ML20005A138
| ML20005A138 | |
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| Site: | Farley  |
| Issue date: | 05/31/1981 |
| From: | Kahn D, Kornblith L, Untermyer S NATIONAL NUCLEAR CORP. |
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- EPRI TESTS OF NNC WATER LEVEL INDICATOR AT ALAMBAMA POWEP. COMPANY'S FARLEY ONE NUCLEAR PLANT FOLLOWING UNIT ONE SHUTDOWN - NOVEMBER 7,1980 ,
k RESEARCH PROJECT 1611 KEY P!'ASF REPORT, MAY 1981 Prepared by NATIONAL NUCLEAR CORPORATION 1904 Colony Street Mountain View, California 94303 Principal Investigators and Authors Samuel Untermyer
- Lester Kornblith David Kahn l .I l
l ELECTRIC POWER HESEARCH INSTITUTE 1
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TESTS OF NNC WATER LEVEL INDICATOR AT ALAMBAMA POWER COMPANY'S FARLEY ONE NUCLEAR PLANT FOLLOWING UNIT ONE SHUTDOWN - NOVEMBER 7,1980 7
, RESEARCH PROJECT 1611 KEY PHASE REPORT, MAY 1981 s
Prepared by NATIONAL NUCLEAR CORPORATION 1904 Colony street Mountain View, California 94303 Principal Investigators and Authors Samuel Untermye: Lester Kornblith David Kahn EPRI contract RP1611-1 i Prepared for Electric Power Research Institute 3412 Hillview Avenue Palo Alto, California 94304 EPRI Project Manager Dr. Patrick G. Bailey Analysis and Testing Program . , Nuclear Power Division
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i ( NOTICE This report was prepared by the organization below as an account of work sponsored by the Electric Power Research Institute, Inc. (EPRI). Neither EPRI, members of EPRI, the organization (s) named below, nor any person acting on their behalf: (a) makes any warranty or representation, express or implied, with the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe
, privately owned rights; or (b) assumes any liability with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this report.
Prepared by National Nuclear Corporation Mountain View, California
l EPRI PERSPECTIVE PROJECT DESCRIPTION Follow?.3 the accident at Three Mile Island, considerable attention has been directed toward instrumentation systems capable of measuring water in PWR vessels during normal operation, shutdown, and transient condition < As a result of the need for reactor operators to be aware of the plant . conditions that may result in inadequate core cooling, the USNRC has
, recently issued guidelines in NUREG 0737 that require each utility to comit to a choice of and begin plans to install a water level reasurement
' system before January 1,1982. The purpose of RP1611 is to review such proposed instrumentation systems and perform limited development, testing, and analyses of alternative and promising concepts.
PROJECT OBJECTIVE ' The objective of this work has been to develop, test, and analyze the results of a proposed non-intrusive water level detection system. This system consists of neutron radiation detectors placed both above and below the vessel . The potential advantages of such a system are its relative very low cost, ease of installation, modification, and parts replacement. PROJECT RESULTS Four separate top detector assemblies and one large bottom assembly, each containing BF-3 neutron detectors, have been constructed for measuring the neutron count rate above and below, respectively, the PWR vessel after shutdown. Tests using only the top detector 5ssemblies were condteted at the Farley Unit One nuclear plant during a normal plant refueling shutdown during November 1980. A number of draindown and refill tests were performed that allowed the water level to reach as low as the core nozzle midplanes. The results of tha measured count rate vs. measured water level indicate that the detection system tested may be able to be used to indicate water level variations below approximately six feet above the top of the reactor core. Additional analyses are being conducted under seperate contract in this project to model the theoretical response of this non-intrusive system concept. Additional tests of the complete system are being planned to be conducted on the Farley Unit Two plant in 1982. l s -
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ABSTRACT
. Following the TMI incident, EPRI asked National Nuclear Corporation (NNC) to de- ,
velop a ncn-invasive coolant level monitor (NICLH) that could be installed en ex-
- isting reactors without penetrating the pressure system. The NICLM system mea-sures mass of water per unit area above the reactor core. The detected reaction radiation consists of photoneutrons created by interaction of energetic gammas from 140La fission product and deuterium in the coolant water. Tests at Farley I indicated that the neutron count rate above the core was affected by water level but that count rates were low. Since the core had been shut down for several days before the measurements were made, this did not conclusively indicate the appli-cability of the NICLM system soon after shutdown.
