ML20207F734
| ML20207F734 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/17/1988 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20207F733 | List: |
| References | |
| NUDOCS 8808230195 | |
| Download: ML20207F734 (259) | |
Text
{{#Wiki_filter:, 1 w I ENCLOSURE 1- ~ PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 > DOCKET NO. 50-327 ..
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T (TVA-SQN-TS-88-20)
.2-LIST OF AFFECTED PAGES Unit 1 3/4 S-4 4-F t
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l-t ! i l, - f n i I, l i 8808230195 880817 PDR P ADOCK 05000327 PDC ,
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e EMERGENCY CORE COOLING SYSTEMS (ECCS) ,
' SURVEILLANCE REOUIREMENTS (Continued 1
- b. At least once.per 31 days and within 6 hours after each solution volume increase-of-greater._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 par 18 months by:
1 -
- 1. Verifying t'.at each accu =ulater isolation valve closes automa-tically when the water level in the water-filled accumulator is 91.0+/.M-5:! 0;.1_;.; inches abo've the tank vendor working line/' hfe-
- d;
- : S.1 15.5 b d.:: when corrected for the ca.ss R32 of cover gas. -
- 2. Verifying that the total dissolved nitrogen and air in the .
water-filled accumu'lator 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 removi6g the membrane installed between the wa.ter-filled and nitrogen bearing accu =ulators and verifyi.ng that the removed membrane bursts at a differential pressure of 40 + 10 psi.
May 3, 1983 3/4 5 4 Amendment 28 SEQUOYAH - UNIT- 1 l e... . .. u ._ ._-...-.,:.. . , a .. . . . - . . ;- . . ~ _.:. . . .: .. . - . . . s _ .
ENCLOSURE 2 - PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT I , DOCKET No. 50-327 (TVA-SQN-TS-88-20) DESCRIPTION AND JUSTIFICATION FOR REVISING UHI LEVEL SWITCH SETPOINTS AND TOLERANCES 4
-e,
l ENGLOSURE 2 I l 1 l DESCRIPTION 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 survolllance requirement (SR) 4.5.1.2.c.1. This change reflects the relationship between instrument-sensed differential pressure, UHI water accumulator lovel, and delivered UHI water volume. A high differential pressure is sensed at the instrunent 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 CHANGE 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 from 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 those presently used, except for their span. Because of the span differences, the switches also have different accuracy characteristics. Demonst rated Accuracy Calculation 1-LS-87 21 determined a new satpoint 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-broak, 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. JUSTJFICATION FOR CHANGE Delivered UHI Water Volume The UHI system in 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 sectica 15.4.1.1.4, a broad spectrum of LOCA analyses has been performed to evaluate UHI performance. The various UHI performance analyses are categorized by the assumed discharge coefficient (C ) of the break and D the presence or lack of UHI water mixing in the upper head region of the vessel (perfect and imperfect mixing, respectively). The limiting case break in the UHI Evaluation Model emergency core cooling system (ECCS) analysis presented in tho original SQN FSAR was the , dischargo coefficient C p=0.6 double-ended, cold-leg guillotino (DECLC) l break with .1 ,arfect mixing of UHI water assumed in the vossol upper head. Compliance with regulatory limits was achieved for this case by l
reducing the allowable core peaking factor (Fq) from 2.32 to 2.237. Minimizing the volume of UHI water delivered ' maximizes PCT for imperfect alxing UHI LOCA cases. The lower bound value for UHI water volume delivery established in the original FSAR C =0.6 p DECLG imperfect mixing case is 900 cubic feet. This value also was employed in the imperfect mixing cases of the 10-percent steam generator tube plugging (SGTP) 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 C D=0.6 DECLG; the calculated peak clad temperature (PCT) for this case is 2.111 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 because 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 ceraoval 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 limiting PCT for perfect
~~
mixing cases. The Cp=0.8 and CD =0.6 DECLG 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 compelse the current licensing basis for SQN are 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 fuol as the upper head drains during blowdown. During the core reflood phase, th!.s hotter fuel will then expel vote injection water as entrained liquid, producing a degraded flooding rate. Existing SQN imperfect mixing cases performed for the FSAR identliy 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 calculated PCT has been determined by WREFLOOD/LOCTA sensitivity runs for each licensing basis imperfect mixing case. The 10-percent SCTp licensing basic imperfect mixing cases are acceptable at an 850-cubic-foot-delivered UHI water volume because the degraded reflood penalty only increases calculated PCT as follows: CD=0.8 DECLC PCT = 2,151 degrees F Cp=0.6 DECLG PCT = 2,166 degrees F
The PCT penalties imposed upon the imperfect mixing cases are 20 degrees F for postulated guide tube flexure failures and 12 degrees F for thitable tubs filling during core reflood. Because the net PCT for the limiting imperfect mixing C =0.6 D DECLG 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-delivered volume is within the bounds of 850-1,130.5 cubic feet. Calculation of Level Switch Setpoints As described in FSAR section 6.3.2, four automatic hydraulic isolation valves are used to isolate the UHI accunciators from the reactor coolant system (RCS) af ter UHI has injected. These valves receive automatic closure signals from level switches on the UHI water accumulator. The level switch setpoints are selected to ensure that the delivered UHI water volume 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 cubic feet. As seen on page 6 of the calculation, a tank level of 95.3 inches (above the working line) equates to a delivered volume of 850 cubic feet; and a tank level 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 compilation of the various inaccuracles associated with the level switches, including drif t characteristico. The limiting inaccuracies of +3.29 inches 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 determine the optinum setpoint for the level switches. As described on page 22 of the calculation, the optimum setpoint is calculated to be 92 inches. This yields limiting level switch setpoints of 95.29 inches to 85.17 inches, which are within the analytical limits described above.
The tolerances used in the revised SR of +2.6/-5.8 inches represent the normal accuracy of the level switches excluding process variables that are unmeasurable at the time of calibration (see pages 3 and 24). As calculated on page 22 and shown on page 23, the accuracy j characteristics of the level switches necessitate calibration at least every 480 days. This level switch calibration is independent of the level switch / isolation valve functional response test required by l SR 4.5.1.2.c.1. As such, the level switch calibrations will be scheduled l and tracked independently. This will also allow for the extension of the calibration intervals based on evaluation of the new icvol switch performance. The calibration evaluations are in accordance with our previous commitment made in response to URC Bulletin 86-02. TVA will continue to rmnitor level switch performance through the normal reporting l process. i
r ATTAC11 MENT 1 + Technical Specification Change 88-20 Westinghoure Letter Dated August 10, 1988 (825 880811 010) A
FROM ECW 412 374 3282 (THU)08.11.'88 13:33 p- HO.14 PACE 2
/ N 880811^-Oth
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got E 25 . . WestinghouSd PowerSystems Nucts Technol0gy systs:Ns:m Sectfl0,00fp0Tallon i Bcx353 Pritsburgh Pennsytvsm 15230-0355
. August 10, 1988
.' i TVA-88-746 Mr.'P.'O. Trudel NS OPLS-OPQII-88-523 -
i Sequoy Ref.1) TVA,RD #428873' Tenness$hPr'ojectEngineer ee Valley Authority
,' . Sequoyah Nu'elear Power Plant , DSC-A 2) W- Gjo. C0 42680 P. O. 2000 Soddy Ihisyl, TN37379 " '
l I k I-i- y ENNESSEE VALLEY AUTHORITY
! S!QUOYAH UNITS 1 & 2 l
EECREASED UNI VOLUME DELIVERY SAFETY EVALUATION
! (SECL-88-410 & 417)
Dear i.
. Trudel: -
. I i
, . Iniesponse depreasingthe ,,tomininr.n your request,,
UHI volume attached is from delivery the safety 900 to evaluation 850 cubio feet. addressing - . . 1 I :
- . 'Ihis safety, evaluation is pro lvided in the following doctroents:
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ITEM SECL-88-410 TITLE .-
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; l "I I' SECL-88-410 .
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i SECL-88-417 lMinittum Required UHI Volume (Non -
, ltheUHIAccumulatorDeliverableWaterVoluje(LOCA, I
;SGTR, Post-LOCA Long Tem Core Cooling and Ibt Leg '
Switchover Accideits)
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If you have any comments or questions, please contact the undersigned. ' f
- : Very truly yours, -
1 l WESTINGHOUSE ELECTRIC CORPORATION l i . n ' t . A. Lordi, Manager + ESSD Projects Mid-South Area L. V. Tomasic/tu
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, Customer Reference No(s).,
Westinghouse Ref. No. WESTINGHOUSE NUCLEAR SAFETY EVALUATION CHECK LIST
- 1) NUCLEAR PLANT (S) SEOUOYAM UNITS 1 AND 2 (TVA/ TEN)
- 2) CHECK LIST APPLICABLE TO: SAFETY EVALUATION FOR A 50 CU.FT. DECREASE IN (subject of Change) THE UMI ACCUMULATOR DELIVERABLE WATER VOLUME
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l
- 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. .
1 Parts A and B of this Safety Evaluation Check List are to be completed only on the basis of the safety evaluation performed. CHECK LIST - PART A
, (3.1) Yes X No A change to the plant as described 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) Yes 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 .-.pment
- important -to cafety previously cvaluated 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?
l (4.6) Yes No X . May the possibility of a malfunction of equipment l 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 to ar/ technical specification be reduced? PAGE 1 OF 2
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SECL-88-4?.7 If the answers to any of the above questions are unknown, indicate under 5) REMARKS and explain below.
-- - If the answer to- any of the above questions in 4) cannot be answered in l 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. l
- 5) REMARKS:
The following summarizes the justification upon the written safety evaluation, (1) for answers given in Part B 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 15.4.1-9 for UMI Accumulator water voluine delivered to reflect 850 cu.ft. minimum volume evaluated in this safety evaluation and the associated footnote.
- 6) APPROVAL LADDER Atha (SAI) Date: O O!88
.. (6.1) Prepared Reviewed by by(Nuclear(Nuclear Safety) Safety): M N MM (SAI) , -
Date: 87 h /8 (6.2) Coordinated with Engineer (s): L3M A A (SAII) Date: Y/MBEB - Coordinated with Engineer (s): Mnf/dC/ (TSA) Date: T-/J - 88 Coordinated with Engineer (s): ACD (COA)_Dato: Ph*/88 Coordinated with Engineer (s)h k'Ab I NeuSAI) Date: '81~ /O~ 6 8 (6.3) Coordinating Group Manager (s) d Mk M (SAII) Date: 0 Coordinating Group Manager (s): 24M&M (TSA) Date: 7/U,/ID/8 N t')[ Coordinating Group Manager (s): ///Yhd (COA) Dato: M*M( (6.4) Nuclear Safety Group Manager 'L) b b l [ ~(SAI) _ Dates _ k[/d/88 _ PAGE 2 OF 2,
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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 BACXGROUND In order to accommodate relaxed UHI system tolerances at Sequoyah Units 1 and 2, Tennessee Valley Authority (TVA) has requested a widened set
,of 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 the 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. ,. BASES LARGE BREAK LOCA - FSAR CHAPTER 15.4.1 In order to accommodate relaxed UHI system tolerances at Sequoyah Units 1 and 2, IVA has requested a widened 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 mininum 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 D 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 co_e peaking factor (Fg) from 2.32 to 2.237.- Minimizing the volume of UHI water delivered is conservative for 4e . imperfect mixing UHI LOCA cases. The lower bound value for UHI water ' volume delivery established in the original FSAR C =0.6 D DECLG 3 imperfect mixing case is 900 ft . This value also was employed in the imperfect mixing cases of the 10% steam generator tube plugging (SGTP) analysis performed in the 1982-83 timeframe and reported in Reference 1. page 1 m
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 mixing of UHI water assumed in the vessel upper head was the C =0.6 D DECLG; the calculated peak clad temperature (PCT) for this case is 2111*F at an Fg of 2.32 with a UHI delivered water volume of 1053 ft3 . 'Using sensitivities appropriate to UHI plant perfect mixing cases, trade-offs ~ have previously been made among various input assumptions to justify increasingthemaximumallowableUHIdeliveredwatervolumeto , 1130.5 ft . Haximizing the value of UHI water delivered is conservative for perfect mixing UHI I4CA 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 =0.6 p DECLG perfect mixing case at 1130.5 ft3 UHI water delivery is 2163'F.
The Cp =0.8 and Cp=0.6 DECLG imperfect mixing cases from the 1982-83 10% SGTP analysis have been reviewed to assess the PCT impact of reducing the delivered UNI water volume to 850 ft 3. The calculated Reference 1 PCTs for the C =0.8 g and C =0.6 p DECLG cases which , comprise the current licensing basis for Sequoyah are 2311'F and 2113'F, respectively. Reducing the UHI water delivery in an imparfect ., 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 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 ft 3 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
- . imperfect mixing case 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 acceptable at an 850 ft3 delivered UHI water volume because the l degraded reflood penalty only increases calculated PCT as follows
Page 2 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 UMI ACCUMULATOR DELIVERABLE WATER VOLUME l C D=0.8 DECLG PCT =2151*F
.CD=0.6 DECLG PCT =2166*F ,
A separate safety evaluat$on performed for Sequoyah during November, i 1986 considered the impact of a possible but unlikely scenario of guide tube flexure failures. The PCT penalties imposed upon perfect and imperfect mixing cases under this scenario are O'F and 20*F, respectively. The net PCT for the limiting imperfect mixing C D=0.6 DECLG case therefore becomes 2166*F + 20*F = 2186'F 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 avent. The thimble volume which must be filled has not been explicitly treated in the sequoyah large break LOCA analyses. Westinghouse had initially assumed that the thimble plugging devices would be sufficiently tight to prevent the ingress of water into thimbles during reflood. However, it was later identified that the plug clearances were sufficiently large 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 on the perfect and imperfect mixing cases are established as O'F and 12*F. The net calculated PCT for the limiting imperfect mixing case becomes 2186'F +'12*F = 2198'F so compliance with the regulatory limit is maintained. Both the perfect and imperfect mixing cases of the Sequoyah large brohk LOCA analysis remain in compliance with 10CFR50.46 if the UHI water delivered volume is set within the bounds 850 - 1130.5 ft 3, with calculated PCT values of 2163'F and 2198'F respectively. i Page 3 m O* - - - , a - . . , ----,---...,r. , . , . , - - - - ,_,_,w -,n - - ._e,-,--.,,.,-.,,,,_n,.,-,,-, - , -
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 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 UHI Small Break LOCA ECCS Evaluation Model (Reference 2), which resulted in the most limiting PCT of 1486*F for a 8 inch equivalent diameter break (Reference 1). A cafety evaluation which considered the effect of charging /SI pump flow chortfall 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
,otandard 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. Because UHI injection is inherently beneficial for the cvaluation model small break LOCA event, the FSAR analysis has assumed c conservative value which is less than 850 ft3 for the minimum deliverable UHI water volume. Therefore, a decrease in the deliverable UHI water volume to 850 ft3 does not effect the FSAR small break LOCA results.
ROD EJECTION MASS AND ENERGY RELEASE FOR DOSE CALCULATION - FSAR CHAPTER 15.5.7 AND TABLE 15.5.7-1 Similar to a small break LOCA, a rod ejection accident analysis is performed to providw primary and secondary mass and energy releases for use in computing the radiological consequences of a rod ejection cccident as per Regulatory Guide 1.77,. This analysis is a long term transient performed specifically to determine primary RCS mass and energy releases through the upper head break and secondary mass and cnergy releases via the secondary code safety valves. These mass and cnergy releases are then used to compute the radiological consequences of a rod ejection accident. A reduction in the minimum deljverable UHI water volume will result in an increase in the mass and energy releases of the primary coolant and a decrease in the secondary mass and energy [ 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
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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 "volume is a reduction in secondary mass and energy releases. Since a net reduction in secondary 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 Sequoyah 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 pressure transients for long and short term analyses, mass and energy releases for postulated LOCAs and cor.tainment 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 temperaturo 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. Page 5
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l i 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 STEAM GENERATOR TUBE RUPTURE - FSAR CHAPTER 15.4.', The steam generator tube rupture event as analyzed in the Sequoyah FSAR
, equilibrates in pressure lat a value which greatly exceeds the maximum UHI nitrogen gas pressure of 1300 psia. Since the UHI system is not actuated during a design basis steam generator tube rupture event, any change in UHI delivered water volume upon actuation is irrelevant to this analysis.
bit)WDOWN REACTOR VESSEL AND LOOP FORCES - FSAR CHAPTER 3.9 , The blowdown hydraulic forcing functions resulting from a loss of coolant accident are considered in Section 3.9.1.5 (Analysis Methods 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 UMI 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 'reak o initiation. For this reason the ECCS, including the UHI accumulator, in not consjdered 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 hydraulic forces calculations. POST LOCA LONGTERM CORE COOLING SUSCRITICALITY REQUIREMENT; WESTINGHOUSE LICENSING POSITION - FSAR CHAPTER 15.4.1 The Westinghouse licensing position for satisfying the requirements of 10CFR Part 50 Section 50.46 Paragraph (b) Item (5) "Long Tern cooling" is defined in WCAP-8339 (Reference 4, pp. 4-22). The Wectinghouse 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 vater provided by the RWST and Accumulators must have a concentration that, when mixed with other sources of water, will result in the reactor core remaining suberitical assuming all control rodo out l (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 l
.~ . . . .
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 mean sump boron concentration.
'ltis reduction in the mixed mean sump boron concentration can be accommndated within the existing margin for the current cycles of operation for Sequoyah Units 1 and 2.
l HOT LEG SWITCHOVER TO PRIVE!W POTENTIAL BORON PRECIPITATION - FSAR CHAPTER 6.3.2.2 The hot leg recirculation switchover time analysis has been performed for Sequoyah Units 1 and 2 to determine the time following a LOCA that hot leg recirculation should be initisted. This analysis addresses the concern of boron precipitation in the reactor vessel following a LOCA and has been performed to support the decrease of 50 cubic feet in the minimum UHI water volume to 850 cubic feet. During a large break LOCA the plant switches to cold leg recircalation " after the RWST switchover setpoint has been reached. If the break is in the cold leg there is a concern that the cold leg injection water will fail to establish flow through the core. Safety injection Cntering the Ar @ a . loop a#1M apill ont the break, while S1 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 will increase until the solubility limit of the boric acid l colution is reached, at which time boron will begin to precipitate. As i the boron precipitates, 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 time at which hot leg recirculation must be established to prevent boron precipitation in the core. An evaluation has been performed to deternino tho of fect of the reduction of the doliverable volume of water in the UHI accumulator on the hot leg recirculation switchover time. This evaluation concluded that the time for hot leg switchover contained in the FSAR (15 hours) is bounding. Therefore, the value in the FSAR need not be changed. Page 7 e
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 CONCLUSIONS The effect on the LOCA related analyses for Sequoyah Units 1 and 2 c. 1 50 ft3 850 ft 3 reduction in the Minimum deliverable UHI water volume to has been evaluated by Westinghouse. The potential effect of the change on the FSAR analysis results for each of the LOCA-related 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 UHI water to 850 ft3 for Sequoyah Units 1 and 2 is acceptable from the standpoint of the FSAR accident analyses diucussed in this safety evaluation. Table 1 lists the effect of the change on the various accidents :hich are discussed here. REFERENCES 1. Sequoyah Station (TVA/ TEN) FSAR - Updated 6/16/86 Amendment 3.
- 2. WCAP-8479 Rev. 2 (Proprietary), WCAP-8480 Rev. 2 (Non-Proprietary), Young, M.Y., et. al., "Westinghouse -
Emergency Core cooling System Evaluation Model Application to Plants Equipped with Upper Head Injection", January 1975.
- 3. WCAP-9220-P-A (Proprietary), WCAP-9221 (Non-Proprietary),
Eicheldinger, C., "Westinghouse ECCS Evaluation Model - 1981 Version", Revision 1, 1901. 4. WCAP-8339 (Non-Proprietary), Bordelon, F.M., et. al.,
"Westinghouse ECCS Evaluation Model - Summary", June 1974.
S.
