Text

Rept of Power Distribution Episode,Oct 1979-May 1980, Nonproprietary Version
	ML19331C682
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Site:	Calvert Cliffs
Issue date:	06/30/1980
From:	; BALTIMORE GAS & ELECTRIC CO.
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ML19268C996	List: ML19331C681; ML19331C682;
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{{#Wiki_filter:I E* 'g lI ~ JHIS DOCUMENT CONTAINS ,I G:. POOR QUAUTY PAGES l I l CALVERT CLIFFS UNIT I CYCLE 4 J June, 1980 .I REPORT OF POWER DISTRIBUTION EPIS0DE October 1979 - May 1980

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I I TABLE OF CONTENTS PAGE I.

SUMMARY

i II. NARRATIVE 1 III. CORE PARAMETER OBSERVATIONS AND DIAGNOSTICS 17 A. Physics Analyses 1. Core Follow Model and Results a. Reactivity b. Axial Shape Index c. Radial Power Distribution d. Power Coefficients 2. Burnup Distribution Perturbation Model and Results 3. General Physics Conclusions B. Core Differential Pressure 23 C. Temperature Distribution 24 D. Postulated Mechanisms 26 IV. CHEMISTRY OBSERVATIONS, EVALUATIONS, AND ACTIONS 40 A. Routine Water Chemistry Surveillance Program 1. Reactor Coolant System 2. Chemical and Volume Cont /ol System 3. Makeup Demineralized Episode Chemistry B. Power Distribution Episode Chemistry 53 1. Trends of Significant Chemistry Parameters a. pH b. Conductivity c. Lithium I -a v--- y 4 9

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I PAGE d. Suspended Solids e. Hydrogen f. Orgen g. Iodine Activity h. Amonia 2. Evaluations and Actions Reactor Coolant System Lithium Concentration a. I b. Hydrazine Addition to Reactor Coolant System Oxygen Ingress to Reactor Coolaat System c. d. Hydrogen Peroxide Treatment Reactor Coolant System Crud Samples e. f. Modifications to Chemistry Surveillance Program 144 C. Post-Episode Chemistry History 154 Pennanent Modific6tions to the Routine Water Chemistry D. I Surveillance Program 156 E. Section IV Attachments 171 F. Section IV References 172 V. CONCLUSIONS AND LESSONS LEARNED 174 APPENDIX A Chemistry Results of the Unit 1 Hydrogen Peroxide Treatment I I I I I

I I I.

SUMMARY

In late October,1979, Calvert Cliffs Unit 1 Reactor Core began to exhibit unpredicted behavior. The local power distribution began to grow; asymetric l axially and an abnormal shift in power to the core periphery began to occur. The initiation of the core power distribution change proceeded by about two weeks the beginning of a slow increase in differential pressure across the reactor core. The increase in differential pressure across the reactor core peaked at 1.8 psid,13% above nomal. The supposition was that the I increase in differential pressure reflected deposition of crud on core surfaces. The crud acted as a neutron absorber and/or insulator, thereby, forcing a core power redistribution. Concern for the effect of the anomalous core behavior on the safety analysis and the crud layer on fuel integrity led to successive power level decreases until 50% was reached in early November. The crud was postulated to consist of corrosion products from Reactor Coolant I System (RCS) surfaces. The higher than normal amount of corrosion products were probably caused by an abnormally high ingress of Oxygen into the RCS. The source of that ingress was found and isolated in late October. By this time, the axial power imbalance had reached 3 peak of 11%. The combination of power level decreases and isolation of the Oxygen source coincided with a slowing and eventual reversal of the growth in axial power imbalance. However, core differential pressure (dr) remained at 1 to 1.8 psid above nomal. Plant Site and Combustion Engineering Task Forces were organized to determine the cause of anomalous core behavior,to assess its effect on plant safety, and to seek a resolution. A comprehensive diagnositic program was implemented including development of a model of the phenomenon. The Task Forces labored from early November through late January,1980. Meanwhile, the situation slowly corrected itself and by late January, all core parameters, with the exception of core dp, were near normal. Core dp was still 1.8 psid above l nomal. i I

I I

SUMMARY

(cont'd) During a cold shutdown in late January, the RCS was treated with hydrogen peroxide. Significant crud releases were observed and upon return to power operation, core dp was observed to be normal. No fuel failures were observed during the episode. In late March, the issue I was consideead satisfactorily resolved and the Task Forces were disbanded. I Task Force investigations resulted in the implementation of several pemanent changes to plant surveillance and operating instructions. Several hardware modifications are also being pursued. In order to assess any lasting effect of the episode on fuel integrity, a fuel inspection program will be perfomed at the next refueling, currently scheduled for October, 1980. In late May, 1980, Unit 1 is operating at full power and all core and fuel performance parameters are nomal. I I I I I I I I I

I I ~ II. NARRATIVE At approximately 0800, October 22, 1979, the Plant Nuclear Engineer observed that the Axial Shape Index (ASI), Planar Radial Peaking Factor (Fxy), and Integrated Radial Peak (F ) had been steadily r increasing since the previous week. Azimuthal tilt (T ) had been q holding steady at about.006. Predictions indicated that F and r F should experience a very slow decrease in magnitude with core xy burnup. During the next three days, The Plant Staff increased surveillance on the critical core parameters from once every eight hours to once every hour and prepared local power distribution maps in order to assess the degree of local change in power distribution since October 13. In addition, a systematic review of other plant information was begun. Specifically, beginning with Cycle 4 Startup, trends of the following parameters were evaluated: - Hydrogen Overpressure in the Volume Control Tank - Differential pressure across Reactor Core and Reactor I Coolant Pumps - Hydrogen concentration in the Reac'or Coolant System I On October 25 a package of raw core powe* distribution data was forwarded to Combustion Engineering (CE) for analysis in accordance with a standard I core verification program performed for Calvert Cliffs by CE. At about 0800 on October 25, the measured peak linear heat rate was 10.7 Kw/ft, F was 1.45, F was 1.56, T was about.007, and Internal Axial Shape r xy q Index was +7.6%. Out of a precautionary concern for fuel integrity, the Plant Nuclear Engineer limited reactor power such that a summation of measured power level plus the Axial Shape Index would not exceed 108%. This was a simple technique for maintaining the peak linear heat rate at or below that which had been successfully experienced through October 25. On October 26, the Plant Nuclear Engineer began a periodic transmittal of core parameter trend data to CE. See Figures II.1 and II.2. 1

I I NARRATIVE (cont'd) I On October 26, the Plant Staff suspected the cause of the increasing pressure drop across the reactor core was due to an increasing crud I deposition on fuel surfaces and began a search for sources of Oxygen into the Reactor Coolant System. During this time, it was also observed that trend data indicated a lower than nomal Hydrogen concentra'. ion in the Volume Control Tank. By October 29, the source of Oxygen had been identified and isolated. While Number 11 Deborating Ion Exchanger was in service (See Figure II.3), it appears that air was introduced into the purification system via the Instrument Air header. Instrument air is nomally used to transfer spent resin. Apparently, two (2) valves (1-IA-234 and 1-CVC-151) leaked by their seats allowing I air to be introduced into the outlet of the ion exchanger. When sampled, the ion exchanger outlet had an Oxygen concentration of 300 ppb. The ion exchangers were bypassed and the Instrum(nt Air header drain valve (1-CVC-154) was opened and left open to ensure that the header remained depressurized, thereby precluding introduction of Oxygen into the Reactor Coolant System. I On October 27, CE verified the power redistribution observed by the Plant Nuclear Engineer. The core was experiencing a slowly increasing roll I of power toward the core center and toward the core bottom. Whereas prediction did indicate a slow roll in power to the core center, the measured roll was greater than the prediction. The prediction did not indicate a roll in power toward the core bottom. I Early the week of October 29, the Plant Staff and CE concluded that the cause of the power redistribution was a crud buildup on the fuel rod I surfaces, preferentially to the top of the core. The crud would contain iron and other oxidized constituents of stainless steel which would act as a mild poison to the fission reaction; and in addition, the crud may change the heat transfer characteristics across the fuel rod resulting in an increasing Doppler feedback effect. This conclusion was also consistent with a small reactivity anomaly evident in a trend of measured versus predicted boron concentration'in the Reactor Coolant System. See Figure II.4. I 2

I I NARRATIVE (cont'd) On November 1, the Plant Staff and CE began a discussion of strategies for removing crud from the fuel rods. In addition, 'the Plant Staff began analyzing for Hydrogen at a Reactor Coolant System hotleg sample point. At no time prior to and during the observation of the core power redistribution was Oxygen observed in the Reactor Coolant System (RCS). However, as a precaution, the Hydrogen concentration in the Volume Control Tank was increased resulting in a corresponding increase in Hydrogen I concentration in the Reactor Coolant System. On November 2, the Plant Nuclear Engineer directed CE to begin a correlation of crud thickness and other characteristics with reactor power redistribution as well as a quantitative evaluation of its effect on the safety analysis. On November 3, the Plant Chief Engineer organized a Power Distribution I Task Force chaired by the Plant Nuclear Engineer and consisting of the Plant Radiation-Chemistry Engineer ar.l the Plant Operations Engineer. I On November 5, the I&E Regional Office was informed of the Power Distri-bution Episode by the Shift Supervisor and also by the Plant Chief Engirieer. In addition, the Plant Nuclear Engineer iesponded to a query from the NRC Project Manager for Calvert Cliffs. At this time, no plant technical specifications had been exceeded. The parameter closest to a limit was F which was measured at 1.64. Limit is 1.66. On November 6, CE informed the Task Force that CE's preliminary evaluation revealed the possibility of lithium concentration in the presence of l local boiling in the porosities of the crud layer. Therefore, CE recomended a decrease to 80% power in order to alleviate that concern and to gain more margin. The Task Force concurred and reactor power was decreased to 80%. lI !I

I 3

8 I NARRATIVE (cont'd) By November 7, the strategy for removing crud had been developed. Lithium concentration would be increased slightly from less than 1 ppm to about 2 ppm in the Reactor Coolant System, thereby raising pH and creating an environment for slow dissolution of the crud layer. At this time, CE had completed their evaluation and determined that the appropriate power level for orecluding local boiling in crud porosities at the hattest point in the core was 50%. CE recommended that the increase in lithium I concentration in the RCS take place at that power level. The Task Force concurred. In addition to detenning the cause of and resolving the power mal-distribution, a charge to the Task Force was to keep the Plant and Offsite Safety Comittees infonned. Beginning November 5, the Plant Safety Comittee was briefed periodically and on November 8 the Task Force made a written report to the Offsite Safety Committee. I By November 8, the reactor had been stabilized at 50% power and lithium additions to the RCS had begun in order to gain and maintain the concentration in the RCS at about 2 ppm. The purification ion exchanger was put back in service. Also, CE formed a Task Force consisting of membars with physics, themo-hydraulics, materials, and chemistry backgrc;u s. I On November 9, Brookhaven National Laboratory (BNL) began investigation of the anomaly at the request of NRC staff. Plant data was provided BNL I via CE engineers who were diagnosing the anomaly and developing a model. { By November 17 potential causes for the anomaly other than crud had been reviewed and discard.d including: broken CEA finger, mechanical flow l blockage, pressurizer heater insulation, and buildup of isotope (s) with i high neutron cross sections. Also on November 17, the first in a long series of reactivity (temperature and pressure as well as power) coefficient measurements were made. It yielded a larger than normal power coefficient. The other coefficients were nonnal. II I 1 4

8 I NARRATIVE (cont'd) By November 19, core parameters (ASI and Fxy) had stabilized to well within technical specification limits and core dp was steady at 14.7 psid. CE recomended a power increase to 60% for further evaluation of core I parameter trends. The Task Force concurred and power was increased to 60% on November 21 after perfonnance of another power coefficient measurement. During the next ten days, CE completed a review of the effect of the power redistribution and reactivity anomalies on the safety analysis and concluded that a conservative evaluation of the data would allow operation at 70% power. As long as core dp remained less than 15.0 psid with no discernable upward trend and other core parameters (ASI,Fxy) remained steady or improved, concern for fuel integrity at 70% power was minimal. On November 30, CE recommended a power increase to 70%. F was 1.49 (down from a high of 1.64 on November 6) and xy decreasing, ASI was steady and core dp was 14.6 psid. The Task Force concurred in the CE recommendation and on November 30 power was increased to 70% for the purpose of additional observations and measurements at higher power level. On December 5, another power coefficient measurement was performed and indicated an improving trend but a still.ignificantly higher than normal value. A fifty liter millipore crud sample was also collected and sent I to CE for analysis of its constituents. During the following week, i I contingency plans were refined for a Hydrogen Peroxide treatment to remove crud and for a fuel inspection (visual and zirc-oxide layer thickness measurements). I On December 8, 9, and 10 a series of pressure, temperature and power coefficient measurements were performed. The purpose of the pressure (void) coefficient measurement was to detect the presence of voiding l l in the porosities of the inferred crud layer. None was evident. However, l ASI and F, values had shown significant and unpredicted increases over x those values existing at the 60% power plateau. Therefore, when data collection was completed on December 10, power was reduced to 50%. I lI l 5 m

8 NARRATIVE (cont'd) During the next 10 days, plans were laid and procedures prepared I for a Hydrogen Peroxide treatment. RCS lithium concentration was allowed to drift toward zero in anticipation of a cold shutdown for the treatment. Meanwhile CE was evaluating the data from the 70% power plateau as well as that from reactivity coefficient measurements made on December 13, 14, 16 and 17. Several power coefficient measurements were perfonnH on Unit 2 foi :omparison with Unit 1 coefficients. Unit 2's measured results were nonnal and as predicted. On December 20, it was concluded that an unexplainable increasing I trend in core dp over the last ten days (14.6 to 15.5 psid) probably reflected an oxidizing medium in the RCS. An oxidizing medium would make the Hydrogen Peroxide treatment ineffective. Consequently, beginning December 20, hydrazine additions were made to RCS makeup water at every addition of makeup water to the Volume Control Tank. Also, CE was not yet able to adequately model the burnup and power dependent behavior of the power maldistribution. The phenomenon was obviously more complicated than that explained by any single postulated mechanism (neutron cross section of crud, insulating effect of crud /zirc I oxide, boron concentration in crud porosities, etc.). Consequently, even though F was slowly decreasing and ASI was stable, a power increase I xy was premature. On December 22, it was concluded that the increase in core dp was probably l due to a combination of aerated RCS makeup water and short tenn injections of air into purification ion exchangers during resin transfer. Procedures were changed to remove all inservice ion exchangers from service during a resin transfer anywhere in the system. This action, in combination lI with the hydrazine addition, coincided with a stabilization of core dp at 15.5 psid. lI

I E

6

I NARRATIVE (cont'd) Power coefficient measurements on December 27 and January 2,1980 continued to show an improving trend. Other core parameters as well as core dp were still stable or improving. Based on this encouraging evidence, CE recomended an increase to 60% power in order to detect any change in the power dependent behavior of I the maldistribution. The Task Force concurred with the CE recomenaation and power was increased to 60% on January 3. On January 5, a power coefficient measurement at 60% power confimed an improving trend. In addition, the power dependence of the core parameters continued to approach nomal. Core dp unexplainably stepped up to 15.6 psid on December 4 but stabilized there. On January 7, this encouraging trend prompted a CE recommendation to increase power to 70% for further measurements I and observation of the power dependence of core parameters. The Task Force concurred and power was increased to 70%. As a contingency, work on a full core replacement option was begun; the core replacement to consist of about half new fuel and half previously discharged fuel. I The results of power coefficient measur~,ents on January 11 and 14 as well as observation of a near nomal power dependence of core parameters at the 70% power plateau were encouraging. However, core dp was still about 15.5 psid; 1.8 psid above normal. For this reason, power was I decreased to 50% on January 15 and remained there until the Unit was put in cold shutdown on January 26 for TMI related modifications. Power coefficient measurements on January 17,18, and 19 added to the expanding data base and continued to confim improving trends.

However, core dp did not budge from 15.6 psid.

I I I I 7

I I NARRATIVE (cont'd) I On January 22 NRC staff was briefed on the episode by BG&E and CE at a meeting in Bethesda. At the previous request of NRC staff I BG&E also explained the procedure for Hydrogen Peroxide treatment. NRC staff declined to be an impediment to performance of a Hydrogen I Peroxide treatment or to be an advocate of a fuel inspection. On January 26, coincident with the start of r.old shutdown, Hydrogen Peroxide treatment of RCS was initiated. Three Hydrogen Peroxide injections were made on January 27. Encouraging crud releases were observed. Clean up of the RCS via purification ion exchangers continued until late January 29. Calibration of the core dp sensing device was confirmed. Effect on core dp was ambiguous until the plant was returned to a hot shutdown condition on February 10 at whicn time I core dp was measured at 14.0 psid. This improvment exceeded the most optimistic predictions. Therefore, contingency plans for continuing the decrudding process by raising Lithium concentration in the RCS to 15 ppm while remaining in hot shutdown were delayed. I From February 10 through 11, a short pot * -shutdown zero power test program including a critical boron concentration measurement, iso-I thennal temperature coefficient measurement and a worth measurem4nt of CEA 5-1 was performed. Measured data agreed with predictions. I Based on this evidence, near normal values of core parameters, and a near normal core dp, power was increased to the 50% test plateau on February 12. During the next week, core dp slowly decreased to 13.8 psid. A power coefficient measurement on February 15 yielded near normal results. Other core parameters were near nonnal. Based on this encouraging I evidence, power was increased to 70% on February 19. I I I e

NMRATIVE (cont'd) Power coefficient measurements on February 21 and 22 continued to show improvement. Other core parameters and core dp were nomal. There was still no evidence of fuel failures associated with the episode. A I conservative treatment of the effect of the episode on the safety analysis justified 100% power operation. Out of a concern for any lingering effects of the episode on fuel integrity power was increased to 85% on February ".3 for an interim period and then to 100% on March 6. I After two weeks at 100% and with all symptoms of the power distribution episode gone, on March 21 the Task Force concluded with CE's concurrence that special surveillance in effect during the episode could be relaxed toward nomal. In addition, work on a core replacement option was I terminated and Lithium concentration in the RCS was allowed to drift down to nomal operating range. Lessons learned were incorporated into plant procedures and the Task Force was disbanded. On March 21, core parameters including core dp were as predicted for an unperturbed core. Power Level 2700 MWi.n Core dp 13.7 psid, steady I F 1.4E5, slowly decreasing xy ASI +.01, steady (unrodded core) local Power Distribution - nomal Reactivity Anomaly - near zero ppm boron l The fuel perfomance indicators were also nomal. l I 131 ~.003 N cc I 133 N.03 A /cc I lI lI lI g

I I NARRATIVE (cont'd) I On May 27 the nominal values of those same parameters were: Power Level 2700 MWth Core dp 13.6 psid, steady F 1.415, slowly decreasing ASI +.01, steady (unrodded core) Local Power Distribution - nomal I Reactivity Anomaly - near zero ppm boron I - 133 .~.003 >4/cc I - 133 s.03 M/cc I Figures II.5 and II.6 trend power level, core dp, F and ASI from September 1979 through May 1980. I I I I I I I I I I 10 .. =. . =..

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.:: n x ': - u -* = ; - ~S n. _:. :. 1,., 'l' - - ~ - .= :. _.. n ;- s-- .= '::_ ^' u;. :=n= - - gii ; lit ni;j4 @ ig; iiEL; jE-jEi : iggE l= :== J.. ni-j.7 liiijF Li:ii. j.2..a q =_ 4; z gg crfr. ~~ yr '= ~ - -....._:nr {:.- j: .,'.p-~ .' r d=i 5i!55 i=3=iE5EE5=!i~ t E" "El-52 4 i= "--. @i- ?!FE: xi. i. ..iiEid "; z= = C2 ..n:n. - QQ =}M=- _ v_ ..a. +....{ r. . Mrg:q:--*- :3 3* g= n+_*~--_ _.. _.. =-*n g.. nr. -

n. M --

~b C d 2[ __nin_

b. j.;1.2.n. ~I. hnd-

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..j p t_: ::... u ni..

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9

+ nt.:.

rr=:=

r N

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n _t .. g u.; -.-t,-.. ...2.......... ..a...-- g..;..;. g .y.. .t.

,y.: 2. :....

g g . ann n__:: 1

g

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7. =

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OV O M *O O

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h I 5 % {a n% tit % W ***o'n t t t ts i 2 t- .a y o n i 9 9 I ~+ s-y 6 4 12 l i

m M M,( M M M M M M M M M M M M M M(M M FIGURE II.3 FROM RCS LETDOWN [ }7 I f 4 L5 A N V V r _h _\\ _h r 3 r 3 r ) No. 11 No. 12 No. 11 Deborating Purificatior Purification !on Ion Ion (Exchangery < Exchanger (Exchangery ( y } l f l f i L A N AN C To A r r VOLUME CONTROL TANK f I 1-CVC-151 l DEMINERALIZED A k k a l [I WATER v i _i INSTRUMENT

g2 g2 g

AIR 77 FM LJ i j 1-I.A-234 1-CVC-154 V i nial'S M

mm m m mm m m n y M mM M M M M N FIGURE II.4 1400_ l 1200 CALVERT CLIFFS UNIT-1

1000, FOURTH CYCLE MEASUR_ED B.ORON.

