PY-CEI-NRR-0327, Forwards Results of Preliminary Review of Conformance to NUREG-0737,Section II.B.3, Post-Accident Sampling & II.F.1 Re Accident Range Iodine & Particulate Sampling
| ML20137M349 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/06/1985 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20137M353 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM PY-CEI-NRR-0327, PY-CEI-NRR-327, NUDOCS 8509130207 | |
| Download: ML20137M349 (18) | |
Text
{{#Wiki_filter:~ ,o: i, it i
- n e q o f, g 1 jpgv i ts o u in s
-< t e 3i ;, ,p p-7g e 1 ( ; ; ". p ; < ,7 a s at v _ .i v P O. BOX 5000 - CLEVELAND. OHIO 44101 - TELEPHONE (216) 622-9800 - (LLUMINATING BLDG. - 55 PUBLICSQUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT September 6, 1985 NUCMAR PY-CEI/NRR-0327 L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 'd-441 NUREG 0737 - II.F.1 (Attachments 1 & 2) & II.B.3 Implementation and Clarifications
Dear Mr. Youngblood:
At the recommendation of Region III [nspectors, Cleveland Electric has per-formed a preliminary review for conformance to NUREG 0737 in the following areas: post-accident sampling (Section II.B.3), noble gas effluent monitors (II.F.1, Attachment 1), and accident range iodine and particulate sampling (II.F.1, Attachment 2). Attachments to this letter describe how the Perry design implements the re-quirements of NUREG 0737 in specific areas. To facilitate future inspections, we are seeking your specific written concurrence with each of theae attachments. Design modifications described in this letter will be incorporated in a future FSAR amendment. If you have any questions on our implementation of applicable NRC guidance, please call. Very truly yours, Murray R. Edelman Vice President Nuclear Group MRE:nje Attachments cc: Jay Silberg, Esq. John Stefano (2) q'I J. Grobe C. Gill (Region III) D. Miller (Region (III) 8509130207 850906 PDR ADOCK 05000440 PDR F
PY-CEI/NRR-0327 L Page 1 of-3 GASEOUS EFFLUENT SAMPLING SYSTEMS: REPRESENTATIVENESS & DESIGN CHANGES Summary The as-built particulate and iodine (P/I) sampling systems, modified as described below, satisfactorily implement the guidance of NUREG-0737 Table II.F.1, Attachment 2, with respect to the representative sampling of plant gaseous effluents. Calculations indicate that the P/I sampling systems installed at PNPP will collect representative samples in accordance with NUREG-0737 and ANSI N13.1-1969. In light of the uncertainties regarding iodine chemical species and particulate size distribution during design basis accident conditions, CEI believes these calculations are suf ficient in lieu of empirical testing. However, CEI is evaluating the feasibility of empirical line loss deter-minations in the as-built sample delivery systems. A decision regarding actual demonstration of P/I deposition, based on sound engineering and economic considerations, will be made prior to second cycle startup. Discussion NUREG 0737, Section II.F.1 Attachment 2, requires that sample flows from gaseous effluent pathways be representative and isokinetic. There are four gaseous effluent pathways which will be functional during the operation of Perry Unit.1: Unit 1 Vent Unit 2 Vent Turbine Bldg / Heater Bay Vent Offgas Vent Each particulate and iodine sampling system 'is designed in' accordance with ANSI N13.1-1969. The following is a description of the as-built sampling systems and design modifications which assure representative sampling. The sampling system originally on each gaseous effluent pathway was comprised-of-four sampling skids: An Air Monitor Corporation (AMC) isokinetic sampler and flow rate measurement' skid, a Victoreen normal range radiation monitor with P/I sampling capability, a Nuclear Research Corporation (NRC) P/I sample panel and a Kaman post-accident range radiation monitor with P/I sampling capability. The original design of the system was as follows: A. The AMC skid measured impact and static pressure in the vent and converted this data to vent flow rate. B. Based on the measured vent flow rate, the AMC skid extracted a relatively turbulent sample from a series of nozzles, through' 1" nominal diameter smooth bore stainless steel pipe and controlled the sample linear velocity =in proportion to vent flow in order to maintain the isokinetic condition. C.- At the AMC skid, a nominal I cfm secondary sample was extracted from the primary sample through a single nozzle and transported to the .Victoreen' normal range radiation monitor via a short run of 1" - nominal diameter smooth bore stainless steel pipe. l 2
Attrchment 1 PY-CEI/NRR-0327 L Page 2 of 3 D. As identified in FSAR Table 7.1-4 Note 17, the AMC and Victoreen equipment and sample line piping were designed non-safety related and not supplied with IE power or qualified as Class 1E equipment. This is allowed by subnote 9 in Regulatory Guide 1.97 Rev. 2 which permits the use of this pre-existing equipment. E. The NRC sampling skid extracted a sample from the vent through appropriately sized nozzles and transported it to the sample panel via nominal 0.25" OD stainless steel tube. F. The Kaman post-accident radition monitor extracted a non-isokinetic sample from the vent and transported it to the skid via nominal 0.25" OD stainless steel tube. The Kaman equipment was procured as safety related, Class 1E equipment. CEI reviewed two recent articles which addressed the plateout of radiciodine in sample lines (2,3). Based upon the application of methodologies outlined in these articles, CEI determined that the plateout of radioiodine in the Kaman,and NRC sample lines would be unacceptable. The following design modifications were made which will reduce radioiodine plateout in order to provide for representative sampling: A. The NRC sample panels have been deleted from service. Three P/I collectors on the Kaman