"Westinghouse Technical Bulletin NSID-TB-86-08, "Post-LOCA Long-Term Cooling: Boron Requirements", October 31, 1986.
Page 8 O
3.. l l WISTINGHOUSE PROPRIETARY CLASS 2 SECL-88-417 . SAFETY EVALUATION FOR SEQUOYAH UNITS 1 AND 2 FOR A DECREASE IN THE UHI ACCUMULATOR DELIVERABLE WATER VOLUME TABLE 1 IS.ut CHAPTEit ACCIDENT DESCRIPTION EFFECT ON RESULTS 15.4.1 Large Break'LOCA eak clad tem ncreasesby$eratureCompliance 3*F. . with 10CFR maintained. 50.46b(1-3) 15.3.1 Small Break LOCA effect on the FSAR NoadvarSingtemperature peak cla calcolat ons, maximum cladding oxidation or maximum hydrogen ceneration. Compliance with 10CFR 50.46b(1-3) maintaine.d. 15.5.7 Rod Ejection Accident No adverse effect on mass and makntakned.-$"k[ChR$$$ ilk $m 6.2 Containment Integrity _(Short and Long Term No adve'rse effect on short or long term mass and energy Mass and Energy PLlease) releases. Compliance with currentenEoironmental salif:. cat gainta:.ned. n limits 15.4.3 Steam Generator Tube No adverse effect on primary-
~'$$ ann bi C$m$tsma$ntakh$0ChR$00l11 1 ned. _,
3.9 Blowdown Reactor Vessel No adverse effect on the and Loop F;rces LOCA hydraulic forcing functions. 15.4.1 PostfLOCA Longterm Core 1 cpm decrease in the Cooling poht-LOCA sump boron concentration. Compliance with 10CFR 50.46b(5) maintained. 6.3.2.2 Hot Le Switchover to FSAR cost-LOCA hot 19g Preve Potential Boron switchover time remains Preci tation bounding. 1 Page 9
,,rmon scv 4 s4 s:e4 otor>os.oe.'ee isist Ho.at
-r , ,
Ps.or : l SECL NO. Sect-99 410 Customer Reference No(s).
~ Recuest fro n TVA Westinghouse Reference No(s).
TVA 87-896 0; WESTINGHOUSE HUCLEAR SAFET:
.' SAFETY EVALUATION CHECX LIS1 s 1.)NUCLARPLANT(S):.SeouovdUnit1and2 4
22)SUBJCT(TITLE): Minimum Recuired UHI Volume s a. . -. R.
'* T .
- 3.) The written safety evaluation of the revised procedure, design change or .
modidicationrequiredby10CFR50.59(b)hatbeenpreparedtotheextent requ' red and is attached. ,
"9c '
incomplete for any. reason,. If a on explein safetyPageevaluation
- 2. is not required or is
- a. . .x~
Parta A and.B of this F on t e basis of the s,a. fety'Safety evaluationEvaluation performed.Check list are to be completed only j'- . CHEC LIST-PARTA!l'CFR50.59(a)(1) 0 . T . J Yes 1 No- A change to-the plant as described in the FSAR7
. . > Yes Yes No 1 A change to procedures as described in the FSAR?
Yes No 1 A test or experiment not described in the FSAR? ' No 1 A(change to the plant technical specifications SeeNoteonPage2) - a 2
- 4) CHECX LIST - PART B -Page 10CFR50.59(lu)de(d)on(Jus
~
must be inc 2.) = (4.1) Yes _ No 1 Will the probabilit of a;. accident previously (4.2) Yes evaluated in t e FSAR be increased? No 1 Will the consequences of an accident previo.usly (4.3) Yes No A., evaluated in the FSAR be increased? May the possibility of an accident which is . o . different than any already evaluated in the (4.4 ) Yes FSAR be created? No 1 Will the probability of a malfunction of equ ment important to safety previously
.(4.5l Yes - eva ated in the FSAR be increased?
H:,1 Will the consequences of a malfunction of equ pment important to safety previously , (4.61 Yes eva uated in the FSAR be increased? _ No 1 May the possibility of a malfunction of equipment important to safety different than any (4.7) Yes already evaluated in the FSAR be created? -
, No 1 Will the margin of safety as described in the bases to any technical specification be reduced?
Page 1 of 5 ' O e- 'q e r
FdOM ECO 412 374 582
* . I M M *II8' ' *
\
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. . \
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! j . '. .
3
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. q .. .i. : , ..' . . SECL-88-410, .
. . . 3. . . . u..
, l NOTES: :' ! . .
l . 1 If thi anlswer\s to. any of the' 'above questions are unknown, indicat 5.)REMARX$andexplainbela.' l If the answer to any of the above questions in Part A (3.4) or Part B cannot be'anskered in the nega fve based on written safety evaluation the chang,e review would requ' r an, application for license amendment as, required,by10CFR50.59(c)a,nd i ubmitted to the NRC pursuant to 10CFR50.90/
- 50) REMAUS: i 1
The followino'.sumarizes the justification upor, the written safety . evaluatioh (I) for answers give'n in Part A (3.4) and Part B of this $ECL PleaIe : see thd attached evaluation
- i !
- 1. i .
,t :
(1)Refere'nce to do,cument(s) containing written safety evaluation: l
- i -
', s f, FOR FSAR UPDATE
'section:I. 'Page(s):
i Table (s): Figure (s):- l _
, Reason' a fo'r/Descrip) l tion of Change: .
;hoNo'nLOCAFSARsectionsarea Ffected by this evaluation -
. i* l,' I .. i, , SAFETYEfALUATIONAPPROYALLADDER: -
; !.Preparidby(NuclearSafety):I.
Date: ( [ ' iCoord'inatedwithEngineer(s):. . O Acc.LM
' Date: 1 /1/'ff
'Coordinati'ngGoupManager(s): l M- _
__ Date: - _
) Nuclear Safety! Group Manager: M/J./E0 - Dat0: # /
I e I , Page 2 of 5 -
} -
k i e
! l
, FROM (Cu 41 374 3:14 ' M0l# > 0 3. 0 6. ' 3 8 14:59 No.21 Poot 4 l
o I .. SEC!r88-410 f ' I i SAFTfl EVALUATION HINDiN REQUIRED UKI VOIlEE FCR SEQUOYAH UNITS 'l AND 2 BAQ G CUND: , , l '- Tabll e 15.4.1-9"Plant Paraneters used in IOCA Analysis" of the sequoyah
*~,,, Units 1 and 2 FSAR specifies that the mininum volume of water delivered by the D been';per Head Injectiog Accurulator for which the I4cA transients have analyzed is 900 ft . Recently, WA requested that a Safety
' Evaluaticri be perfomed Wich assesses the amount by Wich this value can be decreased shile still satisfying the current licensing basis IOCA and .
Non-:tcCA analyses. '
%e pirpcse of this ' evaluation is to determine the maxinum'aincunt by Wich -
the yolume of the UMI accunulator can be decreased without havirg an - inpact on the Sequoyah Units 1 and 2 licensing basis Non-10CA safety - analyses. ' I.VAIM.$i:
- i .
s - We jsequoyah Units 1 'ard '2 Upper Head Injection systers each oansist of an accur.nlator pressurized to between 1200 and 1300 psia Wich prwides a ficQ of borated vatar ditxctly into the upper head Wen the reactor ' coolant pressure decreases belw the accumulator pressure. A rwiew of the is or p'dy m:delled and ac%ted in the follwing steamline break
' an l
o steamline Break Mass /Enerty Palease Inside Cbntainment (IFSAR Section 6.2.1.3) o Steamlire Break Cbre Pasponse (FSAR Sections 15.2.13 and 15.4.2.1) '
- In order to detemine the mininum volume'of deliverable water needed in the tHI acctmulator so as not to have any inpact on the previously
- ment'loned analyses, the amount of water actually injected by the UKI duriirJ the transients was detemined. Because the flow fren the UHI is onl/ a fenction of the difference in pressure between the UHI accumulator arx1 the reactor coolant system, the ancunt of water injected into the RCS by the UHI is raximized in the steamline rupture event which causes the -
i RCS to depressurite the snost.
%e ealt'ations shich were performed in order to datamine the irpact of lewdrirn the minirum arount of water khich nay be delivered by the UHI are .
su:nsrizcd on the following pages. \ ' 1 Page 3'of 5 - e G g . e'
-w- - . _ - - - . - , ,--._....._._,__.,,,_.,.,__.____..m, ,-,__,_.m. ,m_- --
N M ,tcw di: Ud 328' s non >os. oJ.
- 3a 18: 5 9 Ho.28 mt 5 SECIr88-410 i .
Steanline Purture PassEnerrN Release Inside ContainMnt (FSAR Section 6.2.1.3) In orl der to deter:.ine if the r.inirma volume o'h deliverabl WI could be decreased withcut inpact3rq the rass/enezqy releases fztra a steamline break inside contairrent analyses, a revics of the rest limiting of this transient was performed. It was determined that a value less than 900 cubic feet of water W. tid be injected by the WI durirq the transient, the current analysis oculd supp6rt a reduction of-the minirum delivert.ble water from 900 cubic feet __ to 696 cubic feet. . In st.gport of this reduction, it should be roted that previous ' sens tivity stuiles have shown that the steamline break rass/ energy relea{ses are insensitive to charges in the amount of water injectn LW.l In fact, amlyses which have been per Mrmed to support renoval of ,^ the tpII in plants similar'to the Sequoyah us'ts have shcwn that the cceplete re cval of the WI system has an insignificant irpact on the rass/cy/.rgy releases cbtained. Etsgline Rupture Core Restenso (FSAR Sections 15.2.13 ard 15.4.2.1) The s;teamline break cases khich were amlyzod for Sections 15.2.13 ar - 15.4.2.1 of the Scqu:rfah ISAR are listed ):clow: .
- 1.
i Pain steamline depressurization with offsite pcNer available (for uniform ard ron-unifom credible breaks). a2. Pain huline rupture with offsite pcuer available for ruptures upstream ard downstream of the steamline flow restric(tor). ' 3. Pain steamline rupture without offsite pcuer available (for - ruptures upctream ard dcwnstream of the stcamlina f1cs 1T.strictor) . . i A rtr/ cM of theso events chcued that the rupture of a rain steam pipo - upstream of the flev restrictor with offsite p:ver available causcd the grea{est DB depressurization of the RCS an:1 also provided the rect limitiny alts. For this case, the arount of water injccted by the WI into the mininra required arcant of 900 ftwas conservatively calculgted ard detcrninod to bo less tha and less than that injectcd durirq the etcamline break rass/ energy release inside contairmnt amlysis. Pago 4 o'f 5 - e g 4
.s. .*
FR0tt CCW 410 I*' 'Sid (H0H)03.04.*68 19:01 f 4 0. 21 PAGE 6 SECIe88-410 I It ir, appuent that doctuasirn the'a. cunt of water which can be delivered by the LMI to the value govemed by the analysis discussed above will have no inact cri the stea:nline break core response results and the conclusions of the FSAR for this transient will re.ain valid. c 21c w SIctG : . l . mW upon the ary= ends presented above, it can be corwiuded that the reduction of the minin:s a:teunt of water khich can be delivered by the UNI to a'valua agaal to or greater than 606 cubic ft will have no i the hass/ energy releases or the staa.line break core response. Ihus,
'gaet en the conclusions presented in the Sequoyah FSAR for these analyses in Section 0.2.1.3 and in Sections 25.2.13 and 15.4.2.1, respectively, will remain valid
.s .
I e 4 Pago 3.of S
. ~ ' '
l ATTACllMENT 2 - Technical Specification change 88-20 Detnonstrated Accuracy Calculation 1-LS-87-21 (B25 880812 501) 6
TVA 10697 (ONE-OA-6-86)~
'7~f ff-2 0 6/ 2. ~ 8W 2 *
~~ DitE CALCULAT10NS w 2 ~ "'" -
l Title - l_ l Plant / Unit DEMONSTRATED ACCURACY CALCULAil0N ,
/-t s .U7 '2 l l S o N P / I ( 7-
~
g l KEY NOUNS (Consult RIMS Descriptors List) (/DreparingOrganization
/
EEB-l&C - l 11C. INSTR, CAllBRAil0N, 'SETF0lNT, ACCURACY '. lBranch/ Project Icentifiers leach time these calculat, ions are*lssued, preparers frust ensure that the l l original (RO) RIMS acesssion ntreer is filled in. l l-L.s. W -21 l_ Rey 1 (for RIMS' use) rirns accession ntreer 4 RO 9f1C41SS0056
/
84t3 '990/Jor190d l Applicable Design Docutent(s) l l l - l l ScPr4- OC- V- 2'7 r1 l R5 I l M I N O8/2 I N l l 1 I i , 1 IR I I i lSARSection(s) l UNID System (s) s l l N /A l l l N/rf lR _ I l 2 l Revision 0 FM"-N- RS I R2 i R3 ISafety-related? Yes ( W ho ( ) lECN ho. (or indicate hot Applicable)l peg 6cgl l l Statement of Problan l L6?s9 1 Austo I 1 l l Prepared l k A c4 AICn $hbgu it'.- r%M l i l Determine the accuracy of the subject 1 l 3 l Checked R A W 4'tr JJgg l l l l instrttrent loop (s) and derronstrate that the accuracy is adequate for the intended l l ( l d' J. A % I I 1 j l Reviewed l purpose. Prirrery eierrents are located in ' l m4B / J B #vfro^/ l @M. l l l a cnvirorrnent. I remeA I i l Subject devices / /are /
~ l -
l Approved not part l j l l l of PM.
- 7 # * #"r*#^' l l l
_- A Ll/l>llAI I I 9 lDate l I #>D lMygl l l l " I \l I l ,' l
'USE FORM l List all pages added l l *" T l l l a .TVA105)4lbythisrevision l l =
= . l l - llFlORE lListallpagesdeleted i Wh t.__ l l ' l l l SPACE lbythisrevision am ,t .ts U3 I l l 3 l REQUIRED l List alI pages changed w709y2u l l l l lby this revision NN,@if$r -2 l . i I f l l ABSTRACT [These calculations contain an unverified asstrmtion(s) that trust Yesbe ( ) verified No % ) l later. - 2 l Calculations were perfortred to determine the accuracy of the subject instrtarent loopThe (s).determined / E - l accuracies were ccrmared to the required accuracles, setpoints, safety limits and/or operating limits and l 3 l 6 [ ll thethe instrtrent accuracyloop for the (s). loop (s) listed below were daronstrated to be acceptable for the intended ft:nction of l - This calculation applies to the instrtrnent loop (s) listed below: - l l i ; i 2 - t.s . Sn- 2t , i,z.-ts.so- 22, ' i, 2 - t. s - tv. zs , lp - t.s . s i- ze l - E l g ^ l
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. I l F l l - l 1 1 l l 3 l " l l l I - 1 l g = N f( ) Microfilm and store calculations in RIMS Service Center Microfilm and destroy. () " l .L.LMiciofilm and aturn calculations to: - J. D Ner l cc: RIMS, SL 26 C-K Address: W9 Bill C-K l - DNEl - 254EW 7
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TV A tCtH (DNE C A6) G N AI.s h' 'E CALCULATIONS ISTLE DEMONSTitATED ACCURACY CALCULATION PLAN T/ UNIT Pft( P ARING ORG AN#2MION
' \ l - t S - 8 '7- 21 XEY NOUNS (Consult BlM,5 DESCQlPTORS LIST)
Son,p//v2 (. 6 i it.l'.0- 1 & C I&C. Il d dALIBRA'T b **;ETPOTNT_ ArrPPAEY 8R ANCH/ PROJECT f DE NTIFitR$ Eac leuens are seswed, prorarers trwn gasure that the oregenel (RO) RIMS eccession
" "'" "'us' usa 5 _ .
l- L 5 - 6 7-2 l _ nius .a.uion numb., 976VICE0054 W W.3' p, n 1. n , nnt
;"'f.*p'. "."; 7"'"" aL0 80127C 0008(AB25 '8'8 i)iX2 INT
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N($ UNIDG TEM (5) a2f 80523E0009M)B25 880516 829 SAaq steiklM1 NM
- n. < -
Revesion O R1 R %1 Safety 4 elated ? Yes O No O ECN No for end.cete Not Appbcsetel
- 4( De.R N/pu(
l 4 ,.3 5 'l NA i2 2s tis /n.o Statement of Problem d.*P tM (W Ad.NQ4 ( - Propered . . y.chdp Determine the accuracy of the
.. '!//e J- subiect instrument loop (s) and
' ?~--G f.6 jy
~
Check ed <$ TJ 1.,u </ demonstrate that the accuracy is 4f/ d.dd - adequate for the intended purpose. AppJovt0 }
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f l l p k0 [ //, Nd -- M LM _ $) \ iklJ t i.,ll.A 9/7/f 7 h f/ ( List all pages added
*
- 3 by this revision, I. f List all pages deleted ih e fEIT 4"eV ga4
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);- by this revision.
Ifl Lis all pages changed ,, by this reeision. Q Vs R Comf L1 Meat.ArWat%'ac.11.. < '. ir y2 . iS'inTiC'.,',7,%.'$.'""Tl,'E**u*o*M" C" Fu r*CS ~ ^ i ' F(5AA s ec. r.3 0 ) .j s e Calculitinns Tht- were performed to determine the accuracy of the subject instrument loop (s). 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 calculation applies to the instrument loop (s) listed below: ( 2 - c. s - 8 7- z t e, z. - L S - 8 7- 2. '3, 1, 2. - L S - 8 7 ' 2 *2- I) 2. - L S - 6 7 - 2 4 unt7 & c Y ct. E 3 fr7 to w T S AlW6' A f 4 & M t- if L t-o meg- niy rN/'$ c Yet t eat. y' ( A otmss e c o s u RI orst<ts enteues,,oq ) g<2, RL 6Y SC 3 This calculation consists of ~ h pages and _2.!-- attachments for a total of I g d h k pages. 22z . D n t ,, e n in O llii n l o v C u.crot.im end sione c46cunates sa RIMS $ervice Center. .- Ou. P -- 9 X - - B 2 6 i' * *"" #"ov O
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it, supponr canacass noposso .ru pe,e a 2cu s V S > TO CHANGs& SN1Tdd Mo D 6 d. , SiffC.!N T sfAlb pfeeuppgy Dn rA l'Aov1DED f0A THf saireil h6f:ER TO R/l Fog UNeT i g' r foA As-Suicy cono , ions, (AGGs ADDED := '7D 2 ftfRt> 7D/ 0, r7gt, 7'n', gggys gyr pyyg,a gg , ArrA. M 31 (SVlie),19trn. A ! 3 2 [ j gor 7, ) fA6cskLvisCDg. I,3, C,7,7 A, 7c, y o, y a;, 7c 7pfgy yN , typ 77f,rel 1 S, 12 6.12c .19,20, 21,22, 23, t 's A , 2 4, 29 A, 24 8, 47, f77/d // 3/. ' ft%d s Dcte Tro ;. 7 Et, 8 A , 98, 23 c , <2 3 0 , i.,18 , Iltra.t/I (3 sHr0, arrn / 7 C 8 wir. ) ; TH25 R6 vi s t eN t-) As Issus0 To : A, 6 L1 M2 M A16 fgoccss (A A o ft, B , 4cvsst v4LvC s closf R la rd t! c., f(vasC d A t.1 f3 A M t 0 N f.ycts gtyifros 2(3 A A c Fet- M OM mi.....o.s....