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I CONTENTS Section Page 1 INTRODUCTION 1-1 Theory of Non-Invasive Water Level Indicator 1-1 History of Water Level Project - Previous Tests 1-2 Contractual Relationships and Project Personnel 1-2 Objectives and Test Program 1-3 2 DESCRIPTION OF EQUIPMENT 2-1 Reactor 2-1 Detectors 2-2 Electronics 2-2 3 CHRON0 LOGY OF TESTS 3-1 4 TEST RESULTS 4-1 Relationship of Count Rate and Water Level 4-1 Wide Range Indication at Temperature 4-3 Streaming or Photoneutrons? 4-4 Decay of Counts After Reactor Shutdown 4-4 Background Count Rate 4-5 5 DISCUSSION AND CONCLUSIONS 5-1 Application to Power Reactors 5-1 Further Areas for Investigation 5-1
. APPENDIX A EQUIPMENT AND LOCATION DRAWINGS AND DIAGRAMS A-1 APPENDIX B EQUIPMENT ADJUSTMENT PROCEDURES B-1 APPENDIX C TEST PROCEDURES AND DETAILED DATA SHEETS C-1 S
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SUMMARY
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Following the TMI incident, Dr. Edwin Zebroski, now Director of NSAC, asked NNC to develop a Non-Invasive Coolant Level Monitor (NICLM); one that could be instal-led without penetrating the pressure system. NNC proposed a system consisting of radiation detectors mounted above the vessel. Comparing readings of these de-tectors with a normalizing reading from other detectors on the side or bottom of the vessel provides an indication of reactor water level. The NICLM system measures mass of water per unit area above the reactor core, there-fore it provides a warning of either low water or boiling. Unlike other level indicators, however, circulation rate or water turbulence will not effect the readings. In practice, it has been found that after shutdown the detected radiations consist of energetic fission product gamma rays, such as those from 140La. These gammas have energies higher than activation gammas such as soCo which are abundant near the top of the vessel. Energetic gammas are detected (in the presence of 60Co) by measuring photoneutron emission from deuterium in the coolant. Neutrons from beryllium are then detected by BF3 neutron counters, which are insensitive to gamma rays.* Relative gamma attenuation between the top and side (or bottom) detectors provides the basis for the water level measurement in the shutdown reactor whenever the core is submerged under more than three feet of water. When the core is submerged by less than three feet of water, neutrons produced in the core are able to pass through the water and reach the top detectors directly; thus resulting in extreme-ly high count rates, giving the operator a clear indication of imminent core un-covery. This counting " spike" which occurs just before uncovery is one of the safety features of the NICLM system.
- Gamma ray detectors cannot be used because they cannot distinguish between 60Co sum gammas (total 2.5 MeV) from the energetic-fission gammas.
The top detectors count until they accumulate a fixed number (typically 100 or 1000) counts. They then repeat the cycle. The reference side detectors are gated to count during the period when the top detectors count, and recycle when the top i detectors recycle. The counts then displayed by the reference detector scalers at the end of each cycle are proportional to: Side detector counts - Top detector counts This quotient is related to water level. BWR. measurements indicate that the attenuation length of neutrons in cold water is between 4 inches and 6 inches of water at operating temperature. Thus, the operating detector readings should increase by a factor of 14 or more when the level falls 16 inches. Consequently, the neutron detectors used during reactor operation will increase rapidly should a void form. This gives the timely indi-cation needed for early reactor shutdown. 1 i l i
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Section 1 INTRODUCTION THEORY OF NON-INVASIVE WATER LEVEL INDICATOR Following the TMI incident, EPRI indicated the desirability of measuring reactor water level after shutdown without penetrating the pressure system. NNC proposed a system consisting of sensitive neutron detectors mounted above the reactor vessel. Readings of these detectors would then be compared with count rates either from existing startup detectors or new detectors installed under the vessel. The ratio of these counts would then provide an indication of reactor water level. In the course of the resultant EPRI funded investigation, two different theories evolved as to the way neutrons reach the top of the vessel through large thick-nesses of water. Through shorter water thicknesses (up to three feet of room-temperature water) there is little question but that neutrons from the reactor diffuse through this water in tre conventional fashion. For higher water levels, however, there is a difference of opinion on the mechanisms involved. Photoneutron Production in Water Les Oakes' (EPRI) suggestion, based on an ORNL test, postulated that energetic gammas from the reactor core may react with isotopes such as deuterium in water to produce neutrons at considerable heights above the reactor. If this is true, then following shutdown, neutrons produced far from the core would reflect gamma levels in the core (hence preshutdown power) and to water geometry near the de-tectors, but would be insensitive to the core neutron source and core multipli-cation (boron). Streaming of Neutrons Around Reactor Vessel During a mee:ing at SAI in October,1980, Dr. Tom Albert explained that extensive calculation on other reactors using computer codes demonstrated that at least 90% of the neutrons reaching the top of the reactor vessel arrived there from the core I 1_1