skid will be used in conjunction with the normal range radiation monitor P/I collectors in order to continuously collect P/I samples through the required range. B. The AMC sample lines have been routed to the Kaman post-accident skids where a secondary sample will be extracted such that the isokinetic condition is maintained at expected operating vent flow. The secondary sample will be transported via nominal 0.25" OD tube, designed such that the length of the tube is as short as practicable. C. All gaseous effluent inlet sampling lines (both normal and post-accident range) will be heat-traced and insulated in order to overcome sample line heat loss and therefore reduce the possibility of condensation as the sample stream passes through particulate and iodine filters. In order to demonstrate that representative samples will be collected using the modified system described above, CEI has calculated expected particulate sample line losses using the methods described in ANSI N13.1-1969 (4) and expected radioiodine plateout using the methods described in references 2 and 3. The following is a summary of the results of these calculations: System description exerpts are included, along with a highlighted P&I diagram, to reflect these changes. J
F l PY-CEI/NRR-0327 L Page 3 of 3 A. The sample delivery systems were designed to minimize the length of sample tube (<15 ft) in which laminar flow occurs in order to minimize particulate deposition via Brownian dif fusion and gravity settling. The estimated depgsition of 0.1 and 1.0 micrometer diameter particles (density = 2 g/cm ) due to Brownian diffusion, gravity settling and turbulent impaction was calculated using the methods and data in Appendix B of ANSI-N13.1. This estimated deposition was shown to be less than 6% for the sampling systems on each of the four effluent pathways. B. The plateout of radiotodine was calculated for the worst case scenario of 100% elemental iodine combined with the design details of the PNPP Unit i sample system and the methodology derived by Kabat (2). These calculation indicate that the plateout of elemental radioiodine will be less than 30%. C. The expected plateout of elemental iodine, hypoiodous acid and methyl iodide was calculated using the average distribution of these species in the reactor building of Pilgrim, Monticello, Oyster Creek and Vermont Yankee presented in NUREG/CR-0395 (5), combined with the design details of the PNPP Unit I sample systems and the methodology derived by Kabat (2). These calculations indicate that the expected plateout of radioiodine will be less than 11% during normal operation. REFERENCES 1. U.S. Nuclear Regulatory Commission, Regicn III, Report No. 50-440/84-13 (DRSS). Summary of July 9-12, 1984 Routine Preoperational Inspection, dated July 27, 1984. 2. M. J. Kabat, " Deposition of Airborne Radiotodine Species on Surfaces of Metals and Plastics"; presented at the 17th DOE Nuclear Air Cleaning Conference, 1982. 3 P.J. Unrein, C.A. Pelletier, J.E. Cline and P.G. Voilleque', " Transmission of Radioiodine Through Sampling Lines"; presented at the 18 DOE Nuclear Airborne Waste Management and Air Cleanind Conference, 1984. 4. ANS1 N13.1-1969, American National Standard Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities. 5. NUREG/CR-0395, Evaluation of Radiotodine Measurements at Pilgrim Nuclear Power Plant, 1978.
Attachmsnt 2 PY-CEI/NRR-0327 L Page 1 of 5 CONVERSION OF POST-ACCIDENT RADIATION MONITOR READINGS TO RELEASE RATES Summary: Perry accident range effluent monitors continuously display and record post-accident noble gas concentrations with acceptable range and accuracy. To improve accuracy, detector response will be corrected for the shift in gamma spectrum with time for computer-calculated offsite doses. Appropriate correction factors will be documented in instructions for manual calculation of post-accident doses assessment instructions prior to fuel load. The analytical -basis for determining these f actors is presented below, and is in compliance with the intent of NUREG-0737 and supporting references noted. Discussion Clarification Item (4) (b) of NUREG-0737, Item II.F.1 Attachment 1, requires procedures or calculations / methods to convert post-accident instrument readings to release rates based on exhaust air flow and considering radionuclide spectrum distribution as a function of time after shutdown. CEI has reviewed the applicable regulatory guidance and interprets this requirement in the following manner: 1. Revision 2 of Regulatory Guide 1.97 states that " Monitors should be capable of detecting and measuring radioactive gaseous effluent concentrations with compositions ranging from fresh equilibrium noble gas fission product mixtures to 10-day-old mixtures, with overall system accuracies within a factor of 2". This has been interpreted to, include all. fission product noble gases which have significant dosimetric implications; namely the Krypton and Xenon radionuclides listed in Table B-1 of Regulatory Guide 1.109 Revision 1. 2. Reg. Guide 1.97 states that " Effluent concentrations may be expressed in terms of Xe-133 equivalents or in terms of any noble gas nuclide(s)." NUREG-0737 further clarifies this guidance, stating " Design range values may be expressed in Xe-133 equivalent values for monitors employing gamma radiations and microcuries per cubic centi-meter of air at standard temperature and pressure (STP) for monitors employing beta radiation detectors". These documents clearly state the acceptability of expressing the responses of: a. Beta scintillation detectors in terms of uCi/cc of total noble gas. b. Geiger-Mueller' detectors in terms of uCi/cc of Xe-133 dose equivalent (Xe-133 dose equivalence of a mixture of noble gases is derived using whole body dose conversion factors from Reg. Guide 1.109).