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10000 i

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a. 14

~ c ...................16-s. I

8 E III. CORE PARAMETER OBSERVATIONS AND DIAGNOSTICS A. Physics Analyses Two types of physics analyses of this event were conducted. The I first analysis was a simulation of the spatial perturbation required to produce the observed effects. The second analysis involved core follow using a three-demensional ROCS model to quantify the departure of various core parameters from their expected values and is presented below. 1. Core Follow Models and Results A three dimensional coarse mesh nodal model (ROCS) was used for all analyses. Two sets of cross-sections were used. One set was based on the CEPAK spectrum code and had been previously used in the design of this reactor cycle. The other set was based on the assembly integral transport code DIT. This latter model better predicts reactivity levels and radial power distributions and was used mort. ntensively in this analysis. Each major parameter characterizing the core is described, and comparisons between measured and calculated values is given. a. Reactivity A measure of the core reactivity is given by the soluble l baron concentration. As the anomaly progressed, the core reactivity decreased, requiring a reduction in the soluble i boron concentration of about 40 ppm at full power. lI If this reduced boron concentration is input to a calculational model which does not contain any additional poison, the l calculated reactivity will be high by an amount equal and opposite to the additional poison worth. 17

8 E The results of such calculatic.1s are given in Figure III.l. Prior to the event,13 values of boron concentration taken at full power were used to define the unperturbed reactivity level. During the event (10/24/79 to 12/3/79) a strong pow?r dependence of the reactivity can be seen. Translated intoapowercoefficient,thisbiasisequalto( }whichisalmostasbigastheunperturbedpower coefficient itself. Since the measured boron concentrations are taken after 2-3 days of steady power operation, one must attribute a time constant of less than or equal to 1 day (3 time constants to reach equilibrium) to the power d ep endence. Af ter 12/23 the reactivity level returned to nonnal. b. Axial Shape Index The measured axial shape index (ASI) is displayed as a function of power level in Figure III.2. Following an increase of the ASI during 100% power operation between 10/10 and 11/6, a linear variation with power can be seen, except for a small displacement following a four pump loss of flow incident on 11/12/79. During recovery, the ASI becarte strongly negative. This is a consequence of having accumulated more burnup in the bottom half of the cere during the previous two months, thus shifting the power to the top after recovery. The difference between measured and calculated ASI is given in Figure III.3. Again a linear dependence of the perturbation with power level can be seen. The difference in ASI during recovery is somewhat misleading because the core follow model does not account for the distorted burnup distribution. Never-theless, the change in ASI between 12/3 and 12/23 is an indica-I tion of partial recovery. 18

I I c. Radial Power Distribution The power distribution distortion during the event was characterized by a shift to the bottom of the core as well as a shift to the core center. The amplitude of the radial shift was monotonic with core height suggesting E that most of the reactivity defect was associated with the upper, outer region of the core. Therefore, the maximum radial peaking factors were located near the top, in the region covered by the fourth level of Rhodium detectors. Two quantities were used to characterize the radial distri-bution, i.e., planar radial peaking factor, Fxy, and gross radial shif t amplitude. The evolution of F versus power level is given in Figure III.4. xy The coments made about ASI also apply to Fxy' The measure of the gross radial shift is dipicted by the ratio R of predicted to measured power in the nine central assemblies. Thus 1-R represents the fractional difference between measured and predicted power at the core center. If 1-R is positive, the measured power is higher than predicted in the central region. The evolution of 1-R is shown at 80% and 20% of core elevation in Figures III.5 and III.6, respectively. At the upper elevation, values as large as 12% can be seen. There is also a positive correlation with power level. At the lower l elevation, the trends are too small to be significant, indicating no radial perturbation at the first level of Rhodium detectors. I I

f I I d. Power Coefficients Measured and predicted power coefficients are given in Figure III.7. During the event, the measured coefficients were about 0.30 to -4 0.40 x 10 ap/%P larger than the predicted values, which further confinned the anomaly in power dependent reactivity. The difference between predicted and measured power coefficients is given in Figure III.8, together with the bias and uncertainty bands defined for this parameter from the analysis of a broader data base. During November and early December, the difference was substantially larger than the one-sigma uncertainty, and marginally larger than the K-sigma uncertainty. A deviation in power defect of 0.175% ao is obtained by integrating the average error in power coefficient (.35.x 10-4 ap/%P) between 50 and 100% power. This error is about 45% of the reactivity defect displayed in Figure III.1 (0.4% ap) based on steady state boron concentrations at various nower levels. Thus, the power coefficients confirm the direction, but not the magnitude, of the reactivity anomaly. Two scenarios can be proposed. (1) The power coefficient is affected by a phenomenon having a very short time constant, and in addition the steady state reactivity is also affected by a phenomenon having a longer time constant (days). (2) Both power coefficients and steady state reactivities are affected by the same phenomenon, which has a time constant of about one hour. The power coefficient measurement, being performed over a period of half an hour, is taken during the l reactivity transient and is or.ly affected by about half of !g '3 the reactivity shift. l l

I I Benchmark measurements were also perfonned on Calvert Cliffs Unit 2, Cycle 3 to establish the value of the power coefficient in an unperturbed core under similar conditions of burnup and power level. These results, given in Figures III.7 and III.8, show no significant departure from the prediction. 2. Burnup Distribution Perturbation Model and Results As a result of operation with a distorted power distribution, the bottom of the core accumulated more exposure and the top less than would have occurred under normal operating conditions. After return to normal operation, the ASI was expected to be more top peaked because of the reduced burnup in this region than would have been the case without the power distribution anomaly. This effect was assessed in order to detennine what constituted "nonnal operation". In order to model the effect of the actual fuel burnup distribution, the ROCS burnup and fuel isotopics were adjusted to be consistent with the measured burnup distribution at 4120 MWD /T (12/25/791, the I date at which the core seemed to have recovered from the u.analy. This adjustment was made as follows: For each incremental burnup value, one can calculate the change in any isotopic concentration N. In other words, the quantity AN I Hu was calculated for each depletable isotope for each node in the ROCS model. This derivative tenn was multiplied by the difference in accumulated burnup over Cycle 4 between CECOR and ROCS. For each isotope at each node an incremental concentration was calculated by: I 21

I aN I n;; = { (Bu - Bu (80C) ) CECOR - (Bu - Bu (800 ) ROCS } in which (Bu - Bu (B0C) CECOR is the nodewise burnup accumulated during Cycle 4 in CECOR and (Bu - Bu (80C) ROCS is the same quantity for ROCS. aN was then added to the ROCS concentration file. The correction was equivalent to about -300 MWD /T for the top half of the core and +300 MWD /T for the bottom half of the core. I Using this modified concentration file, the core follow depletion was repeated for the period of 12/23/79 to 1/24/80. As expected, the quantity most sensitive to this change was the ASI which became 0.07 more negative. The difference between the measured shape index and the shape index calculated using the updated burnup distribution is given in Figure III.9. A difference of.05 between measured and predicted ASI is now obtained, which might suggest that the power-dependence of the perturbation had disappeared by 1/24/80, but that a residual fixed perturbation remained. One must also consider that the correction to the burnup distribution assumes that CECOR has accumulated the correct exposure over Cycle 4. This correction did not take into account CECOR measurement uncertainties in instrumented assemblies of CECOR synthesis uncertainties in uninstrumented assemblies. The effect of the modified burnup distributiun on the radial power distribution is not as strong. At the 80% core elevation, it produced a 1% change in radial shift (Figure III.5) and at 20% core elevation, the effect was negligible. This correction to the burnup distribution should be considered as I giving a more qualitative rather than quantitative assessment of the post-event power distribution. An assessment as to whether the core has recovered should not be based on the ASI alone, but upon the entire range of measured data. I I I I 22

I I 3. General Physics Conclusions In conclusion, a strong perturbation took place between September and December, 1979, which affected many physics parameters of the After a slow buildup during October, a strong power dependence core. of the perturbation was observed in November. This power dependence has a time constant no greater than a few hours as evidenced by the rapid changes in power distributions following a change in power level and by the increased measured power coefficients. In mid December a strong recovery of all the physics parameters I discussed above took place, leaving only a residual bias to the ASI and the power coefficient. B. Core Differential Pressure The core differential pressure (dp) history from 9/21/79 to 1/22/80 is illustrated in Figure 111.10. In general, the data are consistent with alternating periods of increasing and decreasing flow resistance which may be the result of crud fomation, migration or changes in surface roughness in both the reactor core and in the steam generators. The core dp remained elevated above a nomal value of about 13.8 psid by as much as 1.8 psi during the September to January period, and, except for downward " spikes" in early and late October, the general trend was one of increasing core dp throughout the period. I Two points should be emphasized: (1) During the peak of the physics anomalies (roughly the period from late October to early December) the core dp anomaly was at its minimum value, running about 0.8 to 1.0 psi above nomal; however, as dp increased during December and January to a maximum value of g l 3 l.8 psi above nomal, the physics anomalies were apparently disappearing. 23

I Although it is true that core dp may be related to frictional characteristics of the crud surface as well as to the amount of crud, the opposing trends of dp and physics anomalies must be regarded as evidence against a reactivity effect model which depends directly on the thickness of a crud layer. I The initial rise in dp, from about 9/21/79 to 10/8/79 was quite (2) rapid relative to some crud fomation mechanisms which are thought to require months. This initial rise in dp was equal to the maximum dp anomaly observed at any time during the September-Jinuary period. C. Temperature Distribution In-core themocouple (T/C) indications have been examined for several periods for any evidence of crudding effects. Typical results are shown in Figures III.11 and III.12 since power levels and power distributions were quite different from day to day during the anomaly, temperature rises indicated by the T/C's are nomalized by the predicted The temperature rises in the assemblies in which the T/C's were located. figures show differences in this normalized parameter between several selected pairs of dates. 1 Examination of other T/C data similar to that illustrated in Figures III.11 l and 111.12 indicates that there was a characteristic change in T/C behavior between 17 and 9/14 and that this changed behavior persisted to at least 1/5/80. Temperature distributions obtained on or after 9/14 were essentially invariant. However, when temperature distributions l prior to 9/14 are compared to distributions obtained on or after that date, the latter temperatures are seen to be systematically higher, typically by 5 to 15% of the assembly AT. This increase was consistent with a reduction in guide tube flow in the instrumented fuel assemblies, presumably ( due to crud formation. A small fraction of the temperature anomaly had disappeared by 1/25/80. Following the Hydrogen Peroxide treatment, further improvement, but not a return to nomal, was noted. !I 24

I Several points should be emphasized with respect to T/C indications: (1) The T/C indications evidencing crud increased in advance of either core dp or physics indications of crud, that is, in late August as opposed to September or October; this is evidence that crud was forming at this early date. (2) There does not appear to be any systematic distribution of temperature increase or decrease within the core which would indicate preferential crud formation in either the periphery or the center; this is probably evidence that a small amount of crud in guide tubes and/or instrument thimbles is enough to cause the maximum observed AT change, with a " saturation" effect applying to any further crud fonnation. (3) The T/C readings, like the core dp indications, appear to be larger after the peak of the physics anomaly, i.e., from early December to early January. This is probably evidenge of further crud shifting in the core at this later time. (4) T/C's in the Calvert Cliffs Units have been unreliable during nonnal operation in the sense that absolute values are not predictable from a knowledge of the core operating conditions cnly. Significant biases due to unknown causes apparently exist. Thus, T/C evidence must only be interpreted as indication of a trend. I I I 2s

I I D. Postulated Mechanisms It was concluded that Many potential mechanisms were evaluated. the primary contributions may come from the poisoning effect of crud and boron, with a contribution from Doppler due to an increase All these mechanisms assume that crud deposition in fuel temperature. occuired preferentially in the upper peripheral region of the core. I Crud deposition may induce local boiling, increase clad oxidation rate, increase fuel temperatures and increase local concentrations of boron. The physics calculations defined the order of magnitude of the effects required to match the observed core power distribution during the It was concluded that the poisoning effect was greatest in anomaly. the outermost region of the core and a maximum in the upper portion In order to explain the physics observations at of that region. 100% power, it is necessary to invoke poison concentrations at this 2 of crud (25% Ni, 48% Fe, 27% 0) axial location of at least 480 mg/: 1 2 on the cladding or a plating of more than 0.05 mgbat/cm on the 0 cladding or an increase of more than 1800 F in the fuel average temperature, or some combination of these mechanisms. The main conclusions reached were: The observed physics anomalies were almost certainly related to the This is presence of an abnomal amount or type of crud in the core. supported by the measured high core differential pressure. It is very unlikely that the physics anomalies were caused solely or even predominantly by fuel heat up and associated Doppler effects. It is difficult to conceive of a mechanism which substantially increases the fuel temperature without an associated increase in cladding Cladding temperature increases of the required magnitude temperature. I would have caused the fuel rods to fail through excessive oxidation, yet no failures were observed. 26

I I A combination of crud-related mechanisms which could have produced I the observed anomalies includes the poisoning effect of crud itself, boron deposition in the crud both under boiling and non-boiling conditions, fuel heat up due to oxide formation, ar1 the thermal insulating effect of crud. I In the postuluted scenario boron concentration in the crud provides the However, this requires very major contribution to the physics anomaly. There is no known rapid baron migration into and out of porous crud. Similar neutronics effects independent evidence for such a phenomenon. These anomalies were ascribed to a I have been observed in other reactors. mechanism involving crud (but not boron) by which the power-reactivity relationship was affected. The details of this mechanism are unknown. I I I I I I I l I I I I 27

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I I IV. Chemistry Observations and Evaluations A. Routine Water Chemistry Surveillance Program The water chemistry program at Calvert Cliffs is outlined in a definitive set of procedures contained in Calvert Cliffs Instruction #406 (Attachment-(la-d). Collectively, this set of chemistry and radiochemistry procedures forms the nucleus of a detailed, rigidly characterized system for the analysis of significant parameters to determine trends and identify abnormal conditions. The basis for the chemistry surveillance program at Calvert Cliffs is formed from the Combustion Engineering (CE) Power System Nuclear Steam Supply System Chemistry Manual (CENPD - 28) (Reference 1). The analytical methodologies, sampling locations, sampling frequencies and parameter specifications recomended in the CE Chemistry Manual have been strictly incorporated into the site specific Calvert Cliffs chemistry program. Insofar as the Calvert Cliffs Unit 1 Power Distribution Episode is concerned, the chemistry control of the following systems need be evaluated: 1 1. Reactor Coolant System (RCS) .I 2. Chemical and Volume Control System (CVCS) 3. Makeup Demineralized Water System (RC M/U) I I I I 40
I I 1. Reactor Coolant System A detailed discussion of the Reactor Coolant System chemistry I monitoring program is contained in Chemistry Procedure 1-202 (Reference 2). Table 1 of RCP 1-202 (Attachment 2a-b), characterizes the procedures / specifications / frequencies associated with significant parameters in the RCS. This is a site specific procedure which incorporates the recommendations of CENPD-28 as regards RCS chemistry. Specification Sheet # 3-3 (Attachments 3a, b, c and d), outlines the CE recomended sampling location, frequencies, specifications and corrective actions for the analysis specified. As regards the power distribution episode the following RCS chemistry parameters are of significance: (a) pH, (b) conductivity, (c) lithium, (d) suspended solids, I (e) hydrogen, (f) iodine 131/133, (g) iodine retia, (h) ammonia. Nominal RCS water chemistry is illustrated in Figures IA - H for the period of time 07/01/80 to 07/31/80. It is readily apparent from an examination of the figures that the water chemistry parameters were controlled to values well withi1 both the CE and site specific limits. I Table IV.A.1 summarizes the nominal nbserved chemistry values obtained from examination of the figures together with both the CE recommended I and site specific guidelines. I I I llI 1
I I-41
TABLE IV.A.1 I Parameters flominal Observed CE Recommended Site Specific (Units) Value I (a) pH (Standard) 5.0 to 7.0 4.5 to 10.2 4.5 to 10.2 Unit at 25 Co (b) Specific 0.0 to 20.) Consistent with Consistent Conductivity concentration (Fmho/cm) of additives (c) Lithium 0.0 to 1.0 0.2 to 1.0
1. ppm maximum (ppm) e (d) Suspended 0.0 to 250 500 or 500 maximum I
Solids 2000 (4 hrs.) s/s (ppb) I o(e) Hydrogen 10 to 60 10 to 50 10.to 50 (cc/kg) I (f) 0xygen 410 41 C 4100 l (ppb) I (g) Activity N/A Not Specified Not Specified 131 ;133 g 7 I (h) Ammonia 4 25 4500 Not Specified (ppb) I
lt should be noted that the CE recomended analysis method for RCS hydrogen concentration is by means of volume control tank calculations.
I I lI 42
M( M M M M M M M M M M M M M M m M( m m ( ( ( P I FIGURE 1A l l l SECTION IV.A . g. (a. ~25 C ~~ '~~ ~ ~ ~ ~ 8. t h 7 a I I 6 G l ,A 5 4 ...u_____... I ? .-.._p._,._ 1 i j l 3 ..a ._.... - p u.. q._ _. 4.. .j I 4 i i i i ....L..d..._....'. l __.j_.... ._J_ j r t _9 - i I. i I-i I i i I. 1 I f R I f f I e f 's I t e i R R R 3 3 e a n a 1 1 m _1 3 !e_ 1 a h_. f. h._ L_._._. i_.__.. _. .u .}____j_ . } _... I. _. l.. - 1 I I ' i i ^**F, I 1 6 i 4 .I...' ' k .. - i... f~. I l i i i i ___ m i
.u. FIGURE IB l i 170 l SECTION IV.A 160 i CONDUCTIVITY 150 07/01 - 27/31/1979-140 130 i .120 ._..._____..._a__ l 110 4 180 -m I UN 90 1 o 1..___. j
)
80 i l l 70 _ j l 00 J_-._.._.__._.-. 50 l i j-j. . g.. j ) . _40 -..... a .i 0 m. t j 20 l.__.:..u. l. i d. I i i ._:____.._____._a q J.. _..L_p _ i... +.. .g_.: j. {... _ J.. _... j. . I.._. -. _ l j. j 7.. t -t t i + jl I I I i i .....i..-_... + ---. ! - th I..d - - - -'f j -- I [- 1-- .t I 3 t I 'I I I 't l I I l' I t t I e! e f t i I I i 1 I t t 'I t I-I t i \\ j
Im Mr e e a m W W W pm M. m.m p m( m FW ( l FIGURE IC i l SECTION IV.A LITHIUM 07/01 31/1979 t 5_ i 6,. l 1 4 u = f 3 1 t a n. 2 1 l 1 1 .. m. 1 .L. 6 h ....---4 ) i i 4 I .1 j I t i ..,-.-....._,._-.._.i...-..,.! i ? -l h 1 l l f [ I j t l f t I'
M M M M M M W m M M M M M( M m M M( m .( ( ( 9 i i FIGURE 10 900_ l SECTION IV.A- + 800 SUSPENDED SOLIDS j 07/01 31/1979 ] 700 _ f .60 l ~ { @500 l Q. .._..p j ._--+..._L.._.,. 1 i i 200 +. _. _ i .- q i j 1 4 I ~ i i l l i 1 i l ._.._,_..._..-_.L i i .i . 1.00 .+. .t l ^ __.-4-_, t l I i i i l 1 I i i I j .____._i... ~ T'I l~ I i l ~ -i I i i, 4 10 I' I I I I I I' I I I I - I I ' ~ ~ I I I I I I I I I 'i I I I I I l l
M M M M M W m e e a e a m l ( ( ( ( ( l l FIGURE lE l 80_ grc71 y; pf,,g ~ HYDROG N 07/01 - _B7/31/1979 - VCT CALCULATED i 70- . HOT LEG i .... 1 60 e ? f 50 I l l 1 3 g Q M 40 s u t u i l 1 l I I 30 . 4__ y -... _. f' l 20 _. a -.. .+.._.. _. - _.. i ~ f t. { { j .~. a- } r_ p a -. _ _10...._..u> j h .} } . ]. -l i f .4-. i .r. .. p _ _ _.: .._. i 2.. -j - 1-
l.l. -i i i ti - i. i i ii ii i i
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.( FIGURE ~;F 1 2.09 O.08 SECTION IV.A IODINE-i 07/01 - 07/31/1979
0. 07_
0.06 _ i

