduations: 10 psi Daily: "D" Static Reference increasing Maximum Decreasing Reset Date Time Each Side Delta-P Set Point Shift Set Point Delta-P Set Point Value Inc. Dec.
(psig) (in. w.c. ) (in. w.c. ) (in w.c. ) (in. w.c. ) (in.w.c. ) 7- 9-86 6:00 am 1000 47.6/ 1 min + 65.1 65.1 59.1 7- 9-86 10:30 am 6.0 Baseline Data 1000 47.6/ 1 min + 65.2 65.2 59.0 6.2 + 0.1 7-10-86 8:00 am 1000 47.6/ 1 min + 65.2 65.2
- 0.1 7-11-86 8:00 am 59.0 6.2 1 0.0 1 0.0 1000 47.6/ 1 min + 65.2 65.2 7-14-86 8:00 am 59.1 6.1 1 0.0 + 0.1 1000 47.6/ 1 min + 65.4 65.4 7-15-86 59.3 '6.1 + 0.2 + 0.2 8:00 am 1000 47.6/ 1 min + 65.4 65.5 7-16-06 59.3 -6.1 1 0.0 1 0.0 7:50 am 1000 47.6/ 1 min + 65.4 65.4 .59.3 7-17-86 7:40 am 1000 6.1 1 0.0 1 0.0 42.6/ 1 min + 65.4 65.5 59.4 6.0 1 0.0 + 0.1 f4 8:05 am 1000 47.61 1 min + 65.5 65.5 59.4 0:10 am f 6.1 + 0.1 1 0.0 1000 47.6/ 1 min + 65.7 65.7 59.6 6.1 + 0.2 12:45 pm + 0.2 996 47.6/ 1 min + 65.8 65.8 59.5 6.3 + 0.1 - 0.1 12:40 pm 1000 47.6/ 1 min + 65.9 65.9 59.5 6.4 + 0.1 1 0.0 12:30 om 1000 47.6/ 1 min + 66.3 66.3 59.6 a 12 : 53 pm 997 6.7 + 0.4 + 0.3 47.6/ 1 min + 66.2 66.3 59.5- 6.7 - 0.1
-36 9:15 am 960 47.6/ 1 min + 66.6 66.6
- 0.1 j-F6 10:55 am 5 9. 6., 7.0 + 0.4 + 0.1 1000 47.6/ 1 min + 66.1 66.1 59.6- 6.5 - 0.5 3
. P .- 8:20 am 1000 47.6/ 1 min + 66.0 66.0 1 0.0 2-1c-41 10:45 am
, 59.5 6.5 - 0.1 - 0.1 995 47.6/ 1 min + 66.2 66.2 59.6 6.6 + 0.1 3-12-07 10:35 am 1000 47.6/ 1 min + + 0.1 66.2 66.2 59.6 6.6 1 0.0 1 0.0 4-14-27 3:20 pm 1000 47.6/ 1 niin +
5- 5-6;' 10:40 am 66.3 ' 66.3 59.9 6.4 + 0.1 + 0.3 1000 47.6/ 1 min + 66.5 66.5 60.0 6.5 + 0.2 6-66 3: 10 pm 1002 47.6/ 1 min + 66.5
+ 0.1 66.5 60.1 6.4 + 0.1
'- 6-67 1:35 pm 1009 47.6/ 1 min + 66.4 66.4 1 0.0 8- 3-87 ;7 30 pm 60.1 6.3 - 0.1 1 0.0 1003 47.6/ 1 min + 66.5 66.5 60.3 6.2 9- 1-87 + 0.1 + 0.2 7:45 am 985 47.6/ 1 min + 66.8 66.8 60.5 6.3 10- 5-87 10:00 am 990 47.6/ 1 min + + 0.3 + 0.2 67.0 67.0 60.6 6.4 + 0.2 + 0.1 Aw:r .n :: s. . ?2.. - * .. u ? . L 2Q. B-11 Lc , . L: . J.-43-27:.2I
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Differential Pressure Switch Test Data Sheet 7301-105 - Model: 103AS-B212-NX-JJTTX6 S/N: 86-6-2367 By: DCK Date: 7-8-86 Diff'I Pressure Cauge: Rosemount Pressure Cauge: 3D Scale: 150 in w.c. Accuracy: 10.2% Scale: 3000 psi Graduations: 0.1 In. w.c.