r Atttchment 2 PY-CEI/NRR-0327 Ti Page 2 of 5 3. Table II.F.1-1 of NUREG -0737 states that this instrumentation should continuously display and record equivalent Xe-133 concentrations of uCi/cc of actum1 noble gases. For the PNPP systems, the low range beta channel response is displayed in units of CPM and the mid/high range gamma channels are displayed in uCi/cc Xe-133 equivalent (utilizing a single CPM to uci/cc conversion constant). This display requirement is applicable as described in Item 2 above and should be within the. factor of 2 accuracy stated in Reg. Guide 1.97. An algorithm was. written in order to evaluate the effect of the decay of fission product noble gases on the response of the radiation detectors used to monitor gaseous effluents at Perry. The parameters used in these calculations include: a. The. initial inventory of fission product noble gases. These source terms were taken from the Perry FSAR Chapter 15 accident scenarios and the Chapter 12 Initial Core Inventory. b. .The decay constants and radiation types, energies and yields for the above radionuclides, from Reference 5. c. The energy response characteristics of each radiation detector type and geometry,1 calculated for each noble gas using data from References 6, 7 and 8.
- d.. The whole body dose conversion factors for the above noble gases, f rom Reg. Guide 1.109 (3).
Table 2.1 summarizes the results of the calculations in terms of the extremes of detector response (converted to detector efficiencies) for each detector / geometry configuration from time O to 1.0E8 seconds after the postulated accident. From these calculations, if detector responses (in. CPM) are ~ converted to the units discussed in ites 2 above, a single conversion factor for each detector type (the mean of the calculated ef ficiency extremes) will ensure compliance with the factor of 2 accuracy. required by Reg. Guide 1.97. .Specifically, the low range beta scintillator conversion constant is 2.6E-8 uCi/cc of total noble gas per cpe, and the mid range G-M tube and high range G-M tube conversion ~ constants are 1.8E-4 and 1.4E-1 uCi/cc of Xe-133 equivalent per cps, respectively. ~The conversion constants.for the mid and high range channels will be loaded into software such that the display and recording of data for these channels is in uCi/cc of.Xe-133 equivalent. Since the low range channel is used by the plant staff to assess-routine releases in cps, the instrument display and recorder units will not be altered, rather the conversion constant for this channel will be incorporated into appropriate " Emergency Plan Instructions. u J
PY-CEI/NRR-0327 L Page 3 of 5 l Calculational methods for converting ~ instrument readings to effluent release rates are contained in PNPP Instructions EPI-B7A and EPI-B7B (both attached) and consist of the following: ~ 1. Instructions in the use of the. Meteorological Information and Dose (. Assessment System (MIDAS), a software package which is capable of calculating release rate and offsite doses based on real-time, user input or default radiation monitor and vent flow rate data.