- I OD I NE-133 i

0 1 i { 0.05 -~ = ow a A-R Ibr .\\ l 1 -\\- -N~ j r 0.24 . _\\... _..,j__'. \\ 1 !l j l f e o l -\\ ,17 - ^^ 1 B. 03_ i / i t ~~ __ g._... _1... f, 4 J _J,_.. ,\\ ', i ~ i, REFUELING OUTAGE - m -]-p/ i is ~~ ~ -r . B. 02 . = b' ~ ~' ~*~ ~ ~~---~-~~~~f t _i 1 L =- + '-100I + l _ B. El . --+ i. i i i i. ~! "k~* g l f -.f h i e j h = i - I J j a 4-g. j t i i i'iiii_t-0 i i, > i i i i i:i i:i i i , ?,
,,i
E E E E M M m e m m e a e e e g I I ( . ( FIGURE lG O.90 SECTION IV.A O.80 IODINE RATIO-07/01 - 07/31/1979 i 4 1 O. 7B_ i i i 1 8.60_ i B. 50 i e O J B. 40 _ +. _.. _. a [ 0.30 I s - - - - ~ - - - * ^ ~~ ~ REFUELING OUTAGE-A q: j e I . - + - - - - - -. +-n_.-.. i o L ..a j 7 a - +.. a.- -} - .i. .} I l j i
0. 10

..._..i.
. I.. u. .. 1._j_:._.. j.. j _..l.. -l. l L _i i. i I 1! i 1 i i i .-+ l 1 i _.._._..a.. .a_ _. .. _... -.. _ _... -.... _ = .- f --- --b-- 14 - - + - - j i i i i i i i. i i i: r e s ' i i i l i-i i i .. i i i i i ii... i __1
M' M M M M M m m m( ( ( ( g FIGURE let 17 SECTION IV.A 18 AMMONIA 07/01 - 07/31/1979 15 I 14 I 13 i 12_ 11 4 10 _ m a-o I 9 - an. i 8 7 3 6 a .5 - _ _.,_.....__,_.__.___;__.7_.._.a._. I ? 4 _ d.. .H l h 3-. 4 t, I t L.~j.. _. _. .__...i 4 i a o r r I I ,_.2 r ..-3,_ j } i i
4. _....
. __L. 1. _. r - _. a _. _ _ r _ _.m _2 _ _:.__ + ,_ g l t' _ I. d i .u o. t. t a g: r t t 8 I 't i I 1' t I 't t 3' 1l - 4 s }- 'I'.g i 4
I I 2. Chemical and Volume Control System A detailed discussion of the CVCS chemistry monitoring program is contained in Chemistry Procedure 1-215 (Attachment 4)which characterizes the procedures / specifications and frequencies associated with parameters of a critical nature in the CVCS. This is a site specific procedure which incorporates the recommendations of CENPD-28 (Reference 1). Insofar as the power distribution episode is concerned the parameter of significance is the volume control tank (VCT) hydrogen over-pressure. The recommended hydrogen I of 9-45 psia corresponds to VCT calculated hydrogen concentrations over pressure of 10-50 cc/kg. This is dependent upon establishing nominal values for vapor phase hydrogen concentrations. VCT hydrogen concentrations are illustrated in Attachement 1E. Inspection of the data demonstrates that VCT over pressure (calculated RCS hydrogen concentration)was within specification during routine operations. I 1 1 3. Makeup Demineralized Water System A comprehensive explanation of the reactor coolant makeup water 3 system (RC M/U) chemistry monitoring program is located in chemistry Procedure 1-201 1 (Reference 4). Table 1 of RCP1-201 (Attachment 5) describes the procedures / This specifications and frequencies associated with the reactor coolant system. is a site specific procedure which incorporates the recomendations of CENPD-28 l (Reference 1). The reconmended chemistry guidelines of CENPD-28 as regards RC M/V are illustrated in table fom as specification Sheet 2-1 (Attachment 6a-b). l Examination of the operational chemistry data logsheets (Reference 5) verified that routine chemistry values were within the guidelines of both the site specific and CE specifications. Table IV.A.2 illustrates the nominal observed values obtained for significant parameters together with the gecommended specifications.
I I I TABLE IV. A.2 Nominal Observed CE Site Specific Parameter Specifications Specifications I (Units) Value 6.0 6.0 - 8.0 5.8 - 8.0 (1) pH @25 C (Standard Units) 0.5 2.0 maximum 2.0 maximum (2) Specific Conductivity (Amhos/cm) I 4.08 0.15 maximum 0.15 maximum (3) Chloride (ppm) I 41.0 Not Specified 10 maximum (4) Sodium (ppb) 2.01 0.02 maximum 0.02 maximum (5) Silica (ppm) 0.1 maximum 40.05 0.1 maximum (6) Flourides (ppm) I I I I I 52
I I B. Power Distribution Episode Chemistry 1. Trends of Significant Chemistry Parameters a. pH (Figures B.1 - 8) During the period 08/04/70 to 03/31/80 including the period of the power distribution episode, the pH of the RCS was controlled within the range 5.0 - 8.0 (measured at 25 C). This range of values I is consistent with the normal operating guidelines established by CE in the Reactor Plant Chemistry Manual and incorporated into RCP 1-202. Table IV.A.1 illustrates this point. A nominal value for pH during the power distribution episode would be 6.5. I I I I I I I I 53
( ( ( ( ( FIGURE 3.1 SECTION IV.B PH 0 25 c ~ 8 7 6 i l U1 J A j 1 5 i 4 i i i r U 3 e ,-.~....-..-.p..--.4--, -.- ; ---. j.-. a. -. j' i i f-e a e a a a e e a e a e a a e a a a a e' a. In -sI e 's .s s-s' s .e s' s e a. i { t t } 4.. ..a - 4 .i. q e a a, i i i - ( - 1._ _ ) . 3..
h....
f, l i l I t i i I i
m m m m m m m m e e e m e e m m m m 1 ( ( ( ( ( 1 FIGURE B.2 SECTION -IV.B 'PH 0 25 C l ~ 8 i 1 1 I, 7 \\ 6 i I m m 5 l ...-...L..._.g_.. t 1 J 7 .__4_.__._..... k ^ t J.. } i ) _..__i__..._-.,.______...___,_. .. j 1 i } ..4- { i I 1 j I i A- 'j 8 + t j I g a 3 g I e e 3 g g e 3 g e 3 3 g g e' g 't g-g 3 g '. 3 e g 3 g a I l . f. - i. 6 +. .w . j... ; _. ' I l. !. } i I i e t r- .g .p 4 4 1 _... l i i i l i i i 1 ~ i
M M M M M M M M M m m m m e e m ( ( { ( ( ~ FIGURE B.3 SECTION IV.B PH e 25 c 10/01 - 10/31/1979 8 i 7 j l w l l ~ ~ ~ 1 ~ I 4 l ..L._.._ ..-.4.... -._u..-. -.f_.~.._.. e.. L e + e r )
_.__j...__._._,-
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t t
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l
.;___.a ...a.._.._..' i } - 3. 8 .j. 1 t 3 f. 1 L.. ..f_ .[ ' ! i i } l i j i I i i i -.l 4 p 'I l ? {. a' } .. _.. _____.l __I_..__._ i l _ __. t i
( ( ( ( ( FIGURE B.4 SECTION IV.B PH 0 25 C -~ ~ ~ 8 7 w ... _ a.. _.1 6 ~ w N 1 5 f f 4 j l .m 1 1 1 1 L -- h... .-_j-__;--.. t [ - } } 4 i 4 I 4 9 J t i R t a t i 3 3 3 3 g 3 3 3 3 3 t 3 3 3 g 3 gL .g
3 g'
.g .g .g g. g g i h r r... i .,_..4 _.- -- - _.~ J l I I i I i .p_ ..g..__.. ._._..j. . q. i i i i i -- 9 a f . l_ f. f, . ? i i l I 4'. t _,. r t i 4' 1 '6 1_.. 5 t I. g.., i i e 9 .1_ _ _1_ - i i -
A -.a-._a.-a. 4 e .A-a h-- m--.-_EL u---.--- ( ( ( l ( ( FIGURE 3.5 SECTION IV.B PH e 25 c 12/01 - 12/31/1979 8 l l I 1 7 j S ___ ____ / N _/ _-g ~ w 6 w O') 5 4 i, i I I e I g P W 3 i. -{- 4 1 l 2 I i i 9 t { t i l t L,, t 4-E I f i i I a e I I I i i .i E A 1 A .I R R A .A R A A A A A R I l i i t ? i i ? . j. i J a. I a.- i. l i i i i i l [ l ( l I i I . a. _. a _ _ .t._ u _. 2 - 1-2 -- a .i.. 1
m m m m m m m m m m m m m m m e e m M I ( ( ( ( FIGURE B.6 SECTION IV.B i PH e 25 c i 1/01 - 01/31/1980 8 t 1 e g 7 ^ 6 U1 5 i 4 4 1 6 p .a-r .. +.. -,, e-I i i 3 ~ ....-_L.___ . - - - ~... -. _,. ._.,._.~ w.. _... I t 4 i e e e a g 1 e e a e a e g g e a a e a g e a e a a e g 's e e e t { l I i e 4-+ te E--e.--f. ++,--.b~*=..p-.
b. --
s i 1-t. { l 1 -1 i. j g-I i l 1 i i 1 4 l' i g 3 l l .j j j i i,
1. -
i. + t l i 4 i 3 i
( i ( i ( ( FIGURE B7 i i i SECTION IV.B ~ ~ PH 0 25*C ~ ~^ ~ '~~ ~ J 02/01 - 02/29/1980 8 l 7 4 ..e .--o 6 ) m j N ,...- +-.. 5 d . _ -..- 7 L i = F 4 $i ...a ,b . ~ - - ~ .. + _. - _. .-..4_,-. y j-j. l
_.4
..y__._..- f t ._2._..+ i i -{ 5 t - i. j i e a e e -e e a e e i e n i i n. a a i.i a a a i a a a i a e in. J D "d j i h r i 4 [ I f -} . - - -.L. - {. .m .s...-- t . i.... ...... 1._.1.... ! 4 h l I f l f . ' _d 1 ! _ __,j i. L:_ i t_ ~ .] .L i . I..=. i i.I i I
W W M M M M m m m ag g g g ( ( { ( FIGURE B.8 I I .i 3 SECTION IV.B i ~ ~ ~ PH e 25 c 03/01 - 03/31/1980 8 ~ 7 ^ / 6 i l ~~ 5 ..e_.. m,r.w==
4