- Accuracy: 10.25%
Graduations: 10 psi Daily: "D" Static Reference increasing Maximum Decreasing Date Time Each Side Reset Set Point Shift Delta-P Set Point Delta-P Set Point Value inc. Dec. (psig) (in. w.c. ) (in. w.c.) (in w.c.) (in. w.c.) (in.w.c. ) 11-16-87 9:40 am 955 47.6/ 1 min + 67.G
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12-16-87 67.0 60.8 6.2 1 0.0 + 0.2 12:30 pm 907 47.6/ 1 min + 67.1 67.2 60.8 6.3 + 0.1 1 0.0
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I Differential Pressure Switch Test Data Sheet 7301-105 , Model: 103AS-8212-NX-JJTTX6 S/N: 86-6-2368 By: DCK Date: 7-8-86 Diff'l Pressure Cauge: Rosemount Pressure Cauge: 3D 4 Scale: 150 in, w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy: 10.25% Craduations: 0.1 in. w.c.
- Craduations: 10 psi Daily: "E" Static Reference increasing AAaximum Decreasing Reset Date Time Each Side Delta-P Set Point Shift Set Point Delta-P Set Point Value Inc. Dec.
(psig) (in. w.c. ) (in. w.c. ) (in w.c.) (in. w.c. ) (in.w.c. ) 7- 9-86 6:00 am 1000 47.6/ 1 min + 66.9 66.9 7- 9-86 10:30 am 59.9 7.0 Eiaseline Data 1000 47.6/ 1 min + 67.0 67.1 60.4 6.6 + 0.1 7-10-86 8:00 am 1000 47.6/ 1 min + 67.1 67.1
+ 0.5 7-11-86 60.5 6.6 + 0.1 + 0.1 8:00 am 1000 47.6/ 1 min + 67.1 67.1 60.6 6.5 1 0.0
+ 0.1 7-14-86 8:00 am 1000 47.6/ 1 min + 67.2 67.2 7-15-86 8:00 'am 60.8 -6.4 + 0.1 + 0.2 1000 47.61 1 min + 67.3 67.3 . 60.9 6.4 7-16-86 7:50 am 1000 + 0.1 + 0.1 47.6/ 1 min + 67.2 67.2 3 60.8 6.4 - 0.1 7-17-86 7:40 am 1000 67.3
- 0.1 7-18-86 8:05 am 1000 47.6/ 1 min + 67.4 61.0 6.3 . + 0.1 + 0.2 47.6/ 1 min + 67.4 67.4 61.0 / 6.4 + 0.1 7-22-86 8:10 am 1000 47.6/ 1 min + 67.5 67.5
' 1 0.0 7-29-86 61.1 6.4 + 0.1 + 0.1 12:45 pm 996 47.6/ 1 min + 67.6 67.6 8- 6-86 12:40 pm 61.2 6.4 + 0.1 + 0.1 1000 47.6/ 1 min + 67.7 , 67.7 61.3 6.4 + 0.1 + 0.1 9- 4-86 12:30 pm 1000 47.6/ 1 min + 68.1 68.1 61.4 6.7 + 0.4 + 0.1 9-22-86 12:55 pm 997 47.6/ 1 min + 68.0 68.0 11- 3-86 9:15 am 61.4[' 6.6 - 0.1 1 0.0 960 47.6/ 1 min + 68.7 68.7 61.7
^
7.0 + 0.7 12- 8-86 10:55 am 1000 47.6/ 1 min + 68.2 68.2
+ 0.4 8:20 am 6 1:. 67 6.6 - 0.5 - 0.1 1- 5-87 1000 47.6/ 1 min + 68.1 68.1 61.6 6.5 - 0.1 2-10-87 10:45 am 995 47.6/ 1 qdn + 68.5 69.0 1 0.0 3-13-87 10:35 am 61.2 7.3 + 0.4 - 0.4 1000 47.6/ 1 din + 68.7 68.7 61.7 7.0 + 0.2 4-14-87 3:20 pm 1000 47.6/ 1 min + 68.6
+ 0.5
~ 68.7 61.8 . 6.8 + 0.1 5- 8-87 10:40 am 1000 47.6/ 1 min + 68.9 68.9
- 0.1 6- 8-87 3:10 pm 62.0 6.9 + 0.3 + 0.2 1002 47.6/ 1 min + 68.8 68.8 62.0 6.8 7- 6-87 1:35 pm 1009 47.6/ 1 min + 68.7
- 0.1 1 0.0 12:30 pm 68.7 62.0 6.7 - 0.1 1 0.0 8- 3-87 1003 47.6/ 1 min + 68.9 68.9 62.1 6.8 + 0.2 9- 1-87 7:45 am 985 47.6/ 1 min + + 0.1 69.1 69.1 - 62.3 6.8 10- 5-87 10:00 am 990 47.6/ 1 min + 69.4
+ 0.2 + 0.2 69.4 62.5 6.9 + 0.3 + 0.2