- 2. =
Instructions in the use of'DOSEPROJ, a software package which is capable of calculating release rates and offsite doses based on user-input or default radiation monitor and vent flow rate data. 3. Instructionsfin the use of backup hand calculations, which are i capable of calculating release rates and offsite dose based on observed or-def ault radiation monitor ' and vent flow rate data.. I For further information on Perry dose assessment, including methods of hand l ' calculation, a description of the MIDAS model, and meteorological data assessment, please refer to report NUS-4336 submitted by PY-CEI/NRR-0159L January 4, 1985. The Perry Emergency Plan also discusses dose assessment systems and analytical procedures in Section 7.3. l I i i l 1 [ i 4 6 ,p-7-.,.~, 7y. m e-
PY-CEI/NRR-0327 L Page 4 of 5 TABLE 2.1: POST ACCIDENT RADIATION MONITOR RESPONSE EXTREMES BETA Detector Efficiency Mid-Range G-M Efficiency High-Range G-M Efficiency Source Tera uCi/cc/ cpm uCi/cc Xe-133 equiv/ cpm uCi/cc Xe-133 equiv/ cpm initial Core. Inventory FSAR Table 12.6-2 2.1E-8 to 3.5E-8 9.1E-5 to 2.1E-4 1.0E-1 to 1.5E-1 Control' Rod. Drop Design Basis Analysis FSAR Table 14.4-13 2.0E-8 to 3.3E-8 9.2E-5 to 2.9E-4 1.1E-1 to 1.9E-1 Control Rod Drop Realistic An; lysis FSAR Table 15.4-15 2.1E-8 to 3.2E-8 9.3E-5 to 2.0E-4 1.1E-1 to 1.4E-1 Stsca Line Break Design Basis Analysis FSAR Table-15.6 1.9E-8 to 3 5E-8 9 1';-5 to 3 4E-4 9.8E-2 to 2.2E-1 Staca Line Break Realistic Analysis FSAR Table 15.6-10 1.9E-8 to 3.4E-8 9.1E-5 to 3.4E-4 9.8E-2 to 2.2E-1 Lors of Coolant Design Basis Analysis FSAR Table 15.6-14 2.1E-8 to 3.3E-8 9.2E-5 to 1.8E-4 1.1E-1 to 1.2E-1 Lota of Coolant Realistic Analysis FSAR Table 15.6-17 2.0E-8 to 3.3E-8 9.2E-5 to 2.8E-4 1.0E-1 to 1.9E-1 Rechar Pipe Break FSAR Table 15.7-3 2.0E-8 to 3.4E-8 9 1E-5 to 2.8E-4 9.8E-2 to 1.8E-1 SJAE Line Failure Realistic Analysis FSAR Table 15.7-9 1.9E-8 to 2.6E-8 9 5E-5 to 3.4E-4 9.8E-2 to 2.2E-1 u_
Attachrent 2 PY-CEI/NRR-0327 L Page 5 of 5 REFERENCES 1. U.S. Nuclear Regulatory Commission, Region III, Report No. 50-400/84-13(DRSS). Summary of July 9-12, 1984 Routine Preoperational Inspection, dated July 27, 1984. 2. Regulatory Guide 1.97, Revision 2, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident. December, 1980. 3. Regulatory Guide 1.109, Revision 1, Calculation of Annual Doses to Man f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, October, 1977. 4. NUREG-0737, Clarification of TMI Action Plan Requirements, November, 1980. 5. D.C. Kocher, Radioactive Decay Tables, 1981. 6. Victoreen Report No. E33320381, 1982. 7. Kaman Instrumentation Report K-82-69-U(R), 1983. 8. Kaman Instrumentation Report K-82-108-U (R), 1983. m PY-CEI/NRR-0327 L Page 1 of 2 NUREG 0737 TABLE II.F.1-2 DESIGN BASIS SHIELDING ENVELOPE Summary The iodine, particulate and noble gas concentrations used to determine NUREG-0737 compliance are 0.70, 0.70 and 12.6 uCi/ce, respectively. These values are a conservative upper limit appropriate for use as a PNPP-specific shielding envelope for determining compliance with NUREG-0737 (personnel exposure limits in II.B.3 Clarification 6 and II.F.1 Attachment 2 Clarification 2, and sample collection times per Table II.F.1-2 " Design Basis Shielding Envelope"). Discussion Table II.F.1 - 2 of NUREG-0737 states that the design basis shielding envelope for sampling and analysis of particulate and iodine gaseous effluents is 100 uCi/cc of each deposited on sampling media for 30 minutes. This shielding envelope is unrealistically conservative with respect to the design of the Perry Nuclear Plant. The shielding envelope used by Perry to assess analytical capability and compliance with GDC 19 is based on the following assumptions: 1. Containment leakrate is 0.2%/ day. 2. Containment design bypass leakrate (test value divided by.75) is 8.07 SCFH. (This corresponds to 6.72% bypass). 3. No arbitrary passive failure of an ECCS component and no containment leakage from feedwater isolation valves. 