"9-O-
,,1 4 g e.- e e D I - - - - =-'-.-- i 3 i .-;-'-~----* -t*~ ~~M l. z. i 4---- 4 t i e i e e e e i e s r' s 4 ? 4 I i ) ~ ~ ^ 6- - - + ~ ' - ~ ~ ' ' '. U - ..._ p _. 1 l .t _ r + *-- ,i i i ( r i e-_, u- - T-~~~~~ - ~ ~ ~ ~, f' 1 -t-1 + 4 4 q c -l + l L i 1 - - - - - - _u_L i _ __2 1 i l
I I I b. Conductivity (Figures B.9-16) The specification regarding RCS conductivity is that the values be I consistent with coolant additives. Under normal operating conditions, the reactor coolant contains only boric acid and lithium hydroxide During the initial chemical additives in significant concentrations. stagn of the power distribution episode RCS condictivity was controlled to within the specification noted in Table IV.A.1 in that In conductivity was consistent with pH and boron concentration. response to a CE recomendation, hydrazine injection to the RCS was initiated during nonnal ope-ation. Whereas conducthity previously ranged from 10-20pmhos/cm, new data points were in agreement with The increase I the concentration of chemical additives in the RCS. in baseline conductivity caused by ammonia decomposition products of hydrazine was anticipated. There were several occasions during the power distribution episode where significant conductivity increases in the RCS were initiated by the injection of excessive into the CVCS. These out-of-trend conductivity quantities of N H24 values (i.e.1/10/79 conductivity-160 mhos/cm) are discussed in It should be noted that conductivity was at all SecHen 'V.B.2.6. times consistent with the concentration of chemical additive I acid, lithium hydroxide, and hydrazine) in the RCS and that the introduction of impurities was not a problem during the power distribution. ,I .I I I I 62
E E E E E M M M M M g g I FIGURE B,9 I 170 SECTION IV.B l J 160 CONDUCTIVITY I 150 08/01 -8/31/1979 140 1 130 i l 120 I t 110 ~ ~~~ ~ 100 .W X U L 90 N O ~ gg --7 70 +I 60 -a--. e---- Sg i, -b~ -'~~~E~~~~~~~~~~~' 40 ... -. _... - + -. - - - - t- - L ---- - ^ ~ ^ ~ .--a._ i e j--- - +-
- - i-
~ ~ ~ - ~~ - ^ l 20 -h- -t '~- I j j; j ~ 4 -[ j j 10_._ p.. .. t - '-~~~~1 - - ~ I ' ~ f 'I I i I I t_ i* I I I I i I t I I~ I I I ! t I I I a i t g g g' g 'g 3 g 't g a t t I
E M M M M M M m m m m ag g g g ( ( I i ( ( l 1 FIGURE B.10 1 1 170 i SECTION IV.B i i 160 CONDUCTIVITY I ggfgi ggf3gfg979 150 140 130 120 l 110 i 100 m Sm g + g l 90 N o I h _.. _ _. ~ 80 a 4 .e--- am I i: 60 15 i j 50 j -.-4..-.. --. 7 - - - --.. - j - - - -- I A0 4 (. ,' _ a __- -- -.-- --- i i -+~ .._ _ --. a 20 - l I i i 7 l I-l i a w I t w i __1 .10 __ .__.. _ _.._ _ + ....g. - } --- l l i 3 6 ..a.. .. -.i -._.
t e
t l' t 'i 1 I i I I I I Il 9! I I I I 1 -I 1 ' i j -.1 I i t t i I t t t I i t t t I
) FIGURE B.11 [ j i l 170 [ SECTION IV.B i 160 l CONDUCTIVITY 150 10/01 10/31/1979- - i I 140 i ~ l I i 1 130 1 1 4 l j 120 i 110 1 t I -i 100 m l LD E U i 90 N O J-g L 80 q ... -. 7_... -. - 70 t + 60 4 ( l 50 .. _.. - _.. L __. a._ _ : - _ 2 _.-... - t i i - ~ ~ - ' _.. _. _. _.... _ ~ i i, 1 30 . ~. i j 1 i i t l 00 ..____... - - ~ _ - .b.- - -I-1--+---,------- - - -- - --I i i i _. - 7' 7 i . __ [ ____ _ _ -.. _ ^ - -- - p la i t i i ) f -] l g r ~ t,. 9-i j% I i i i I i i i 1-1 I I I I I I I I I I E 'l I I I I I I E 'I I' I I I ^ I i
M M(M %M M M M M M M M M M M g M(M M FIGURE B.12 1 170 SECTION IV.B 180 l CONDUCTIVITY 150 igfgt _ gif3gfig7g. j i i i 140 i l 138 i. i 120 i 11e 100 x i U 98 _ n. - BE .-Q 7 j. }' 7B j ) 80 ~ i; jl 58 kb -_L ..-.--..A i l + i 30 g I j: h t 29 f _1 !.. i. - _ _ _ _ _ ._ L }. J. f, _._19. b ._ [ _ - _ _ h, _ _. _ __.._. _ _ ._i I I I i i g. 7.._.. _. u.. -. a - }_ _. p. -i .... a...:._.. i e i i e i i e i i i r i e i e l i a i ri e i.. si i e i 1 4
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M M( M ( ,....t u. l M M M M M M M M M M M M M( M ( g i FIGURE B.16 i t t l 170 l SECTION IV.B: ISO ..___a 1 3 + l L CONDUCTIVITY; l 4 ! -M - --- - ---- - - -s j 158..... 83/81 - --- 93/31/1988 l----r-i l 9 i i 1.4. 8 - _.._ J' i i 1 i l 130 i 120 t l j. i i . _._.i i i ..i... 7_,._.._ i _.118 _.._-._.,1 7 l i. t t g - 10O __ I
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I .I c. Lithium (Figures B.17-24) In accordance with CE guidelines,the site specific limitation for lithium in the RCS is 1.0 ppm maximum (Reference Table IV.A.1). During the initial portion of the power distribution episode, the lithium concentration was maintained within this guideline (Figures B.17, B.18 and B.19). However, in early November the lithium concentration was increased to approximately 2.0 ppm pursuant to a CE recomendation to maintain lithium concentration as high as possible but less than 2.2 ppm. With the noticeable exception of January 10, 1980, the lithium concentration was controlled to approximately the CE guidelines. The RCS lithium concentration increase of January 10, 1980 is discussed in l Section IV.B.2.a. I lI
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i e m M M m m m m m m m m m m mM m ( ( ( ( ( n 4 1 FIGURE S.17 ,1 l 1 SECTION IV.--B-LITHIUM -- - i 08/01 - 8/31/1979 : ...--_..__.y... _.L _.. 4 I i .-___.._L. i l 5 1 1 l- .._.. L... a. ___4 __ _ _ :._....._i _-. -a a...-.. 4 l 4 I i i N i N i 4 S k l Z .L ..E l 1 L g. 7 f ...._.._e.--_.t s j i I ._.._w__...__ 4 4 t ? 'j-j r t I t {' . _. _ adme j j-N.- [. I t. t 1 I. i 4 __.____,__4 f 8 i i ) l' s e, _ _, _. _. _ 1 I I R f f f f 9 9 9 R R 'I f f I E f R R f R 'f 9 5 9 I f I t E '9 R' t ..f . f'. _.f f I } .j. }. [___ i ._..d.___ :.. 4 i _7_ 1 l i 1 .i .I i .i .p. k f l l i q e _____4....___. l t,. .t t i ( l 4 1 .L- + l .I __7 f l l l
W M M M m m e e e a m ( ( ( ( ( FIGURE B.18 SECTI'ON IV.B ~ ~~ 4 i LITHIUM 09/01 - 09/30/1979 l i f 1 f I i } e j &-_-_,a_ - ~... -. - -. i } 4 I 4 i 8' y l W 1 3 4 4 i ._.4 g O. - -... ~ i _j_.... i j t d J i L p, -. 4, -. >. l 1 s 1 [-. i l f, 3 - f. - t, 3 g 3. 3 3 g .._.,_._q I t ? 1 f. {- I ) g, 3 .g 3: t 9 R R 1 9 3 3 3 e e a 0 3 3 g a g_ g 3 3: g o s e l l 1 d 4 e-. .u-e== ee..ee-.-.-.==w. .. =. - > hh e- --e ....,...e .ee...4 ..._..-.-..-.us. i 1 i i j._ q. 4.- +.. -{. j 1 ] i l I t I t t I' s l _........_7_.4.__ -_____._.7.. I -l ,1 i i I, -t-- r 1 2 l 1. r_,_ i a 7 l.. Lu { 1 ....a. i j_ _ _ _. _ _
m m m I ( I l ( i. FIGURE 3.19 SECTION IV.8 LITHIUM m 10/01 - 10/31/1979 1 1 i 5 i l ._...a i i 4 J I N a> b h i 3 1 1 { g Q. t i 2 i i i il.' l j' b 1 i i 1 } i. ,e i, i i 1 J __..g -N j j j. 4 i i 4 i i r i s e a a e e a a a !n a a a e a a a a n' s !a ei e 's e !a a a !s e a !a e - l-l i P i i e 4 ,.___ _.r._____ .. _ _........, _... l a' - _p i i. i .j. _... _ _ _ ___..p._.. ..___.._...a 1 F
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! W W W W W W W W m W W W W W W W W W W 1 ( ( ( l ( ( .,w., c. 2 FIGURE B.23 3 i i -W- -~ i -SECTION~IVrB 3 t-j j I } s i i .~.. T -tITHIUM '+ i T 02/01 - 02/29/1980-i l i- .a. . a._. -- _._. ~ .... = l h I h J .i I t 1 a l i i j i I -r 1 + i I i _.L.._.....4.- 5 a. p - f. I-j h 2 ..'.___.J._.. i {.._ _; I l 4 1 i, .} I f 1 i I i j l _.4 I I ._...._..___7 f I j i i 4 ? l t l I t I l 1' i i 6 I j e { y 1 I j -l c. . I. 1,. t .i g L t J, I i i i i. i ' i i i i r j j I l _ _ _... + i ..-.. g. ._._...q. l i j I . 7 ..q __ y =i ~t,jTHIATINGNEFIONEXCFANGE: BED, i ~ E 1 1 g! p e _.a 2 _.a.__ .a___ _.-.__.. ._a. I l l .._-_.;_.. :... __._.___.__..__.i_.... . __. __ :... A j .j y l_ .l__ _.a._ i i 3 1 l COLDISHUT'D0sN I l d I. I i i g. .q .,t. .} i i l t + 1 I 1 i i I I' t I -..E i = .A;.j
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W W W W W W W W W W W m m m m m m a m 2 t'. 4 FIGURE B.24 ,. _ _ _ _ _, _. _... ~ _ SECTION IV.8 l .L-ITHItM 4 j 03/01 - 03/31/1980 4 .,__.~. ~ i 5 t I u ~ l I ,j _d __.... _ h N i o t ese ,-.-._i_._.... W 7 I g __.J._. %.7_.._ ... _ j .. - _. - ~ 1-D. i t-t 2. .. N __t ti 4 j ~.... _.. 1 d t i i 1 4 1 j 1 j l 1 i _ __.. l.... ; _ _.. .} 9 + l + t l t i i j -.} } 1 j + i i _., _. I I I i t 1 I I f 9 9 9 i I f I t i I i-t 't t ' I k i I t t 'I t' t 'I e _....,.4 4 i l t i-p i 1 _u..-...-. p i i 2 i p. 1 7 7 7 I j i t j } I l I i 1 e I i .~.. ..__4' .__.4.. .,I ) l { { t _t_ i
'I d. Suspended Solids (Figures B.25-32) Figures B.25 through B.32 present the concentrations of suspended solids .I (s/s) found in the reactor coolant during the months of August 1979 through March 1980. The data indicates that for the period 08/01/79 to 11/11/79 (Figures B.25, B.26, B.27 and B.28) the levels were well within the CE and site specific guidelines of a 500 ppb maximum for nonnal operation. Values obtained were generally less than 25 ppb. On 11/08/78 the sampling frequency was increased from weekly to daily. Except for spikes attributable to plant power transients, suspended I solids remained low (average s50 ppb) until early December (Figure B.29). At this time, levels increased and became erratic, ranging from 100 to I 500 ppb. These increases were attributed to the spalling of crud off the core, apparentiv as a result of chemistry actions taken in early November. Core dp began to rise during the second week of December, possibly as a consequence of an increase in the roughness of the remaining core crud deposits due to spalling. Concurrently, the reactivity and power distribution anomalies appeared to recede, as discussed on Section III. The very large spike of 1/10/80 followed an inadvertent over-addition of hydrazine, and is discussed in Section IV.B.2.b. The addition of hydrogen peroxide to the RCS during cold shutdown on 1/27 I produced a large increase on suspended solids, as expected. The hydrogen perioxide treatment is further discussed in Section IV.B.2.d. I I
I I
I I 80
)M M M M M M M M M M M M M M M M M M M 1 ( ( ( ( iIGURE B.25 900 .- ~ I SECTION-IV.B-800 [_ _ _.. _ _.. . SUSPENDED -SOL-IOS - 08/01 - 8/31/1979 .-...-..u.. l 700 l i 600 4 4 ..E - _. - =. 4 m 500 a3 a. _.._2..._. b .1P .._1. -. s em 400 300 t l H_.._._......y l .. 1 i 200 i_..._... ___2____. 4 4 I ~ i j I t }. 6 4 l 100 I i n g 3 g 3 s e a._-+-1 } l..%- [ .a--. i i i 1 -- i i i i i .i i .p i I,. - ... l,.... u 30, 4 ,., i, y-- e 'N s = * - ~.. I
l l m M M M M M M M M M M M M M M M M M M ( .. ( ( ( ( 900 FIGURE B.26 SECTION IV.B 800 [ SUSPENDED SOLIDS 9/01 - 09/30/1979 700 ,I 600 l J J 500
o.
m N b. + l l 400 t L f 4j F. i 30 l i 4 _L. _._i_ _. ;__ _... ._.u.___ .a { i h f i t i r_., I 1 l l l 9 { { i ,e -i - ---v- ,-.... - -.. - - +. - - ~ - c. 6 i i 100 . au = =. _ _. _. ~... i ..*.---------m'------ -+- i . A' t. ,..I i ,I l.. .. + l g ? 6 f. i c _.a i i I { l l t l l i .._l' .f . j z ..j ...p _ _.. q.. __._.._I I: I I I I i I* ,I
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( ( ( l. FIGURE B.27 900 1 SECTION IV.B 800 SUSPENDED-SOLIDS-10/01 - 10/31/1979 I ( s d e i !g 500 1 Q-4 e_ ..._a.__-- ..~ a. 400 I t I 4 ,_._-e ...F_.4.--.. .. - _...... ~. t .= g Q00 .. - _u I t .b b _-w-m._....m..--.eh, e .-_e. a l. t 200 i 4 I r f 7 = g. 3 100 I i _j p_. -j_.. + ___2 m \\ l t i i [ i ._ m.. +_.y q.. p.m.J. ] g
7. j iIg _g
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l ( ..( ( ( ( u FIGURE B.28 900 SECTION IV.B 800 SUSPENDED SOLIDS-11/01 - 11/30/1979 700 --=~ 1 i 500 @_1 . g_ _. m 1 A g .. _ a.
== +. 1 j 7_.._. .-n-_._. 1 i 303 l 1 ) _-.._-J J l 200 --_-+7---r---- I I ._ a. .._.-.--,..._k~._-. _-.----l- + -.. - - + - I l 100 = _ _ _.. ._.-.______-r------ .k ..j.. .._.7_ l I I i J _____e. _ _ _ _ _ _ __ 1 _.1__ -_4 k l + l ., -.._. _ J._ 2 f I, I l-1 It I-t i I i 1 I - .j t j I I! I I ^ u n i I I I I I s i i u a i n_ _ __m'
e e m e m M M M M M M M M M M M M W(W i .. ( ( ( ( FIGURE B.29 900 SECTION IV.B 800 O_ SUSPENDED SOLIDS 12/01 - 12/31/1979 ] i 700 \\ 600 1 e, 500 m a m w D l f@@ 'i \\ 4 300 J 200 l ) .. _ __-.._a.-_-.. ~. - -. - -.. - +.. - - - + 4. l 1 i 5 e i 100 - - + ._y__- i i .i l I i t i i I 1 i t . < 10, .i -i-t i i, t i i i i ie i i 's i i i i'i e i ii 's i t i 6 'n ! i' i i: i: i e i! 1
M M M M WB m W M M M M M M M EB( W m( m m __ g g v.. a w, ( i 900 .FI iURE B.30 I SECTION IV. B -- .800 -SUSPENDED-SOL-IDS : , - --- i-- 01/01 - 01/31/1980-i m. .-__...__d_..- i 700 s. a. i .600 -l l j i ..i { i j un .. am=. .- l_.. f s j a. .y_..i___y.___._.__..__,-... . ~. I i f 1 I 400 1 i i f f e. 1_ - ~ _ _ [ .i l. l e. 300 .-.- _t_. i J i y
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I I e. Hydrogen (FiguresB.33-40) Examination of Figures B.33 through B.40 illustrate the following points: (1) During the period 08/01/79 to 11/1/79 hydrogen in the RCS was controlled within the guidelines of both CE and site specific specifications (Reference Table IV.A.1). I.1 samples obtained during this period were in the range of 10-50 cc/kg. Note that the analysis method for RCS i I hydrogen is perfonned utilizing VCT vapor phase hydrogen concentration. (2) Subsequently the hydrogen concentration in the RCS was increased to a nominal range of 50-80 cc/kg. This modification to the chemistry program was prompted by a CE recomendation to increase RCS hydrogen inventory. I I I I lI I lI I l I e .9
m W W M M M M M M M M M M M M M W W M i ( ( ( ( ( 4 FIGURE B.33 l 80 _. _.. _ _ SECT; ION! VIi B. _. _. _. _ _.. _.. i 70 08/0L _. 08231/1975L. -... i l i l 60 VCT CALCULATED + HOT LEG j f 4_ _ i_._4...___;.-........_-... i 50 i i .j_.._..__. 1 1 c -.. _ .Q__ 7__._.__.-.._.... _. .;. __Q-.___ ;._._._p l i 40 i t t ] . y... ..._;._____..____.-4..
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I e M(m m m M M M m W W W W M M M M M M l ( ( ( ( FIGURE B.36 80~ '" SECTIDN IV.B ~~ ~ .-._.._.=-._2__ HYDROGEN ..70 . _ _.. __ q.. 1 1 2 1i. - L1/3041979 _.. i 4 I 60 2 i i. . _._4 SO i. _a .4 __.+. e .. g.. v._. .i_ ..r.._. l 40l (. { l- _._._-.__-u-- u i i i 7 1 i l ... j .. _ _g 1_ l 30 + l-i t- ,_....'..__7_... ! __ _. _._ VCT. CALCULAT.ED_. i 4 i i _..._....__.,.._f_._t _.i....;... _. I ..a_ .J i l I 2@ l ' ~ ' ~ ,_. 3._
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M M M M M M M M M M M M M M W M M M M ( ( ( ( ( l 3 FIGURE B.37 OO SECTIONlIV.B. .. + -. _.. l HYDROGEN +_..... +.._12/01,[12f31f1979 -. 70: f.._.. 7 _._]l__._ '. _ 60 g } 1 I. . V I I 50 L ._-.i___ u> ~ ~~ i VCT CALCULATED a HOT LEG f. j J i a i .... _ Q l' -.., ~ I { _-....__Q_. i U I i l t i l a li l ( ~ t i 1 i _.1. _L.__ ____! _ ) i 30 i l i .)._. I 3 l t I 1 i 20' i i i i i i ] i__. l 4 1 j t _.w 1 3 3 .i._._.L__. f f I r__ l f i .L ... _.9_. l _i.10 i ___._.i 4 t i i 4 ..{. l i '_.. _. _. +... ._L
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M M e M M M M M M e M eM M e W M M W ( ( ( g ( j FIGURE B.40 80 SECT; ION IV.B .___._._t.4.._.. YOROG N. i 4, 70 . -.___- _ 03/B .=._03/ 1/1980 i . p. : _._....... 1 .[ 60 VCT CALCULATED -t- _._...L.. .. HOT-LEG 50 1 I i _-....._..a.._.-._. s .t i
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I f. Oxygen (Figures B.41-48) A detailed study of Figures B.41 through B.48 generate the following points of interest: (1) RCS oxygen concentrations under nomal operating conditions were at all times within the CE and site specific guidelines (Reference Table IV. A.1). A nominal value for oxygen data points was 410 ppb. (2) In early November 1979, plant staff routinely analyzed the avocan concentration in the VCT (based upon a chr.rging pu acnarge sample point). Although not recomended by by Reference 1 this action was prompted by a subsequent CE recommendation to investigate sources of oxygen ingress to the RCS. Nominal values for VCT oxygen were less than 100 ppb. However, on several occasions (i.e. December 20,1979,800 ppb) there were significant increases in exygen values. Sources of oxygen ingress were determined to be via the resin transfer I
ystem and from partial aeration during storage of the nomally deaerated makeup water. Oxygen ingress to the RCS is discussed in Section IV.B.2.c.
(3) In late December hydrazine injection to the CVCS was established as a nomal operation. The purpose for the hydrazine addition was to compensate for oxygen concentrations in the RCS makeup water due to air absorption in the demineralized water storage tank. Pursuant to a CE recomenda-tion hydrazine was injected at a rate and concentration sufficient to establish an approximately 10:1 hydrazine to oxygen ratio. The ratio was later modified to 5:1 in response to subsequent CE recomendations. Further discussion of the I hydrazine/ oxygen congntration is contained in Section IV.B.2.b.
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W m W m e e m Ge m e m an a m e e e a m ( ( ( FIGURE B.42 0.90 i t t l SECTION--IV.B '-~ -~~ j 0.80 OXYGEN /HYDRAZINEr - -- ~ ~ - ~~ ~ - 09/01 - 09/30/1979 1 O. 0 1 .__..2-__...._.._. i i 2.60 -t n 3 m. i j t I - 0.50 o a l A i 1 .-.-.-.--_g.-.---,---.. i t [ e .---+----~~5--- 9-- . -. -. - - - -. ~ ---e . ~ - -.. - -~ l ~~ I f { l l I ....a..--.-r. s...+_.. _a 0.30 l _. : _ _...i_. _ _ I -- _. i i j _..____.-.__u._; a-l I I l. y l i O.20 ..,i _. i .j -p 4 j. i i i .i i i t i g. --.- Q. } 0 } t i } i I ._.1...__..- -_.-.__a i 4 i i - ...t.... .t... 'l i i-i.. i i I i 4 .1 ,_i,J 1 I l. ,,{_,_,n,,_,,, ;,,;,,_. .?._. I.. k. l .I l e . ~ r --*- r n.. rt _a... g_ _ _.. _g1"S ;_. ! j_ L 40.01:i i :- i -e .-r r.. .t. a .r r .r r .r 1 -r .. 4 4
W(W . W W W W W W W W W W W W (W W m 3 -- ( ( ( 4 i 1 i ~~ FIGURE B.43 0.90 1 4 SECTION --IV. B - -- 0.80 OXYGEN /HYDRAZINE- -- " --- - ---- - - 10/01 - 10/31/1979 l 0.70 N 0.60 .= i .i __. 9* i I ~, 0 50 a. c b i a.. u.--_. )
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em W W m Eus e m W W W W m m m m I j ..( ( ( ( l ^ l FIGURE B.44 0.90. 4 1 SECT-ION -IV. B - l 80 -OX-YGEN/HYDRAZ-INE-i 11/01 - 11V30/1979 . _. _ _.. _ i l 5 0.70 . -..w. ..e.e.._.. 9-%. 4 .{ j Se.b2._. HYDRAZINE i 4 j _..._.4._.I._.._..._.f.. t j i 0.50 Z o a. - -. a -. 2 t N .. _ - ~ - - - - -.. - i g j J.- ? .} t p .}-.
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4 m W m m m m m m M ( ..( ( ( ( FIGURE B.45 O.90 -SECT-ION-iV. B i j 0.80 OXYGEN /HYDRAZINE-12/01:- 12/31/1979 1 -...___...__._,_.--._=1 i, i O.70 4 i 1 l g _==._ __ 'g,. e j g. i
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W M,, M m' M M m W W W W W W W 4(l ( 1( ( ( i 1, t FIGURE B.46 2.90 4 ggg7. gg.. pjg._.. I i 0.80 ..__..._.--i -OX-YGEN5YDRh2INE I B1/Bli- 01/S:llB81 5 l__ O.70 .._4_... L l HYDRAZINE I l l . L __. B. 60._. )' i i
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i m M M M M W. M M M M M M M i e(m .( ( ( ( ( FIGURE B.47 B. 90 ...- - SE :-t ' O N - I % E - - i 0.80 - rOXYGENiHYDRAZ-INE- - l 02/01-02/29/1980 t i 0.70 1 i i { 0.60 i ^ l HYDRAZINE-i i I . i_. 4 I j , 9. 5 0 _.. a..._ c W L E + i i t i _i.. -._I + l, i e .i i 0.40 l.. ;.. \\ 'l ._..._.u_._.. ..a 't_ J )1 f' 8 + l 0.30 ..... -.. _., 'i. I. i I 8 m. _ a_ __d -. I. 1 a , -----+- - - - - - - + - - 1 ii i i i i
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.= _
4., - _L - l j i' l j p. ..' r - - ~ ~ ~ ' ^ ~ - ~ ~ t f 8.. .... _M I { I- - - - - - - - - - - - - - + - - - - - - * - - - =._7... __4 .. l . 4. 3_} 4 1 .i.._. '.. _;._. _4_ ' OXYGEN;VCT 4 e i, i,,
i t

,8 i 1 - - c i F \\ 1' s.._....g._.. _... _la l m -.g':,,i p k ap v,v-r r_. I ) j 0 01p i, 4.j.. _ = _. i i i :i i-i ii ii i ii i i: i i i i-i i i i i
m W W W W W m W W W W W W m' W W W W ( ..( ( ( ( FIGURE B.48 0.90 _. _...__.. _. SECT-I ON-I W 8 1 f -0XYGEN/NYDRAZINE - 0.80 +. 03/01'- 03/31/1980 .-_..-...-_..._L._..___...-... i B. 70 -. _._.J -._. _..- _ i __ _1' i j l B. 60 -_. #..-. i i l t t i i i
i..
1 4
2. 50
_.m ._.a._ ......_...__._3 0 4._ a l ,f i I l l %l.: } t 3 ,,_ A_. _... -., L - -. L.. .L .L._ __s, _....... j I i 0.40 t i i i l i i l 1 t 3 j }. i .t. _.2 f j j i i I I 4 i
0. 30 - _.
._i 3 I 4 I I [ j I .i -y_._' p e OXiSEN-VGT-I -- -- -i
0. 20 -.4....
l !Jli i i i c , t i i y _.p. _ g ... i. _. _ _ __ q . [. .i 1 B.10 t %_V 1 i i i. } - t:. 7 =.5_ / \\ ja,iYDRAZINE. p. i 4 t... i i e u < o to.1,.,..a. l.,, s-r,' ' ",gpi.vW-f,.wd,mQ+p-.. Q,_-h,;w:_f,f.4-.I-.-+y.%,,4.,,l i -/~ - e, r 4 ,,. i i. l i _?- i 4
I I g. Iodine Activity (Figures B.49-64) Figures B.49 through B.64 depict iodine activity values obtained during the power distribution episode. Values obtained for the radio-nuclides Iodine-131 and Iodine-133, as well as the ratio of I-131 to I-133 showed normal variation with plant conditions. I q Fluctuations due to power transients and operation of the purification system were as expected. I I I lI I I I lI lI !I l 107 k,
._7.. l 1 i i i t u i i j -l l l, + I 4 4. 1 I i i. l 1 i i i I i e y .{ ..I'.._.. I is l i i 1 .p.
4. _.._. _.. ' _.. l.. _
e i
'y l
.l j g i (V) i ...N_ g, I% 2; i a 8 .; M
7. _. _.... g.
l.:- g, g3.. p._.. u. '-4 i l i i i l i . -..... 4..,,,I..h' .._ { - g)3' r-~ I I g3 I i .Z. l l,[i Z! i i i i .{. ]/ _/.. L. ; .. L.-- -. i 4 ) i i I I l l e t i j.__- j 3z .- 4.. . o.. [ i I i j :- t r
s i
.; L i i 1"- L i r I ,. O) pl . l.. .i-i I [ g3, i ts i j_.._ i_ . j.... 33 %s. i l$ . [., i \\ i i i ..X.L _4 . _.. _. 2_ m... y I
1
-l " M wm i \\ ZN l 1%s, j t-g g . _ _.__ _ _ p I* [ o i m_ H I 'y? .....2._. 7,, w ,,. " / l (f) G j... j L-I g a.. G) ' N "* s j .i. i t53 i ^ i _.. \\ .7 . 4.J i I I l 1 l 1 s . i.... j _ - t._..._4. -. _ i 1 7- _ g i !j I ..j..._,.. _~ s i s, I \\ i 1 i i I \\ r i g e i -t l t-I...,,1 s i t I ... t .t i.. 1 .i t ,1 ,I ,f i \\ I I i 33/3rf. I C) G) (N (O If) T OJ
==4 3 G (5) (53 (5) (53 G (53 CSI (51 108
e e m e e m m m m W m W W W W W m(e m ( g ( FIGURE B.50 0.09 SECTION IV.B IODINE-09/01 - 09/30/1979 0.08 .,',r O.27 f -,,/ s. .,I \\ 1 . 4 9.06 [ ..._f / _._-_L ---------- I OD'I NE/133 ----- - ,o i. ,s ,/ ) u l r;
0. 05 S..____..
_... -s ,'N ./ u ./ <. \\..... ..<' / N,' . i.... = s s ) R.3 i /-. \\
/
r 0.04 \\ . _ - + -... +-..7.-_. -. +. - I / l Y. i i i i .s. r j. i j 0.03 '/ a __
4. _ --. _ L _-...
t i, i i i 1_'
1. _.1 - _
.._...__....-.-.....-l--._ .-._. L. -__L__ _. _.- i i i i- + i i j 0.22 I .__Q.... . __ _..._ _ _.. _.. _. {._. l ._.._ l 3 q i 7_. _ t... 1' i t l i -t. L O. 21 .=__L.._.__ _-.,__._._..._.._4 a '- - -4 .--I INE-1 I l . I. # l-i i }. 4 (.. _ ; _ - 7 .L i ,.... I' -_,~.I.- _ i.__... ' o i i I 1' .n_ ._.t..._ .I I 1: I .I l' I I I I 'I I_ f 't Ii j i. - l .l. j _._ !'... - : 1 a .r t 'I I* m I I I I' I. . I. I I. I I I I I I I t l
l M M M M M M M M M M M M M M M M M M ( ( ( ..( ( i FIGUREB.51 0.09 1-. l SECTION IV.B IODINE 10/01 - 10/31/1979 0.28 i O.07 N s 'N.. 4 ._ i f,.. _. '\\ s S- / - 1
0. OS
_f .. /._ g _..____ _. /._... g.. IC DINE-1 3-s, -= / g 1 I ..s \\, ,/- \\, U ..\\ i f g,,, l u / / s ,f. _ ~ 0. 05 s.__ .s.. o \\ o t l Q \\, /'t _l' 's ? ) \\ \\ ~ j/ i 4 i
s i
l 0.04 .. c '.. -.. _/ .'i.-._. + L.._: L. -. p_.. _1._ _ ;... " L. ...__ J _. _.4.. _.,; l i } l .,i.,,/, i i i k _..g [ I I I ,I g ' I _.t .. _(:1... 0.03 .,. / t 1 -i l. _q q_.. . _._..q.. _._ _.. l i i 1
7...
j i I j 0.22 _ -.. [. _ _. _ _ _ / _. 44 q i_..y_...f l 1 [ 1 2 1 i o - __.._. _. _ g _ )J.. __ _ l I ! -..;_,..._.._L...._...._: ..._._p__. m 1 i . k. .i i. ' I O, 21 __.. j_.. _. __._.
IOkINE-13-h-d j
. k... -. - 1 .i. _.-..yi._,_ _ _4 ...,...'.j.-_.., .. 1. 2. - ;j. }.. a.:.. .._ } a. ..g.. j 'I I' l' I l' t t I I' I I I I I I l 3 't 1 I I l l l' ' ' I t-t "3 I' t'
e t