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) Attachment 6 I
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\ ; Page 1 of 1
\,f cal.CUI.ATION DESIGN' VERIFICATION /(INDEPENDENT REVIEW) FORM
,s ')
~ 1-LS 21 R3, Calculation No. Revision Method of design verification (independent review) used (check method used):
- 1. Design Review /
- 2. A1tornate 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 method, identify the pages where the alternate calculation has been included in the calculation package and 9xplain why this nothod.is adequate. (f , Muthod 3: In the qualification test method, identify the QA documented source (s) where testing adequately demonstrates the adequacy of this calculation and explain. AS STATED T4 THE REVl5f Dd u6 , THE CALC v)A S REVIS E D To CH ANGE TH E CALI B R A TION CYCLE To ELIMATE THE PROC EST _ ERQOrt PA EAMETER AA>D ku'/15E VA LV5 5 TRoK E TIM E . I
. u A\iE RE VI ElAJ E D TH E JUSTf FICA TiOAJ FOR TH ESE Ci( A AJ 6 E S AMO TN MM JUDGEMENT TH E ITUSTI FIC A Tr o AJ A A>0 CH A N 6 E 5_
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NEP-3.1 Attachment 6 j Page 1 of 1 9 . ( i
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CALC'JLATIC!! DESICp VERIFICATI0:l/(IllDEPEllDE!1T REVIEW) FORM
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f - L S -P 7 - B-l ,9 A i Calculation No. Revision ' l Method of design verification (independent review) used (check method used): Design Review V 1. 2 .- Alternato Cniculation
- 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 method, identify the pages where the alternato calculation has been included in the calculation package and explain why this method is adequate. Method 3: In the qualification test method, identify the QA documented l f
.A source (s) where testing adequately demonstrates the adequacy of this calculation and explain.
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CALCULATICll INDEPENDENT REVIEW VERIFICATION FORM
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/ 97- 2/ I L b Calculatica flo. 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 the calculation package and explain.why this method is adequate. Method 2: Identify the QA' documented source (s) where tosting adequately demonstrates the adequacy of this calculation and explain. Method 3: Justify the technical adequacy of the calculation'and explain how the adequacy was verified ( alculation is similar to another, based on accepted handbook' mathods, appropriate sensitivity studies included for confidence, etc.). T l] ave. l~c vlewe $ ~lbe (bleukk- in su h , culna l, ( .! i
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DEMONSTRATED ACCURACY CALCULATION y. 8 T A BL_ E O F- CONTENTS = _ LOOP PURPOSE OF CALCULATION ___ _______ ___ ____.______ __________ UNVERIFIED ASSUMPTIONS __ ___,__ ___ _ __,_______________ _____ .A_ DEFINITIONS & ABBREVIATIONS ___________ ___..__________ ____ 1 LOOP COMPONENT LIST _ _ __ _ _ _ __ _ _ _ _ _ _ _ ______ ____ 1 COMPONENT DATA __,_._____________ _______,_____,_________,__ COMPONENT NOTES _ ,___________ __ _ , _ _ _ LOOP FUNCTIONS, REQUIREMENTS, & LIMITS ___,_________,_____,__ d b LOOP DIAGRAM __ __ __.___ _ _ _ ___ ____ _ ___- _ ____ ____ _ _ J S INSTRUMENT SENSING DIAGRAM ___ _ ___ _____________,___ _ ___. N PROCESS UNCERTAINTY DISCUSSION / CALCULATION ______,____,,_______ 12 k WATERLEG UNCERTAINTY DISCUSSION / CALCULATION _____________,__ [ /M \ ACCURACY DISCUSSION ____ ______________________ ___________ d ((( ACCURACY CALCULATION INDEX & CALCULATIONS ____ _____,_______ lT/O 1
SUMMARY
OF CALCULAFED DATA __,___,_______ __,__ ____,.,__________,__ E-E -2.3A 24A 82 % CONCLUSIONS _______ ___,____ ,__ __________,_________,____ b v *so r REFERENCES / ATTACHMENTS ______,______.,,____,__,___,___,_____, k h _Rww.u mers_____ ___ _____________________ M st 0 ________ _ _______-__. --_--_---- -
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l PURPCSE C fr i C AL C UL. A7 I U3 N
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ac uracyTheof pur;::oso of this celculation fu a) to determine the an1 b) the instrumentat. ton covered by this calculation, to demannt. sto that the instrudentation is nuf ficiently ac: urate to perfera its intended function without safety or oo trationaP_ limits being r xceeded. i UNUERIFIED ASSUMPTIONS This calculation contains no unverified assumptions. The follcuing unverified assumptions were used performanco of this calculation. These assumptions in the require f urther anal ysi s and reevaluation. Thia calculation may revisicn if the assumptions below are shown to be invalid.require PLANT / UNIT (S) M [ N REV.,[_ PREPARED [ j/[ __ CHECKED _Y_flyn 7 DATE j.,/_T,/17 SHEET 7_ C/03
d BRANCH 'ItOJECT IDENTIFIER /- t s. 5? 7 '2 / DEMONSTRAT D ACCURACY CALCUIJ. TION e
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DESIGN INPUT ; DATA A) DEFINITIONS & ABBREVIATIONS \
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Aa ACCIDENT ACCURACY-ACCURACY OF DEVICE IN A HARSH ENVIRONMENT CAUSED DY AN ACCI NT Aas COMBINED ACCIDENT ANb SEISMIC ACCURACY ' Ab ACCEPTANCE BA.lD-THE RANGE O VALUES ARot.ND TMU 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 ENVIRON! TENT NOT AFFECTED BY AN ACCIDENT OR PRIOR TO AN ACCIDENT As POST SEISMIC ACCURACY ffq); /V0& MAL MfAsu/Relf ACCUAACY - SAMA 45 Ac haedP7 /setuCfS fQ, fAc cCSS VAprAetfS 4/MicH MAf uNm/Asundest 47 Tyr 7tMr oc cAtrasarroH CV CVCS LETDOWN LINE BREAK ( De DRIFT INI.CCURACY HELB HIGH ENERGY LINE BREAK IAD INTEGRATED ACCIDENT DOSE ICRe INPUT TEST INSTRUMENT READING INACCURACY ICTe INPUT TEST INSTRUMENT CALIBRATION INACCURACY INDRe INDICATOR READING ERROR ire INACCURACY DUE TO CABLE LEAKAGE I L LOSS OF COOLANT ACCIDENT M MARGIN-THE DIFFERENCE IIETWEEN THE SATETY LIMIT /OPERAT7NG LIMIT AND THE NORMAL / ACCIDENT ACCURACY (Mn= NORMAL MARGIN Ma= ACCIDENT MARGIN) N/A NOT APPLICABLE OCRe OUTPUT TEST INSTRUMENT READING INACCURACY g kV All Of~'A84 6 VAluf - sit /WINTfg% R'I. (\ REV 1 PREP vc DATE S.n.99 CHECK % DATE G-t >-s'a SHEET 3 t C/O M REV _ PREP DATE CHECK DATE SHEET C/O REV- PREP DATE CHECK DATE, SHEET C/O
3 RANCH / PROJECT IDENTIFIER I~ d 6 ~ O '7 ' ~ 3 / DEMONSTRATED-ACCUltACY CALCULATION
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DESIGN INPUT D AiT A \. A) DEFINITIONS & ABBREVIAT.ONS CONTINU.ED
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. 'PSEe INACCURACY DUE TO POWER SUPPLY VARIATIONS -
PV PROCESS VALUE (ACTUAL) RADe INACCURACY DUE TO ACCIDENT RADIATION EXPOSURE , Re REPEATABILITY INACCURACY RH R!iR LINE 3REAK- T k RNDe NORMAL RADIATION DOSE BETWEEN CALIBRATION Se INACCURACY FOLLOWING A SEISMIC EVENT SECu SPAN ERROR CORRECTION UNCERTAINTY SL SAFETY LIMIT SP SETPOINT SPEo ZERO ERROR DUE TO EFFECTS OF OPERATING PRESSURE TAe TEMPERATURE EFFECT AT ACCIDENT CONDITIONS , TID TOTAL 40 YEARS INTEGRATED DOSE TNe TEMPERATURE EFFECT IN THE MAXIMUM / MINIMUM ABNORMAL TEMPERATURE RANGES TPRe TEST POINT RESISTOR ERROR , WLo WATERLEG UNCERTAINTY WLHP WATERLEG HIGli POINT WLLP' WATERLEG LOW POINT 8 deifAo ,yt! P/?o/>ti c o 6 t t t r Y - TP d c w s*WE S S *$ 4 4Muf f W AM'"'N RdeAreo Meutisernrs or nu ocorkr f.** gyr sog we.u r er w/trl
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- C/ O., ,,,,,'
{ gio_ DATE r./ ad !.s-, CHECK CJ 6 DATE tr/ trat SHEET In C/0, g REV._1,.,_ REV 2 PREP PREPhQ'ye DATE,, sis.99 CHECK oc ,,, DATE c.is.n SHEET C/O
u,. k. O T .
- \/
,Rogrossion Output: ,, ,, Constant 0.039625 S ANDARD 400% C A '/ G S11M AT S Std Err of Y Est 0.595909 R Squared 0.560761 l b M ' d 9s* % c e N F2 0a d e d )
No. of Observations 390 s ( o. sq cq ) (I 96 ) Degrees of Freedom 387 1 17 X Coefficient (s) 0.001842 1.233246 Std Err of Coef. 0.000256 0.131531 t THf JHf0RmarJ0M CN feston/N6 fndr/S 9D1 TMRu 7D9 Mar gssd
+
cateuta160 us INdt /0fus j23 4 JA/ fM R f 6 A C .s f r e d fuMiled Y : U< lb (R A ^* P ) +.k 2. (EA TPONE ZM L )IJHfAd tC y Is yni MrdN QF THE soff0JNr* DivJntrcN OfTHE 7E5740 J Alsrsums. ors . 1H6 Ddys detump .Ts THE No. 0F DdyS PAst Tt/c~ 2s A suAsrJ rurc~ 'VAtut fen TNf ( 6A t 28 A A T20N On YS THS A A MI* DAts ect umd. THis A)tte n6 U360 JH fMf dugyf ff f ffpSppppy grepu.rc 1H6 cunv/ FeA dim TION Vs. DMys gypfstro ye gg bl .. Er teNearra t of ras form y j< c i i W). 70 uts torus t23 Tuts VAtuf Prust 4r su&sirrarro IN. 7xt T is 35, R t = No . !! payr passeo entr$Adited. Lorar 7xed esteutarts A euser Ftr of THE fe/ft
-va y - (o.ced uns)+ 1.m 6 g') , o.omas-r ,, rancuod su, rue ,,nn osvieres ne rn.orso 0" (A&fC VDI 7WRu r7p9, M- see nort i cN sur. ro?
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-( !' \-' ;
/. +EXFONENTI RN4P 1DEV*ATIon DAYS EXPOEENTIAL / CURVE FIT :I GUESS .
1
-0 A 0 *'o '
O.039625
-0.3 0 0 0.039625- f 0 0 d 0.039623 I
-0.3 0.039625 !
-0.2 0 0 1
-0.1 0 -0 0.039625 - -
-0.1 0 0 0.039625 F
-0.1 0 0 0.039625 0.0 0- 0 0.019625 [
3 0' O.039;25 ;' 0.0 0 0.0 0 0 0.0396*3 O.0 0 0 0 03s625- t 0.0 0 0 s.029645 ? 0 0 .") ) 6 2 5 0.0 O.1 0 0 0.039625 0.1 0 0 0.03962h i 0.1 0 0 0.039625 ~ ~ 0.1 0 0 0.03s62 0.1 0 0 0. 03* J 15 , 0.2 0 0 0.039625 i' 0.3 0 0 0.039625 ' O.1 1 0.028167 0.076205 0.075205 ( 0.028167 0.1 1 0.028167 0.076205 , 1 [i 4 0.2 0.2 1 0.028167 0.076205 0.2 1 0.028167 0.076205 0.1- 2 0.055540 0.111806 -. 0.1 2 0.055540 0.111806 r 0.1 2 0.055540 0.111806 0.2 2 0.055540 0.111806 l 0.2 2 0.055540 0.111806 ; 0.2 5 0.133122 0.213010 , 0.2 5 0.133122 0.213010 l 0.3 5 0.133122 0.213010 ! 0.3 5 0.133122 0.213010 i 0.3 5 0.133122 0.213010 0.0 6 0.157539 0.244965 0.2 o 0.157539 0.244965 .
- 0. 3 ' 6 0.157539 0.2443f5 0.3 6 0.157539 0.2449G5 0.4' 6 0.157539 0.244965 !
0.276072 i 0.0 7 0.181269 " 0.3 7 0.181269 0.276072 0.3 7 0.181269 0.276072 [ 7 0.181269 0.276072 . 0.3 O.3 7 0.101269 0.27607?. l
?
-0.1 8 0.304330 0.306355 I 0 . ,1 8 0.204330 0.306355 0.204330 0.306355 {
k' O.3 8 l
-- - - . . . - . - . . . . - . . _ . . _ . . . , _ _ i
! > W.. . 5.:0. .3.E. .. . . m: L.ud>' fl. j
-- ?'.. Som% _ 7PL.. 99), 1 {
i 6 f l !
d 4 (
, xq -
1 s
\
\ s
~
) \'/.EXPONENTI
+ RAMP DEVIATION DAYS ZXPONENTIAL / CURVE FIT GUESS i 0.4 8 O.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 0.2267/2 0.335836 O.5 9 0.226742 0.335836
-0.6 13 0.310251 0.446194-0.6 13 Oc310251 0.446194 0.6 13 0.310251 0.446194 0.6 13 0.310251 0.446194 0.6 13 0.310251 0.446194 0.3 14 0.329679 0.471996 0.4 14 0.329679 0.471996 0.5 14- O.329679 0.471996 0.5 14 0.329679 0.471996 1.1 14 0.329679 0.471996
-0.6 20 0.435281 01613284 0.6 20 0.435281 0.d13284 C.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' O.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 28 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 57 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 ( ' l.1 75 0.882680 7Hn SHeu 1s 1.266371 1.266371 i tp orn esy p _/2. l ?::9.N.C 5_u:.9_8.. : I ?
- n e'.t 1 t S. 8 7- 21_. l '
l~** , 4h 2E2. C / 3 7_D.J . . '2. fh . .GQ.M_. j I
e, (' , , g', .; ,
\,
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4 I
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i' h- Y . 'EXPONENTI ,
, I + RAMP. '"'
DEVIATION . DAYS EXPONENTIAL / CURVE 1 FIT ~. GUESS
.' . C 75' O.882580 1.'266371
.3.2 75 0.882680 .; 1.266371.
1.2 75 0.882680 8 1.266371 i 1.3 75' O.882680 1.266371 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
- g. 1.4 75 0.882680 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 1.7 117 0.964664 1.444859 1.8 117 0.964664 1.444859
~( 1.9 117 0.964664 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 1.644859 2.5 117 f. 964664 1.444859 2.6 117 0.964664 1.444859 2 .- 8 117 0.964664 1.444859 0.5 152 0.987000 1.536891 0.8 152 0.987000 1.536891 1.0 152 1.0 0.987000 1.536891 152 0.987000 1.536891 1.2 152 1.3 0.987000 1.536891 152 0.987000 1.536891 1.3 152 1.4 0.987000 1.536891 152 0.987000 1.536891 1.4 152 1.5 0.987000 1.536891 152 0.987000 1.536891
".6 152 0.987000
.6 1.536891 152 0.987000 1.536891 1.6 152 0.987000 1.536891
(, 1.7 152 0.987000 1.536891 Xu s_ sWtsr 2s stoo6D At al2 " vc. , S-ii-99 /-zs.gy, p[ , GG 9-6-%% 7D3 7Dy 2 i< i
;n .
- it
.q, M '\ w- ;3-g
\ .
( ', \
/.EXPONENTI
+ RAMP DEVIATION DAYS EXPONENTIAL / CURVE FIT
, GUESS i 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 O.987000 1.536891 0.3 180 0.994159 1.597307 0.6 180 0.994159 1.597307 0.9 180 0.994159 1.597307 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 1.4 380 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 0.994159 1.597307 1.6 180 0.994159 1.597307 1.7 160 0.994159 1.597307 1.7 180 0.994159 1.597307
'1. 8
( 1.8 180 180 0,99.59 0.994159 1.597707 1.' 07 2.2 180 0.994159 1.e 00 7 2.2 180 0.994159 1.59:J07
, 2.5 180 0.994159 1.597307 '"
.0.2 216 0.997911 1.668263 0.5 216 0.997911 1.668263 0.8 216 0.997911 1.668263 0.9 216 0.997911 1.668263 1.1 216 0.997911 1.668263 1.1 216 0.997911 1.668263 1.2 216 0.997011 1.668253 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 C.997911 1.668263 1.9 216 0.997911 1.668263 2.0 216 0.997911 1.668263 2.4 21o 0.997911 1.668263 2.7 216 0.997911 1.668263 0.3 247 0.999138 1.726892 0.6 247 0.999138 1.726092
(
.ZW.I. W .*7..!#.Oof0 /I/.#/t _ _ _ .._ ._ _
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,,n ./ -
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{ - s
~
y j. EXPONENTI
- + RAMP DEVIATION DAYS EXPdJENTIAL / CURVE FIT GUESS / ,
t8 247 0.999138 1.726892
.. 0 -
247 0.999138 1.726892 1.1 247 0.999138 f 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 g; 1.8 247 0.999138 ' 1.726892 + t 1.8 247 0.999138 1.726892, 1.3 247 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 3 -(\ 0.s 279 0.999654 1.786486 1.2 279 0.999654 1.786486 1.3 279 0.999654 1.786486 1.4 279 0.999654 1.786486 1.6 279 0.999654 1.786486 .. 1.6 279 0.999654 1.786486 1.6 2'9 0.999654 1.786486 1.7 279 0.999654 1.706486 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' O.999654 1.786486 2.3 279 0.999654 1.786486 2.4 279 0.999654 1.786486 2.7 279 0.999654 1.786486 2.9 279 0.999654 1.786486 0.6 303 0.999826 1.830916 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 1.6 303 0.999826 1.830916 1.6 303 0.999026 1.830916 1.6 303 0.999826 1.830916
( 1.7 303 0.999826 7pse swest is papen bf Rlt-1.830916 VC, 5. l i . W /-4S 87 2/
% S .t b -\1 7D5 7Db 2
'm 6e*-
v- rt um- - " wry vv 9mm-e-- + -m
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\'! +EXPONENTI RAMP DEVIATION DAYS EXPONENTIAI, l CURVE FIT GUESS 2.0 303 '/ .
0.999826- 1.830916 2.0 303 0.999826 1.830916 l 2.0 303 0.999826 ' 1.830916-2.0 303 ' ' O.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 0.999826 1.830916 3.1 303 0.999826 1.830916 0.7 334 0.999928 '1.888158 0.7 334 0.999928 1.838158 0.8 334 0.999928 1.888158 1.0 334 'O.999928 1.888158 1.4 334 0.999928 1.888158 1.5 334 0.999928 1.888158 1.6 334 0.999928 1.88815F 1.7 334 0.999928 1.888153
'1. 7 334 0.999928 1.8881',8 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.S^8158 '" 2.2 334 0.999928 1.888158 2.5 334 0.999928 1.888158 3.0 334 0.999928 1.888158 3.1 334 0.999928 1.888158 0.5 362 0.999961 1.939795 0.6 362 0.999967 1.939795 0.8 362 0.999967 1.939795 0.9 362 0.999967 1.3 1.939795 362 0.999967 1.939795 1.4~ 362 0.999967 1,939795 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
.Tns. swr?.Anpp & ph. _ _ . . . . . .
' N C. . . .. 5
- H.-Y ..
t .h.4SM 2 (.... '
. 4. 9 s T-n .Yt 786.. '
707 - . 2. .
\.t i kI\ -
a
^
\
I \
-(
\ - *EXPONENTI I + RAMP DEVIATION DAYS' EXPd1ENTIAL / CURVE FIT GUESS ~j
^
.0 362 0.999967 1.939795 i
.0 362 0.999967 1.939795 l
O.6 390 0.999985 ' 1.991405
-0.6- 390 0.999985 1.991405 1.0 390 0.999985 1.991405 1.1. 390 0.999985 1.991405 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.C 390 0.999985 1.991405 1.9 390 0.999985 1.991405
- 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 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 2.1 419 0.999993 2.044846 2.1 419 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 2.2 419 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 3.6 419 0.999993 2.044846 0.7 453 0.999997 2.107493 1.1 453 0.999997 2.107493 1.5 A53 0.999997 2.107493 1.6 453 0.999997 2.107493 1.8 453 0.999997 2.107493 1.9 453 0.999997 2.107493
{* Hrs rsrcf7 73 AonF1) Af R/2- _ VC, . 5./F 99 m'
/-J.T.37 2/
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. f +EXPONENTI RAMP.