4. MSIV leakage equals 100 SCFH. 5. Water leakage equals 10 gph. 6. Dilution of activity restricted to the minimum plant vent flow. A value of I cfm was used in calculating the concentrations given below. This can be factored for any desired dilution flow. 7. Annulus Exhaust Gas Treatment System flow rate to plant vent equals 2000 cfm. No other dilution flow is assumed to be present. Iodine Analysis 1. In the first 30 minutes post-LOCA, 239.6 Curies of iodine are released via the water leakage pathway. Therefore, 6 3 239.6 Ci x min, x 10 uCi xft = 282 uCi/cc 30 min. I ft' C1 28317 cc assuming a unity dilution flow. J PY-CEI/NRR-0237 L Page 2 of 2 2. The equivalent bypass leakage source is 930.6 Ci in 30 minutes or 1095.5 uCi/cc for a unity dilution flow. 3. The containment' leakage to the annulus and MSIV source (after ' filtration) is 16.3 Ci in 30 minutes or 19.2 uCi/cc for a unity dilution flow. 4. The total of the above three sources is 1396.7 uCi/cc for a unity dilution flow. For a dilution flow of 2000 cfa, the resultant concentration would be 0.70 uCi/cc.- The. equivalent particulate source term is also assumed to be 0.70 uCi/cc. Noble Gas Analysis The equivalent data for the noble gases is a total release of 10723 Ci in 30 minutes or approximately 12623 uCi/cc for a unity dilution flow (the water leakage does not contain. noble gases). For a dilution flow of 2000 cfm, the resultant concentration would be 6.31 uCi/cc. Due to mechanistic-transfer of activity. associated with the multinode model of the containment, drywell and annulus, the noble gas activity release will peak at a time later than 30 minutes. The maximum value of.the noble gas peak activity was shown to be less than a factor of 2 over the.30 minute average. Therefore, a value of 12.6 uCi/cc will be used for noble gases. I j~ t I i t f f 1 1. 7 I u PY-CEI/NRR-0327 L Page 1 of 1 NUREG 0737 SECTION II.B.3 CLARIFICATIONS 4 & 8 PRESSURIZED REACTOR COOLANT SAMPLES, BACKUP SAMPLING ANALYSIS Summary Sufficient backup capability for hydrogen analysis exists to meet the intent of Criterion (8) of NUREG-0737 Item II.B.3. Perry SSER 4 Section 9.3.2 "(8) Criterion (8) of NUREG-0737, Item II.B.3, specifies that if in-line monitoring is used for any sampling and analytical capability, the applicant shall provide backup sampling through grab samples. Established planning for analysis at offsite facilities is accep-table. Equipment provided for backup sampling shall be capable of providing at least one sample per day for 7 days following onset of the accident, and at leas
- one sample per week until the accident condition no longer exist In the Perry design, undiluted and diluted reactor coolant grab samples and containment atmosphere grab samples will be obtained for the chemical and isotopic analyses.
In addition, an in-line chemical analysis panel is provided for reactor coolant pil and containment atmospheric hydrogen concentrations. The staff finds that this is consistent with Criterion (8) of NUREG-0737, Item II.B.3." Discussion As accepted by the NRC in Perry SSER 4 dated February 1984 (based on PY-CEI/NRR-0060L dated 9/16/83) back-up analysis for dissolved hydrogen-will be provided by gas chromotography on reactor coolant grab sample off gas. The range of detection by this back-up method is comparable to the in-line meaurement. In addition, the Combustible Gas Control System contains two in-line hydrogen analyzers (Class IE) which provide hydrogen concentration in the containment atmosphere.- Core damage assessment procedures will utilize this containment atmosphere in-line hydrogen analyzer. I L J
~. l' I Attachant.5 PY-CEI/NRP.-0327 L Page 1 of 1 NUREG 0737/II.B.3 1 BORON. ANALYSIS Summary The,above described PASS modification continues to meet criterion (7) of NUREG 0737, Item,II.B.3, as invoked by Revision 2 of Regulatory Guide 1.97. Perry SSER 4 Section 9.3.2 l- "(7) Criterion (7) of NUREG-0737, Item II.B.3, specifies that the analysis of primary coolant samples for boron is required for PWR's.
- However, i