g_ '3' _ a __' _j,__ _ _ g _ .3 _ [ g I .l 1
ie e e m m m m m m m m m m m m M M M M ( ..( ( ( ( 4 - 1 B. B9 [ FIGURE B.52 i ei SECTION IV.B [' IODINE 1 11/01 - 11/30/1979 B. BB
f,
/ 8 3 I t .) B. B7 .I I t ,\\ l j. .. /, B. Be \\ i .. - _ _ _l. _. b
......g...-Ih INE-l as i,
( / i i l .,i i g. iu / - 0.05 .P._ f' 'g .j .l . _.f.,6 i l \\, l w j f-- l ~ t; / ( .,.._g._ m...._...; _. ..L n' h, li \\ O l 'o' .. _ _7._._,...,,n ~, g, g4 f _..,..i , / ,= s.. 1 .; I y \\ '. 3 \\.. W /o ....t_u L.4.__..._...:.____L.___._. i i g.. 8 I t 8 t t / \\,_._
0. 03
.. j. _.. . l. t ( . l.-. r-L.._l>I&e ~ fi_.. , _. _. - - - + / .t
0. 02
. / f. , /. A' I. s .i_..._ 1._ ] I 1 4 i 1 1 L y. -i .__.7_. l.... _ _ q _.. _ l 7___p_._,.._.._.. _ _ J i . i,. /_ _. 1 .o. 1 ... IODINE-1$1- . - - - l i ..s. i i i 0.01 _ \\,. 7__ _ ;_. _.. _. -i l .. t :. i.
1..
..] .}..4._ :_..__ 8 ? i i i I i i -4._.. t..._ l I ~ l t l _ _.. _ i.. l -
4.
t t t t 3 3
I I
tt. t I ..t. a a- .I f. .I I I I' t i I I I. I I-. t I I I i t t t* I I tI l' t-tt
m m W W W W W W m m m m M M
m. m M
M M ( ..( ( g ( ~- 1
9. 89 5_ d, FIGURE B.53
"/\\ SECTION IV.B IODINE-l S.88 jf \\.:., - 12/01 - 12/31/1979 '\\ J i 9.07 j i \\ (- i i I j 8- = 8. \\ 7 0.96. i \\ N ^ -IODINE-133 l ,'. N. l o; ". .) i! 1 i 0.05 M.', --(,.-...g L s m
i
,1 ,- i
j..
j ..{ -e i r u, A, ll _ 9.04 e - -t- - 7.. g _.l#..__ g \\ I 5 f-i N, 1 _p..._._ _; . 9 _.,.j _, _ % s 4' / _.._.._...__.__.q[__._f...__._%',_ _.. _. _.1 I i B. 03 i A: i. t /i y [ 7 _. _ _ #...._.... _.. \\.... /. % _.,/ }
~l -
,i i, j l ..\\. / j, ___i.'g !. ,5,' r s 1_ ~-l r i i-i-
t. -
- i, i {
8. 82.....
...i_.g 1 t ..._ r. j j gp: l r-i i. i I i g/ -I-r i i -i i ~; i i 0.01- ! I00INE -131---- ---- :--k -p-t . _.._. _.m._ _7 - - -l ._;...._._..._..__;.,i i 4 4....,._. a -~ i i i j i I 6 l 3 l >.--+-L-.-.. 1 P J ._....,g
m m m me M M M M M M M M M M M M M M ( __( ( ( ( l FIGURE B.54 0.09 SECTION IV.B IODINE OflYE1-01/31/1980'
0. 08 t.
1 1 l t B. B7 f i 1 8 \\ / fs, l 0.26 [ . l_ ______;,--I Od Ik-133 - --- --- - \\ s, g ,T s .... g. ; - .g. { 0.05 Q... _.
_}.... _.. 2.. f,
. /.. _.. _ _. \\, . 's.. i \\ u _a.___.. '\\ o i x-- u s i i f' L ....._4___.........-.. .-1--.- ..p.. ,.. 4_,?. ._.:-. - 3 _ -._... ...._y O. 04 j
4..
.,f...... i..,,V,- I i
0. OS t
\\, i,. g.. .-~._ -.._ -_- -. - 2 t i ... i _ i___k _.;_..__ _J j
8. 0 2...._.. __
i t i i 1 e t, - -l .1 l i i. i i j l 1 i i e __!_ '------I bOI NE-131 !
9. 01
_... _..._ p _.y...___g_u. _., -r - -- 1 {. .f. l..i i j. i j~ -.. }. _. f _.. .. -.,. p. _... [.. _;. _._ 1 _... . -. ;._, l . 7....... _.... _..__ .q_... l' L 7...-..
_ __t L i
I I ' I i
i i~ I f .I f I I i*f I I t-I 't I-t I I I I t t' I t i e a f 1
m em m em mm m M M M M M M M M M e(a se ..( ( ( I FIGURE B.55 B. 89 SECTION IW B IODINE ~
9. B8 t
o B. 87 E I I i t j B. B6 ..J- - ' IODINE-133 ? a l U i B. B5 u l ~ n I s i A .n O IJ t k ( .._u.._.. _.._. u i q I I I ' i ; 3 e ._....,____7.._. i j-l i i! ll 1 l' ..L.__.-_ _1 i 1 i e ./_..a i q:, i sip,_l1 _,- p,
4..gl ;
a i:. j... i t .J. g.i I lt. [_j ' . Ii,_j j. .l l B. 02 _ 4,_ _ _ __ __y . + _ _.. i ,2 , i. t i .._ _ q._ _ 9_ __,(. ..;.. i
,i
.L j ., f., _ .p 3 i 8 Il 8 } i i g __. _. ?,i i j, .l i .._.a. 4 i 3
g. gi
-..g. _ _ _ _. _ _.. -- i -- 4.- .._a.L - . _ _... _. a.. t_ . m. r.. i r l i i
.i r
J l 4nDINE ' 31 i J. 1 ! ' i u....i.. + i. i 1 n .a i .f ,g g g g, ~
e ee mm mm W W W M M M M M M M M E l ..( ( ( ( i
8. 09 FIGURE B.56 I
SECTION IV.B i IODINE
8. es
~~ 03'8 - 03/31/1980
0. 07
~ 1\\ i I i
s. s 1
l
0. OS
-- IODINQ-1S3 - I L l4 t 1 o 1 i 0.05 o e i i i ~ .s. t 8 8 ,r, _..... _.. _ _ _..... _ i u t i
l [.
i t a.l ,4, l: i t.J i .y. 1 0.04 J: o ,I _.,r, 1_ 'l i .i ,i '[! 7 ,i ,_/.$ [', ) k ' i.,. _._.'.4..,....._,.'_......,,.. sf is 0.03 7 i, i i \\__l '/ / i, 1 i ,i 8 ,s .i( 1 I ..,i F i f ,8 _.4s _ ._.3_. i 1 .,Y I I i 0.02 i ! _., l,.,'._.. _ _ i..,,. ___0, ", t ~ i l ! i i f l I ..._.__ _,_ g y l_. _._.. _ _._. t i .i
0. 01
[ NE-131---4---i-----,I p.. j. +.. _. __ . p.__j -.q .. i.. .i. , i, ,4 ,,, i, ,i, L , i, , i, ,., i, - x-
W W W M M M M M M M M M M M M M W.M M ( .. ( ( ( ( r' F GURE B.57 g, gg j SECTION IV.8-B. 80 IODINE RATIO-E18/01 - 08/31/1979 1 B. 70 \\ t l l 0.60 . ___ u. .._ p.. l. ._.. x.. l 0.50 Ch a. ,.. i. ......_.___ J..._.. k.__ _4._.. 0.40 .g -__.______.7.__. j { i g, I r _.._e..____.__-._ -t ~.. -. 4 i. i l 0.30 m-t i t r 1 .L g, j ~ i I i ~ ~ ~ I~ ~~ 0.20 .-___m ..____..___._____e _ _ _ _. ~._ __f 7 4._. }. g. j- .F j 3 3 4-_j -..,- L .i 4 ._._ _ _ - --- - l __ a. f . 7 i a I I I i j i
4.. a 7 --.
....._..__..___.__.__-._I 0= 10 .p_..__ . _.d____ ___ ; j l. l. i. .__;_..___.__.l_____..__p._. .._.. l. a --t- -- b ' t i. i.- _ _ _ _ _ _ _. }. _ _ _ _.... _ _.. { __..7.. .m.. l l, __7.. l l i-I .j. _ - _ ..{.. _ f. __. _. l g 4 ..j. 4 1 I I-1 I I, I I I I i I II I I i'I iiiii1 'I t' i
l I ' I I
t t t t -l l i i 1 1
e mM M M M M W W W M M M M M M W W W i i ( ..( ( ( ( ~' ~~ FIGURE B.58 0.90 SECTIGN -IV.8 l IODINE RATIO -r l 0.80 j 09/01 - 09/30/1979 i I O 70 l 4 i 0.60 1 j 8 j = O. 50 I l L ~ 7 _.. t - '-^# i O.40 t-i j l 4 . a I t j 0.30 f p j i r 8.20 p._. -_...._. 9 i l t f-f' i- ] l + i 1 I l l 6 I i. .i. i r 8.10 i i J l. 1 j . i... v I l 1 t __ i j .._ g _. ; y_; l -- i - - - - - - - ~ - - - - -+ i-:--t- -f-- i- .t'- - - - - - r 2 I !I I-I e a t i n' I I I t'I i t a t. t a't i e a a ei n a i l 1 d
m M M M M M M M M M M M M M M M M M M ( .( ( ( ( FIGURE 8.59
0. 90 SECTION IV.8:
8.80 I OD I NE-RAT I O ' ---- : -- -- ------ 10/01 - 10/31/1979 0.70 I 1, 0.60 = 4 r _. f.. m. _ i i i ~ 0. 50 .4 1 i 1 .._.4. .... _ _.._i.._.._. _... .._.J_ l
0. 40 t
l l-g. 2 i, 0.30 __.__.__m._. _..g l. a 'I i j .._..j.~..-... g..._ M, __.4. ..--w_.-. 1 ) i 0. 2 0..... _ _ i l t _ m __. l l i t. ..j 4 5 t .i_...._.___._____ i 3 .{ r 0.10 I 4 j-i l i i .4 . _..;_ : _}. i i ....a. l _ -_. f ' .__t_._.2__.4._._.._.a.. j I } }. t ~ l- 'l l f I -._. _.7 ,,'6 .j. 5
3. _.:-le I:
I I I t I t-I t t t t i e a a 3 a a a: l e a si : nI i
N(N M N H H H M M M N N m N N N N M m ( ( FIGURE B 60 i 0.90 SECTION IV.B-O. 80 [ IODINE RATIO-- 11/01 - 11/30/1979 i ^ 0.70 . -.d _ _. -_ __... _i. _ _ m _ _ I --. 2 _ = -. - -.. O 60 _ I i W pe .ww g.., e .-- -+. .-?----+ j r. t U. kB .p \\ - = - - - - -. - - - - -. - - i t _____.-.L. ____.a. 1 i i i ,9., s.~...~e-
~
.j j f i j t { 0, 20 ._ i i p -[.__m.__4-_- i l 4 j i i i t-- i i j t 9 4- [ -j + I g* I g + ---i 9 + i i - -.. _.- - F-t-~ __ i [.. l i . f. ...L.- i _.7_ { } r - -- L- - + - - - L-l j !n '