DEVIATION DAYS EXPONENTIAL l - 4 - - CURVE FIT
*- 2.2 GUESS / ,
'453' O.99'9'997 5.,07493 f 2.2 .453 ' 1 -
O.999997 .2.107493 2.3 453 0.999997 l 2.3 453 2.107493 0.999997 2.107493 - 2.4 453 0.999997 2.5 453 2.107493 0.999997 2.107493 2.5 453 O'.999997 2.107493 2.5 -453 0.999997 2.107493 2.6 453 0.999997 2.8 453 2.107493 2.8 0.999997 2'.107493 453 0.999997 3.1 453 2.107493 0.999997 2.107493 3.7 453 0 999997 3.7' 453 2.107493 0.7 0.999997 2.107493 495 0.999999 1.1 495 2.184378 - 0.999999 2.184878 1.4 495 0.999999 2.184878 1.5 495 0.999999 1.9 495 2.184878 2.0 0.999999 2.184878 495 0.999999 2.1 495 2.184878 0.999999 2.184878 ( 2.2 2.2 495 495 0.999999 0.999999 2.184878 2.184878 2.4 495 0.999999 2.4 495 2.184878 2.5 0.999999 2.184878 -" 495 0.999999 2.5 495 2.184878 0.999999 2.184878 2.5 495 0.999999 2.6 495 2.184878 2.8 0.999999 2.184878 495 0.999999 2.184878 2.8 495 3.2 0.999999 2.184878 495 0.999999 3.6 495 2.184878 3.7 0.999999 2.184878 495 0.999999 C.9 525 2.184878
'C 1.2 0.999999 2.240151 525 0.999999 1.4 525 2.240151 1.5 0.999999 2.240151 525 0.999999 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 2.3 526 2.240151 0.999999 2.240151 2.4 525 0.999999 2.5 525 2.240151 2.5 0.999999 2.240152 525 0.999999 2.6 525 2.240151 0.999999 2.240151
( 2.6 525 0.999999 2.240151 3.rs swter2s Anoen dy 4/t [ ' sc, . S..n.42 1.cs 3y:2 l_. .
. ? h . S.rt N - V t.
70 8. . 7of. _1_ },
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( !
\
\ /
c
' EXPONENTI D2VIATION DAYS + RAMP
_EXPDNENTIAL / CURVE FIT GUESS ', 2.7 :525 0.999999 2.240151 2.8 ' 525 0.999999 2;240151 ' 2.8 '525 0.999999 ! 2.240151
- 3 .' 4 525 0.999999 2.240151 3.7 525 0.999999 3.7~ 525 2.240151 0.999999 2.240151 o
1 N( T E : 1, THE Lo T u s _ l'gocsR a m Is usco so4 ety
- To s u cit,, Es T 4 9 sou a rtorJ
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~2364 06/08/87 0.70 07/06/87 0.60 08/03/87 0.60 09/01/'87 Q.80 10/05/8"/ 11/16/87 12/16/87.
2365 1.7 0.70 0.70 0.90 2366 0.7 1.7 0.5
1.8 '2.1 2.2 2.2 2.4 0.6 0.9 1.1 2367 1.4 1.3 1.4 l 1.1 1.2 2368 1.7 1.9 1.9 2 1.9 1.8 2 2363 2.2 2.5 2.5 2 1.9 1.8 2.5 2369 2 .1 ' 2.4 2.4 1.5 1.4 1.4 2.1 2370 1.9 1.8 2 2.5 2.3 2 2.4 2.8 2.8 2371 2 2 2 2.8 2.8 2372 2.4 2.6 2.6 1.7 -1.7 1.9 2.7 2362, 2.2 2.3 2.4 2.2 2.2 2.3 2.5 2373 2.6 2.8 2.8 0.8 0.8 1 2.8 2374 1.5 1.5 1.5
- 1.7 1.6 1,7 1.5 2375 2.2 2.2 2.1 3.1 3 3.1 2.2 2376 3.6 3.7 3.7 3 3 3 3.7 2361 3.5 3.7 3.6 3.7 1 0.9 1.1 2377 1.6 1.6 1.4 1.6 1.6 1.8 1.4 2378 2.2 2.3 2.2 2.2 2 . 2 .1 2.3
-2379 2.4 2.5. 2.5 2 1.9 1.9 2.6 2380 2.3 2.5 2.5 2 2 2.5 2.6 3 3.1 3.2 3.4
( tf2AN 1.7850 1.7100 1.8200 2.2000 2.3100 2.3050 2.3650 Wrs fnd,E /1NO 7HE ptz 7 3 pgd,ES Com/Itf THE DEV.rn 7zo al 6F sETPo rs/r FOR 7h's asreo stuni punssR f 2N$TRum m is ON THE DAY THAT THEY AJfA'd dMEdK60 TN6 ($o r1pir) LINCS TJ/EN dALCULATE YH6 P16AA/ DEVr A r10^/ OF THE SETPo 7W 73 f0A THE DA7 extexeo. 7He isignu Dtvzittros! VS, TI M S 2S diA APHE D ON ja ndr5 7.T. [ %.. 5-II: 9e . ' n / 4S .8? 2/ ., l 4 c- 96-w Mf .r/ Q . 2__ _ ,'
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'2354 07/09/d6 07/10/86 01/11/86 07/14g86 07/15/86 07/16/86 07/17/86 0.00 0.10 0. 1 0 0.20 0.30' O.30 0.30 2335 0 0.2 0.2 b.3 0 . 7. 0.3 2366 0.4 0 0.2 0.1 0 0 -0.1 2367 0 .1 - 0.1 0.1 l 0.2 0.3 0.3 0.3 0.3 2368 0.1 .0.2 0.2 0.3
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- 04. 0.3 0.4 2369 0 2370 -0.2 2371 0 2 3'7 2 0.1
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2376 0.1 2361 -0.3 - 2377 -0.1 , 2378 c1 ' 2379 -0.1 2380 0.2 K4 (MEAN -0.0250 0.1600 0.1400 0.2600 0.2400 0.2400 0.2600 I a E
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l 07/18/86 07/22/86 07/23/86 07/29/jB6 08/06/86 09/04/86 09/22/86 2364 0.30 0.6 0.90 2365- 0.3 0.6 *' 0/70 1.40 1.40
.0.6 0.8- 1.3 1.1 2366 -0.3 -0.6- .0.6 -0.2 0.4 2367 0.4 0.4 0.6 !'O.7 0.8 1.2 1.1 2368 'O.5 0.6 0.7 0.8 1 1.2 1.1 2363 0.4 2369 1.6 0.5 1.2 2370 1.1 2371 2.3 I 0.3 1.4
. 2372 0.5 ! 2362 1.4 1 . 1.7 2373 0.6 2374 0.9 1.3 1.7 2375 1.5 2376 1.4 1.3 2.1 2361 0.9 2377 1 -v 1.1 1 2378* 1.3 2379 1.3 1.1 1.2 2380 1.4 1.3
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- MEAN 0.2400 0.3600 0.5600 0.4200 0.9733 1.1000 1.3300
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, 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 2.T7 0 -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 -
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-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 1.5- 0.8 0.6 0.5 0.6 0.8 0.8 2377 gV 1.6 1.4 1.4 1.4 1.5 1.6 1.6 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 1.9 2.1
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point baseline DEVIATION 2364 2364 07/09/86 ~60.7 2364 2364- 07/09/86 0 60.7 l 0.00 2364 2364 07/10/86 1 60.8 0.10 2364 2364 07/11/86 2 60.8 2364 0.10 2364 07/14/86 5 G0.9 0.20 2364 2364 07/15/86 6 61
- 0.30 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 2364 0.30 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 2364 1.40 2364 11/03/86 117 62.6 1.90 2364 2364 - 12/08/86 152 62.2 1.50
,2364 2364 01/05/87 180 62.1 1.40 2364 2364 02/10/87 216 61.6 2364 0.90 2364 03/13/87 247 61.5 0.80 2364 2364 04/14/87 279 61.4 2364 0.70 2364 05/08/87 303
( 2364 2364 2364 2364 06/08/87 07/06/87 334 362 61.4 61.4 61.3 0.70 0.70 0.63 2364 2364 08/03/87 390 61.3 2364 0.60 2364 09/01/87 419 61.5 2364 0.60 2364 10/05/87 453 61.4 0.70 2364 2364 11/16/87 495 61.4 2364 0.70 2364 12/15/87. 525
^
61.6 0.90 f 2365 2365 07/09/86 , 61.2 2365 2365 07/09/86 0 61.2 0 2365 2365 07/10/86 1 61.4 2365 2365 0.2 07/11/86 2 61.4 0.2 2365 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 3365 07/17/86 8 61.6-2365 2365 0.4 07/18/86 9 61.5
- 0.3 2365 2365 07/22/86 13 61.8 2365 2365 0.6 07/29/86 20 61.8 0.6 2365 2365 08/06/86 28 62 2365 2365 0.8 09/04/86 57 62.5 1.3 2365 2365 09/22/86 75 62.3 2365 1.1 2365 11/03/86 117 62.9 2365 1.7 2365 12/08/86 152 62.6 2365 1.4 2365 01/05/87 180 62.6 2365 1.4 l
( 236S 2365 2365 02/10/87 03/13/87 216 247 62.3 62.5 1.1 1.3 Ve, ..G-n.19 ' l LS .87 ?l.. i 1 D. 5:D .W . 7J. ' '2 M. 2 5
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DEVIATION 2365 2365 _04/14/87 279 62.6 2365- 2365 05/08/87 303 62.8 1.4 2365 2365 1.6 06/08/87 334 62.9 1.7 2365 2365 07/06/87 362 62.9 2365 2365 1.7 08/03/87 390 63 1.8 2365 2365 09/01/87 419 63.3 2.1 2365 2365 10/05/87 453 63.4 2.2 2365 2365 11/16/87 495 63.4 2365 2365 2.2 12/16/87 525 63.6 2.4 2366 2366 07/09/86 2366 63.6 2366 07/09/86 0 63.6 0 - f 2366 2366 07/10/86 1 2366 63.8 0.2
, 2366 07/11/86 2 63.7 2366 2366 0.1 2366 07/14/86 5 63.8 0.2 2366 07/15/8.6 6 63.6 2366 2366 0 07/16/86 7 63.6 0 2366 2366 07/17/86 8 63.5 2366 2366 -0.1 2366 07/18/86 9 63.3 -0.3 2366 07/22/86 13 63 2366 2366 07/29/86 20
-0.6 63
( 2366 2366 2366 2366 08/06/86 28 63.4
-0.6
-0.2 2366 09/04/86 57 64 0.4 2366 09/22/86 75 64 2366 2366 11/03/86 117 0.4 2366 64.8 1.2 2366 12/08/86 152 64.1 2366 2366 01/05/87 180 0.5 2366 63.9 0.3 2366 02/10/87 216 63.8 2366 2366 03/13/87 247 0.2 2366 63.9 0.3 2366 04/14/87 279 64 2366 2366 05/08/87 303 0.4
~ 2366 64.2 0.6 2366 06/08/87 334 64.3 2366 2366 07/06/87 362 0.7 2366 2366 64.1 0.5 bg 2366 08/03/87 390 64.2 0.6 2366 09/01/87 419 64.5 2366 2366 10/05/87 4ft 0.9 2366 64.7 1.1 2366 11/16/87 495 64.7 3366 2366 12/16/87 525 1.3 64.8 1.2 2367 2367 2367 07/09/86 65.1 2367 07/09/86 0 65.2 2367 2367 0.1 2367 07/10/86 1 65.2 0.1 2367 07/11/86 2 65.2 2367 2367 0.1 2367 07/14/86 5 65.4 0.3 2357 07/15/86 6 65.4 2367 2567 0.3 2367 07/16/86 7 65.4 0.3 7367 07/17/86 k 2367 2367 07/18/86 9 8 65.4 65.5 0.3 0.4
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- p o i n t b a s e l i n e ~ 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 2367 1.5 2367 12/08/86 152 66.1 1
~ 2367 2367 01/05/87 180 66 2367 0.9 2367 02/10/87 216 66.2 2367 1.1 2367 03/13/87 247 66.2 1.1 '
2367 2367 04/14/87 279 66.3 2367 1.2 2367 05/08/87 303 66.5 1.4 2: -i7 2367 06/08/87 134 66.5 1.4 2367 2367 07/06/87 362 66.4 1. 3, 2367 2367 08/03/87 390 66.5 2367 1.4 2367. 09/01/8.7 419 66.8 1.7 2367 2367 10/05/87 453- 67 2367 1.9 2367 11/16/87 495 67 1.9 2367 2367 12/16/87 525 67.1
, 2 23C8 2368 07/09/86
( 2368 2368 2368 2368 07/09/86 07/10/86 0 1 67.1 67 66.9 0.1 2368 0.2 2368 07/11/86 2 67.1 0.2 2368 2368 07/14/86 5 67.2 2368 0.3 2368 07/15/86 6 67.3 2368 0.4 2368 07/16/86 7 67.2 2368 0.3 2368 07/17/86 8 67.3 2368 0.4 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 0.7 2368 08/06/8'6 28 67.7 2368 0.8 {S 2368 -09/04/86 57 68.1 2368 1.2 2368 09/22/86 75 68 2368 1.1 2368 11/03/86 117 68.7 1.8 2368 2368 12/08/86 152 68.2 2368 1.3 2368 01/05/87 180 68.1 1.2. 2368 2368 02/10/87 216 68.5 2368 1.6 2368 03/13/87 247 68.7 1.8 2368 2368 04/14/87 279 68.6 2368 1.7 2368 05/08/87 303 68.9 2 2368 2368 06/08/87 334 68.8 2368 1.9 2368 07/06/87 362 68.7 2368 2368 1.8 08/03/87 390 68.9 2 2368 2368 09/01/87 419 69.1 2368 2.2 2368 10/05/87 453 69.4 2368 2.5 2368 11/16/87 495 (, 2368 , 2368 12/16/87 525 69.4 G9.4 2.5 2.5 1 VC., s n-sB l L.? .4%.'21...
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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
?.363 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 11/16/87 495 62.4 2.4 2363 2363 12/16/87 525 62.1 2.1 2369 2369 07/09/86 61.4
( 2369 3369 2369 2369 07/09/86 07/23/86 14 0 61.4 61.9 0.5 0 3369 4 2369 09/22/86 75 62.6 1.2 N 2369 2369 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 3 2369 2369 11/16/87 495 63.4 2 2369 2369 12/16/87 525 63.4 2 2370 2370 07/09/86 61.5 3370 2370 07/09/86 0 61.3 -0.2 2370 2370 07/23/86 14 62.6 1.1 2370 2370 09/22/E6 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
'3370 2370 01/05/87 180 63.7 2.2 2370 2370 02/10/87 216 63.5 2
(_ 2370 2370 03/13/87 247 63.7 2.2 I ~ : Nc , s -m 81i'. .
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*********************************ine DEVIATION
;2370 2370 04/14/87 279 2370 63.9 2.4 2370 05/08/87 303 63.9 2370 2370 2.4 06/08/87 334 64 2.5 2370 2370 07/06/87 362 2370 63.8 2.3 2370 08/03/87_ 390 63.9 2370 2370 '09/01/87 419 2.4 2370 64.3 2.8 2370 10/05/87 453 4 64.3 2370 2370 2.8 2370 11/16/87 49.5 64.3 2.8 2370 12/16/87 525 64.3 2.8 2371 2371 07/09/86 2371 64 2371, 07/09/86 0 64 2371' 2371 07/23/86 14 0
64.3 0.3 2371
, 2371 09/22/86 75 65.4 2371 2371 ,11/03/86 117 1.4 2371 66.1 2.1 2371 12/08/86 152 65.8 23/1 2371 1.8 01/05/87 180 65.8 2371 2371 02/10/87 216 1.8 2371 65.8 1.8 2371 03/13/87 247 6S.8 2371 2371 04/14/87 279 1.8 2371 65.9 1.9 2371 05/08/87 303 66
(. 2371 2371 2371 2371 06/08/87 334 66 2 2 07/06/87 362 66 2371 2371 08/03/87 390 2 2371 66~ 2 2371 09/01/87 419 66.4 k. 2371 2371 10/05/87 453 2.4 2371 66.6 2.6 2371 11/16/87 495 66.6 2371 2371 12/16/87 525 2.6 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 2.1 2372 12/08/86 152 67.8 1.7 2372 01/05/87 180 67.7 2372 2372 1.6 2372 02/10/87 216 67.6 , 2372 03/13/87 247 67.7 1.5 2372 2372 04/14/87 279 1.6 2372 67.7 1.6 2372 05/08/87 303 67.8 2372 2372 1.7
-2372 06/08/87 334 67.8 1.7 2372 07/06/87 362 67.8 2372 2372 1.7 2372 08/03/87 390 68 1.9
{ 2372 09/01/87 419 68.3 2372 2372 10/05/87 453 2.2 2372 2372 68.4 2.3 2372 11/16/87 495 68.5 2.4 2372 12/16/87 525 68.6 2.5 I
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sor data sor data s days from increasing increasing INCREASING s/n s/n date baseline se
*****************************************tpoint baseline DEVIATION 2362 2362 07/09/86 61.3 2362 2362 07/09/86 0 61.2 2362 -0.1 2362 08/06/86 28 62.3 1
'2362 2362 09/22/86 75 63 1.7 2362 2362 11/03/86 117 63.5 2362 2.2 2362 12/08/86 152 63 2362 1.7 2362 01/05/87 180 63 2362 1.7 2362 02/10/87' 216 62.8 1.5 2362 2362 03/13/87 247 63.2 2362 1.9 2362 04/14/87 279 63.3 2 2362 2 3 ti2 05/08/87 303 63.4 l 2362 2.1 l 2362 06/08/87 334 63.5 '
2362 2.2 2362 07/06/87 342 63.5 2.2 2362 2362 08/03/87 390 63.6 2362 2.3 2362 09/01/87 419 63.9 2.6 2362 2362 10/05/87 453 64.1 2362 2.8 2362 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 0.9 2373 11/03/86 117 62.5 2373 1.5 2373 12/08/86 152 62 - e-1 2373 2373 01/05/87 180 62 1 2373 2373 02/10/87 216 61.8 2373 0.8 2373 03/13/87 247 62 1 2373 2373 04/14/87 279 61.9 2373 0.9 2373 05/08/87 303 61.8 2373 0.8 2373 06/08/87 334 61.8 2373 0.8 2373 07/06/87 362 61.8 2373 2373 0.8 08/03/87 390 62 1 2373 2373 09/01/87 419 62.5 2373 1.5 2373 10/05/87 453 62.5 2373 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 62.6 2374 2374 07/09/86 0 62.6 2374 0 2374 08/06/86 28 63.9 2374 1.3 2374 09/22/86 75 64.3 2374 1.7
, 2374 11/03/86 117 64.9 2374 2.3 2374 12/08/86 152 64.2 2374 1.6 2374 01/05/87 180 64.2 2374 1.6 2374 02/10/87 216 63.9 3374 1.3 f 2374 03/13/87 247 64.2
\ 3374 1.6 2374 04/14/87 279 64.2 1.6
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~ /n date baseline set DEVIATION
****-************************************* point baseline 2374 2374 05/08/87 _ 303 64'2 1.6-
. 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
'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 2,375 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 1375 07/06/87 08/03/87 362 390 67.9 68 3.1 3 3.1-h 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 237S 2375 12/16/87 525 68.6 3.7 2376 2376 07/09/86 64.3 2376 2376 07/09/86 0 64.4 0.1 2376 2376 08/06/86 28 65.6 1.3 e 2376 2376 09/22/86 75 66.4 2.1 237G 2376 11/03/86 117 66.9 2.6 2376 2376 12/08/86 152 66.8 2.5 2376 2376 01/05/87 180 66.5 2.2
, 2376 2376 02/10/87 216 66.7 2.4 2376 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 2.9 2376 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 67.8 3.5 2376 2376 10/05/87 4)3 68 3.7 2376 2376 11/16/87 495 67.9 3.6 2376 2376 12/16/87 525 68 3.7 (_ 2361 2361 07/09/86 60.3
- - N C, . .. 5-\\: 33 M S. %.2 I.. . '
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2 4 s-M d es#34 _ , . _ __c._ ;_ , _ _ , _ . , _ . . , _ . _ . , _ _ -, . _ _ _ . . _ , ,_ _ __,__._
i 8 k 4 sor data sor' data days from increasing increasing INCREASING s/n s/n date baseline
***************************************setpoint baseline DEVIATION 2361 2361 07/09/86 0 60
-2361 2361 -0.3 08/06/86 28 61.2 0.9 2361 2361 09/22/86 ' 75 61.3 2361 1 2361 11/03/86 117 61.8 1.5 2361 2361 12/08/86 152 61.1 2361 2361 0.8 01/05/87 180 60.9 0.6 2361 2361 02/10/87 216 60.8 2361 2361 0.5 03/13/87 247 60.9 0.6 2361 2361 04/14/87 279 61.1 2361 2361 0.8 05/08/87 303 61.1 0.8 2361 2361 06/08/87 334 61.3 2361 2361 1 07/06/87 362 61.2 0.9 2361 2361 08/03/87 390 61.4 2361 2361 1.1 09/01/87 419 61.9 1.6 2361 2361 10/05/87 453 61.9 2361 2361 1.6 11/16/87 495 61.7 1.4 2361 2361 12/16/87 525 61.7 1.4 2377 2377 07/09/86 2377 2377 61.7 07/09/86 0 61.6 -0.1 2377 2377 08/06/86 28 62.8
( 2377 2377 2377 2377 09/22/86 75 62.7 1.1 1 11/03/86 117 63.3 1.6 2377 2377 12/08/86 152 63.1 2377 2377 1.4 2377 01/05/87 180 63.1 1.4 2377 02/10/87 216 63.1 2377 2377 1.4 03/13/87 247 63.2 1.5 3377 2377 04/14/87 279 63.3 2377 2377 1.6 2377 05/08/87 303 63.3 1.6 2377 06/08/87 334 63.3 2377 2377 1.6 2377-07/06/87 362 63.3 1.6 2377 08/03/87 390 63.5 2377 2377 09/01/87 419 1.8 kb. 63.9 2377 2377 10/05/87 453 2.2 64 2377 2377 11/16/87 495 2.3 63.9 2377 2377 12/16/87 525 64
'2.2 2.3 2378 2378 07/09/86 2378 65.5 2378 07/09/86 0 65.6 2378 2378 08/06/86 28 0.1 66.8 2378 2378 09/22/86 75 1.3 66.8 2378 2378 11/03/86 117 1.3 68 3378 2378 12/08/86 152 2.5 2378 67.2 1.7 2378 01/05/87 180 67.3 2378 2378 1.8 2378 02/10/87 216 67.4 1.3 2378 03/13/87 247 67.7 2378 2378 2.2 L 2378 04/14/87 279 67.8 2.3 2378 05/08/87 303 67.8 2.3 vc, s 0 43 /,zs.97 7/
4' S - (3 -%4 74 7A 2.