Revision.2 of Regulatory Guide 1 97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs I Conditions During and Following an Accident," specifies the need for. [ l primary coolant boron analysis capability at BWR plants, thereby making this criterion applicable to the Perry post-accident sampling system design. a In the Perry design, boron analysis is performed by ion-chromatography on a diluted sample collected at the sampling panel. 4 l The accuracy for this method is 18%. The staff considers that this 4 design capability meets Criterion (7) of NUREG-0737 Item II.B.3, as invoked by Revision 2 of Regulatory Guide 1.97." t Discussion By letter PY-CEI/NRR-0060 L dated September 16, 1983, CEI described 1 post-accident sampling system (PASS) design and analytica1' laboratory. i j provisions for boron analysis of a diluted sau:ple in the chemistry lab. ~ Modifications to the portable Dionex 20101 ion chromatography (IC) system I will be made to permit boron determination at *.he Chemical Analysis Panel (CAP). An improvement in accuracy to 15% is expected.- The following description, revised from the original submittal (page 3.6 from_ Sentry _ 4 Report No. 162), applies to the modification: j Primary Coolant - Chloride and Boron Content The PASS Chemical Analysis Panel provides means for chloride and boron determination using portable modules from a Dionex 20101 ion 1 chromatography system. The modules (eluent and regenerant chen-- ical reservoirs, pump, conductivity monitor, and chart recorder) { 4 are brought to the shielded CAP front on a cart. Dedicated-sample j loop, chromatograph valves, columns and conductivity detector j .(CE-2) are located in the CAP rear. At the panel rear, entering i sample fluid passes through a phase separator (DG-1) to remove gas l bubbles from the depressurized liquid sample stream and to-assure the chromatograph sample loop is liquid solid.. Eluent is pumped l from the panel front through the shield, to the panel rear-where; the chromatographic anion separation and detection is performed. ~ Analysis results are complete approximately 10 minutes after } initiation and are displayed on the chart. recorder. ' Recorded peak j heights are simply ratioed to a calibration solution peak height .to establish the sample concentration.- i m . m.-*
,g. m, e - ~ ..n.. 2 -1 j ~ [ ascer ice: Ec4 27978-0 -1910 REV. B. b i D dor,,-ots I ATTACMMENT'88 12 sj 4 s AA 12 11 10 13 m ? h ~
- ' h,,.,ul
~ FUNs STftA84pfWm48 't 'M g I e end 58CTioma q s,a.ga g ,t, pt.w p,vemmas casameam l >* ' MN5 q . o l .s. m 1 l r [ i (el s..,,,. _.... jfamanierA, i........, i........... _ , u n.= .... - uis re-w s. static n l, entsssM g a '"5' - P'd ' .I 5' ls si,-sn,h pi-A6 (f se-4 sr.es o. r, IPC-10 sF-49 sP-49 ' ~ - s 18 SEE NOT E 5 s s %A O i ,y,v n .I No Th> ./ 'T e ed i
- c. Aeast
) g y" su \\- i w ( 4 8 i t; e I PT h p a
_._...m m_.m_..m.- ~ MAIN PLANT VENT g.. b D19 KAMAN L._. $1 b. K- +-. - - -- io.D e.M viALLNif. 5) 4 i: A-ff as Pslc, sump.se i* INSTRUMENT Ay g L AIR SP-4 j ]' gjppy ~ ~ ~ ~ (NOTE 5) $p,y { r i U SEE. 5 21 554 NOTE C, C'* O l WQ9 R r ,Fss PI f p AP Mvo of IOl1HMO 522 s osi 8 F534 X ' 7 __RAsc_as_ _ _ __, 4 $. 2 Mau 1 g ,t I PSv0t tot %;oc l [ [^*F&1" A I te P%iC. Lvi it caumAm i i h u 9s u os u c5 T_M 4_ ___q / N72 1 i j 'l
- 5 P "
T 1 Ett 515 511 F53'- 555 'O V vot Oog cyo4 h l l t 1 I II I t TituLETE I t IODit4E ?. g Fi LT E R FS% i $$EMBut3 .F.qv$ 7 l S 2 l PSVC,6 e, 3 24. 5Z' rsts d vo7 FT S . vots r I i m, m. l 3 F 5Z9 PCI AP l l1 ,____._________a 1019 P 300 l
- g..
1 ltict.-C25 > - q E i4 Tc L__ _ _D.'J 6_1 I.HT L. 4 T -- i h @ T l
- 3..
VENT FOW Raid i IDA J100 I p.g I ?: w fAsu ktg u r .t g g 1 1 -,.... m. m. ,,,s [ (EIUAY lEa401h) 5&t :4h_q f '4 __ _ _% NOTE 3 1 I i-I O A ioiunoe j ( l M ia. A L _co.g.S'.*:c'.i L A,o,qaw, I
- e _ _c _i et., e i i
-E g. p n w m ns.,,t ua = =.c _;,,,, ; j -[
- o. i s z
u iv i E nit i 4 i m3rs:4 j ff 'i ' A' T V sL1ss M l* Do w n".ic e4 I - - ~ +. p e
- ---=~-'we*
-e. .h !kV
E-. n, . -.. : -. _,c ~%. c. m q l t!-4 '
- t