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Differential Pressure Switch Test Data Sheet 7301-105 ,' o Model: 103 AS-B212-N X-JJTTX6 S/N: 86-6-2368 By: DCK Date: 7-8-86 Diff'l Pressure Gauge: Rosemount Pressure Gauge: 3D Scale: 150 in. w.c. Acc'_: racy: 10.2% Scale: 3000 psi Accuracy: 10.25% Graduations: 0.1 in. w.c. . Graduations: 10 psi Daily: "E" Static Reference increasing Maximum Decreasing Date Time Each Side Delta-P Reset Set Point Shif t Set Point Delta-P Set Point Value Inc. Dec. (psig) (in. w.c. ) (in, w.c. ) (in. w.c. ) (in w.c. ) (in. w.c. ) 11-16-87 9:40 am 995 47.6/ 1 min + 69.4 69.4 12-16-87 62.5 6.9 .t 0.C 1 0.0 12:30 pm* 987 47.6/ 1 min + 69.4 69.5 62.7 6.7 1 0.0 + 0.2
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t F Differential Pressure Switch Test Data Sheet 7301-105 , Model: 103 AS-8212-NX-JJ TTX6 S/N: 86-6-2363 By: DCK Date: 7-8-86 Diff'l Pressure Cauge: Rosemount . Scale: 150 in, w.c. Accuracy: 10.2% Pressure Cauge: 3D Graduations: 0.1 in, w.c.
*
- Scale: 3000 psl Accuracy: 10.25%
Graduations: 10 psi 2 '.Veck: "A" . Static Reference increasing Date Time Each Side Maximum Decreasing Reset Delta-P Set Point Delta-P _ Set Point Shift (psig) (in. w.c.) Set Point Value Inc. Dec. (in. w.c. ) (In. w.c.) (in. w.c.) (in.w.c.) 7- 9-86 6:15 am 1000 7- 9-86 47.6/ 1 min + 60.0 60.1 ~ 10:50 am 1000 47.6/ 1 min + 52.4 7.6 Baseline Data 7-23-86 10:50 am 59.7 59.7 52.4 1000 47.6/ 1 min + 60.4 7.3 - 0.3 ' 9-22-86 1:10 pm 997 60.4 52.9 7.5 11- 3-86 47.6/ 1 min + 61.6 61.6 + 0.7 o , 9:30 am 970 47.6/ 1 min + 53.8 7.8 + 1.2 12- 8-86 11:15 am 62.0 62.0 54.1
+
1000 47.6/ 1 min + 61.6 7.9 + 0.4 ' 1/ 5/87 8:40 am 1002 47.6/ 1 min + 61.6 53.8 7.8 - 0.4 2-10-87 11: 15 am 61.5 61.6 454.0 1000 47. 6/ 1 min + 61.5 7.5 - 0.1 '2 3-13-87 10:50 am 1005 61.6 54.0 7.5 4-14-87 47.6/ 1 min + 61.8 61.9* 1 0.0 i s . ., 3:35 pm 1005 47.6/ 1 min + 53.7 / 8.1 + 0.3 5- 8-87 10:55 am 61.9 61.9 54.2
' - 0.3 1005 47.6/ 1 min + 62.0 7.7 + 0.1 + 0.5 6- 8-87 3:25 pm 1012 62.0 54.4 7.6 7- 6-87 47.6/ 1 min + 62.0 62.0 + 0.1 + 0.2 1:45 pm 1005 47.6/ 1 min + 54.4 7.6 1 0.0 8- 3-87 12:40 pm 61.9 61.9 54.4 1 0.0 1010 47.6/ 1 min + 61.8 7.5 - 0.1 1 0.0 9- 1-87 8:00 am 990 47.6/ 1 min + 61.8 54.5 ! 7.3 10- 5-87 62.1 62.1 - 0.1 + 0.1 10:15 am 1000 47.6/ 1 min + 54.5 7.6 + 0.3 11-16-87 9:50 am 62.4 62.4 54;87 1 0.0 1000 47.6/ 1 min + 62.4 7.6 + 0.3 + 0.3 12-16-87 12:45 pm 990 62.4 54.8- 7.6 47.6/ 1 min + 62.1
- 62.2 1 0.0 1 0.0 54.6 7.5 - 0.3 - 0.2 2-minute hold 22 /2 "Z6
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Differential Pressure Switch Test Data Sheet 7301-105 , Mode!-: 103 AS-D212-N X-JJ TTX 6 S/N: 86-6-2369 By: DCK Date: 7-8-86 Diff'l Pressure Cauge: Rosemount Pressure Cauge: 3D 2 Scale: 150 in. w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy: 10.25% Craduations: 0.1 in, w.c.