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%f fcR fA W df 7Hf 7ssND INswwrMS. (nu ogg in zu.ajc) k, sor data sor data days from increasing increasing INCREASING s/n . s/n date baseline set point baseline DEVIATION e-**************************************** ************************x*****
.2378 2378 06/08/87 334 67.7 2.2 2378 2378 07/06/87 362 67.5 2 2378 2378 08/03/87 390 67.6 2.1 2378 2378 09/01/87 419 67.9 2.4 2378 2378 10/05/87 453 58 2.5 2378 2378 11/16/87 495 68 2.5 0
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 08/06/86 28 67.8 1.1 2379 2379- 0,9/22/86 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 1.3 2379 2379 04/14/87 279 68.6 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 08/03/87 390 68.6 1.9 09/01/87 419 69 2 . .'. 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 ~" 1 2380 2380 07/09/86 64.7 2380 2380 07/09/86 0 64.9 0.2 2380 2380 08/06/86 28 2380 2380 66.1 1.4 al/ 09/22/86 75 66 1.3 P 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 l 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 07/06/07 362 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 2380 11/16/87 495 67.9 3.2 2380 2380 12/16/87 525 68.1 3.4 l, ~
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t 7 I t BRANCH /PRCJECT IDENTIFIER I"66 Tl DEMONSTRATED ACCURACY CALCULATION ( C O M P U T A T I O N S / A N A L,.Y S E S D) ACCURACY CALCULATION INDEX f f4
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BRANCH /PROJENT IDENTIFIER /. 2 S . f **- 21 __ _ DEMONSTRATED ACCURACY CALCULATION
' C o 't P U T.A T I O N S / A N A L Y h E S B) WATERLEG UNCERTAINTY DISCUSSION / CALCULATION
/
APPLICABLE TO ALL LOOPS LISTED ON SHEET I.
, APPLICABLE ONLY TO. LOOPS:
4 WATERLEG BECAUSE: UNCERTAINTY IS NOT CONSIDERED FOR THE CALCULATION NO WATERLEG EXISTS FOR THIS CALCULATION. THE EFFECTS OF WATERLEG CHANGES ARE INSIGNIFICANT. SEE DISCUSSION / CALCULATION BELOW. OTHER. SEE DISCUSSION / CALCULATION BELOW. A WATERLEG UNCERTAINTY DOES EXIST-FOR THIS LOOP. SEE CALCCLATION/ DISCUSSION BFA:4M. ou Wr A ec V SEE SENSING LINE DIAGRAM ON SHEET /0 OF THIS CALCULATION. i L REV_Q., PREP DATE CHECK DATE _ SHEET C/O REV._L PREP f(A DATE ,.e1 if CHECK fJA REV_L PREP
~
DATE___ _ CHECK DATE f t W SHEET DATE SHEET A C/0 4 C/O (..a
t 5 t BRANCH / PROJECT IDENTIFIER l-I.S'87-*/
. , DEMONSTRATED ACCURACY CALCULATION ne From the discussion on page /Jb , the longest reference leg.had a pressure of 305.4 INWC with an error of 2.5 INWC for a maximum
[3 pressure of 307.9 INWC. From drawing 47E225-10 rev 2 the , t3mperacuro extremos of the room is 40 to 110F with the normal range from 70 to 92F. Attachment 23 shnws the temperature history of the UHI. room. This data givec assurance that the UHI room was between 65 and 85F when the setpoint was determined. 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 round outside of the range. Therofere, the temp 9rature induced eirors will be based upon the original setpoint determination temperature between 65 and 85F and the operating temperature between 70 and 90F, Assuming that the tank's temperature remains constant, the error caused by temperature variations is the density changes in the reference leg. The densi:y of saturated water at: G5P = 62.3403 lbm/ft 70F = 62.3053 lbm/ft 3 85F = 62.1717 lbm/ft 3 90F = 62.1157 lbm/ft The waterleg egror, referenced to water at 68F,14.696 psia (62.316 lbm/ft is: 65 to 90F: ((62.3403 - 62.1157)/62.316)
- 307.9 = 1.1 INWC ""
85 TO 70F: ((62.3053 - 62.1717)/62.316)
- 307.9 = 0.66 INWC ,
The error going from 65 to 90F represents a decrease in pressure on the reference leg. This requires a lower nank level to reach the instrument's differentia.1 pressure setpoir t. Viewing this
~
change from an instrument accuracy perspective. this is equivalent to raising the instrument setpoint. This yields a positive error. .The change in, temperature from 85 to 70F then represents a negative error. The waterleg error due to temperature variations is +1.1 / -0.'.' INWC.
@6 D' 5 d u h5 0N t$ F'A.TWO h9 tT T p.c.e G tnt.e Lt. 4 6 FRoM '
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i 8 t BRANCH / PROJECT IDENTIFIER __.j_ _L _~. __
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kl_____ DEMONSTRATED ACCURACY CALCULATION LOOP DIAGRAM ' LOOP IDENTIFIER: APPLICABLE TO ALL LOOPS LISTED ON SHEET' d. APPLTCABLE ONLY TO LOOPS: VALVE [g . _ _ _ _ - . _ . . - - LOGIC ( I I e L L15 PLANT / UNIT (S)MhI[,h.t1 REV.'j_ PREPARED ig,1_ CHECKED _'fC' ,,,t DATE _i/_',/_'_" SHEET h C/0[h
,---y - - - - - - -, , , , , -,_4 7---
r i 8 t BRANCH / PROJECT IDENTIFIER __.)_ d 3.2.h_7_~_db________ DEMONSTRATED ACCURACY CALCULATION INSTRUMENT SENSING DIAGRAM ( LOOP IDENTIFIER: APPLICABLE TO ALL LOOPS LISTED ON SHEET [.
, _ _ APPLI' CABLE ONLY TO LOOPS:
A CL . := ' ' i c" y_ _ 993
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i i 8 k BRANCH / PROJECT IDENTIFIER DEMONSTRATED ACCURACY CALCULATION __.f'_ h i h M _--_---- ' ACCUR ACY DISCUSSION l The accuracy of thi s instrument f or normal and post seismic conditions will be determined by considering the parameters tabulated on sheet __ of this calculation. The accdracy calculation f or seismic (As) is bounding for all seismic events . Accuracies calculated in this calculation will be determined by algebraically summing those f actors which are not independent va-i abl es (i . e. , unidirectional temperature, waterleg uncertainty, seismic, etc.) with the results of the square root of the sum of the squares method for those f actors which are independent variables. L/
' The square root of the sum of the squares method shall be used in this calculation for calculating accuracy since the f actors af fecting accuracy are independent variables.
V Bi-directional errors 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 the negative portion of the bi-directional error. This method is conservative and therefore it will be used in this calculation. Example: 110 = bi-directional error
+5 = first uni-directional err or
-2 = second uni-directional error Total Error = (+ 10 + 5) to ( 2) = + 15 to - 12 others r
! .9 - PLANT / UNIT (S): hhh!]Ikh REV 0 eReeAnso ;_ddfic_ CwcCxEo _ M;.-:p oATc e e.J.<!> snecT E CeoJ6 em
i t BRANCH / PROJECT IDENTIFIER __j_$__[_2..b.[___ DEMONSTRATED ACCURACY CALCULATION ACCUR ACY DISCUSSION (CONTINUED)
/
.i THE FOLLOWING DEVICES ARE CALIBRATED INDIVIDUALLY.
THEIR ACCEPTANCE BANDS ARE AS FOLLOWS: DEVICE ACCEPTANCE BAND REFERENCE 2 - LS-G7- 2 I I / > D " H10 # IO I L - L S ~ B 7- 2 ~* 2 l .h" M10 cig _Li -L S - 6 7- 2.3 _ I _. h " H~ O * /C _
'( 1 - LS - 4 7 - 2,A rJ.0" !4 to e/O
' THE FOLLOWING DEVICES ARE CALIBRATED TOGETHER.
THE ACCEPTANCE BAND FOR THE COMBINATION OF THESE DEVICES IS AS FOLLOWS: DEVICE ACCEPTANCE BAND REFERENCE REV,h_PREPARCD '. CHECKED ' ' E ' "- DATE /'/W SHEET h C/Ojf i ---- - ---
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4 BRANCH /PROJECTIDENTIFIER__h[_3-h2r_dI DEMONSTRATED ACCURACY CALCULATION r . ACCURACY CALCULATIONS INDEX S YM BOL_
;) PcPca.45!;.;r/ W Accuf AcY &
0 R unopu u su.irr remo 2,
- 2) DE.2i~ ildA CC.02.hCV bc-
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- 4) SE!SMic IDACCURACY Se
- S) ET~4nc ACC:su,c: E-lTcT 5=&. gl
- 6) /dP()T TEST ltJSTROMEDT CAuBRATIch I CI'e_
it)AC. CURACY ICRC ( /) INPUTlA)ACC.UR.AC.Y TEST WstiWMEl)T RENG
- 8) WATEELECr U/J C E R ' E N I Y 'MI 8-C]) ACCEPTANCE BAno Au jo f2cc.ss S yp cc1?-17\wT'( Pao c Se lC) Pt.occ35 Lwcccran'n' PROCSe m II) WORMAL ACCURhCV Art
- 12) POST Seismit Accuekt9 As e c Au eeAric a' caca cAusc ii 13 I4 Amb gt l ~ -. _ u s ve,. c-w ; .Av l CUlGN[O 4 e Oncxin 9 (p{[q}
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// COMPU.TATIONS/ ANALYSES D) ACCURACY CAI4UIATIONS
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i , ; .. BP.ANCH/ PROJECT IDENTIFIER /-tS.67 2I DEMONSTRATED ACCURACY CALCULATION
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s ? BRANCH / PROJECT IDENTIFIER /-ZS- (9 2), DEHONSTPATED ACCURACY CALCULATION
SUMMARY
0F RESULTS [ (BISTAELE-] v APPLICABLE TO ALL LOOPS LISTED ON SHEET F .
,_ APPLICABLE O!1LY TO LOOPS: k LIMIT 95 38 guc,p/ g7. o / _
PV = SP + Aa _, _ A///
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PV = S P + A s PV = SP + An 9 5 2 c) SETPOINT (SP) 62. Co PV = SP - An Pfe/3 /3 PV = S P - A s _ _ _ PV = SP - Aa y /A MARGIN d.of -- SATETY LIMIT FS./O )N I ALL VALUES SHOWtt ARE JN.or AJA/ER ABCVf Vixwn /4cotxt bar l ( REFER TO ACCURACY DISCUSSION, SHEET n FOR-CLARITICATION OF ABOVE )
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. REV 0 PREP ve DATE 5129M CHECK % DATE T f S-W SHEET f 34 C/O 74 REV A PREP vc DATE 7.77.W CHECK /w DATEStt./O SHEET C/O REV 2 PREF, ,DATE CHECK DATr. '~~
SHE"T C/0
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- TITLE: ,-/S-F7-91 ,
REVISION: 2. # 57 POST-SEISMIC RECAL. /IS IS NOT h CALIBRATION FREQUENCY: 4 TO DAYS REQtTIRED N//P h I40P ANf: .f 2. st? - y, yt/ JN. N4TEg MODIFIER / INDICATOR ANf3 ANf INSTRUMENT ANf INSTRUMENT 1, 2'~ LS- t 7- 2 I f 2*C9l- $*77 JAt. pgrER I, 2
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i 8 BRANCH / PROJECT IDI TIflER /* /S
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DEMONSTRATED ACCURAC.' CALCULATION ( , C O !! C L U S'I O N S ' ~ _K APPLICABLE ~TO ALL-LOOPS LISTED ON SHEET _6 . APPLICABLE O!!LY TO LOOPS: b TMS 996SSNT Sf7P01NT 2S NOT ADipop/76 To supMfi~ ZhE ANA urre ' tzinirs Dr./ 70 fr. ? elwuss Aga! 7N! //
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BRANCH / PROJECT I DENT IFIER l__/--d_S_~ @7_-'_U_ _ _ . DEMONSTRATED ACCURACY CALCULATION
, . REFrERENCES/ ATTACHMENTS NUMDER -------------------REFERENCE (RIMSM)----------------------
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t = t BRANCH / PROJECT I DENT I F I ER _ _ j_-_/,,$__8.'Z__2_ i___ _ __ _ ___ DEMONSTHATED ACCURACY CALCULATION (. REFERENCES /ATTACHNENTS N JMBER -----------------RE F E R E N CE ( R I MS # ) ------------- - ---- _._?__ . _:hc_1s.v.L=,_&s12:cAnak.bh _kzuasans ____ __ __. BLESS.u2E__htcaes__0_GauSED__2___/ Z EE_l;il.-33 ______ __A_ s!p_ __3__+4_ _~_L97f_____3 4.5__%_M_ 15_M____ _ _ _ _ __ _ _ _
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DEMONSTRATED ACCURACY CALCULATION k REFERENCES / ATTACHMENTS NUMBER ----------------R EF E RE NC E (RIMS #)-------
. . AETJMahCaL. ImWG)IS.L.G2dGML.kE' ?.4.1LU5)3 ~1.% 5O 127%d212.LT "LAD
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I G $.thrng Ei. ment mw r t.pt.,- 3 i Correct.d W nwnum D. 5 B nd 8 (3) to 12 (3) - 18 36 psi t i 1 Approsim i. M.nimum D..d B.nd t too p.id $.9 Point - 27 psi I 4 T q .oswa.tt naut Attachnsent No __3 Shee+. L. ef.3 _. Loop A/ldentifier l ~ L 'i ' b 7 - 2 I W WD ,