[-- --,.._.-a____ s g 4 -. ininne h e (. .i t Pttet ventitarios easieri it anett tiw Locarts in e.arr ever dt' e~n ' t; - turn re.fra - 4 pi smittote sciarittativs v "s,j MAIN PLANT VENT ottieroes. p,. 8 l icts t at est aims r see t. ..r_ 1 e i t Dl7 VICTOREEN f a, iw t. .'s"a, ..c i innent p E p r---- A A i I es rt i see p r ,.,,.n ~ j I rse l l isr l l sse l i@ i@ r l f I c-c-- J I g l.- 1 4 Q 4 r I Y 4 f hi I I I I I M 1 I innoiss 1 c i I I asua to-l l [ lut3-Ps3G sas somit:B g 't I' t f "' "' " "'L hc -_.L._____.b._____rfu__-__ 5-Eli I d -entes scact c:= rut sitrew 1 31Nct il fl 180 CP1 ptr 2 4 4e- -,- -- _ - _,1 - - _ _,.p - _ - y, A I A 1 us r't i P t * - - - - - l te)$ H -- d l "I l Iul3-7434 8 enii 2 s211 l 181171'; f L-MD806on) 7 84 stirs 7tr I EGai W q l.13-7868 lecitt acsit:a i ,6' " L lL _ - _ _ _if u _ _ _ at =: ' u " "' :" " - / cutes sec t Caminct pitch 3 s y-I psict: 18 f: ill :Ps /
- I A. ir :
g a_.__,--___- Tu-__ y gg', p/ B_ _.. f r I --- d 7 f b taul Y u.i a nis l IBil-Plc4 I / , - ---{ s_ sos-an > j L unetsa E*5 II17199t t a e!? I N III I" " * "O' J Allt41-a!ftf RitM Flet g i c c sa a n,r.m s m. -_.l.--. t L Sanct: I870183 cps ne'r't sh [ A... v.oir.u -._ ._____J j e tell 7904 l ,/ c F L. - - -{ B-40s-e31 > b / t l j i -)
1 - 1 u m 7 , -_.. y. 7 n--- r- - - -,-- q q VALVES VALVE OPERATORS HEAT EXCHANGERS PifyNG aux.A ~ -e -1.'.::. =.~* 3* a,W.*~'i' d C m". E
- -a*'
1*** =J'.*J:::L.- ucr -. , '(.:.:;.g::::;l r..,.b...r. $ - e ou i - r- ..4= i / .r ,,r n., m& .g. - - .es. we ~ e
- - '.,1 m
TfWR/R) GAL R$1PS _9,,a .=~e ru <suro.en s s
- 4*-,,,,,
,,~.-s mmeew. ~*- '*uae, rw-s o w =rm
- p. -az
'as.ar.A e ver,.,,r,a, er.e s.o.f 4f ma r( .a waroca mero.r --,.- e wrem ae ue : .s-s wrrrms a c an.nsrua r .c. .ae. NL n ar s~sm ** m' $7577,((gggyggy$ ~ %8*"*^'"" mm.w= .P,,e amp CarCA R.Atted.is.7 re.g.ae6 ',%":- /.'!",' ~~rar ea-a e ~ rusea,-w u,,,,,,,, VN VC C.nf7KA TCu a statrA4 a.rFW4 >==. A,,, g,,p,Ca,[88t rie.G .s,m.e /po.e,mo.s. anwr.4 oo ar ru nrau. ear) er. gy rg m.6.A r'C418',O.C f,3S M'.18. em.88.r.rr 8%d.a=
- e. n s.
.s s -ru.,,rr cues d* E . ~ < > 4>- a sr a,ua gy ~;,,,-~.'.':7.w~' U ov~ao ca.wr=< rme < FIRE SERVIE MISC. 4 s ,(,,,,, l 7._ l _,s,- _ e .,m 3.,- s . -<L ra., s 4 ea ,a ca <r y a,,,,,,,, - r>,acac<a co 4ou -O r.,.,=ie r y,,,, -X-. =~n=,-as-aan m rL. mro r.a Q *,*,':,y,f, {i}e. g,,r.ne i r-u-a usa << ~ _a gp,.;-~r -=< m .r,, --4.-.. - u, -< F **<~ = = car -s .~=-rwnse) -E}- "Ta*Tira** ** l = ~='c*~"'" a 4.. y u,r.- rue,. -{>- r';*" /, ~,,, 4-. w u au, q -cas ea o,xmur ~ n.aa
- r m asr
& **~ ~ G1 u yg5Sg75 ,c,_,,,,,,,,,,, _,,,, t mr .~' - 0.-- a ,mu. - anae <,, ar d
- i..,f,,;;;;;..7<".' da
= .ns ,.ca a. a
- 8F D'***6 # I.5 4'#4 4.
S.C4.r&dJ.St.df g $#4Ar pep ( ed t pre.en#.sda 89 e Jg e a et te.ebe.ar.r ) co, ?',?.E'.'r nnar. y - e. ness ese...sco, e g .n.v.eaa ca.= L$gqq .nw.eate,.ee orran r. 3 .,u.c.r.o.m..s se.. e m se m .u .r _.yy- ~ .O--} -cs-- o<so < u.< us.a.ana ,a. r-s**-au - n n u,,,,..,,, OdC# sauf 4 -so.fte gass e's d ,e. P.m.em.m, S,P.s.,N. awe.esta i m. l . ors. c.o r.o.n.ar.ee er s.ee 7 Sout s r 4r sd I 4W F#6Fu 4E644ArW4 j l l
1 'A. a
- b.,.
_,,._.__p ~ m. m g,,, l; '?4- }e !h' 4*3 L.~..(- [ y s 5 -p 4 ( f 3 3 2 [ I 1 ~ DES 6N FLAGS MISCELLANEOUS IN5iKUMENTATION . I I q can. casa.u, maosntro,*) /~l.'/A#[/CM [j[$gjNATOQ$ FUL
- L,*
on o=,D..-1Sv%,'t. 5 .g.a s w o-c,<rt C.e' 1
- o-.m ana,
I warr ca-ss .a sacet oe., s sasrc,9 a.ec,.e.,, ,g c.,,,,,,,, l a.e.se 6 + .a,c r.,e-a,.u ~ <a ,<.no {3J rj,,J gg lJ.*d y s. as s.s a .. c c. u % --.,,,,,,cnn,.,.,s. de mraes e,,,e,n,,a,e { gy,s,a .r* m +s.,r,- c.uss r casseg<e ar.m s,,wsneag vraar e, .isme.- 74s ',"i.i <,', " 2* s ')* r-- ev.m'.r--<.~ a O alqviru v w n G'D or 1 saw ca.c,rm. I ae' *** ** --" -, = = > u.anc,e-os,sa. aw a.s swa za ns r m as r uu vr coe suo.e. l },,.,,;"**'*****
- '0**r***
s
- ""'**'*(8'"4 3). C.- ~'7,'"
{ ,v,=,e-. uw,,,,y e 7,:',:'; r.~ W.L \\,,J ,,,-.o.,., a 5 oenusamne.nus = = -, = ~ y, o--
- .:=.w,a c,ana n
a.asm GDIfLLH3d\\ M ..~~~~' l ',"5., %*w as, a,.r.e %
- 'wn.