a---

-- h i-I - --. -- - - A-r -- F -- t-r---- n'.. _ ei i _--.'t I I 's ! i I I I I I I t-1 f I I I I l s t t I a l iI i 1 I f 2 I I
m(mmmm m 88 m m M N N M N N N N M m -( ( 1 ( (
0. 90 FIGURE B.61 SECTION IV.B:
~ ~ ~~ ~ B. 80 I O D I N E R A T I O ! - " - ------ - ~~- 1' 12/01 - 12/31/1979 i 4 I l 2.70 i a I 0.60 i i 4 I M 0. 5B -.? o j
== ] i 0.40 . _ _. _ _. _ _ i _ _1_. i t 4 t t i 4_ _ -.... - -. .J.._- _.-,_._..,_N..,.; e e .._..- _-_._.i-_. - _. ..-~4..___+..__y -e... - +. - w._.ew.~._oa_.. m-4 e .%.g ' _ _q 2 ^ 0.20 r b j l i i -d [ l r 2 j i i ) i ?- tI-I i t l-f -i j -.,,, _ - _ _. _. _ _.~ i i 4 r 7 p . p. B.10 _.:._ _.a.. _.I.. 2 _ _p _. j.. _ ,_. _._ m.4. ;_.l.__ j. 4_ ..L. . m.y - 4 i i. f, t .o i .i. i .o t i. i j j
j...-.. u. -._. {
t l i . f. ..p..__.... _.g._ .._2_. ... :. u_ _p. 4 _.._.. 4._ _ 2_ _ :2.. 'a n 2 !-:_.t _'s .. t.
in. it
_1 -.. n .1__ i _ a 2.n i L..a. ..n i ..-.t_ir_s_. L a __ s....i.. 1 _. 1 I
m n H H H M M N M M M N N M M N M N M ( --( ( ( ( 1 FIGURE B.62 1, 0.90 SECTION IV.B B. 80 IODINE RATIO- -- -- " - ----J 01/01 - 01/31/1980' i e l B. 70 I i 1 2. 0.60_ l l j j 1 1 ~ 0. 50 m. e._ _.... _.. ~ p j i ... _ _ _. + - _.. .____r_.+.__._.=_._.._._. O.40 . +. _. i t 1 r -- - -' - - -- r --* - - -- - I + -..i i 4 i i ..._...e. __..__p_ .L t i 1 6 1 1 i 0.30 i i l i i .i. i .k .f __.i. l.-? l
== 0.20 -- -- i l j i t i _i. 4 i } .p j._ _. { 9 I l 1 t 8 i f 4 { ~ { l =.. t .t. .l..... _ 4._... 2. 1 s i B.10 i i i .. _ - _ _ _. _ ~.. p.. + 1* f .. -,.i.- G_., l I l i i t F. ._sm-t i 1
I I
I i I I I ...__ I, p._...: _-. .. +!. _. ..p. 3. i-.. _. - 3 ,,,1 I I' t 'I I 1. t I I I t !t i: 'l 't . - t ' ' t-t .3 i t t t t 3 t i t L i i l
- }^ " j - ~ ]-~ ~ ~ '] - l j. t l ..q._..4.. j-l ]", a.. I i i l -r I 1 t ....-.r...-.-._'.- v
3..
)- m i i {- 1 f L 4 t i i l l. ..i. ..i w oc l 4....._ f l. i ' Iw a 1 p 4 c i + M I a W 1. .L, I I' i i i t l I 4 { 4.,,, f.. j.. 4 _.d. _. - i i l j { I l-j i. . _h .. }i I i l w i { 1, i, j.. .. l. .4.. - i 3 6 7. -. j.._. a._.. I I i i I I i I - - - - * - - ~ ~ * ' ' - * ' * * * ~* * - - 7 "1 - .t'-- -t - - - - f - -- {t o - l l i i i j l 8 Lmt m; i i 4- --- + . l an I m .O. N,' } } Fm' ..L._ i I I H <N! I Q:: N, i i Z N i J..._ .. L ..i e i O IJ.l G l l-Iw s< z i b, - l 6-4 ~ -v ss I t, t i til .O, g* .i. -.. _. i.....; _... - ;._- I m l .p. 4 g 1 i N m j .a j. .+ E 1 ._.i..._ 3 l 8 i i l i i i i!_ 2 e t i: t i i j t } I q.. _. .. p.p g. 4 6 j j. j . = l l l i l I_ v.......,....,....,........,....,. !. c;..L J.,, i --.p., c .1 -l..l-I i i 1. I v S E S S S S S S S --I -
I G
00 (N (O 10 v (T) N .-e i i . =. J. - m m m m m s s a m i !g 122 l ,E 1 I l
e M(M 35 M
M M M M yM M M .M M. M M (M M ( l 0.90 ._ _ 8 "_ i 4 i SECTION IV.B 0.80 [_ _= I ODI NE RAT I O ---- -- H --J 03/01 - 03/31/1980 2.70 ' ~ - i _. ~ _ _.._ 0.60 _.._..___1....__-__... 4 l _ __ _... _ j 1 1 ,1, ~ 0. 50 _..._ .. _ _ _ _ ~ _.... i ru j i j i ? i i } O.30 i I j i _L_ _t.__ _ p _._. _ ,.__;__...a. t i-i i l 0.20 '_.__a'_ I. i a i t i i y i i I f f, " 6 t _... _.___ 3_._ { . i. i. l l. l. _} h. e .<n ..._....l._ a.. s i .*m. l I I I f_ ,.__,I _ _. f _....., _ _ : _. i,... .. u.,.._ :._...,.... i l k 4 .t } j l_ f I I I I
f I'
'l I 3 I I f I' I k I 'l' t' f 'l II i t iI l' t i I t-3 !I ll t t t i
I j h. Amonia (Figures B.65-72) Examination of data regarding RCS ammonia concentration generates the following observations: (1) Prior to the injection of hydrazine to the CVCS i via RCS makeup water, the RCS amonia concentration was maintained to within the CE recommended level of 500 ppb (Table IV. A.1). Nominal values were 4100 ppb. (2) Subsequent to the hydrazine injections, RCS ammonia concentratians were a function of the injection levels and ion exchanger media condition. Those instances of excessive RCS ammonia concentrations were a result of increased hydrazine injection concentrations (i.e. January 10, 1980, 14 ppm). I I .I I I O I '5 .I ) 124
l m m m m q M M M M M M H H M M M M I t ( ( 1i ( ( 4 t 4 FIGURE B.65 i 1 i j 17 i SECTION IV. B - - - i i i-16 L I --AMMONIA -t i 08/81 - 8/31/1979 I - - - - - - - - - - = - - - - - - - r 15 u. _ _. j 1 i i i 14 i = _ - - _ _.. - _.. - - i am l 13 t 'i .L.._..__....-. i 12 t i
== 4 11 i i } am f i s 1g I ~ i I . a -...__ m E i l 9...L i L _..._...._.4_..__.__ ~ ~ t + 8 8 g ..t_._.....___...__. i . k' ...I .I. I j g I 7 j i l l i j. 6 1 l i 5 [ t j I i j 1 j _... ; i 4 i. i t t ~~ i .a -i t l I I ___.{ ..l.. j 3 j .I i __ I i ..I.. I i j j i
8..
2 8 1 .. q i 4. I i ...1._.., .!..,._..t..._....... T o e I 1
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I I 2. Evaluations and Actions a. Reactor Coolant System Lithium Concentration As discussed previously, DCS lithium concentration is normally I maintained at less than 1.0 ppm. As a result of unexpected increases on axial shape index, radial peaking factors, reactor vessel I differential pressure and abnomal power distributions, on 11/08/79 CE reco':.nended that RCS lithium concentration be increased to a maximum of 2.2 ppm (Reference 6). The resson for the recommendation was to increase crud solubility in an attempt to transfer it from core surfaces. As evidenced from examination of the lithium plots, plant staff implemented the recommendation as part of near term corrective action. Lithium concentration in the RCS remained at the I prescribed level until CE's recommendation of 03/07/80 to reduce the chemical parameters to original specifications (Reference 7). It should be noted that on several occasions RCS lithium concentrations drifted slightly above the lithium concentration guideline. These deviations were caused by nomal chemistry control problems associated with plant operation and were not considered significant. For instance, on 03/01/80, an aberrant episode in lithium concentration occurred (Reference 8) over a three day period. The maximum lithium concentration observed was 2.4 ppm at 2000 hrs. on 03/04/80 for a period of less than 10 hcurs. The nominal lithium range of (1.8-2.2) was exceeded for i approximately 30 hours. The apparent cause of the perturbation was the removal of an ion exchanger from service following a planned power transient. Lithium hydroxide monohydrate (liOH.H 0) additions to the 2 RCS were not coordinated with the purification system lineup. As a l result, obersved lithium concentrations was in excess of anticipated values. Investigation into the cause of the anomaly resulted in the ion exchanger being placed in service with subsequent RCS lithium concentration reduced to within the nominal operating band. The incident is displayed I in detail in Figure IV.B.2.a.1. No significant effects on the power anomaly were observed due to the minor excursions from normal lithium concentrations experienced during this and associated incidents. lI l3 m
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I b. Hydrazine Addition to Reactor Coolant System Based on a concern for potential air ingress into the RCS on 12/11/79, CE recomended that hydrazine be added to the VCT in quantities which were based on analysis of oxygen in the makeup water (Reference 9). After an evaluation of the recomendation to insure that there would be no effect on overali RCS chemistry, plant staff initiated continuous injection of hydrazine to the RC makeup pump discharge during normal operation. The hydrazine was injected at a rate and concentration that would provide an excess of hydrazine to the RCS. Plant staff was concerned that hydrazine additions would significantly increase RCS ammonia concentrations. Examination of Figures B.65 through B.72 illustrates that baseline ammonia level in the RCS increased when hydrazine was injected into the makeup water. On several occasions, excessive levels of hydrazine in the RC makeup resulted in significant increases in RCS amonia and conductivity levels. The initial incident occurred on 1/10/80 and was accompanied by a rapid decrease in core differential pressure. The event was caused by the inadvertent addition of 15 gallons of 35 wt% hydrazine to the chemical addition metering tank. Hydrazine injection to the RCS makeup occurred from 2000 on 1/9/80 to 0730 on 1/10/80, when the injection was tenninated and an investigation conducted. Sampling at the charging pump discharge she.ved a hydrazine level of 3.2 ppm compared to a nominal value of approximately 300 ppb. The excessive I amonia level which resulted from hydrazine decomposition caused release of lithium from the in-service ion exchanger due to an upset in the equilibrium concentration. I I nS
I I Lithium increased to approximately 3.8 ppm as a direct result of this incident (Reference 10). It was postulated by CE that the cause of the core differential pressure drop was due to'the amonia forcing lithium from the resin bed. The Sudden high I lithium concentration caused crud removal from the core. Subsequent hydrazine levels outside the nominal band have been observed in the CVCS as a result of operational difficulties with ine temporary injection system. I I I I I I I 'I I I = I I I 13e
I I c. Oyygen Ingress to Reactor Coolant System As a result of concerns regarding the introduction of air into the RCS via the RC makeup water the following modifications to chemistry procedures were initiated: (1) VCT hydrogen addition rates were recorded and monitored to determine if consumption was excessive and samples were taken to establish a baseline for oxygen entering the RCS througa the purification system under nonnal conditions. (2) Initial quantification of oxygen ingress was accomplished by perfonning daily oxygen analysis downstream of the charging pumps. These analyses were performed at the following conditions during normal power operations: (a) Just prior to adding makeup to the VCT; at the low extreme of the nonnal operating band. (b) Within 15-30 minutes after adding makeup to the VCT; l at the high extreme of the nonnal operating band. (3) If oxygen at the charging pump discharge was measured at greater than 5 ppb, samples were taken at the following locations to detennine possible sources of air ingress: (a) Charging pump suction (b) Volume control tank (VCT) (c) Reactor (primary) water storage tank (d) Letdown system ion exchanger inlet and outlet ! I !I 137
I I In addition, the following modifications to operating procedures and hardware were made to prevent oxygen ingress from the resin transfer system to minimize air ingress from the RC makeup water and to increase solubility of crud in the RCS. (1) Hydrazine leaving the VCT was controlled to stoichiometric quantities based on analysis of 0 in the makeup water entering 2 the VCT. (2) Hydrogen overpressure in the VCT was increased to a level sufficient to increase H dissolved in the RCS to 40 cc/kg. 2 (3) Nitrogen instead of air was used to transfer resin. (4) Two leaking valves in the resin transfer system were repaired. (5) The leaking power operated relief valve was repaired. Evaluation of Figures B.41 through B.48 describing oxygen levels in the RCS and VCT reveals that the combined corrective action recomended by CE (References 12,13) and implemented by plant staff was effective in minimizing oxygen ingress. I I I I I I I E 138
I I d. Hydrogen Peroxide Treatment The hydrogen peroxide treatment, initiated on January 27, 1980, was very successful in returning core differential pressure back I to pre-episode levels. A complete and detailed documentation of the chemistry and radiochemistry aspects of the addition is contained in Appendix A. The following is a summary of the results of the tjdrogen peroxide treatment: 1. The hydrogen peroxide chemical treatement combined with the plant cold down/ heat up temperature shock reduced core differential pressure from 15.6 psi to the pre-episode value of 13.8 psi. 2. A total volume of 15.1 liters of hydrogen peroxide was added to the RCS in three separate injections. I 3. Increases in total Co-58 activity and suspended solids indicated the hydrogen peroxide treatment produced a significant crud release. I 4. Based on a comparison of data collected here with the results of an EPRI study, reactor core deposits appear to be the major source of activity released. I 5. Approximately 600 Curies of Co-58 was removed from the coolant during and following the hydrogen peroxide treatment. 6. Hydrogen peroxide additions did not cause unexpected changes I in shutdown radiation fields. I I I I I 139
I e. Reactor Coolant System Crud Samples As part of the assessment of the power distribution episode, two samples of circulating crud were taken from the reactor coolant and submitted to CE's Nuclear Laboratory for analyses. The following is a summary of analyses perfonned and results obtained: E Sample #1 was taken on December 6, 1979 near the peak of the core physics anomaly, with the plant at 70% power. It was hoped that the sample would provide clues as to the cause of the anomaly. Sample #2 was taken on January 28, 1980, with the plant at cold shutdown, during a crud burst generated by the addition of hydrogen peroxide. This sample was taken to satisfy an NRC request for infonnation on the composition of crud released due to hydrogen peroxide. I The following analyses were perfonned on the samples: visual examination and (for Sample #2) drying and weighing mounting for X-Ray fluorescence y - spectroscopy (for Sample #1) X-Ray fluorescence to determine elemental composition (atomic number 12 - magnesium) X-Ray diffraction to detennine crystalline compounds for (Sample #1) digestion in oxidizing acids to provide liquid solution for atomic absorption and emission spectroscopy elemental analyses by atomic absorption - Sample #1: Li, Be, Na, Mg, Ca - Sample #2: Li, Na, Mg, Ca, Cr, Fe, Ni emission spectroscopy for boron 140
I I Sample #1 was found to be nickel-rich, with a substantial concentration of nickel metal. The reactor coolant system had apparently been chemically reducing at the time the sample was taken. The overall composition was consistent with corrosion product release expected from the major system materials. Most of the materLI originally came from the steam generator tubing (Inconel-600). The immediate source of the crud (in-core or out-of-core surfaces) could not be established. Nothing was found which could be related to the anomaly. Sample #2 contained iron and nickel in about equal proportions. This composition was consistent with observations that peroxide additions favor the dissolution of nickel relative to iron oxides. The crud appeared to have been released from core surfaces. Nothing was found in either sample which would raise concerns l relative to accelerated corrosion of Tael cladding due to the deposition of these materials. I I I l I I I l
I I f. Modification to Chemistry Surveillance Program During the power distrubtion episode, periodic adjustments in the chemistry surveillance program were implemented. For the most part, these changes were prompted by recommendations from CE followed by evaluation by plant staff to assess impact on overall chemistry management prior to implementation. The following modifications to the routine chemistry surveillance program were instituted (Reference 16,17): (1) The following parameters are now analyzed in accordance with the predetermined sampling frequacies and the results recorded in a graphic form in order to reveal any trends that may develop. The parameters of interest are RCS oxygen and hydrogen concentra-tions, and the Iodine 131/133 ratio. (2) Hydrogen inventory requirements in the primary system are I recorded / graphed / evaluated. Thir information is displayed in a graphic fcnn in conjunction with Item (1) above. (3) Volume Control Tank (VCT) hydrogen consumption rates are recorded / graphed / reviewed to determine if excessive consumption is taking place. (4) A baseline level for oxygen concentration in the effluent of the RCS ion exchanger's under normal operating conditions (steady state power--no abnonnal plant evolutions) was established. (5) 0xygen ingress into the RCS was quantified by performing an analysis on samples taken at the charging pump discharge. A daily sample must meet one of the following criteria: I I na
,I I - Sample obtained just prior to adding makeup to the VCT. (Low end of nonnal operating band). - Sample obtained within 15-30 minutes after adding makeup to the VCT. (High end of nonnal operating band). If this sample indicates a higher than expected oxygen concentration, then additional samples are taken at other potential air ingress points, e.g.: - Charging pump suction [ VCT { RCS makcup to the VCT - Reactor water storage tank - Purification system ion exchanger . I
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I I C. POST-EPIS0DE CHEMISTRY HISTORY I An examination of post-episode trends of significant chemistry parameters generates the following observations: (1) pH (Figure C.1) was controlled within the nomal pre-episode qu belines established by CENPD-28. (2) Conductivity (Figure C.2) was consistent with the concentration of chemical additives. New baseline level was increased above pre-episode concentration due to the presence of hydrazine in the RC makeup water. (3) Lithium (Figure C.3) was reduced to pre-episode levels of less than 1.0 ppm toward the end of March 1980. (4) Suspended solids (Figure C.4) was controlled to within pre-episode I levels less than 25 ppb and well within the guidelines of both CE and site specific guidelines of less than 500 ppb. (5) Hydrogen (Figure C.5) was controlled within the upper portion of the allowable band to ensure an adequate hydrogen inventory in the RCS. (6) 0xygen/Hydrazine (Figure C.6) Hydrazine was maintained well in excess of measured oxygen levels in accordance with CE guidelines. RCS oxygen values continued to remain within the pre-apisode recommended specifications. (7) Iodine 131/133 Activities (Figures C.7,8) Reflects no adverse I effect of the power distribution episode on fuel perfomance. (8) Ammonia (Figure C.9) is consistent with the concentration of hydrazine injected into the RCS. Observed levels were within the CE guidelines. I 144
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M M M M N N M M M M M M N m M N m m M ( ( ( ( ( FIGURE C.5 i ~ ~ ~' ~ . 80 S E C i J. O N',I V. n~~- ~ ~ ~ ~ ~~ ~~ ~-- ~ l HYDROGEN l ...__._ _ 04/01 ig4/.33/,1983 __ 70 -1 1 4 I ...... -. -.. _.,.... + 60 I i i l r
r i
_.__u_.,__..;_. i t M f l l IVCT CALCULATED ' HOT LEG . --.._. 7 _ i l g . -....... (3 40:- y .a l e j x_ u i i U i a r-i -i-l l y l I i i i~ -t 7 36 ~~ ~ ' 4 ..__-i..__..!- i -t d l f f f l I 20 l j i
i 4
~_ + t 1 i. l ...p j ..___..p _ _- _L.__. - y t I l } 4 i I i i. _u.. a . 10 i i ;. i F i o .]. . p- ..t-- i . ' -T - - ~ ~ ' - - 1 l i i a : e a-a. a .a in a s! ..s a " !'. -_ _ .._.'.L_.__. f..... _. ;._.. a. 1 t r i ' a l s. al. i . gn l 4 I j c. 4 t j g a s t-:n s n-a :n i t e a n. ) t I l.I I~ E! I. J, : .,l..
l'
.:i.. ..1 :..... m!!:.' i r- : r. t 3:-
!! i r-r r--
!n i-i i i l i 1
( ( '_ ( ( ( v. FIGURE C.6
9. 90
...SECTf0N-tV.C-3 i S.80 - -- r---t - -- OXYGENdHYDRA-ZINE' 04/01 -f04/30/1980 _...q
p. -_... _
t. ? i 0.70 j B. 6 9.._ M. - _t l l YDRAZ-E - I j. -.i i i l @ 0,50 --_+____-.____.__..___a._ ___.. _ _ _ _ q _ i l . L _._ i j I .-~ p -i q 0.40 t l p _ p _.. _4 l 7 1 j. j. j [
i..
j g i p..__ 4.. _.. _ _... _.. J .i 7-
i..
i t 0.30 J __. _ _ i i j 7 i I i i __ _ 4 __ _p y {.. _ j_..p .. _ g. j j
0. 20. _
j _ _ ;._.. __. i i -i c -- OXYG EN-VOT + - ----j .{ -..g g.._ .__p__:._____ ~ .p .g 9 j _.. _..... l. t i t..- t.. I 'I i ,.l..._._____ ) l i ? i ..__..._.p _ _... _ _. _ _. _... ; _ t.. 3 .j L t_; 1r). ..i l A _% r v ~ _ --- -a i i t t._ i s x. f = 1 4 i i i j
- '--- p "
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El i~l 3 ,3 g 3. -l' It3. 3' 1 3 : 3 3 3 g g a 3 g !g 3 g g 3 I + I t
m m m m m am an m an M M N M M N N M M M l i ( ( ( ( ..i, FIGURE C.7 0.09 g SECTION IV.C gogggg 04/01 04/30/1980 j O.28 i IL .t j i
I._ ___
,8 i, i I} j i 'i d
0. 07 \\,
_.____.m.__._.._... i _. i, i e, s ,s \\ i, .j! , i,. g l I t I i, J' 0.06 d.. i.I.. _. j _ _ _ L. _.qiyc hgfg_g g3_ i -._a -- e i f1 t 1 j i j e !i i i .8 ..l ..l. i i i i t i, i t i si s, ._J . J... _.._ _ l .D.J._ _ -.. _ _._ _. 'J, G 0. 05 . L.. l l : i ~ o, i i l. s i 4 q '1 _q. _ f. . _.. ;,._ p ... -.. _.l ; 4 p_ _.q _.- 1-i i -4 h I: 1 f... i lr _. \\'._.. ~4 / i i g, 0.04 ._? _l' i g; j ' i (........ _ m.. i 1 i _d L..A,... _ i, / j s,'y _ .. 3 j ' j - ' _] j i i i j s -
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0.50 m
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0. 20
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m.. i
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m m-2- -*L ______-,e_ & '+9' / / TEST TARGET (MT-3) I i 1.0 gmna d a gg m m l,l hD bb l.8 'l.25 1.4 1.6 l 4 6" l i l b + 4 Md/,)e# $e>A#s v < w ,4, o x1.
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( ( g ( .. +. .n 4 1 1 FIGURE C.9 4 _.. _... _ - ~. 17 SECTION IV.C.- j 16 - AMMONI A -- i 4-----------,---

4 i

i i i 04/01 - 84/30/1988 I 15 I 14 m, ,e... e e+_. -e WW i se 3 L I aa f l 4 12 _.._p__..__..._._..____.._.q i. i 1, e 1 1 AL e* j f ~ is.. _4 _...; _ _ _ _..__ _. _. 4.. g 9 .._.n. ._i____.r.._....:_....._..... (L. i -t 1 r i O t i i I l. t
== I 7 t } 6
==. ...____4___.. ._.-_.2 I 4
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I D. FERMANENT MODIFICATIONS TO THE ROUTINE WATER CHEMISTRY SURVEILLANCE PROGRAM The significant changes incorporated into the routine water surveillance chemistry program are summarized below: (1) Modifications to the frequency ana surveillance location for RCS hydrogen. (2) Increased surveillance frequency for analytical methodology associated with monitoring for fuel perfomance (iodine activities). (3) Incorporation of a correction factor for the RCS hotleg hydrogen determination to compensate for the inefficiency of the gas purging evolution at the degassing station. (4) Maintenance of VCT physical parameters at levels that will ensure adequate hydrogen concentrations are maintained in the VCT and therefore, in the RCS. (5) Increased Control / Analysis for CVCS hydrazine/ oxygen to minimize oxygen ingress into the RCS. (6) Detailed procedures for the injection of hydrazine into the CVCS to minimize control prcblems. In addition, the feasibility of installing a pemanent deaerator in the effluent of the demineralized water storage tank is being l evaluated. It is projected that the installation of the deaerator will minimize oxygen ingress into the RCS and eliminate operational problems associated with injection of the oxygen scavenger, hydrazine, l and the subsequent RCS chemistry perturbations (ammonia, resin equlibrium). lI l I 154 t
I The table below lists the nominal values obtained for significant chemistry following the power distribution episode compared to pre-episode values. It also lists the post-episode specifications. Parameters Pre-Episode Post-Episode Post-Episode Nominal Value Nominal Value Specification
1) pH @ 25 C 5.0 to 7.0 6.5 to 7.5 4.5 to 10.2 (Standard Units)

2) Conductivity 0.0 to 20.0 10.0 to 40.0 Consistent w/
(pmhos/cm) additives
3) Lithium 0.0 to 1.0 0.0 to 1.t.
1.0 ppm maximum (ppm) I
4) Suspended 0.0 to 250 425 ppb 500 ppb maximum Solids (ppb) based on VCT Hydrogen 3

5) Hydrogen 10-30 50-70 Consistent w/over-3 (cc/kg) pressure & concentration in VCT

6) 0xygen/H;drazine N/A 5:1 ratio 5:1 ratio I

7) 0xygen (ppb) 410 4 10 4100

8) Ammonia (ppb) 10 1000 Not Speci.~ied

9) Fuel Performance N/A NA N/A
/ Parameters I I
I 155 l
I I E. SECTION IV ATTACHMENTS 3 (la-d) Calvert Cliffs Instruction #406. Inda of Rad-Chem Procedures. I (2a-b) RCP-1-202. Specifications and Surveillance. Reactor Coolant System. Table 1. (3a-d) Reactor Coolant System - Operating Chemistry Specification Sheet #3-3. CENPD-28. (4) RCP-1-215. Specifications and Surveillance Chemical and Volume Control System. Table 1. (5) RCP-1-201. Specifications and Surveillance Makeup Demineralized Water System. Table 1. I (6a-b) Makeup Water System - Operating Chemistry Specification Sheet #2-1. CENPD-28. I I I I I I lI I I lI lg 156
n i i numen i tiaf Asisz.A vr wat CHEMISTRY AND RADIOCHEMISTRX PROCEDURES MfdTUAL - RCP 1 CURRLNT RET # RCP 1 - 100 Series - General Infoz=atica 1 - 101* Methods for Revising and Changing Rad-Chen Procedures 8 1 - 102* Records k 1 - 103 QC Procedure 3 1 - 10h Standard Safety Precautions 1 I RCP 1 - 200 .cpecification & Surveillance Scope of Section 200 h 1 - 201* Make-up De=ineralized Water k 1 - 202* Reactor Coolant System a 1 - 203* Co=panent Cooling / Service Water Syste: 3 1 - 20h* Refueling & Spent Puel Fool Syster 6 1 - 205* Safety Injection Syste= sh 1 - 206* Liquid Waste Releases 12 7=3) 1 - 207" Boric Acid Storage Tanks 9' 1 - 208* Boric Acid Storage Tanks 7 1 - 209 Domestic Water System 0 1 - 210*' Steas Generators 8 1 - 211* Condensate, Feedvater and Main Steam System 8 1 - 212 Sevage Treatment Plant h 1 - 213* Neutrali-ing Tank 1 1 - 21k Auxilia:7 Boilers k l 1 - 215* CVCS Systems 6-1 - 216* Stator Cooling System 0 l 1 - 217' Diesel Gen. Jacket Cooling 2 l 1 - 218 Un cnitored Discharge Surveillance Progra: 1 'I 5i.; Ch. 13 i
Required POSRC Review 157
As Iat,nMtni t loj laur.,x ur Wau n CHEMISTRY AND RADIOC E ISTRY PROCEDURES MANUAL - RCP 1 "E RCP 1 - 300 Series - (future use) CURREITT REY. #
.gs RCP 1 400 Series - (future use)
I RCP 1 - J00 Series - Sanpling Requirements 1 - 501* Sa=pling Techniques 0 1 - 502* Sampling of Cases for Activity 3 1 - 503* Post-Accident Sa=pling of Reactor Coolant & Containment Conditions 0 I RCP 1 - 600 Series - (future use) RCP 1 - 700 Series - (future use) RCP 1 - 800 Series - (future use) le ecP 1 - 900 Ser1es - mater c,emist,y P,oceeure EE 1 - 901 Detercination of Conductivity 0 1 - 902 Determination of pH 2 1 1 - 903 Determination of Boron 3 1 - 90k Determination of Gases 1 1 1 - 905 Determination of Dissolved Oxygen 1 1 - 906 Determination of Chloride 3 1 - 907-Determination of Fluoride 1 1 - 908 Deter =ination of Lithium and Sodiu= 1 l l 1 - 909 Determination of A=monia 1 l l 1 - 910 Determination of Hydrazine ~2 ~ ~ ' 1 - 911 Determination of Suspended, Dissolved and Total Solids 3 1 - 912 Determination of Total Hardness 0 1 - 913 Determination of Alkalinity 1
Required POSRC Reviev Ch. 14 l
158
1 ATTACHMENT (lc) INDEX OF WATER CEDCSTRY AND RADIOCEDGSTRY PROCEDURES MANUAL - RCP 1 .:.E CURRENT REV. # I~.'3: ' .... '.r - ~ ' ' '. '7. ~
J.'
RCP,1 - 91h. ~ ~ Deter =ination of Phosphate 0', ' 915 Determination of Chro= ate 0 1 - 916 Determination of Scluble Silica 2 1 - 917 Deter =ination of Nickel 1 1 - 918 Deter =i2ation of Total Iron 1 1 - 919 De'.:rmination of Copper 0 1 - 920 Deter =ination of Sulfite 0 1 - 921 Deter =ination of Free Hydroxide 0 1 - 922 Determination of Residual Cblorine 3 1 - 923 Deter =ination of Morpholine 1 '-j%? 1 - 924 Determina' tion of Sevage Treat =ent Flant Chemistry 0 . h=:-. 1 - 925 Deter =ination of Turbidity 0 - ~, 1 - 926 Determination,,of Chro=iu= 1 ..15'h...- . ~; - * : =Gnt '?..^
.y-7 ~1{ -
1 - 927 Deter =ination of Chliform Populations in Domestic ~ ": 1 and Weste Water -- 1 f~ M'_^ .e.E? ?.". ~ l - 928 Deter =ination If 011 and Grease 1 ?9 M: = -,g_.,. !...a,;. RCP 1 - 1000 Series - Radiochemistry Procedures 1 lS ~I*.A -f.~.' ~ l - 1001* Deter =ination of Gross Beta-Gama (Alpha) .?.n " Degassed Activity 3 \\ yy..-p. ;:.:. 3...... Deter =ination of, Gaseous Activity 0 F F.., ' 1 - 1002,t.- i:
3..:......
t l' ce.r'-g-.-o. $'-l' {l'003'.;[Ieter=ihati%o'f'. Iodine Activity a m,.. u... u..... - $:7s.;:.r_}.D.. :1 -.100.h;;, Radiochemical' Analysis for Radioactive Cesiu= ~e"---- 0 ~' 3M F- 1 ' 1005 ' Deter =ination of Barium and Lanthenu= 0 .. n : w..:.-- :. :
e. -+ 3-3 1 - 1006 Deter =ination of Strontiu= Activity 3
-im LT 1 - 1007' Deter =ination,of Tritium Activity b l 1 s....... l -1. .J-, 1. 1008 Determination of Corrosion Product Activity 0 j. -o-Q....*o'-*.. ~ -*
u.: : :- -..
-y..'-7 ' '. Required POSRC Reviev Ch. 9 e ;.- 1 1. 159 l M =m
j AlIALHMtNI (10) INDEX OF UATER CHEMISTRY AND RADIOCHEMISTRY PROCEDURES MAHUAL - RCP 1 CURRENT REV. # ~ IZE 1 - 1009 Determination of E 3 RCP 1 - 1100 Series - Purchase Specification 1 1 0 1 - 1101 Plant Chemicals I 1 f 1 - 1102 Resins 1 I RCP 1 - 1200 Series - Special Procedures 0 1 - 1201 Auxiliary Boilers 1 - 1202 Determination of Water and Sediment in Fuel Oils 0 1 - 1203* Deter =ination of the Ability of TSP to Dissolve 2 1 - 120h Observation Well Depth Recorder & Well Water 1 Usage Records 1 - 1205 Special Procedure for Nuclear Orade Resin 0 Surveillance ~ 1 - 1206* Special P.~ocedure for Reactor Coolant System 0 Hydrogen 1eroxide Treatment f ' I t I i " Required POSRC Review Ch. Ih 160
g 3 RCP 1-202 ATTACHMENT (2a) Rev. 8 Page 2 $ie ~~ SPECIFICATIONS AND SURVEILLANCE REACTOR COOLANT SYSTEM TABLE I HOT LEG (OR LETDOWN SX 6h58) g' ANALYSIS / PROCEDURE SPECIFICATION FREQUE' ICY FREQUDICY E A (1) B (1)
1. pH 8 25 C/902 h.5 - 10.2 5/W 3N Consistent with