- Craduations: 10 psi 2 Week: "B" Static Reference increasing Maximum Decreasing Date Time Each Side Delta-P Reset Set Point Shift Set Point Delta-P Set Point Value Inc. Dec.
(psig) (in. w.c. ) (in. w.c. ) (in. w.c. ) (in. w.c. ) (in.w.c. ) 7- 9-86 6:15 aa 1000 47.6/ 1 min + 61.4 61.6 7- 9-86 10:50 am 56.2 5.2 B'aseline Data 1000 47.6/ 1 min + 61.4 61.4 55.9 5.5 1 0.0 7-23-86 10:50 am 1000 47.6/ 1 min + 61.9
- 0.3 9-22-86 61.9 56.6 5.3 + 0.5 + 0.7 1:10 pm 997 47.6/ 1 min + 62.6 62.6 11- 3-86 9:30 am 57.1 5.5 + 0.7
+ 0.5 970 47.6/ 1 min + 63.0 63.0 57.4 5.6 + 0.4 + 0.3 12- 8-86 11:15 am 1000 47.6/ 1 min + 62.6 -62.6 1- 5-87 8:40 am 57.c -5.6 - 0.4 -- 0. 4 1002 47.6/ 1 min + 62.6 62.6 +57.1 5.5 + 0.1 2-10-87 11:15 am 1000 47.6/ 1 min + 62.6
. 1 0.0 3-13-87 62.6 57.1 5.5 1 0.0 1 0.0 10:50 am 1005 47.6/ 1 miei + 62.6 62.6 4-1R-87 3:35 pm 57.0 f 5.6 1 0.0 - 0.1 1005 47.61 1 min + 62.7 62.7 57.0 5.7 + 0.1 5- 8-87 10:55 am 1005 47.61 1 min + 63.0 63.0*
1 0.0 6- 8-87 3:25 pm 56.6 6.4 + 0.3 - 0.4 1012 47.6/ 1 min + 62.9 62.9 57.1 5.8 - 0.1 7- 6-87 1:45 pm 1005 - 47.6/ 1 min + 62.8 62.8
+ 0.5 8- 3-87 12:40 pm 57.2 5.6 - 0.1 + 0.1 1010 47.61 1 min + 62.8 62.8 9- 1-87 8:00 am 57.3 y - 5.5 1 0.0 + 0.1 990 47.6/ 1 min + 63.3 63.3 57.3 6.0 + 0.5 10- 5-87 10:15 am 1000 47.6/ 1 min + 63.2 1 0.0 11-16-87
, 63.2 57367 5.6 - 0.1 + 0.3 9:50 am 1000 47.61 1 mia + 63.4 63.4 12-16-87 12:45 per. 57.8- 5.6 + 0.2 + 0.2 990 47.6/ 1 min + 63.4 63.4 57.9- 5.5 1 0.0 + 0.1
*2-minute hold ~
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Differential Pressure Switch Test Data Sheet 7301-105 , Model: 103 AS-8212-NX-JJTTX6 S/N: 86-6-2370 By: DCK Date: 7-8-86 Diff'l Pressure Cauge: Rosemount Pressure Gauge: 3D I Scale: 150 in. w.c. Accuracy: 10.2% Scale: 3000 psi Accuracy: 10.25% Craduations: 0.1 in. w.c.