# WMW?Nfr M '.!M TA.m d bc y md.%DJd6QkinL., X'F ' W l. M "E '"i - .
h.4%jg y/# J.7$4*MErD*M,*Ca'ifiM/d'LYd'*k% Yr h'Af ( ; M*b g ) . , j. f ,
e yemperature - Remote Bulb 40 - 2250F 203T A-B125-J J TTX6 gg Note 4a 203N6-B125-JJTTX6 203T A-BB125-J JTTX6 203N6-88125-J 8TTX6 40 - 2250F 20 XT A-B 125-J J TT X 6 Nste 5 20X N6-B 125-J J TT X 6 20XT A-BB125-J JTT X6 20XN6-BB125-JJTTX6 High Static Working Pressure - Dif ferential Pressure for Accident Conditions to 325'F/25 psi (less margin) Range Max Working Pressure Notes 5-35" w.c. 1500 psi 103 AS-8202-N X-J J TT X6 (7 6 11; 1850 psi (7.8612) 7-100" w.c. 103 AS-B 212-N X-J J TT X6 10-100" w. c. 1850 psi 103 AS-3 8 212- N X-J J T T X 6 (8) 1850 psi (9 or 13) 20-200" w.c. 103AS-8203-NX-JJTTX6 30-200" w.c. 1850 pst 103 AS-B B 203-N X -J J T T X 6 9) 3000 psi 3-60 psid 103 AS-B 903-N X -J J TT X 6 5-60 psid 3000 psi 103 AS-8 8903-N X-JJ TT X6 50-300 psid 3000 psi 102 AS-8405-N X-J J TT XS ( ,0 ) 3000 psi (9 .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-JJ TT X 6 (9 6 10) 100-500 psid 3000 psi 102 AS-B B 305- N X-J J TT X6 (9 6 10) For availability of other ranges, please consult the factory. Notes 1 Test Conditions: 227oF/7 psig Acton 17344-82 N-D /18441 -83 N 2a Test Conditions: 435'F/115 350cF/115 psi 6 spray Acton 17344-82N-C psi 5 spray & trradiation Sandla 83-2652 2b Test Conditions: 2c Test Conditions: 380 F/48 psi Acton 18577-83N 2d Test Conditions: 325cF/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) Attodment No. 3 Sheet 7 of 3 lav 4/fdentiher f - t. $ . Ag . t. p
W - s ECR QUALIFIED SWITCH LIS? I ; b TABLE 1 Fir accident temperatures to Adjustment For accident tencerature 2 2*F and 5 ps) (Note 1) Range to 350'F and 115 psi and spray (Note 2) , Nota ' 1246 h-NX-C1 A-JJTTX6 .5 - 6 psi (Note Za) 12TA-84-NX-C1 A-JJTTX6 l 1M6-BB4-NX-C1 A-JJTTX6 (Note 2d) 12TA-BB4-NX-C1 A-JJTTX6 12H6-05-NX-CI A-JJTTX6 ' .75 - 12 psi 12T A-9 5-N X-C1 A-JJTTX6 1:N6-BB5-Nv-C1 A-JJTTX6 12TA-BB5-NX-C1 A-JJTTX6
, 11 tid B:.5-NX-C1 A-JJTTX6 1 - 16 psi 12TA 845-NX-CI A-JJTTX6 12tM-BB45 NX-C1 A-JJTTX6 12TA-BB45-NX-C1 A-JJTTX6 4,N5 34-NX-C 1 A-JJTTX6 2 - 25 psi 4T A-84-NX-C1 A-JJT TX6 al' 4N6-8 84-NX-C1 A-JJ TT X6 4T A-BB4-NX-CI A-JJTTX6 4N6-B5-NX-C1 A-JJTTX6 3 - 50 psi 4TA-B5-NX-C1 A-JJTTX6 4N6-BB5-NX-C1 A-JJTTX6 4TA-BBS-N X-C1 A-JJTTX6 4N6-B45-NX-C1 A-JJTTX6 4 - 75 psi (Note 2b) 4TA-845-NX-C1 A-JJTTX6 ,
4N6-B B 45-N X-C1 A-JJTTX6 4TA-BB45-NX-C1 A-JJTTX6 6NS-B3-NX-C1 A-JJTTX6 12 - 100 psi 6T A-B3-N X-CI A-JJTTX6' 6N6-BB3-NXoC1 A-JJTTX6 6TA-BB3-NX-C1 A-JJTTX6 6 NG-B5-NX-C1 A-JJTTX6 20 - 180 psi
- 6T A-BS-N X-C1 A-JJTTX6 ,
6N6-B B5-NX-C1 A-JJTTX6 6T A-B B5-NX-CI A-JJTTX6 6N6-B&NX-C1 A-JJTTX6 25 - 275 psi 6T A-845-NX-C1 A-JJTTX6 6N6-9845-NX-C1 A-JJTTX6 6 TA-BB45-NX-C1 A-JJTTX6
$N6-B3-NX-C1 A-JJTTX6 25 - 240 psi STA-B3-NX-C1 A-))TTX6 b SN6-B0 3-NX-CI A-JJTTX6 ST A-BB3-NX-CI A-JJTTX6 ,
SN6-B5-NX-CI A-JJTTX6 35 - 375 psl ST A-B5-NX-C1 A-JJTTX6
$N6-B B5-NX-CI A-JJTTXG STA-BB5-NX-CI A-JJTTX6 SN6-845-NX-C1 A-JJTTX6 45 - 550 pti STA-B45-NX-C1 A-JJTTX6 5N6-BB45-NX-CI A-JJTTX6 S T A-B B 45-N X-C1 A-JJ TTX6 Note 3 9N6-B4-NX-C1 A-JJTTXE 100 - 500 psi 9TA-84-NX-C1 A-JJTTX6 Note 3 9N6-BB4-NX-C1 A-J ITTX6 9TA-BB4-N X-CI A-JJTTX6 Note i 9N6-05-NX-CI A-JJTTX6 200 - 1000 psi 9TA B5-NX-C1 A-JJTTX6 N9tc 3 9N6-BB5-NX-C1 A-JJTTX6 9TA-BB5-NX-C1 A-JJTTX6 ,
Nota 1 9N6-845-N X-C1 A-JJT TXS 200 - 1750 psi 9TA 845-NX-C1 A-JJTTX6 N.itu 3 9 N 6 - B B 45 -N X -C14.-J J T T X 6 9TA-BB45-NX-CI A-JJTTX6 I N6-845-NX-C1 A-JJTTX6 500 - 4000 psi 1TA-845-NX-CI A-JJTTX6 ' IN6-BB45-NX-C1 A-JJTTX6 1 TA-BB45-NX-C1 A-JJTTX6 . 3 N6-845-NX-C1 A-JJTTX6 1000 - 7000 psi 3TA-845-NX-CI A-JJTTX6 3N6-B B45-NX-C1 A-JJ TT X6 3TA-BB45-NX-CI A-JJTTX6 4/ecuum Cage , 34N6-B118-NX-C1 A-JJ TT X6 30" HgV to +.5 psi 54TA-0118-NX-C1 A-JJTTX6 54h6-8 0118-NX-CI A-JJTTX6 54TA-B B118-NX-CI A-JJTTX6 . 1cupa ature - Direct Mount M1 N G- B 125-J J T T X 6 80 225'F Note 4alb 201 T A-B 125-JJ TT X 6 Note 6 201 N 6-d B l ? 5-J J T T X 6 201 T A-B B125-JJ T TX 6 heathment No._3 _ gee, 3,Q l , Lamp illdentifier _ /- t s -s 7 2 m ,_ _ _ _ - _
.g--- 3 . g , . ." r v' a + ' --
3.0 SPECIFICATIONG . Power Requirements: 115 VAC +/-10%, 60 He
. Control Rangen Avail abl e:
DCVM/D-1: full scale 0.5 toat100 upPSID to 1000 PSIG 1ine pressure. BCVM/D-2: 0. 5 scale at to 300 F3ID full 11rie pressure. up to 2400 PSIG Mwasure<hent Ranges: ' Full scale ranges consistent wath the conteci customer speciftedrangos, nSoc t..i n e Pr e n s ur oAccuras
. PA'3 5 engineering units.
-~ %
% +/-0.1% Full Scales Difforent'al Accuracy: (+/-0.05% Full Scale optional)
+ /-0.1 */. Fu l l Seele 16 0
(*/-0.05% Ful1 Scal e op ti ona1 ) at at.morpheric line pritsnur e. At line pressure abnve atmospheric. and g ! grpy g a calibeation NQ
~
uncertainty of +/-0.1 wgter (0.004 PSI) inch of
.s s t Mardi a : ,
Instrument air or nitrogen .. (Separ eytors must be used on l i qui d-f 1 l l ed u y.s t enu ) 2nlet Prensurrr Nequi amentr.: 110*/. o f maximum l i ne pr er.sure. Pressure Re.adout: Inlet G. <,. Di gi t,a l 5-dacit L.ED disp 1cy. Dimou. tuns: 1-1/2" dial.
-H-3/4"H (19" reckxmount 16-1/4"W ' 10-1/4"D F'ressur is Connecttons: avat1oble)
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\ 4AL TEST CERTIFICATE FOR DIFFEREMYlAL, PRESSURE HiiTCH g f;5 ~
Customar __tggg,33rgy Atgg,gegi
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d % E' d { fy 's t n 4R FI A N T- Custemor P.O. paptC.- &57M ,
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5 (D _ 3 ales Order No. AMe 1: Item No. _ l t/<dal *: umber FINAL TEST AND CAllBRATION DATA 32 rial Uumoat jt), lag.ggym .gfy. gyp g * ( gy.]y7) pf- 7 3 ei? ? g.:Q-3_ ff '7 3/N.\ tau UU w r tw91..S/ 2 LS 17-Q 2 Lht7 23 l Hydexuth: Tast per IL, or H_C &d 2 thst- V _O a305-035 hv. ^ / Fe^msorW Rosults i
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_ Ma@j Arc i Med [pps' ~? *' SOR Gaugs [ lumb 2r
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wp - 2 21 . f SET T-0 INT CAllGRATION he SittST CYCL 3 Set'Ft., increasing ,,
, pg% g "L 9(; 4/"
S t ,1. , Dicreasing .,.tf7pfffy gy,y" , Dead Band g 7, % g7,I % h;75e.h
/6. ) ' s /0 o /%
t 9e 3 % i ~ SECONO CYCLE /01 Y h. Sot Pt. . increasing A h 97,g"g } 9 7, f"',' , , 93, y L -- $7,f'[wc. t$ in Pt., Decreasing 9 7, j ".,g h j m f 7. / % . 'p'fN-gA Dead Dend , { 1' ~
/0, / b.c kJ W f .. . I.'k'.
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_ _ Soft Cauno Humber W/r 3'/$ '
' ?- M E '
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TEST PROCEDuflE 1)
- 2) Connect pressure source to high sideVorfry tait gauge has been callbrate .
- 3) side process connectica to atmosphore. process connection and vent low 4)
- 5) Decrease pressuro to decreasing set point and rfecord. Increa Reduce pressura to zero psig.
- 6) Repast St2ps 2, 3 and 4 7) bf insts and rccord in QA calibration leg. Chock calibrotlon of.gsuge at s
~~ .1% of full scale, all pressure switches testod onIf the gauga varlos me:4 than callbrition must be retested per this procedure. au e since last h At n st a v Wnt No. t M .w x_ ?A 9, J i oneiv 4,,u,.ne.. p '/ % 4c., L oaf, wdawnr.1-ts -wp.2i
- .: ,<s o.ie _7 . e r q.3 0
d Tf,b - M n -~ MM j us ~ k.%wve 4345-050 es y,,g CAUORATION (*EnTIFICA TF l jl*;] . .. .. g g ,& . OO ......-
, ....J...... .......,.---..o . ,r .- , i == , ,
r.o. sox m t$ m m. o r.4 r an ir y ' cuna. xuaAs a pq . sa.neC% /cceccitwe FINAL TEST CERTIFICATE FOR DIFFERENTIAL PRES 5URE SWITCH
,Y Customer 71:yng t/Auef_ Amer 7y a tA customer P. O. MPtC.- B.57kyt g Smy*AH MtynAR ptAN*r Sales Order No. gwc I 900< c7 Item No, 1
l_ _ FINAL TEST AND CAllBRATION DATA Model Number lO3Ag. Jytygg .Agg.JJT'T4 . _g Serial Number fp7.]y7f' ff"-7 3 yyf' Tag Number : % Hydrostatic Test
,. y ,g 7 g ; 9,37.g y.g ; y Rev. [per 4Pressurt or H 0 A4 0 40 8305~056 //f! tsJ' / 1/ 1 e s' 4 e.
^ . ~ :-
. .s g Results my pg r. ere. \
y. t*s43 y .. SOR Gaug'e Numbe;' pept 2 2 f ' *#* SET POINT CAllBRATION _ __ FIRST CYCLE
- g-
.,, Set Pt. , increasing 4g g"g *p. ,'
9 7, g ** Q ,;Q Set Pt. . Decreasing y ., , , p , *. ,- & Dead Band 7, C j y , 7 ", SECOND C' ..E as Set 1. Increasing 9g % .y y, p g g Set Pt.. Decreasing g 7.,, , n,e gy, j n,,, , _ _ _ Q,;;nl W
- ?" ' . f,WY Dead Band., 'p f , jm 7 "ee .
u.
. m. ' yhu SOR Caugo Number
*/9M. f"/# ... - -U .
i, TEST PROCEDURE 11
- 2) Verify that gauge has been calibrated and recorded in 'QA callbration log.
Connect pressure source to high side process connectico and vent low side process connection to atmosphere. 3) Increase pressure from zero psig to increasing set point and record.
- 4) Decrease pressure to decreasing set point and racord.
_ 5) Reduce pressuro to zero psig. f
- 6) Repeat Steps 2, 3 and 4 7) gauge et set point immediately efter each series of y Check tests andcalibration record in of,QA callbration . If the loggauge verles more than
~
4 - .M of full scale, all pressure switches tested on the gauge since last calibration must be rotested per this procedure, f a . : b- <5'-]
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- - - Date 7-29 M b vevu e,.
muu as W. _ 7.'~v ',S. ew n0s-en i
. I ceunRATION CERTIFICATF ,gg g.'y..... ..
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- QtlALIFICATICnt TE5f!Mi CF .
j . LASS II ELECTRICA.'. 2 QUI;KZar 9
!" ,*.CC020.* M !!!Til IEEE STD. 323-1974, IEEE ST0pAh,a& ^p st : vio ,
M W G Of88 ! chW.I"' ~., t1.'ll* ' SCR, INC. Lh- ~ m HOV M F.4 ! 11 0 i u T= , a 660,1 ,l _ _ y. cw aza ,
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EQUIIt!ENT QUALIFIED: . SCR, ItaC. O!FFERENTIAL FRES$URE SWITCIIES: . iOOEL 10MS-8212.HI-JJTTI6 Ano 'p , . H00EL 103AS-3B903-MI-JJTTI6 sei'Q 3 # . ,o 6 e ',} o 6951 Purcits:e Ordw No.
-w
. 3 t
Prepared by: - - / - M Dat
/M Nck D. Cox, Senior N.E.Q. Scientist N /
NTS/Acton 533 Main Street, A: ton, MA 01720
%;'ti 3A. '1' f. L L U r n w
. D,,,
\ s Q H. J. Fredkin. Jr., H.E.Q. Manager NTS/Acton 1, S JSC/rla:203 ,
k RIMS, !!"A C M( Attadhment Nc. 5 sheet 1 _of 4 Loep g/identirjer d
\ /- LS 2) 1:
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3
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1 m. 4 : i e Test Report No. 18878-84N-3 4 i Page ~h-Z I .. TABLE 1: SurmARY OF FundCTIOMAL TEST DATA - Ol7FERENTIAL PRESSURE SWITCH . 1 IMITIAL FUNCTIOMAL TEST POST-IRRADIATION '
, .POSI-SEISMIC l
~
INCREASE OECREASE
- INCREASE . DECREASE, INCREASE DECREASE 9
SETPOINT: 103AS-B212 14.76" 1l20 103AS-B3903 10.43" H 2O 14.76* H 2O 33.5 Pi!G 31.0 PSIG 10.56* H 2O 15, 3" H 2O 11.26" H 2O 35.0 PSIG 31.5 PSIs 35.u PSIG 31.0 PSIG AVERAGE DEADBAND: El jj h .7 103AS-B212 103AS-88903 4.33" H 2O 2.5 PSIG 4.20" H 2O 3.5 PSIG 3.87" H 2O 53 4.0 PSIG INSULATION l i
'I$ RESISTANCE: f Ez 103AS-B212 >100 Gohns g {9 103AS-BB903 >100 Gohms
>10 Cohns
>400 Hohes
>10 Gohms N > 10 Gohns
- N, OlELECTRIC W.V.
LEAKAGE CURRENT:
}
Fu, 103AS-8212 <1 d i . U)? 103AS-BB903 <1 sA
<1 d <1 sA t- <1 mA 9 <1 sA
- l l i
, c, Mote: i .
gF No adjust:nents to the factory setpoint were made to either test unit throughout the test program.
; i Fi )
I. i O
. l 1
l P.O. 60X 591 'f7^4 J.ACX.C KCD ' Nif r _ _ -.l_lu r%Ab;2 ,a ,0Yu-a y1,/connelDevices co n
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TEST REPORT FOR BASELINE AND ACING TESTS AT SOR. INC. I
/ FOR ACTON NVIRONMENTAL TESTING CORPORATION !
TEST PROCEDURE NO. 18870-8tlN l SPECIMEN: HICH STAT!C PRESSURE - LOW DIFFERENTIAL PRESSURE SWITCH FOR MODELS
!
- 03AS-D212-NX-JJTTX6 (S/N 3-5-3573)
I 103AS-GB903-NX-JJYTM6 (S/H 04-5-3579) , 1.0 PURPOSE - To determina the influence of: *1 1.1 tiet point on dead band - 1.2 Static pressure on set point ( 1.3 Temperature change on set point 4 g 1.1 Temperatur2 agi y ano cycfc ag!ng per Paragraph 7.2 of Actcn , 2nviroamintal Testirig Corporation Test Frccedure No. 18678-84N. 4
)
2.0 PROCEDURE 2.1 E s t .voint influence on Dead Dand ( ' 2.1.1. I.isthed - The switch was cailbr5 tad it 10 and 100 inches .
; w.c. using water column manometers for reacout.
- 2.1.2 Results 4 2.1.2.1 gin 84-5-3373 (
Set Point 10.0d w.c. 100" w.c. 64 Ucad Sand 3.G" w.c. 7.7" w.c. ( 2.1.2.2 S/N 04-5-3373 (using pressura. gauges for readout) j Set Point 5 psi 30 psi 60 psi l' Dead Band 1.0 ps! 3.6 psi 4.1 psi y 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 470 , differential pressure transmitter. The low pressure port was manifolded to the tranrmitter low pressure port. I Supply, equalize, and vent valves were in the manifold. , The static pressure was applied with the eclualize open and us the transmitter zero was confirmad at each static after the 4 supply valve was closed. The differential was then slowly chenged by cracking the supp'y valve to increase and the equalize valve to decrease. 2.2.2 Results g 2.2.2.1 S/N 8t-5-3578: 2.2" w.c. change to 1500 psi g static. 0 2.2.2.2 S/N C4-5-3579: 1.9 psi change to 1500 psi static. s 2.3 Temperature Change influence on Set Point
$ 2.3.1 Method: The switch was place in an oven. Temperature was monitored by a thermocouple placed on the switch el body. Pressure was read out using a manometer with the (r pressure. applied to the high pressure side and with the low a pressure port vented to atmosphere. ... Attochment No,__ T _ Spe,,_y,,,,, egg _, ;
a Loop p/qgent,pe,_j - L g, p ,_. __ - , l
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- ACTON TEST PROCEDURE FOR A// If 82 M-710 :
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2.3.2 Results from a 0 to full scale applied pressure cycle are
. shown below: , ! 2.3.2.1 S/N 84-5-3578: '
- Set Point Set Point Temperature increase 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 increare 31.7 psid Decrease 29.2 psid ].
70'F 33.4 psid 28.8 psid E
. 2.4 Temperature and Cycle Aging I
2.4.1 Method
With the switch in the oven, temperature was > monitored by a thermocouple placed on the switch body.
- Pressure was cycled using the cycling apparatus of Figure d,
- 2. The switch contact load was 15 watts except one contact
- was 5 amps 120 VAC on S/N 84-5-3579. K 2.4.2 Results 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. 2.4.2.2 A temperature 280/282*F was maintained for 120 b hours. Using the Arrhenius equation the E equivalent 150' time g _ 1.24 , 1 1
~
K 2
= (120.8) exp .8617 x 10 ' 338.89 411.11 h
= 209,022 hours E Where: 2 exp = 2.71828
.8617 x 10" eV/*K = Boltzmann's Constant w 1.24 eV = Lowest activation energy on switch
$ materials .
338.89'K = 150'F 411.11'K = 280'F ~- This corresponds to 23.74 year.* of service at 150*F without margin, 21.58 years at 150'F with 10% ma rgin, and 40 years at 141'F with 10% margin. l CO 3.0 Data - Attached Atrochr.ient No. 6 Sheet 4 of.I-- 7 '! Loop t/ldentifier / - M ~@~ D ,4
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i l Account nunbar p020 765-U-01-D2111 should La utilized by CZ for this G.. . t odi fic atioa.
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i;^ sh a projact<J /iclJ atset 04te (70D) for this t:aJifiestion 12 t'a s '- l b. 9 -cyc14 3 out e-s far %n mits. [, ;r) - b~ Ycu are authoriavd 1151 CM for desisn anJ procurea: ant (if applicable). :.4
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~, "0" ring evitch h!si 103A. The switch was fasts 11ad ta parralal with . 6, r one of the Barte.a level switches and calibration was checked for a sia i4 aceth period of time at 30 day intervals. The switch did set require Q, l { re-calibration f or the entire test. If gestifiaatise testing shows ; ~
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- 1. Detail method or present p/ocedure and show man tourPerf ormance of $1 196 619462 each O}g? 5l 30 day
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?.7 ESSURE, TEMPERATURE AND CIFFEP.ENTI ALM ..-
"'liTCHES QUALIFIED TO lEEE 323-107'; Sr.d 36~.1 % ].T ,
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'. continued effort to provide qualified products to thy]nis IlinUgwo,nCI,
-- ,.;r , us are unclusir.9 an updated "Abstract of Tests"* rdtetHAaven-474-{ %,.
.4. itch testing qualified to IEEE. This abstract offers:
7-- A d 0t.-it e d listing of qualified pressure, teraperature and differential pressure switch models available, . 7: Concise information on the additional testing parfoisred at Aw.n Er.vironmentai Testing Corporation.
;i A synopsis of the different types of switches testec.
O Sample dimensional drawings of IEEE qualified mo fels.
.e.