2. Specific conductivity /901 conc. of additives SN 3/W

3. Boron /903 (Tech Spec 3.1.1 & 3.9.1)
Variable 3N (2) 1/2k rs. (2) h
h. Lithiu=/908 1pn= (=ax) (3) 5/W 3N E 5. Chloride /906 (Tech Spec 3.h.7) 0.15pn= (rax) 1/72hr.
1/72 hrs.
6. Fluoride /907 (Tech Spec 3.h.7) 0.13pp= (--av) 1/72 hrs.
1/72 hrs.
7. Suspended Solids /911 0.5pn= (rax) 1/W 1N l A Hydrazine/910 1.5x =easured Op cone.
(k) None
9. A-nnia/909 (5)
IN None
10. Oxygen /905 (Tech Spec 3.h.7) 0.10pp= (Max) (6) 1/72 hrs.
None
11. Hydrogen /904 10-50ce/kg (7) 1/W None

12. Nitroger /90b Not specified c.s Pecuired AS REQUIRED l

13. Total Activity (Tech Spec 3.h.8) 100/E uCi/g (=ax)(8)
'l/72 hrs. 1/ W '
14. I1 31 Dose Equivalent (Tech Spec 3.h.8) 1 uci/g (8) 1/1h ays None d

15. Gross Degassed Activity Not specified IN IN

16. Gross Alpha Activity /1001 Not snecified 1/W 1/W t

17. I1 31/I133 Ratio /1003 Not snecified 1/W (deleted)

15. Tritiu=/1007 Not snecified 1/W IN
_ 14. Crud Activity /1008 Not specified 1/M 1/M 'j (Tech Spec j._. E Deter =ination/1009 Table b.h h) Not snecified 1/6=ths. None l 321. analysis (Tech Spec 3.h.8) Iodine isotocic l ^ Not specified (9) (9) W i 161
RCP 1-202 g ~Rav. 7 Pega 3 5 ATTACHMENT (2b) SPECIFICATI0:S MID SURVEILLMiCE REACTGR C00LAUT SYSTEM TABLE I
0TES I
(1) Frequency A = Modes 1, 2, 3, h Frequency B = Modes 5, 6 (2) Bequired 1/24 hrs. to verify shutdown nargin per Tech. Spec. 3.1.1. in Mode 5 In Mode 6, 1/72 hrs, as per Tech. Spec. 3.9.1. (3) Nor=al range 0.2 to 1.Oppm. Lithium should be maintained 0.2-0.5 when B g_50 ppm. (4) Prior to exceeding 150* F. Tne presence of hydrazine vill be verified folioving any chemical addition of hydrazine to the coolant. (5) nor=al concentration about 1.opps. Must be within specification prior to heatup 7250 F. I (6) (7) Hydrogen must be maintained within these limits for all plant operation above Less thes 5cc H /kg E 0 (STP) is required for opening the reactor coolant 1 Erit. 2 2 b system to atmosphere. (8) If the total activity >100/E uCi/s or >1.0 uCi/g dose equivalent I-131 perform analysis #21 of this procedure 1/h hrs. until the activity is returned to within spe cification. l (9) This analysis shall be performed according to the following schedule: ~ 131 exceeds a) Once per k hours, whenever the dose equivalent I 1.0 uCi/ gram (until the RCS specific ac+1vity is restored within its limits), and b) One sa=ple between 2 and 6 hours folloting a thermal power change exceeding 15% of the rated thermal power within a lI cne hour p riod. 1 I I 1ez
7 g ATTACHMENT (3a) TABLE 3-3
SUMMARY
OF REACTOR COOLANT CHEMISTRY SPECIFICATIONS Analys'is Precore Core Loading Operating pH @ 77 F 9.0 - 10.4 4.5 - 10.2 4.5 - 10.2 Conductivity Note 1 Note 1 flote 1 Hydrazine 30 - 50 ppm 30 - 50 ppm 1.5 X 0xygen ppm (max. 20 ppm) l Ammonia <50 ppm <50 ppm <0.5 ppm <10 cm3 (STP) Dissolved Gas kg H 0 2 prior to a depressur-ization shutdown Oxygen <0.1 ppm <0.1 ppm <0.1 ppm Suspended <0.5 ppm <0.5 ppm <0.5 ppm Solids 2.0 ppm max. 2.0 ppm max. 2.0 ppm max. Chloride <0.15 ppm <0.15 ppm <0.15 ppm c Fluoride <0.1 ppm <0.1 ppm <0.1 ppm Boron Refueling Concentration <4400 ppm Lithium 1 to 2 ppm 0.2 - 1.0 ppm 0.2 - 1.0 ppm l (Note 2) (Note 3) 3 Hydrocen 10 - 50 cm (STP) 2 t (Note 4) Iodine-131 Note 5 Tri tium Note 5 Reactor Coolant Note 5 Liquid Activity E Note 5 l NOTE 1: Consistent with concentration of additives. I Refer to Section 3.3.2.1 for the length of time this specification NOTE 2: will be in force. 7 l NOTE 3: If the purification ion exchanger is being <aturated in situ with Li maintain 1-2 ppm Li until saturation is react;ed (indicated by i s breakthrough), then revert to 0.2 - 1.0 ppm Li. Saturation s,,ould be acgomplished prior to criticality. NOTE 4: <5 cm (STP)/kg(H 0) before securing the reactor coolant pumps. NOTE 5: See FSAR, Techni al Specifications. Revision 2 163
M .M M M M M M M M M M M M M M !q!!% M p 4; c! { SPECIFICATION SHEET NO. 3-3 SYSTEM REACTOR COOLANT - OPERATING E Sampie Sampiing(a) g Analysis Location Frequency Specifications Corrective Action Notes 9 4 pH
1. Hot Leg loop 5
4.5 tu 10.2(b) 1.Confinn value. la) Frequency Code 'j (Measured at or Purifica-
2. Perform 0, H 1 = 1/ week 9
2 25 C) tion Filter and lithium 2 = 2/ week Inlet (PF analysis to Inlet) detennine cause. 5 = 5/ week
2. Purification 1

3. Valve in standby column 2Y = 2/ year Ion Exchanger if high pH due to high S = During shut-Outlet (IX lithium.
downs and Outlet)
4. Add Li-7 if too low.
startups 5.If pH change due to AR = As required high 0, follow (b)The pH limit of 7 corrective action 10.2 must not be under that heading, exceeded; see Section 1.3.2 for further discussion. !g Reactor Makeup 1 6.0 - 8.0
1. Confirm value.
Water Tank
2. Drain and refill if req'd.
Oxygen
1. Hot Leg Loop 5
Less than 0.1 ppm 1.Resample to confirm lc)Hydrazine is added
2. Reactor Makeup 1
valu~. to recirculating e reactor coolant 2.If during(heatup, add Water Tank hydrazine c) to 1.5 during heatup if times 0 concentra-required to remove 2 5. tion. excess 0. The 2 S.
3. Perform H2 analysis system cannot 8,
if at power, add H exceed 150 F until 2 as required. the 02 operating m 4.If pH and H also low limit or a hydra-2 out-of-spec, add zine residual is NH. established. 24 3 Hydrogen Hot Leg Loop 2 10 to 50 cm3 (STP
1. Add H2 as required.
<5 cm (STP)/kg H 0 H /Kg H O
2. Degas as required.
beforesecuri$g 2 2 reactor coolant pumpt s 3 Total Dissolved Hot Leg Loop AR <10 cm (STP)/ kg H O
1. Degas as required.
2 Gas prior to shutdown
M M,M M M M M M M .M M M M M M M M . i:t-gjip a SPECIFICATION SHEET N0. 3-3 SYSTEM REACTOR COOLANT - OPEr.ATING (Continued) M Sample Sampling (a) y Analysis location Frequency Speci fica tions Corrective Action Notes l Ammonia (d) Hot Leg loop 1 Less Than 0.5 ppm
1. Initiate or increase (d)Antnonia is due to b
or Pi Inlet Nil purification flow, hydrazine decomposi-N' 3 ~ 2.Or reduce Np content tion or radiolytic of Reactor Coolant, combination of as applicable. N and H ' 2 2 Lithium
1. Hot Leg Loop Daily; 0.2 to 1.0 ppm

1. Initiate flow to de-(e)Todeterminewhen or PF Inlet after lithiating t.:d if high.
when bed saturation additions; takes place during and AR;
2. Add Li-7 i f '.,.
lithiation. (Note 1) 2.IX Outlet *) 1 I 5 Boron 1.PF Inlet 5 (f) Add boric acid or (f) Boron concentration or Hot Leg makeup as required. varies with burn-Loop up. The predicted
2. Reactor 1
Zero concentration is Makeup Water found in the Final Tank Safety Analysis
3. Volume 1
(f) Report of each Control Tank plant. Liquid 4.Refuelirg Water 1 (f) NOTE 1:At least every 4
o Tank hours during 3,
5.IX Outlet (wher 1 (f) boration or g deborating) dilution operations. o
6. Pressurizer 1
(f) Prior to and after Q boration/ dilution, Chloride 1.PF Inlet 5 Less Than 0.15 ppm
1. Check IX Outlet operations, unless or Hot Leg Loor these are part of 2.IX Outlet 1

2. Initiate or increase a casualty, then purification flow.
sampling should be Fluoride
3. Reactor 1
Less Than 0.1 ppm
3. Check Reactor Water ASAP.
Makeup Water Makeup Tank and bleed Tank and feed, as required.
4. Isolate and shift

4. Volume 1
columns. Control Tank
5. Replace resin bed, linuid as recuired.
L
m M.m W M M M ma m m: M M M M M M M m m SPECIFICATION SHEET N0. 3-3 SYSTEM REACTOR COOLANT - OPERATING (Continued) m 4 Sample Sampling (a) Analysis Location Frequency Specifications Corrective Action Notes Solids: 1.Concentra-
1. Hot leg Loop 1,5 Less Than 0.5 ppm (II

1. Initiate or Increase (1)Theabnormal Purification Flow.
condition of 0.5 tion of Suspended 2.PF Inlet 1,S (max. of 2.0 ppm)(,)
2. Bleed and feed if no to 2.0 ppn is Solids extra purification is pennitted for up available.
to 4 hours to (Crud) 3.If maximum limit of allow for crud 2.0 ppm is exceeded, burst conditions. an orderly shutdown is required. (m) Suspended solids level must not exceed 2.0 ppm, cn
2. Total Reactor Plant 1
Less Than 0.5 ppm Bleed and Feed or re-the design limit Solids Makeup Tank place water to reduce of most major solids level. primary components.
3. Activity

1. Hot Leg Loop 1,S As it relates to Initiate or increase of Sus-E (g) nurification flow.
(n)These will indicate the ability of the pendeo 2.PF Inlet 1,S filter and IX bed Solids (i) 3.IX Inlet (") S to remove the solids. 4.IX Outlet "} S I Tritium 1.PF Inlet or 1 (g) . -[ Hot Leg Loop 4 E
2. Reactor 2Y Concerning Waste E
Makeup Water disposal Tank ro
I REV. 6 PAGE 3 ATTACHMENT (4) SPECIFICATI0 i", NiD SURVEILLANCE I-CVC:: SYSTEM 3 TEE 1 I Analysis Procedure / Method Specification Freauency A. Ion Exchangers 1. Conductivitv/901 (1.) AS REQUIRED 2. pH 8 25oC/902 (1.) AS REQUIRED 3 Boron /903 DF=2(min)(2.)(3.) AS REQU...:D h. Chloride /906 0.15 ppm (max) AS REQUIRED 5 Fluoride /907 0.1 pp= (max) AS REQUIRED 6. Lithiu=/908 NS AS REQUIRED 7. Quantitative Ga==a DF = 10(min) (2) 1/M Activity avg 8. Dose Rate, Vessel Contact N.S. 1/M B. Filters 1. Suspended Solids /911 DF = 10 (mi.-) 1/M C. VCT 1. Hydrogen /90h 9-45 psia 3/W (1) Should be consistent with concentratiors of chemical additives. (2) DF = influent / effluent. (3) When deborating ion exchanger is operating. i lI
I llI l
167
1Tt% L> V a as ava i .svv.. i CALVERT CLIFFS RSCE d/[--" - r SPECIFICATIoI;S kid SGVEILL/'!CE POSRG - - "11 NUCLEAR POWER PLANT MA'G UP EDtI'!EF ALIZED WATEP. I.'. , Chid C.'G:; e i ATTACHMENT (5) TABLE 1 Reactor Coolant Make Up Pucps Discharge I Analy:is Procedure / Method Speci'fication Frequency (1) 1. pH @ 25 C'902 5.8 to 8.0 3/k' 2. Conductivity /901 2.0 u=ho/cm3 (:,nx) 5/w 3 Chloride /906 0.15 ppa (=r.x) 1/n I h. Sodium /qcf 10 ppb C m4) 1/n I 5. Silica /916 0.02 ppm (max) 5 /W I g=m Samples may be collected from either units reactor coolant make up puup 9 1. or other suitable semple point off the Denincralized water system. I 9 I ' I I l I l I. l
I 168
.. ~
M GM M M M M Me M M M M M M SPECIFICATION SHEET NO. 2-1 SYSTEM MAKEUP WATER Sample Sampling Spec _i fi ca tic,.is N Analysis Location Frequency Normal l Abnormal Correct.ive Action detes k 2 --i
onductivity Makeup

1. Continuous
<l.0 1.0-2.0(a)
1. Isolate offending (a) See Section 2.3.2 y
Water in Line umho/cm umhos/cm train. for further discus-System De I Monitor
2. Perform pH, Cl-sion of the out-of-mineralizer 2. Daily Grab and Conductivity spec condition.
Effluent Sample on grab samples Makeup water that (MWSDemin. 3. Prior to put-from effluent line exceeds 2.0 umhos/cm Effluent) ting train on and from tank that is unacceptable for line it feeds, use. J. Commence Resin Regeneration if out-of-spec con-dition verified (otherwise, clean 8 cclls).
4. Check performance of entire train if water volume sinct last regeneration is low.
6.0fC -
1. Isolate offending (b) A pH as low as 5.8 is b
pH MWS Demin.
1. Daily 6.0-8.0 Effluent

2. Prior to 8.0 train.
acceptable only if putting train
2. Check performance caused by CO2 absorp-on line of entire train tion.
Boil sample if water volume according to Section since last regen-6.4.13; Remeasure eration is low. pH. Correct as (c) See Section 2.3.3 necessary. for further discus-3.If CO2 is not the sion of the Out-problem, commence of-Spec condition. regeneration.
g g g g a m M Ml M M E E E E SPECIFICATION SHEET NO. 2-1 SYSTEM MAKEUP WATER (Continued) bM Sample Sampling . Specifications g Analysis Location Frequency Normal Abnormal Corrective Action Notes
9 Chloride MWS Demin.
1. Daily
<0.15 ppm 0.15(d). g Effluent Grab
1. Isolate Offending (d) See Section 2.3.4 E
ppm tra i r.. Sample for discussion of
2. Prior to