- Craduations: 10 psi -
3 Vleek: "C" Static Reference increasing Maximum . Decreasing Re' set Set Point Shift Date Time Each Side Delta-P Set Point Delta-P Set Point Value Inc. Dec. (psig) (in. w.c.) (in. w.c.) (in, w.c.) E w.c.) (in.w.c.) 7- 9-86 6:15 am 1000 47.6/ 1 min + 61.5 61.6 53.1 8.4 Baseline Data 7- 9-86 10:50 am 1000 47.6/ 1 min + 61.3 61.4 53.2 8.1 - 0.2 + 0.1 7-23-86 10:50, am 1000 47.6/ 1 min + 62.6 62.6 54.1 8.5 + 1.3 + 0.9 9-22-86 1:10 pm 997 47.6/ 1 min + 63.8 63.8 54.7 9.1 + 1.2 -
+ 0.6 11- 3-86 9:30 am 970 47.6/ 1 min + 64.3 64.3 55.0 9.7 + 0.5 + 0.3 12- 8-86 11:15 am 1000 47.6/ 1 min + 63.7 63.7 54.7 9.0 - 0.6 - 0.3 1- 5-87 8:40 am 1002 47.6/ 1 min + 63.7 63.8 354.8 8.9 1 0.0 + 0.1 2-10-87 11:15 am 1000 47.6/ 1 min + 63.5 63.6 54.7 8.8 ^ - 0.2
~
- 0.1 3-13-87 10:50 am 1005 47.6/ 1 min + 63.7 63.8 54.8 f, 8.9 + 0.2 + 0.1 4-14-87 3:35 pm 1005 47.6/ 1 min + 63.9 63.9 55.1 '
8.8 + 0.2 + 0.3 5- 8-87 10:55 am 1005 47.6/ 1' min + 63.9 63.9 55.1 8.8 1 0.1 1 0.0 6- 8-87 3:25 pm 1012 47.6/ 1 min + 64.0 64.0 55.2 8.8 + 0.1 + 0.1 7- 6-87 1:45 pm 1005 47.6/ 1 gnin + 63.8 63.8 55.2 8.6 - 0.2 1 0.0 8- 3-87 12:40 pm 1010 47.6/ 1 min + 63.9 63.9 55.3 : - 8.6 + 0.1 + 0.1 9- 1-87 8:00 am 990 47.6/ 1 min + 64.3 64.3 55.5' 8.8 + 0.4 + 0.2 10- 5-87 10:15 am 1000 47.6/ 1 min + 64.3 64.3 55.47 8.9 1 0.0 - 0.1 11-16-87 9:50 am 1000 47.6/ 1 min + 64.3 64.3 55'.4 8.9 1 0.0 1 0.0 12-16-87
- 12:45 pm 990 47.6/ 1 min + 64.3 64.3 55.6 8.7 1 0.0 + 0.2 A;tebh. -: . 72
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Differential Pressure Switch Test Data Sheet 7301-105 Model: 103 AS-D212-N X-JJTTX6 S/N: 86-6-2371 By: DCK Date: 7-8-86 i Diff'l Pressure Gauge: Rosemount : Scale: 150 in, w.c. Pressure Gauge: 3D 8 Accuracy: 10.2% Scale: 3000 psi Graduations: 0.1 in. w.c.
- Accuracyi 10.25%
Craduations: 10 psi 2 Week: "D" Static Reference increasing Maximum Decreasing Date Time Each Side Delta-P Reset Set Point Shif t Set Point Delta-P Set Point Value Inc. Dec. (psig) (in. w.c. ) (in. w.c. ) (In. w.c. ) (In. w.c. ) (In. w. c. ) 7- 9-86 6:15 am 1000 47.6/ 1 min + 64.0 7- 9-86 10:50 am 64.2 57.1 6.9 Baseline Data 1000 47.6/ 1 min + 64.0 64.0 57.1 6.9 7-23-86 10:50 am 1000 47.6/ 1 min + 64.3 1 0.0 1 0.0 9-22-86 64.3 57.3 7.0 + 0.3 1:10 pm 997 47.6/ 1 min + 65.4 65.5 57.9 7.5
+ 0.2 11- 3-86 9:30 am 970 47.6/ 1 min + + 1.1 + 0.6 66.1 66.1 58.4 -7.7 12- 8-86 11:15 am 1000 47.6/ 1 min + 65.8
+ 0.7 + 0.5 1- 5-87 8:40 am 65.8 58.4 . 7.4 - 0.3 1 0.0 1002 47.61 1 min + 65.8 65.8 2-10-87 11:15 am 1000 47.6/ 1 min +