INSTRUMEN TATIOM re. s as, R.'S Nt* c~ %' *,*.*.N. #'a'.'*e'4.,ew .a f g ns or m s us,. .er.,s,t,e.,c,r,.
- .g.t.o
.c sm ..a e,..c o e-4.,,,..,,. g.
- aa n.
I
- s n.
g .I
- m*=
c., ,, ur, =<rx e a,.s naa A cm.,*~ow,m*r*.*" -=.=~rv C p
- - ~= u-r**
- 4 e a y.
6,cs.r .c,n .s. s=<- c =
- i. -r s.sc.v u m,
,.n., os. e ster .e.n .&..J sed c e .so ~.- - s ~ c4 e rr y R
- a, *;,';'i'.;
- V v
f'%= ;n.'.'a' g***.J"*
==e ,.mT:;.* ,%'d~,w~ c.~.s orsac mc L ,=c.~,?o,,u ca.,, .~<- H M,v- .m"*"V*~';" *i*J Wf""- COVTROL Sv/TCNES co.s.st ent.m s xa.,eo C ---- --- O 3.r. ,,.or .c., Tl c ^ " * ' * ' 8. "o,=,. m,m, O a Q m,..~y;=,=.= APER 1,URE -u -- 9 g <-.. _ @{:: -~ pl g.,m.m p," CARD E 0 -, ,n - -6 3., 2 . ~,., t.. ~,a,m%g h.. .. _.o., I-... y O,. 4. ' ~, i c e >~~ -" .' =. = mo. m, I tlao AvdJable On y u,_. ~ p.:.=. h- ~. >
- =_::.m,,,=
Aperture Card W .--a~~ 3 2 =_.,,;,~,,~,._.~- O--g,_,. a q-----t"S g ~a o a,. -0 w ._q =, _ _,m.,, ,-,...o,,, e G.4,%._ a V -~ n,,,,_. a;.. ~ ~ ,.n 1.; ~ ~., -~.-- .,,.a T g <+- x.x,:. g p. -.a.-. .,,a-w T @-.6 -.6 -6 l V, < - < ~ = 4--== t 0,,_.. m,u + + ~ ~ g' c ~ raa y tg*f.~=a' ,, w;,~, g,,,,,,,,,,,,,., e a. v.- ..-a e ,,c L,.n u @ ~~~ -a n <~ ~. < ~ o E.b e. or><, s rce
- -.o.,sa -*
6 )1 l .. ~,., wsrawcur ioenrirwm arren, ..,i ,e, ..,) L*se6*C.Lt.su.vts.st ase,) ca g4 0 r.a,s4 gu,( O oN$wur'f 94
- t w;tneutWAT/0M M...
...,.%.m,.'.,' ...... _- m._.,..,. 1i g-l o..... s> T .s. s aea e .,, e.g - a., o e t.e,., m.,,o,s,,e .,. v.s.,,.,,o a,..-.,,c,,, cs..,.. c.c s t,w,f.w..,.u, - m,m .n.r.c.. .,,,,.. -, ~. a.w.,.... ~., y .,e, - m - c..o. . u.. i s - . ~,.e ~ <, ~,- ....m.n ~. . i> .a l ~..
- c...m :;;;<~
n.e,.,,,,
- =.=:
- =.,w h ---
l r~==l=.,'.::'~2 , = = ~:1, . m u.s,,4, s,,,-.ob.m = .n.-
- ~~ r
- a -a u.e. 1,:u U'..**'...m y s. .. c J v,, '"JJ.M-'" y hi h h p N fN E m,h> ~.N Up" 2..m@aed.),p%s, t.n. f, m,p,,. l. """" I ". '."U ' '.*=*.^'_' 'm. l @- I. %g, { a 3. w: w3. g m mt th,h.p,P'WqH.,v p@y04 ; n* K. 4 mend ,e m~ m m R M4 t -3 g M9 a Hi k iJ.@q.. i.. -, a. - g% tm ..r hiWi is ~ ~ ' - ~ --_...J k m,6mm Wi rr.ie wrg Br 1 ' i, t 6 i LL_LW h}}