, N sp.alications not covered by this abstract, pleas e contsc'. tha factor,,' for
.c tec< nt testing information.
a pu for your time and Ir:terest ano shoulc' you have en) questions or i f . .: r.tn be of assistance, please contact... , SOR, INC. PO BOX 591 Olathe, KS 66061 Attn: Ms. Jane Peternal Teitphone: 913-76ti-2630 H.g.a.as, r[1 u - ,0 )J .s./L. d - Jd.'.' Paternel Nu'.m ir Coordinator Atto:hment No. 9 Shcet-l Oll M - A. , io Loop #/ identifier /~5 ~E-2 # - 0 .' au-05 4/15/85 - f%'ciWI
- r. P. O. DesMarais Co. cc: PIMS. SL26 C-K., w/ attachments 4 513 Po 80s i.). n Q e.A0<308 RoAO CLA's E xaNS AS 653619'3 764 2633 Tet cr.2 ATER K ANS AS CITY AREA CA3;E son INO TELgr 42 6'30 s04 INO sica o R ; CONTROL DF0:E1 INTERNATIONAL TELEX NUMBER 493 2783 s0R us
ABSTRACT OF TESTS SOR has qualified the gage pressure, vacu Jm gage, high static working pressure-differential pressure and temperature s'vitches listed in Table 1 to IEEE 323-1974, IEE,E 344-1975 and NUREG 0588. The switches have been thermally aged to a 20~-yea r life at 150*F service temperature (40 years at 140*F); electro-mechanically aged to 33,000 cycles, 5 amps, 250 VAC; irradiated to 33 megarads (LOCA unit to 223 megarads); vibration aged .75' g for 90 minutes each axis over the range of 5 to 200 Hr, 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 5/9 SSE each axis), SSE tested at 25g over - the range of 4 to 30 Hz at 11 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 18577-83N 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 ccmpression-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 (Class Braid impregnated Wire Insulation) Silicone Rubber (Secondary Diaphragm) Honeywell 11SM244 high temperature micro switch ANALYSIS divided - On the by piston basisidentical mass, of higher natural frequencies computed from spring rate
. materials, mechanical construction features and equal or lower total weight the untested switches listed in Table 1 are also qualified.
SEE MOUNTING FIGURE Pressure Switches N6 Housing 1-20 Screws - 2 nt 14 ft-lbs 1 TA Housing 1-20 U-Botts - 3 3 Y L# l Loop A:to:hrr p/8 der.tifier.SNo.- Idhb (
*; 2 i
SEE la0V aY mG FIGtJRE T :.. :..:ci tore Switches
- n;ng . .5 - r. 4 - 2 at 85 in-lbs plu; support urmored n.r!: ach 2 ft *2 ,
. . . , m u .' g r y - a, y
' r a ;; ;;r . -- '.a u n t in Thermowell
's s
- 0< .->c %1 Pecssure S.vitcnas ~-~
Pa ~6 %diing UIIth Seismic Bracket 7" Dolt circle to match Barton i - 20 Grade 5 bolts - 4 at 85 in-lbs 5 m3 o .'n': sing with Base Plate 5
... ,2. -tc - Replace the cover gasket each time the covar is removed (:xcept
.ut oniostment). Calibration frequency is not recommended by SOR as a.3 o.ain Spag ud calibration change ruults.
a5T! TUT!Ot;S - For oil sarvica, fluscc .r's ., . k.9 5 ...a y L,: at:J .I s . . IPR is r.o t compatible with hydrccarbcas. Monal pr a:;su ra ports 1" r witchcs only) and longer ! cads are available. m '!: 'a r3 M!D PROBLEMS OF THE TEST PROGRAM.
'.L suuroroof Pressure - The 12N6-B4 in Test 17344-82N-O was not operated during
'tiP umidity test so addendum tests were run on this unit in 18441-33N at 227*F/7 p :ve tne lead wires external to the seal exposed to the steam. The pressure in the melosed housing caused by the thermal expansion of the ale is shown on Page c- . ...a :.ddendum report to reach 5.8 psi and is the cause of the increase in :st
. n : . 5 psi.
% nwuats.re
'*ha R iTT0125 was irradiated as part of 18441-83N to determine tha radiation'
<fict on Freon 12. Since there was none and the 201TA-8125 is a ST A-845 set: cure switch with a temperature bulb charged with Freon 12 attached, the popure switch qualification applies, in 18878-84N-4 both local and ramote bulb temperature switches were tested through seismic. Including sine beats. The operability requirements during seismic tests are shown by the similarity of the pressure switches in Repo-ts 17344 and 18878-84N-2 which were operated during seismic.
Differential Pressure The 103 A5- B 202 of' Report 18878-84N-1 when subjected to the 3g, 2 to 35 Hz sinusolda! OBE aging was being' pressure cycled by its own contacts merating alternating current solenoids, and contact ch.atter input resistors. The in'e. action of vibrcticn. and induced voltages from the solenoid coils "painted" the chi.rt. For the ISE tests, the pressure was cycled using a timer to drive the solenoids and a DC chatter monitor circuit for the visicorder; also equal water legs were added to the differential pressure input to provide damping. We obs3rved Commonwcalth Edison's test of a Model 103 AS-0203-N X-J J TTX 6 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 riounting plate instead of the bracket designed to match with Barton's 7" bolt circle mounting holes as tested at Acton. The supplcraental tests of 18878-84N-3 were run to determine the seismic influence r on a sli higher range and higher rntur al frequency differentbl pressure switches.ghtly The test showed if there was chatter (r d-fee--56E-rw mid te
..c..r.:n Is 9 :. - Er H1R = ID 'l' I .. . . . ; . . . . . l-l.s - 8 7 - 2. l. - -
- sine beat frequencies and orientations on the 103AS-8212 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 th'! HliLO shown on Page 7-49 of Repor6 18878-84N-1 is addressed in the conclusions. HIGH 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 test (Test Report S AND83-2651) on two of Model 4T A-D45. However, in the second cycle (See Figure 2 and Tab!e 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 350*F/115 psi in the Sandia test. (The Switch operated in spite of the steam in the housing.) The corrective action 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.
Scaled Natural Housing Temperature Effect influence Change in Set Point = .04 osi -
.0003 x SP 'F
'Y *F .
For example, for a 100'F increase in temperature and a 200 psi set point
.04 x 100cF .0003 x 100oF x 200 psi = 4 - 6 = -2 psi in 18878-84N-2, the OBE data was interfered with by the differ ential t-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: 913/764-2630). Direct your inquiries to Ms. Jane Peternel. Abbreviationt IEEE Institute of Electrical and Electronic Engineers NUREG Nuclear Regulatory VAC Volts alternating current LOCA loss of ccotpnt accident g 32.2 ft/sec = acceleration of gravity Hz Hertz = cycles per second OBE operational basis earthquake SSE safe shutdown earthquake ,,. TRS Test Response Spectrum (Seismic) " EPR ethylene propylene rubber DC direct current HELG high energy line break accident psi ound er square inch Attoch nent N1_ 9 5 e$t c "we inches of water column (differential) 1. cop #/ identifier /d"NY
'Hg inches of mercury column (vacuum)
.g.
SOR QUALIFIED SWITCH LIST TABLE 1
% .c: mt tear m:. >: to Adjustment %c ,c:::Jmt teo oarature 1 *. .- ae ; ;si 1.%.3 1) Range w iO*F cnd 115 psi ::nd
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.. i I. - M . : . s .' ) .~T X 6 .5 - 6 psi liiote 2a) 12 TA-34-NX-CI A-JJTTX6
- LN * - S S 4-dX- CI A-JJ TTX S (Nota 2d) 12TA-GB4-NX-C1 A-JJTTX6
' INS-35-NX-C) A-JJTTX6
.75 - 12 psi- 12 TA-d 5-N X-C1 A-JJ TTX6 "N6-BB5-NX-C1 A-JJTTX6 127A-855-N X-C1 A-JJTTX6
- "3-? 45-NX-C1 A-JJTTX6 1 # U in-045-NX-CI A-J)TTX6
* "" E D E-N X- 01.'.-JJTT X 6 GTA-aBu-NX-Ci A-JJ (TX6 Z-D'.-NX-CI A-JJTTX6 2 - 25 psi ::TA-34-NX-CI A .'JTTXS
, ~ 2 4-M-C1 A-JJTTX6
- ',- J,5-N X -01 A-JJTTX6 0 A-J ft4-NX-C1 A-JJT TX6 3 - 50 psi a f A-35 .iX-C1 A .'JTTX6
, ? B5 'iY-C1 A .'JTTX6 ;T A-si.,i;-u; -CI A-JJ (TX6
- M3-945-NX-CI A-JJTTX6 4 - 75 psi (Note 26) 1TA-? 45-N X-C1 A-J JTTX6
%-3 345-NX-C1 A-JJTTX6 *iTA-B D45-NX-C I A-JJTTX6
.N6 -3 3-NX-C1 A-JJTTX6 12 - 100 psi 6TA-03-WX-C1 A-JJTTX6 CN6-B B3-NX-C1 A-JJTTX6 6TA-BB3-NX-CI A-JJ FTX6 S N6-8 5-NX-CI A-JJTTX6 20 - 190 psi 6TA-B5-NX-C1 A-JJT TX6 S':6-BBS-NX-C1 A-JJTTX6 6TA-i355-NX-C1 A-JJTTX6 6N6-9 45-NX-CI A-JJTTX6 25 - 275 psi 6T,1-8 45-NX-C I A-JJTTX6 GN6-BB45-NX-C1 A-JJTTX6 STA-0345-NX-C1 A-JJTTX4
^
'MS-33-NX-C1 A-JJTTX6 25 - 240 psi 5TA-83-dX-C1 A-J JTTX6 5!!6-BB3-NX-CI A-JJTTX6 STA-833-ilX-CI A-JJYYX6 3"5-05-NX-C1 A-JJTTX6 35 - 375 psi STA-85-NX-C1 A-JJTTX6 -
SN6-BB5-NX-CI A-JJTTX6 STA-BBS-WX-CI A-JJTTX6 SNS-845-NX-C1 A-JJTTX6 45 - 550 pLi STA-845-NX-CI A-JJTTX6 5 N6-B B45-NX-CI A-JJTTX6 STA-8845-NX-C1 A-JJTTX6 Note 3 9N6-04-NX-CI A-JJTTX6 100 - 500 psi 9TA-B4-NX-CI A-JJTTX6 g Note 3 9N6-BB4-NX-CI A-JJTTX6 9TA-B B 4-NX-C1 A-JJTTX6 ' * ~ Note 3 9N6-BS-NX-CI A-JJTTX6 200 - 1000 psi 9TA-B5-NX-CI A-JJTTX6 Note 3 DN6-03 5-NX-CI A-JJTTX6 9TA-BBS-NX-CI A-JJTTX6 Note 3 9N6-B45-NX-C1 A-JJTTX6 200 - 1750 psi 9TA-845-NX-CI A-JJTTX6 Noto 3 ONS-B B45-NX-C1 A-JJTTX6 9 TA-BB45-NX-C1 A-JJTTX6 I NG-845-NX-CI A-JJTTX6 500 - 4000 psi I TA- 845-NX-C1 A-JJ TT X6 1N6-BB45-NX-C1 A-JJTTX6 I TA-B B45-NX-CI A-JJTTX 6 J N6-845-NX-C1 A-JJTTX6 1000 - 7000 psi 3TA-B45-NX-C1 A-JJTTX6 3146-BB45-NX-CI A-JJTTX6 3TA-BB45-N X-CI A-JJTTX6 Vacuum Gage 54N6 .2118-NX-CI A-JJTTX4 30" HgV to +.5 psi 54TA-B118-NX-C1 A-JJTTX6 54N6-BB118-NX-C1 A-JJTTX6 54TA-38112-NX-C1 A-JJTTX6 Temperature - Direct Mount 201 N S-B 125-J J T TX 6 40 - 225'F Note 4alb 201TA-B125-JJTTX6 Note 6 201 N6-B B125-JJTTX6 201TA-B B125-JJTTX6
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5-Temperature - Remote Bulb Note 4a 203N6-B125-JJTTX6 40 - 2250F 203TA-B125-JJTTX6 203N6-BB125-JJTTX6 203TA-BB125-JJTTX6 Note 5 20X N6* B125-JJTT X6 40 - 2250F 20XTA-B125-JJTTX6 20XN6-88125-JJTTX6 20XTA-88125-JJTTX6 High Static Working Pressure - Differential Pressure for Accident Conditions to 325'F/25 psi (less margin) Notes Range Max Worgg Pressure 103 AS-8202-N X-JJ TT X6 (7 6 11) 5-35" w.c. 1500 psi 103 AS-8212-N X-JJ TT X 6 (7. 8 & 12) 7-100" w.c. 1850 psi 103AS-BB212-NX-JJTTX6 (8) 10-100" w.c. 1850 psi
.103AS-B203-NX-JJTTX6 (9 or 13) 20-200" w.c. 1850 psi 103AS-BB203-NX-JJTTX6 (9) 30-200" w.c. 1850 psi 103AS-8903-NX-JJTTX6 3-00 psid 3000 psi 103AS-BB903-NX-JJTTX6 (12) 5-60 psid 3000 psi 102AS-8405-NX-JJTTX6 (9 & 10) 50-300 psid 3000 psi 102AS-BB403-NX-JJTTX6 (9 & 10) 50-300 psid 3000 psi 102 AS-B 305-N X-JJ TT X 6 (9 6 10) 100-500 psid 3000 psi 102AS-BB305-NX-JJfTX6 (9 6 10) 100-500 psid 3000 psi For availability of other ranges. please consult the factory. .
Notes 1 Test Conditions: 2270F/7 psig Acton 17344-82N-D/18441-83N 2a Test Conditions: 435 F/115 psi & spray Acton 17344-82N-C l 2b Test Conditions: 350 F/115 psi & spray & Irradiation Sandla 83-2652 2c Test Conditions: 3800F/48 psi Acton 18577-83N 2d Test Conditions: 325'F/25 psi Acton 18378-84N-2 3 Formerly 8 4a Acton Report 18878-84N-4 4b Acton Report 18441-83N j 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 platus in air serv!ce 9 By analysis - higher natural frequency 10 By analysis - o-ring scaled piston vs. diaphragm 11 Acton Test Report 18878-84N-1 12 Acton Test Report 18878-84N-3 13 Wyle Test Report (currently CECO p.operty) Attochr,ent No _ 7 Sheet.[2_.of_/G. Loop i/Identifict / ~/ S ~)6~1-El
m-a i TABLE 2 , Model4 Post Post Post c S e rir.t .* Raoort initial Radiation Seismic Accident I!!( ,< - 17344- 0 2.5 ps) 2.7 psi 1.5 psi 2.5 p:1
.J i . .. < 5. 3 n t 2.05 psi none .$cne 2.0 psi 1 4 : e. _ 17314-C 2.5 psi 2.9 psi 2.56 psi 66.0 psi Note 1 52-o- La ,
1:T A- 3 4 13577 3.05 psi 3.20 psi
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' ' " t 2 .2 ': 10373-2 3.0 psi none 3.0 psi 3.1 psi
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< ( A-5 6 SANDIA 38.0 psl Simo w/LOCA 10.0 p.ti 38,0 psi J. -;-i .w R d3-2652
. D .~. e J : d .18441 182.50F 178.3*F C3-4-3530 '
2 017A-8125 18878-4 45.3 'F 41.5 'F 46.3 'F 34-5-1. 0 203N5 9125 18878-4 42.0 'F 37.4 'F 39.7 'F E n 2 t:4 0 103A5-B202 18878-1 7.48" we 6.45" we 7.16" we 7.10" we 83-9-3610 -
. 103 AS-B 212 18878-3 10.43" wc 10.56" wc 11.26" we 84-5-3578 103AS-BB903 15878-3 31.0 psid 31.5 psid '31.0 psid 84-5-3579 Note 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. . M. Ats:4 A r m r.t N s. Y - Shw 7 cfND Loop s/ld:r.tifi t !"'687~ E l (3/4/55) abstract 3, rev2
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L-SquP f- , SI-196 sage 3 APPCfDIX A Revision 9 Page 2 of 19 s [ LMI'l . __ Date,_
;,,.1! ,T]C i M %n II/iL 3WITC1! LS-87-21 (continued) .
1.7 lteinatall the .vant plugs and connect a calibration pressure source to the high
=
. .;ida of the water box.
g IM [ < 1.4 cenaset a continunity tester across the i ' = ninals 11A and 1106VG in JB 1612 (U-1)
;c sceninals 21A and 2106VG in JD 2164
.y ;e 2).
Q IM 1.9 01 mly increase the pressure to the high Jitto of the switch (water box) until c:ntact closure occurs. Repeat two times to encure repeatability. Record the "As _ Teund" values below. 710H: Unit 1 and 2 have different sotpoints. t- Select the unit being tested and !J/A the unit not bein; tested. Desired TS Allowable As Found As Left
~
f 1-LS-87-21 122.02 = 1" H 0 ;*,0" H 0 2-LS-87-21 129.18 1" Hto a 2.0" H 0 g IM __
/
Date 1.10 ff the "As Found" values ..re within the - desired tolerance, record the "As Left" values. 1.11 Ti the switch is out of TS allowable s
.olarance, notify the SIMP. N/A if not applicable.
IM . 1.12 If recalibratou 19 required, recalibrate and record the "As Left" values. Attochment No _ 10 Sheet l-- :I b Loop t/tdentif:er - l'L'*$7'2I 0139R/mit
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g Page 28 A?PENDIX B [ Fags 2 of 18 navision 9 : i U: FIT Date - _. t
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4 CALIBRATIC;l 07 tnII IIVEL s'tITC11 LS-87-22 (continued) - - . t 4' 1.7 Reinstall the vent plugs and connect a '.- ' calibration pressure sourco to the high side of the water box. .. 4 1.8 IM Connect a continunity touter across . 1
. -terminals 12A and 1206VG in 3 1513 (U-1) 3' or terminals ?.?.A and 2206VG an JD 2165 1
(U-2). J-
^
i n - IM , i
.1.9 Slowly' increase the pressuro to the high t side or the switch (water tox) until contact closura occura. Rapest tuo times.
' to ensure repeatability. Racord the "As Found" values below. ' i l
', !JOTE: Unit I and 2 have difforent ,
cetpoints. Salect the unit balng > tested and fl/A the, unit not c'alug - " tested. '
- P C
Desired TS A11ouable As Found As Left- 6 1-LS-81+22 224.02 e 1" !!:0 s 2.0" !!ao
- t 2-LS-87-22 125.93 a ' " 11:0 e 2.0" !! 0 t
I ..
, . t IM Date '
I 1.10 If the "As Found" values aro within the 4' decleed tolerance, record the "As Left" values. ' 1.11 if the switch is oist of TS allowablo , tolerance, notify the SDIF, ll/A if not , required. '
- .M 1.12 If recalibraton is required, recalibrate and record the "As Ptt" valurs.
A.t S nc.,t No ]O . 55tet 3_- cl 0142R/mit
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. Page 46 APf4:NDIX C 4_ Page 2 of 18 Rovision 9 UNIT _ . , _ . ,
tP2 _ 4 1.9 !
- 3. C;.LIcRATJQil OF IAll _ L*NEL SWITQI LS-87-23 (contin.nd)
- 1. 'l .Winats11 the vent plugs and connect a calibration pressure source to the high side of the water box.
2.9 w. .act a continunity tester across I:t ~ t:rminals 13A snd 1306VG in JB 1614 (U-1) o.
- armin31e 22A and 2205VG in JD 2166 01-2).
s IM
; 1.5 slowly increase the pressure to the high side of the switch (water box) until y contact closure occurs. Repeat two times to ensure repeatability. Record the "As .
.$- round" values below.
[0I3: 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 s-1" H 0 e 2.0" H 0 -- 2-LS-87-23 129.18 m 1" H 0 m 2.0" H 0 _ l / I IM Date i- . 1.10 If the "As Found" values are within the desired tolerance, record the "As Lwit" values. 1.11 If the switch to out of TS allowable I tolerance, notify the SIMP. N/A if,not required. IM ! 1.12 If recalibraton is required, recalibrate -
+ and record the "As Left" values. ,
L i 0143R/m1t Attechment No.__ / D Shcet.3-- cf b i Loop g/tdentifier Mb . g G s t 4 & Z , ,, . -- , _ . , . - -- - --. - ,- - --.