. 58.6 7.2 , 1 0.0 + 0.2 3-13-87 65.8 65.8 58.6 7.2 10:50 am 1005 47.6/ 1 min + 65.8 65.8 1 0.0 1 0.0 4-14-87 3:35 pm 58.6 f 7.2 10.0 1 0.0 1005 47.6/ 1 min + 65.9 65.9 58.7 '
7.2 5- 8-87 10:55 am 1005 47.6/ 1 min + + 0.1 + 0.1 66.0 66.0 58.7 7.3 + 0.1 6- 8-87 3:25 pm 1012 47.6/ 1 min + 66.0 66.0 1 0.0 7- 6-87 1:45 pm 58.9 7.1 1 0.0 + 0.2 1005 47.6/ 1 min + 66,0 66.0 53.9 7.1 8- 3-87 12:40 pm 1010 47.61 1 min + 66.0 1 0.0 2 0.0 9- 1-87 66.0 59.03 7.0 1 0.0 + 0.1 8:00 am 950 47.6/ 1 min + 66.4 66.4 59.0 7.4 10- 5-87 10:15 am 1000 47.6/ 1 min + + 0.4 1 0.0 66.4 66.6 7.4 11-16-87 9:50 am 1000 47.6/ 1 min +
, 59. 2 + 0.2 + 0.2 12-16-87 66.6 66.6 59.5 7.1 1 0.C 12:45 pm 990 47.6/ 1 min + 66.7 + 0.3 66.8 59.5 7.2 + 0.1 1 0.0 b.... 22 /S 26 ~5
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Differential Pressure Switch Test Data Sheet 7301-105
- Model: 103AS-8212-HX-JJTTX6 S/N: 86-6-2372 By: DCK '>
Date: 7-8-86
- Diff'l Pressure Cauge: Rosemount s Scale: 150 in, w.c. Accuracy: 10.2% Pressure Cauge: 3D Graduations: 0.1 in, w.c.
- Scale: 3000 psi Accuracy:_10.25%
Graduations: 10 psi 2 Week: "E" Static Reference increasing Maximum Date Time Each Side Delta-P Decreasing Reset Set Point Shift Set Point Delta-P Set Point Value (psig) (in. w.c. ) Inc. Dec. (in. w.c. ) (in. w.c. ) (in. w.c. ) (in.w. c. ) 7- 9-86 6:15 am 1003 47.6/ 1 min + 7- 9-86 10:50 am 66.1 66.1 57.6 8.5 1000 47.6/ 1 min + 66.2 66.2 B'aseline Data 7-23-86 10:50 am 1000 57.6 8.6 9-22-86 47.6/ 1 min + 66.6 66.6 58.0
+ 0.1 1 0.0 1:10 pm 997 47.6/ 1 min + 67.5 8.6 + 0.4 + 0.4 11- 3-86 9:30 am 970 67.5 58.6 8.9 + 0.9 47.6/ 1 min + 68.2 68.2 + 0.6 12- 8-86 11:15 am 1003 47.6/ 1 min + 58.9 9.3 + 0.7 + 0.3 1- 5-87 8:40 am 1002 6 7 . 18 67.8 58.7 9.1 2-10-87 47.61 1 min + 67.7 67.7 58.7
- 0.4 - 0.2 11:15 am 1000 42.6/ 1 min + 67.6 9.0 . - 0.1 b 0.0 3-13-87 10:50 am 67.6 58.7 8.9 4-14-87 1005 47.6/ 1 min + 67.7 67.7 58.6
- 0.1 1 0.0 3:35 pm 1005 47.6/ 1 min + 67.7
/ , 9.1 + 0.1 - 0.1 5- 8-87 10:55 am 67.7 58.7 9.0 1005 47.6/ 1 min + 67.8 67.8 1 0.0 + 0.1 6- 8-87 3:25 pm 1017 47.61 1 min + 58.6 S.2 + 0.1 7- 6-87 1:45 pm 67.8 67.8 58.7 9.1
- 0.1 8- 3-87 1005 47.6/ 1 min + 67.8 67.8 59.0 1 0.0 + 0.1 12:40 pm 1010 47.6/ 1 min + 8.8 1 0.0 + 0.3 9- 1-87 68.0 68.0 8:00 am 990 47.5/ 1 min + 68.3 59.0!' 9.0 + 0.2 1 0.0 10- 5-87 10:15 am 1000 68.3 59.1 9.2 + 0.3 47.6/ 1 min + 68.4 68.4 1 0.1 11-16-87 9:50 am 1000 47.6/ 1 min + 5 9;.37 9.1 + 0.1 + 0.2 12-16-87 12:45 pm 68.5 68.5 59.4 990 47.6/ 1 min + 68.6 9.1 + 0.1 + 0.1}}