2. Check performance the Out-of-Spec of entire train condition.
putting train if water volume on line since last regen-eration is low. Fluoride MWS Demin. As required <0.1 ppm 3.Comence resin Effluent for Primary regeneration if makeup chloride level 't SiO MWS Demin.
1. Daily (*)
v'eri fied. 2 <0.01 ppm 0.0 .02
1. Isolate Offending (e) This frequency should o
E f fluent Grab Samples ppm
train, be revised at end of 2.If analysis con-preservice period, firmed, reduce (f) See Section 2.3.5 flow throug' for discussion of the train.
Out-of-Spec condi-
3. Follow corrective tion.
action outlined in Section 2.3.5.
F.
~Cl ION IV REFERENCES 1.
Combustion Engineering Power Systems. Nuclear Steam Supply System Chemistry Manual CENPD-28. Revision #2. 2. RCP-1-202. Specifications and Surveillance. Reactor Coolant System 3. RCP-1-215. Specifications and Surveillance. Chemical and Volume Control System. 4. RCP-1-201. Specifications and Surveillance. Makeup Demineralized Water. 5. RCP-1-102. Records. Chemical Log 1-102-2. 07/01/80 to 07/31/80. 6. Letter dated 11/08/79. BG&E-10276-70, P. W. Kruse to L. B. Russell
Subject:
Calvert Cliffs Unit I Power Distribution Anomaly Letter dated 11/19/79. BG&E-10276-75, P. W. Kruse to L. B. Russell
Subject:
Calvert Cliffs Unit I Power Distribution Anomaly 7. Letter dated 03/07/80. BG&E-10276-99, P. W. Kruse to L. B. Russell
Subject:
Calvert Cliffs Unit I Power Escalation Program 8. Memorandum dated 03/11/80. R. F. Eherts to PDTF
Subject:
Unit I Power Anomaly 9. Letter dated 12/11/79. BG&E-10276-8, P. W. Kruse to L. B. Russell I
Subject:
Calvert Cliffs Unit I Power Distribution Anomaly
10. Memorandum dated 01/15/83.
A. J. Kaupa to PDTF
Subject:
Hydrazine Addition 11. Letter dated 01/15/80. BG&E-10276-88. P. W. Kruse to L. B. Russell
Subject:
RCS Hydrazine Addition 12. Letter dated 02/15/80. BG&E-10276-93, P. W. Kruse to L. B. Russell l
Subject:
Calvert Cliffs Unit I Crud Anomaly 13. Letter dated 12/11/79. BG&E-10276-87, K. W. Kruse to L. B. Russell
Subject:
Calvert Cliffs Unit I Power Distribution Anomaly 14. Letter dated 01/19/80. BG&E-10276-87, P. W. Kruse to L. B. Russell
Subject:
Volume Control Tank Level 15. Memorandum dated 01/04/80. R. F. Eherts to PDTF Subj ect: Discussions with D. Morgan, Combustion Engineering l
16. Memorandum dated 02/26/80.
R. F. Eherts to J. R. Speciale/PDTF l
Subject:
Unit I RCS Chemistry lI
17. Memorandum dated 02/26/80.
R. F. Eherts to J. R. Speciale/PDTF
Subject:
Unit I Power Anomaly 171
I V. CONCLUSTIONS AND LESSONS LEARNED Although the evidence is circumstantial, it is reasonable to infer that the reactivity and peser distribution anomalies were caused by the slow buildup of crJd on the core surfaces. The deposition I of crud was preferential to the core top and periphery. The crud was a product of the corrosion of RCS surfaces by slight 1/ higher than normal Oxygen levels in the RCS. The source of the Oxygen was instrum_nt air from an ion exchanger resin flush system. Two in servies values leaked past their seats and increased the Oxygen concentration in the water of the purification section of the CVCS to approximately 300 ppb for several weeks. Although this concen-tration was further diluted prior to injection back into theRCS, it was apparently enough to overpower the scavenging effect of-I the Hydrogen in the RCS. Once the conditions for oxidation of RCS surfaces had been established, the normal Oxygen concentration levels in RCS makeup water were enough to maintain that oxidation state even though the original abnomal source of Oxygen had been isolated. In order to mitigate the effect of 0xygen ingress during this episode and to preclude it from reoccurring in the future, the following short and long term actions have been or are being taken: (1) The leaking resin flush valves were repaired. (2) The resin flush medium has been changed from air to nitrogen. (3) The RCS makeup rate has been reduced by the action of rebuilding a power operated pressurizer relief valve which was a significant I source of leakage from the RCS. (4) Chemistry procedures have been modified to tighten surveillance at potential sourcas of air ingress into the RCS. (5) Gauges have been added which allow monitoring of any pressure buildup in the nitrogen header supplying the ion exchangers. Although it is not expected that the introduction of nitrogen to the RCS would result in an anomaly such as that caused by Oxygen, the monitoring of header pressure provides an extra measure of conservatism to prevent the inadvertant introduction I of insoluble gas to the RCS. 172
(6) Hydrazine in stochiometric concentrations is metered into the RCS makeup water at the point of its injection into the CVCS. A control scheme is being developed to automate this process. (7) Pertinent core and fuel performance parameters are being trended and the surveillance and evaluation frequency has been increased. (8) The feasibility of deaerating the RCS makeup water is being investigated. (9) A fuel inpsection program forthe purpose of documenting any lasting effects of the episode is being developed for performance at the next refueling. I I I i 173
APPENDIX'A CHEMISTRY RESULTS OF THE UNTT 1 HYDR 0 GEN PEROXIDE TREATMENT 4 1. ulSCUSSION I On January 27, 1980, hydrogen peroxide was added to the Unit 1 reactor coolant system and various chemistry parameters were monitored in order to detennine the effectiveness of the ex-pected chemical shock to the system. Hydrogen peroxide has been added to a number of other nuclear facilities and an EPRI report has been published which documents the findings of a limited sur-vey of utility experience and the results of two intensive test programs (reference 1). The pertinent findings of that report were: 1. Greater than 90% of the Co-58 activity in the primary r.oolant is nonfilterable subsequent to the peroxide injection or oxy-genation. 2. In-core deposits are the major source of the activity released during shutdown with or without peroxide injection. 3. Peroxide or oxygen addition had no major impact on primary system shutdown radiation fields. 4. Oxygenation and hydrogen peroxide addition produce similar effects on the release of Co-58. This results from the in-terrelationship of oxygen and hydrogen peroxide caused by radiolytic effects in the core. 5. Since Co-58 is present predominantly as a nonfilterable species subsequent to oxygenation nr the addition of hydrogen peroxide, neither dropout nor the high radiation fields associated with dropout would be expected to occur. The main purpose for perfonning the hydrogen peroxide treatment on Unit 1 was to affect a chemical shock to such a degree that an im-prcvement in core differential pressure would be manifested. It should be pointed out that the EPRI report concluded that the hydrogen peroxide technique, "can be of significant value in eliminating the occurrence of significant releases when purification to reduce re-fueling platform manpower exposures would impact on the refueling outage schedule". Although Ft. Calhoun observed improvement in reac-tor coolant flow as an apparent result of the hydrogen peroxide tech-nique (reference 2), the EPRI work did not address any effects rela-tive to possible core parameter improvements. There is, therefore, no other evidence that the hydrogen peroxide treatment will result in a decrease in core differential pressure. II. PLANT PROCEDURE FOR HYDROGEN PEROXIDE ADDITION A plant procedure was prepared for the hydrogen peroxide treatment (reference 3). The procedure delineated the initial conditions I 174
required, the collection of baseline data, the addition of the percxide and the sampling / surveillance program needed to monitor the effectiveness of the addition on the reactor coolant system chemistry. Of crucial importance was the perfomance of the chem-ical and volume control ion exchangers. The ion exchangers were needed to control the expected high coolant activity which wou'd result from the solubilization of the Co-58 isotope tnd also control other corrosion products. In order to determine the endpoint of the hydrogen peroxide addition certain chemistry parameters needed to be monitored carefully after each addition. The plants in the EpRI study appeared to monitor Co-58 activity increases after peroxide additions as a primary para-meter. In addition, oxygen and hydrogen peroxide levels were consid-ered useful in detemining the endpoint. The decision was made to teminate hydrogen peroxide injections when there was an inability to produce an " effective" chemical shock as detemined by suspended solids, oxygen, and Co-58 activity. Therefore, a combination of these parameters would be utilized to detemine the endpoint for the additions. Another aspect of the procedure considered important was the opeiation of the reactor coolant pumps. It was decided that the peroxide would first be added to the loop from which letdown was being withdrawn. Therefore,12A and 12B pumps would remain in service during and fol-lowing the first addition and then the other loop would be flushed by switching to one pump per loop operation. By operating the pumps in this manner flushing of the core and steam generator surfaces would be more effective and purification could then be employed 2 for removal of soluble and insoluble crud. III. RESULTS A. Chronoloay of Events Table 1 consists of a chronology of events be' ore, during, and dfter the peroxide addition. Of particular note is the venting and repressurization of the volume control tank (VCT) with nitrogen prior to shutdown in order to reduce the hydrogen in the coolant to a level corresponding to the lower end of the nomal operating concentration, (i.e.,10-50 cc hydrogen /kg water). Following shutdown, degassification continued until hydrogen was less than 5 cc hydrogen /kg water. The increased rate by which the hydrogen was successfully lowered may be attributed to a lowering of the nomal operating band of the VCT water level. This increased the efficiency of gas stripping in the VCT vapor. Also of note from Table 1 are the periodic changes in the reactor coolant pump operation. As mentioned earlier this was accomplished intentionally in order to insure a high degree of effectiveness from the peroxide additions. 175
B. peroxide Additions A total of 15.1 liters of hydrogen peroxide was added to the reactor coolant system within approximately 9 hours. Table 2 lists the peroxide additions and gives a comparison of theroe-tically calculated oxygen levels with observed oxygen levels based on the overall decomposition reaction: 2H 0 2H O + 0 + 22 2 2 The data shows that the last peroxide addition resulted in close to predicted oxygen levels indicating that equilbrium had been reached. C. Effects on Chemistry Figure 1 is a plot of the Co-58 activity, Co-60 activity, and I Co-58/Co-60 ratio during the peroxide additions. Figure 2 is a plot of other chemistry data collected. The peroxide additions are highlighted by arreas at the times the addition was completed. The addition of the hydrogen peroxide resulted in significant changes in the chemistry of the reactor coolant system. Of I particular note were the increases of Co-58 total activity and suspended solids. As exp.ected, the increase in solubility.of cobalt and nickel oxides present in the crud caused high dissolved Co-58 activity levels and the sudden shock on converting the chemistry from a reducing environment to an oxidizing environ-ment caused crud to spall off system surfaces as indicated by the increase in crud levels. The resulting oxygen levels re-flect the addition of the peroxide and appear to show that con-sumption of the oxygen occurred while conversion of the oxides to soluble foms took place. ~ The criteria for temination of the hydrogen peroxide addition to the reactor coolant system was based on several parameters. One of the critical parameters monitored was the oxygen level in the reactor coolant system. The oxygen level showed a decrease in a short time following the first addition showing that the system had not yet come to an equilibrium. At 2040 hrs., following the second addition, the oxygen level was.25 ppm, while the next or final injection brought the oxygen level up to 1 ppm. This level was close to predicted and indicated I that oxygen was essentially at equilibrium (Table 2). The next sample at 2400 hrs. showed a constant level of oxygen of 1 ppm. In addition.to the oxygen parameter, suspended solids and Co-58 I levels had peaked earlier and showed a slight decreasing trend which was expected because of the small purification flow rate of 40 gallons per minute. Peroxide additions were therefore teminated at 0020 hrs. on 1/28/80. 176
I Reference (1) concluded that in-core deposits were the major source of the activity released during shutdown. The addition I.; of hydrogen peroxide to Unit 1 appear to confim that con-clusion. Reference (1) showed that the average Co-58/Co-60 ratio of crud deposited on steam generator diaphragms was I significantly lower than the ratio observed during the release of crud following peroxide addition. This was attributed to increasing solubility of crud on core surfaces vice out-of-core surfaces. Table 3 shows the results of smears taken from Unit 1 and Unit 2 steam generator diaphragms. Figure 1 shows the ratio of Co-58 ta Co-60 during and following the peroxide additions. The data shows thot Co-58/Co-60 ratio following I the peroxide addition was about 200 whe'reas the steam generator diartragm typical ratio is censiderably lower. These results appear to confim that tha maj-)rity of the crud observed in I the reactor coolant system following the peroxide addition to Unit 1 came from in-core surfaces. I D. Reactor Coolant System Cleanuo I During the addition of peroxide letdown flow was approximately 40 gpm. At 1400 hrs. on 1/28/80, flow was increased to a nom-inal 120 gom to more rapidly affect cleanup. During these periods two purification ion exchangers were in service. They I consisted of a cation removal ion exchanger and a cixed bed (cation and anion removal) ion exchanger. Both ion exchangers were utilized in series operation. Table 4 shows the Co-58 decontamination factors (DF's) detemined across the ion exc. hangers at various times. l Cleanup of the reactor coolant system while utilizing reactor coolant pump operation continued until about 2000 hrs. on 1/29/80 when draining of the systs.i was started. After that time the shutdown cooling system remained in-service to continue I to remove soluble Co-58 and suspended solids. During the peroxide addition, Co-58 levels increased to 2 uCi/cc I as opposed to the baseline data of 6 x 10-3 uCi/cc and the nomal shutdown levels of 4 x 10-1 to 8 x 10-1 uti/cc. The system was not allowed to be opened or drained down in order to allow a I-cleanup of the system to baseline levels. This was to insure that the radiation levels of the system components would not i.e higher than nomal due to a possible redistribution of the crud. Purification was r.aintained until the Co-58 levels returned to I nomal shutdown cooling levels and the system was not experiencing additional crud releases while alternating reactor coolant pump operation. The decreasing trend in suspended solids, except I for a small crud release and correspondino increase in Co-58 activity levels at 0800 on 1/29/80, indicated that cleanup was effective. The 12 hour period on 1/29/80 from 0800 to 2000 hrs, I indicated that the system chemistry was continuing to trend down to nor..al shutdown levels. Therefore nomal shutdown conditions had been achieved and the draining of the system could begin. In addition, shutdown radiation levels were showing a continuing downward trend towards normal shutdown levels. I 177
It has been estimated that from the period 1510 hrs. on 1/27/80 I thru 1400 hrs. on 1/28/80, 282 curies of Co-58 were removed from the coolant. This assumed a nominal flow rate of 40 gpm. From 1400 hrs, on 1/28/80 thru 2000 hrs. on 1/20/80, 291 curies of Co-58 were removed at a nominal flow rate of 120 gpm. Therefore I the total Co-58 activity removed from the coolant starting with the peroxide addition until draining of the cwiant was initiated was 573 Curies. E. Effects on Shutdown Radiation Levels During and following the peroxide addition several areas were selected in the plant for intensive radiation level monitoring. l The following locations were selected: 1.
12 Purifi;ation Ion Exchanger 2.
Valve 1-SI-306 (Outlet flow control valve on safety injection) 3.
11 and #12 Shutdown Cooling (SDC) Heat Exchangern 4.

11 A and #118 Cold Leg

12 Purification Ion Exchanger was monitored in order to deter-mine when it should be removed from service since the radiation level is a critical parameter with respect to use of shipping casks for ultimate disposal of the resin.
The ion exchanger reached a peak radiation level of 600-900 R/hr about ils days following the last peroxide addition and it was then removed from service. The radiation levels at the other locations are shown in Figure 3. The radiation levels monitored at SI-306 and the SDC heat exchangers show maximum readings near the times of <g'g the peroxide additions. This appears to reflect the crud release which occurred at that time. The radiation levcis at #11 A and filB cold leg do not appear to reflect the crud release, however, there is a gradual decrease in radiation levels at those locations and may be an indication of the clean-up of the system. Historical data regarding previous radiation levels at these locations appear to support the fact that the dose rates I shown in Figure 3 existed before without the peroxide treat-ment. Dose rates up to 350 mR/hr on the SDC heat exchangers have been experienced during previous shutdowns as well as dose rates of about 150 mR/hr on ill A cold leg. 51-306 dose rates have generally averaged about 60 mR/hr during previous shutdowns which is close to the average dose rate experienced following the peroxide treatment. I 178
I I F. Effects on Core Differential Pressure The addition of hydrogen peroxide to the Unit I reactor coolant system appears to be responsible for the reduction of the core differential pressure observed following heat-up on February 11, 1980. Figure 4 shows the various core parameters monitored and their respective values prior to and after the hydrogen peroxide chemical shock. Core Ap dropped from 15.7 psi to 13.8 psi or about a 12% reduction. I Based on the results of the hydrogen peroxide treatment the following summary is given: 1. The hydrogen percxide chemical shock appears to have reduced core differential pressure by 12%. I 2. A total volume of 15.1 liters of hydrogen peroxide was added to the RCS in three separate injections. 3. Increases in total Co-58 activity and suspended solias indicate the hydrogen peroxide produced a significant crud release. 4. Based on a comparison of data collected here with the results of the EPRI study, in-core deposits appeared to be the major source of activity released. 5. Approximately 600 Curies of Co-58 was removed from the coolant I during and following the hydrogen peroxide treatment. 6. Peroxide additions did not cause unexpected changes in shutdown radiation fields. I J 179
I TABLE 1 CHRONOLOGY OF EVENTS FOR H 0 TREATMENT OF U-1 RCS I. 22 1/25/80 0830 hrs. RCS Hydrogen 18.2 ccH /kg H O 2 2 2000 Vented & Repressurized VCT w/N 2 4 2105 Vented & Repressurized VCT 4 times w/N 2 2120 Commenced Reducino Power for Shutdown 2357 Opened TG Output 1/26/80 0110 hrs. Stop 12A & 12B RCP 0150 Commenced Cooldown I 0200 RCS Hydrogen 13.5 ccH /kg H 0 0245 Started 12B RCP Stop 11B RCP 0400 RCS Hydrogen 7.8 ccH /kg H 0 I 0446 In ibde 4 It 2 2 0700 Secured Degassing VCT; Filled & Vented 4 times 0920 Stop 11 A & 128 RCP's 0925 Start SDC with 11 LPSI 0936 Restart il A & 12B RCP's 1215 In Mode 5 1343 Start LPSI Pump on SDC 1720 Completed Press & Vent VCT 1/27/80 0220 hrs. Removed #11 purif ion exchanger from I service, #12 purif into service #11 deborating in service 0635 Start 12A RCP Stop 11 A RCP 0854 Stop 12B RCP Start llB RCP I 180
TABLE 1 (CONT'D) 1/27/C0 1035 Stop 12A RCP Start 12B RCP 1225 Stop 11B RCP Start 12A RCP 1250 Started addition of 9.1 Liters of Hydrogen Peroxide 1415 Completed add of Hydrogen Peroxide to RCS 1736 Stco 12A RCP, Start 11B RCP 1746 Started Addition of 2.0 Liters l Hydrogen Peroxide to RCS 1816 Stop 12B RCP Start 12A RCP 1835 Completed add of Hydrogen Peroxide 2058 Stop 11B RCP Start 12B RCP 2110 Started Addition of 4.0 Liters Hydrogen Peroxide to RCS 2155 Completed add of Hydrogen Peroxide -i!z. to RCS E= 1/28/80 1030 Stop 12A RCP Start 11B RCP 1315 Start 13 Chargir.g Pump (11 Already Runningj 1335 Start 12 Charging Pump 1400 Increased Purif. Flow to $120.gpm 'I 1530 Completed Collection of Suspended Solids Sample for Chemical Analysis 1830 Stop 11B RCP Start 12A RCP 1/29/80 0230 Started 11B RCP Stop 12A RCP 1030' Start 12A RCP Stop 11B RCP 1125 Remove 12 ourif IX from service and placed 11 Deborating IX & 11 Purif IX In Series i 1151 Stop all RCP's I I 1e1
TABLE 1 (CONT'D) 1/29/00 1248 Start 11B RCP 1252 Start 12A RCP 1825 Start 12B RCP Stop 11B RCP 2150 Stop 12A & B RCP 2155 Stop SDC Flow Thru IX 2200 Stop 12 & 13 Charbh; Dump 2220 Stop 11 Charging Punip I 2233 Start 11 Charging Pump 1/30/80 0200 Stop 11 LPSI 0630 Purification on SDC I ge I I I I. I E 4 I I 182
I ~ TABLE 2 THEORETICAL VERSUS OBSERVED OXYGEN LEVELS FOLLOWING HYDROGEN PEROXIDE ADDITIONS I ADDITION VOLUME THEORETICAL OBSERVED RATIO TIME ADDED(LITERS) OXYGEN (PPM) OXYGEN (PPM) THEORETICAL /0BSERVED 1415 9.12 1.57 0.109 15.7 1835 2.0 0.76 0.250 3.04 2155 4.0 1.52 1.00 1.52 .I I I' I I 'I
I m
I l I I 183
TABLE 3 TYPICAL Co-58/Co-60 RATIOS FROM l STEAM GENERATOR DIAPHRAGMS UNIT 1 Co-58/Co-60 ACTIVITY (uti) Co-58/Co-60 RATI_0,0 Outage #2 2.38E-1/1.30E-1 1.'8 Outage #3 5.26E-1/1.29E-1 4.1 I UNIT 2 Outage #1 6.89E-1/7.48E-2 9.2 Outage #2 7.44E-1/8.78E-2 8.5 I I I+. I I b h en I t l: 0 l I 184 --.--.~.2
TABLE 4 Co-58 DEC0tiTAMll1ATION FACTORS Co-58 Activity (uCi/ml) DEC0fiTAMItiATION DATE TIME IllLET OUTLET FACTORS 1 l 1/27 0247 4.7 E-1 6.6E-4 712 1/27 1800 1.54 8.5E-4 1812 1/28 0800 1.17 4.3E-4 2720 1/28 1600 8.1 E-1 2.3E-3 352 1/28 2000 4.5 E-1 3.5E-3 128 l 1/28 2400 3.3 E-1 7.8E-3 42 " 1/29 0800 1.2 E-1 2.8E-3 43 1/29 1145 2.3 E-1 1.3E-3 1772 1/29 2000 1.3 E-1 4.9E-3 262 I* .I >I I l 1 Decontamination factors were taken across #12 purification ion exchanger (cation) and #11 deborating ion exchanger (mixed bed) in series operation 2 #12 purification ion exchanger removed from service and #11 purification l ion exchanger (cation) placed in service at 1125 hrs. on 1/29/80 I .I I 185
I REFEREflCES I 1. EPRI Report f(P-692, " Effects of Hydrogen Peroxide Additions on Shutdown Chemistry Transients at Pressurized Water Reactors", April 1978 2. " Fort Calhoun-1, Reactor Coolant System Peroxide Treatment 11/10/74 to 11/13/74", Principal Investigator-D. J. tiorgan 3. RCP 1 1206 " Reactor Coolant System Hydrogen Peroxide Treatment" Revision 0, January 9,1980 I ~ I I !I g:. l I I l I lI ~ I I lI ~ 186 =
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ML19331C682

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