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SQUP SI-196 g, , . Page 64
- APPDIDIX D Revision 9 Page 2 of 18 s UNIT Date 1.0
~
CALIBRATION CF l'ill LL"/EL SWITCH LS-87-24 (continued)
,,, 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 ac oss ' teminals 14A and 1406VG in JB 1615 "(U-1) or terminals 24A.cnd 2406VG in JS 2167 (U-2). L1 - .. IM
'p 1.9 Slowly increase the pressura to the high side of the switch (water box; until '
contact closure occurs. Repeat two times , to ensure repeatability. Record the "As
'Found" values below.
NOTE:,, Unit 1 and 2.have difference g setpointhT '561ect 'the"bnit bsing g tested and N/A the unit not being
, tested. - t-Desired TS Allowable ye Found As Left 1-LS-87-24 124.02 1" H 0 2 2.C" H 0 2-LS-87-24 125.98 s la H:0 2 2.0" H:0 -
IM Date l 1.10 If the "As Found" values are within the y desired tolerance, record the "As Lef t" u values. 1.11 If the switch is out of TS allowable I tolerance, notify the SIMP. N/A if not required. IM 1.12 If recalibraton is required, recalibrate and record the "As Left" values. At ::h nent No._ /6 c. :t.d-49,g_ cib lcop f/lk al'liCf 0144R/m1t , 3a , g..
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- RM ordec 1409 Recordeo V i Distributeo MUCtfNt (EIN!!RlW OIRECTCR'S Cf,rtCE F0)flNG/DIStall)Ullel r .rt ntns to. l- U 8806 $6 W7 0Att :tetsyt0 7-2-% vit cv cCetntxt _f -Jo ~J6 ffE01W.RCAf f / /
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Ol5TRIBU!ICN ./ [ COPY COPY / CCPY H. Peckter, W) CI 55 C-r R. O. 2.3rnett, h9 0?24 C-9 7 K. I. Myers, Wil 819 C-K W. D. Hall, Wl? C62 C-K ' C. A. Chandley, W7 Cl?6 CIK C . L . O' De l l , W5 C99 C-K R. R. Mcesly, 9 11) $8-K l J. P. Fenton, W5 0176 C-K S. A. Shirvmn, W4 0??4 C-8 C. W. Kiloore, Wl? Olli C-K f W.5.Rauoiley,W9Cl?6CAK M. t. Rayfield, P-104 58-K ~J.Xlaussten, WiO TITC'K . J. P. Stapleton, A10-8FN EE T. h. Roterts, W5 0181 C-K , l _ itrrel, Wil Cia C-K J. P. Vineyard Wl? C61 C-K C. f. Cantrell, IP $$ 85E-C D. N. Wilson, ONE, OSC-A, S(*r t. W. lau, Wlo 0??0 C-K J. M. McGri f f, BR $N ISA-C J. H. Miller, LP '>S 1500-C RIMS, St ?b C-K __ loff: / - Inforretion H - Handle R.- Reply 8 ", or (1) etc. - See notes Atixhment No. / / Sheet / of i Loop J/ldentifier _ l-LS-p'l ') I 09074 (Use other side for a&fitlensi notes)
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- s. . .t .va (. m- yo8 a~ 860630 997' -
l . To : J. Br . HeGriff, ch, DR $NChief. 15A-CElectrical end Instrument and Controls Services o 7 BON : F. H. iler, Cupervisor. Instrument cnd Controlo En&ine3 ring Coction. BR SS 59A-C JUN 3 01986 y, 3UBJECT: SEQUOYAH (SQN), BROUNS FERRY (BFN), AND WATTS BAR (UBN) 1!UCLEAR PLANTS - MIETINC PRESSURE SWITCHESHINUTES - ERRATIC BEHAVIOR OF STATIC-0-RIUCS (SOR) DIFFER 1.0 Date and Place of Heetine The nestin5 was conducted on' Juno 12, 1986, at the Nuclear Re5ulatory Commission (NRC) offices in Dethesda, tiaryland. Attach..ent i documents the meeting agenda. 2.0 6t*andance 2.1 Attachment 2 is a complete list of the attendees. , 2.2 TVA attendees: W. C. Ludwig Nucleat' Safety and Licencing Staff F. H. Siler, Instrumont and Controls Engineering Section ,_
~
J. D. Thompson, Instrument Maintenanco Section. DFN J. D. Wolcott, Licensing Staff DFN 3.0 Comnents 3.1 In opening comments, Gary Holahan of URC stated that the meeting was called so NRC could determine if directives should be issued to utilitios as a result of COR instrument failures at LaSalle Generating Station. He stated that representatives. from LaSalle and Oyster Creek Nuclear Generating Stations would describe testing which they are conducting on SOR differential pressure switches and asked all other utilities present to describe their use of SOR dif ferential pressure switches and to provido any testing history available. 3.2 TVA responded that the only SOR different191 pressure switches installed at SQN had been in Jervi<e only a short period of time prior to the LaSallo event; only the initial instrument calibration following installation had been performed. However, a calibration was performed as a result of the LaSalle Aito:hment No. Il Sheet A cf Loop pfld ntifier _Id S 1
2 J. ;t. McGriff OEQUOYAH (SQN), 2n0WHS FERRY (BfN), AND WATT 3 DAR CHt!) 133CLCAR ?LfJITS -
".tETIllG HINUTES
.'I'ES VRE, SWITCliEO- EERATIC DEHAVIOR OF STATIC-0-nit:0 (003) din 32NTIAL b
event. All SOR switches were within their Technical Specification limits. TVA cascribed the special test conducted , on one 30R differential pressure switch prior to tts installation. '1RC only noted that ua hcd povitivo resulto and did not ask fer copies M the tos; 4:.ta. TVA stated that we were in the process of inst llinc .ca differentisi pressure switches at 3rN fer resion1 hral remova t (idiR) miniflow valve actuation. This mcdifientien ha ben put on holo. 1 o utility prosent, other than LaSalle and Oyster Crook, has had an SOR differential pressure switch installed long enough to gather periodic calib. ration data. 3.3 Oyster Creek inst.alled SOR differential pressure switches for both low and low-low level scran and safeguards actuation service. The model switch used for low levoi had one raicro switch while the model switch used for lo.e-1cw love s t had two inicro switches. Otherwise, the switches .<ere physically identical. At the first 30-day survelliance interval, one of the low level switches was out of toler:nce. At the next ,, su*veillance interval, a different low level switch uss out of tolerance. The frequency of testing was increased to overy two weeks. Switches continued to be discovered ov6 of tolerance with no recognizable pattern., During this period, the low-low level switches remained within tolerance.
- The low level switches line connected weretap.
to the upper installed with the instW:.cnt sense SOR reco msnded the lower tap be used for liquid servico. Since the lower the level, the greater the differential pressure, the setpoint for low-low level was in the upper part of the instmment span while the
. low icvel setpoint was in the lower portion of the span.
Although extensive testing by Oyster Creek and SOR could not detemine why the low-low level switches perfomed botter. Oyster Creek is replacing the low level switches with the sa.se model SOR switch as is used on low-Ic.w level application. They are also installing them in the some instmment configuration.
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4 3 J. M.'HcCriff . SEQUOYAH (SQH), 3ROWUS .?iIt' Y (UFN), AND t/ATTS DAR !!IDN) IDICLEAR PLANTS - MEETING llINUTES - IRRATIC SEllAVIOR OF STATIC-O-RINC PRESSURE,SWITCHE.' (SOR) DIFFERENTIAL 3.4 Af ter the June 1,1936, event, La0.111o Muclaar Station ' initiated a testing program on all installed SOR switches. Preliminary.conclucions 3ra that the differential pressure swi.ches have a definite chlft uhan calibriiec at atmosphora pec;curo and subsequently subjected to system operating proscuro of over 900 psig. The amount of shift is not consistent from switch-to-swit:h. This phenomena cuggests that calibration , should be perforned at the system operating proscuro. The switches also exhibited a definito setpoint difference between the first cetuation af tar a prolonged period of inactivity cnd successive actuations. 1.aSclle believes with enough test data they can modify their testing / calibration proceduros and/or system setpoints to assure themselves and NRC that the unit will be safs to operate. However, they are also looking at other contingencies such as installins an analog trip system (ATS), 3.5 Ceneral Elsstric company (CE) reprecentatives gave a short presentation n the cafety significance for boiling water _ reactors of the 'silure of the reactor to scram at the low reactor water 1cvs1 setpoint as experienced at LaSalle. According to CE, tha cafety significance was very low if the reactor water low level scram did not occur at the plant Technical Opscification setpoint. In-respbnse to an URC question as to why the Technical Specifications were so rigid, CE stated it nac believed the instrumentation used would meet these limits; thereforo, these setpoints were put in the Technical Specificationc. LaSalle has contracted CE to conduct a new safety analysis to determine more appropriato and realistic limits on water level actuation setpoints. 3.6 JSO made a lengthy procentation on the design and operation of the S09 dif ferential prescuro switches.* They conceded that testine has determin2d approximately 2" H9 0 dit t erence tri-lIIp~oint on first actuation and successivo actuations after a switch has been subjected to_ogegattna pressure. Subjectifg'
'Ine switch to system operating pressure hardens the two "0" rings in which a shaft must rotate approximately one degree to actuate the
' Attcchment No.-
Il _ Shettiof1 l Loep A/ldentifier I ~ LS-B'/-11 l
4 J. H..McCriff SEQUOYAH (SQN), UROWS FERRY (BFN), AND WAT*S BAR 0;BN) 1:UCt.!A'A PLANTS - L MS! TINGSWITCHES p?.ISSUTsE. ttItNTES - ERRATIC DERAVIOR CF STATIC-0-Mitts - (4' 03) DIFF222NTIAi ulcro switch. 'Ihis adds to the backforce used to datormine che sotpoint. SOR stated that they are conducting a test program dasigned to sive moro data about switch perfornance at
- peratinr, pressures typical of e.hos's coun in *:cisar plants. SOR plana to issue ;aare detailcd ecli*vt ation procecuros baJad cn the results of these tests.
3.7 Concludinr, remarks by llRC were that th;y -no no u Nd c.t this time to issue any directives to the "t'F t! U may will te 1 coking closely at the results of testing at teralla, Oyster Sy ek, and SS2 - 4.0 cenelusions 4.1 DFN 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 velve-nctuation. 4.2 SQ?! uses SOR differential pressure switches for upper head injection valvo closure. We have limited operating wporience 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 Both SQN and BFN should review their calibration proccdures to verify that they are adequato 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 GE, 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.
/ . , a. .Y W F. H. Siler NTH:TMS:HRH Attach. tents
" " A'm. Wee N __l/.
D. a $ _ M_1 } Loep s/Lerlific. /- L3'b7Id
-..%.o.nr x;'..**.' , wice. . ' - ..-.
.-. 3'
, J. H. McCriff SEQUOYAH (SQN), 3RO'.nlS 72RRY (UFil). IdID UATTS UAR (UBl!) 11UCLEAR PLANTS -
MEETI!!G HItAJTES - ERRATIC DEH.WIOR OF STATIC RIL'G - (CO3) DIFFERENTIA PRESSURE, SWITCHES g P cc (Attachtnants): / RIHS, HR 4N 72A-C # C. R. 3rimer. 0E3. Sequoyah ! R. E. Burns I:13, Drowns Forry F. E. DiCo_ls. U12 A6 C-I* H. D. Elkins. Ills, Sequoyan H. L. Rayfield, 51att:: Dar J. P. Stapleton, 3ro'es Ferry
- D. W. Wilson, Sequoyah 0337C
( g., :* - *
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'!f:r r': : _l-45 ,67- llQ
. Attach: tent 1 OTATIC "0" RING DIFFERENT1hL PRESStlRE SWITCHEJ MEETING AGENDA JUNE 12, 1986_ *
- 1. Nelcoma and Opening Coments -
Holahan/ Jordan
- 2. Sumaries of Operating & Halutenance Sqeriences - LM.ilities
.s:sila
- Oyster Creek
- Browns Ferry
- Sequoyah
- Others
- 3. Safety Significance for BWRs (Design / CE Licensina Dasis) - l
- Rx Water Level
- Other Applications
- 4. Design and Operation of SQR dP Switches - SOR. Inc.-
- 5. Discussion of Possible Futurn Actions - Open
- Reporting
- Testing
- Calibration
- Potential Replacement or Modification . . .
- 6. Concluding Rett. arks Holchan/ Jordan Attachmei.t No.. II _Sh'eci
_. ... b of-Loop #/ldentifier _1"LS ~ 87 ~LI
Attachment 2 Attendees Wayne A. Priest SOR. Inc. Ross E. Johnson SOR. Inc. Chief Design Engineer Harry P. Hartman Exec. Vice President SOR. Inc. Manager. QA Russell C. Engel SOR. Inc. Tom'H. Crawford Houston Lightn.& Power Uuclear Sales Manager Ketineth R. Eibon Staff Engineer GPU. Nuclear I&C Engineer Tom Hoatson CPU. Nuclear John Rogers Project Engineer CPU.Nuc1 car Jack Donohew NRC Liconsing Engineer Larry Nicholson URC Project Manager Bob Samworth Region II NRC-MF0 Lamont H. Youngborg CE Sr. Reactor Sys. Engr. H. C. Pfefferlen CE Principal Engineer Bob Pierson NRC Hanager. BWR Licens. Prog. M. Grotenhuis IP., PAT NRC Joe Holonich URC Project Manager T. J. Xenyon NRC Project Manager C. J. Freerun WPPSS Project Manager Marjorie Widmeyer WPPSS Technical Staff Jon McCaw SCE Technical Staff Wowell Porter Licensing Engineer WPPSS John O. Bradfule Engineering NRC D. B. Vassallo Project Manager URC James J. Shea NRC Chief. FOB /NRR Vincent D. Thomas NRC Project Manager, MP-1 A. W. Domenick IE/ECCR URC ! Cornelius T. Coddington IE/ECCR N. K. Trehan PA Power & Light. Co. ~ Senior Project Engineer URC Theodore C. Daldiat EICSD/DDL
- PA Power & Light. Co. I&C/C Supervisor Martin C. Santic James S. Abel Comonwealth Edison I&C Supervisor '
Kenneth L. Craesson comonwealth Edison Energy Manager Michael S. Turbak Comonwealth Edicon Div. U.P. Nuc. Sta. Frank M. Siler Comonwealth Edison Nuclear Licensing TVA Wm. C. Ludwig TVA 16C Engr. Sec. Supervisor Dave Lynch Nuc. Safety & Licensing NRC Clarence M. Root INPO NRR/ DBL /PD (13 Eliot Abolafia A&E Division J. D. Thompson Northeast Utilities Nuclear Operations TVA .. J. D. Wolcott TVA I&C, Browns Perry M. Srinivasan NRC Licensing, Browns Ferry W. Hodges NRC/ DBL /EICSB WRC T.' Collins WRC ' DDL/RSB M. Virgilo DBL /RSB NRC Chief. BWR Assessment Br. Attochmer.t th) f xc t.h_. 2f _T '
, locp //IdeMiIicr .
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E. daker . ;TRC 2a:e.ond T. Scholl URC - Chief, React. Inspec. I:ichnal P. i:urphy CME /DWR TID /SRA.Inc. Conwultant ,0per.Enge. Assos. Daniul P.. i'uller !TEC Donald J. Florek DJL/PD #2 WRC Jim Prell- RI/DRS/OS URC Bob Newlin RI/DRS/0B NRC OPA Sheldon .*i. ::chwartz iT3C 17; thri-Jo Sn:cnone *!RC r*L E. L. Jordan NRC G. C. 'drir.ht IE Dept. NRC D. Allison ITRC RIII-AIT Loader R. Woodruf f I&E HRC IGE J. T. Ser.ed NRC C. Holahan ChS / WR 1.'RC ORAS rus:Han . 0337C 4 3 B
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TVA SEQUOYAH WESTINGHOUSE PROPRIETARY CLASS 2 DESIGN CRITERIA UPPER HEAD INJECTION SYSTEM - Table 3.5-3 UH1 Instrument Setpoints TVA Westinghouse Instrueent Instrument Setpoint Number Number Description Function Setpoint 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 dag werking 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 to alarm 2.3 Inches 2 PA-87-2 1-PJA-908 Accumulator Gas Laut alarm 1209 lb/in 9 l FM
- f0? Hi p/dtm I?b) /D)<n' LS-87-30 1-LS-910 Her.brane Leak Detector Detect ' (Set in fie d water in gas line to detect water level h ,
above membrane (Hydraulic service system settings) Hydraulic Accumulator Normal .i200 lb/8.n2g 2 Gas Pressure to alarm 2800 lb/in 9 H.vdraulic Accumulator Normal 24# Fuio ius, cat m alar m an D4skd : .M*- Hydraulic System Lo alarm factory set Fluid Roscrvoir Level - 4
- Level setpoints are referenced to the lower level tap.
" ", 'p.t ;d t e sie-- h --- 4: d':dhd by ; 0T nd ': t: 5: r:d:
;: : r-t H. CCN 0007.
pr I Atto:hment NO.- I "' l g"-B '7 'll __ imp f/tdentifier _ 97090:10/071785 64
WESTINGh0USE PROPRIETARY CL';5 2 ! TVA SEQUDYAH DESIGN CRITERIA UPPER HEAD INJECTION SYSTEM TABLE 3.7-4 UH' ACCUMOLATOR TANK PARAMETERS 2 4:rter Stainier: stsel :13d carbon steel Aatorial - 2 1800 A Design Pressure, Ib/in g 300 Design Temperature. 'F ' 70'- 10d - Operating Temperature, 'F ~~' , fe 2 3255 Maximum Operating Pressure, Ib/in 9 2 1185 Wini:num Operating Pressure, Ib/in g 1800 Each Tct:1 Veluto, ft 3 3 1805 x
" Water 'lelu 4, ft ,. ,_
Volume N Gas, ft 3 ' _1800 " ~ 2 2100 Boren Concentrat on, ppm eax i
\ .
ppm min 1900 - Y 7* 6 ' - 2 1800 ' Relief Valve Set Point, 1b/in g -' ASME Section !!!, Class 2
. Code
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4 EMERGENCY CORE COOLING SYSTEMS (ECCS) , UPPER HEAD INJECTION ACCU!!ULATORS LIMITING CON 0! TION FOR OPERATION 3.5.1.2 Each upper head injection accumulator system shall be OPERAtiLE with:
- a. The isolation valves open, \p ,
- b. The water-filled accumulator containing between '1805 and 1851 cubic feetofboratedwaterhavingaconcentrationofbetween1930and 2100 ppa of boron, and
- c. The nitrogen bearing accumulator pressurized to between 1185 and 1285 psig.
APPLICABI W : MODES 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 STANOBY within the next 6 hours and in HOT SHUT 00WN within the following 6 hours,
- b. With the upper head injection accurnulator system inopersole 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 1s. 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 t, orated watcr volume and nitrogen pressure in the accumulators, and
- 2. Verifying that each accumulator isolation valve is open.
' Pressurizer Pressure above 1900 psig._ -~~ [ h Y.
gp pju,.61'N M[ h E}S' N AttMMU I # l L SEQUOYAH - UNIT 1 3/4 5-3
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EMERGENCY CORE CCOLING SYSTEMS (ECCS) SU '.VEILLANCE REOUIREMENTS (Continuer 0 .
. b. At least once par 31 days and within 6 hours after each solution volume increase-of-greater than or equal to 1% of tank v31use by
. verifying the baron concentration of the solution in the water-t'illed accumulator.
~
- c. At least once per 18 months by:
4
- 1. Verifying that each acetimulator isolation valve closes automa-tically whan thw water level in the waterfilled accumulator is 32.1 +5.6 inches above the tank vendor working line. This correipends 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). -
.. gn
- d. At least once per 5 years by removing the rembrane installed between the water-filled and nitrogen bearing accumulators and verifying that the removed membrane bursts at a differential pressure of 40 + 10 psi. . _ . , . . . . . .. .
,, . 4-hay 3, 1983*
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