through clearance between the shield and the vessel, or by other streaming paths between the core and the outside of the shield. If this theory is correct, then the neutrons above the vessel should depend on post-shutdown neutron production. Past shutdown neutron production in turn de-p;nds on source strength and core multiplication. Since core multiplication (bo-ron) affects neutron production of this theory were valid, it would seem that bu-ron content would have an effect on the top detectors. These theor4s have been discursed extensively with APCo and EPRI personnel, in-cluding Dr. Pat Bailey, J. J. Thomas and the APCo reactor engineer, Randy Marlow and tentative conclusions based on Farley tests will be discussed later in this report. HISTORY OF WATER LEVEL PROJECT - PREVIOUS TESTS During the Sumer of 1979, under EPRI contract TPS79-741, NNC conducted tests using a large 252Cf source ir a water tank which indicated the proposed method of level measurement had promise for levels up to 8'10" cold water depth. Under contract TSA79-296, NNC made measurements at Rancho Seco (SMUD), Prairie Island (NSP), and Trojan (P.G.E.) reactors during their scheduled outages. Tests at Trojan in particular, which were made with a properly shielded and biased de-tector, indicated promise; so a much more extensive test, under EPRI sponsorship was planned for James M. Farley Unit No.1 (APCo). The previous tests are sum-marized in " Water Level Tests at the Trojan Nuclear Generating Station and the Design of Prototype Water Level Indicator" May 4,1980. This report is attached as Appendix 0. CONTRACTUAL RELATIONSHIPS AND PROJECT PERSONNEL Experimental work on this project by NNC is being funded by EPRI. Dr. Pat Bailey is the Project Engineer. EPRI is also funding the manufacture and test of the complete set of detectors and electronics used in this experiment. Under separate contracts, EPRI is funding calculations by reactor physicists at SAI (San Diego) and by another group located near Oak Ridge. Finally, EDRI is arranging for a test of a single detector, at low water levels, by the E.G.&G. group at LOFT in INEL at Idaho. This test was performed in late 1980.
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While NNC equipment and services during the test was funded by EPRI, this tsst would not have been possible without the extensive and continuous assistance of APCo and Southern Services personnel. Bill Hill of Southern Services served to coordinate the work in Alabama that led up to the conduct of this test. Ron George (APCo) participated in this preparatory work. During the test, NNC and APCo personnel worked essentially as a unit to inctal? equipment and to collect and interpret the data. In general, APCo installed equipment, particularly in areas where respirators were required, er where work interfaced with other APCo operations. NNC could, therefore, concentrate on installing and mair.taining elec-tronics and on taking and interpreting data during the test. In the later stages, however, as APCo technicians became accustomed to using the equipment, APCo also operated the counting equipment. Only through this close relationship could this test have been completed without serious interference with the normal APCo shut-down schedule. Personnel involved in this test and their principle functions were as listed be-low: e J. J. Thomas, APCo, Controls and Instrument Supervisor at Farley. Thomas was in overall charge of this test, and made all arrange-ments for its conduct. He also suggested many improvements in the procedure and in the equipment. In particular, his suggestion for shielding the detectors materially improved the utility of the system. Under Thomas' direction, many technicians, generally su-pervised by Bill Lee, handled work on the test throughout the plant. All level readings and startup counter readings taken in the con-trol room were obtained through personnel under Thomas' direction. e S. Untermyer, Project Manager, NNC e L. Korr511th, Principal Engineer, NNC e M. Schmitt, Field Engineer, NNC. Installed and maintained elec-tronic equipment Test operations during the period November 10-14 were on a continuous basis round-the-clock. NNC personnel took reactor head counter data until November 13, when APCo technicians took over all data collection. Throughout the test, APCo pro- ' vided data from the control room (level and startup counters, as well as boron content of reactor water). OBJECTIVES AND TEST PROGRAM The objective of the test was to obtain definitive measurements of the relation-ship between neutron count rate above the reactor vessel after shutdown and re-actor vessel water level. . . _ u
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ksecondobjectivewastodiscoverwhichvariablessuchascorereactivity, shield-ing, and neutron background affected this relation. A third but incidental objective was to learn approximately how rapidly this count rate decayed during the period of measurement. A fourth objective was to determine as well as practical the true cou..ter back-ground of these counters due te cosmic rays, naturally produced neutrons, a'd n alphas from tne detector materials. - The test procedure prepared by J. J. Thomas is contained in Appendix C. This procedure follows tht patterns laid out during a meeting at Farley on September 31. A few changes were made in this procedure during the test to accommodate infor-mation developed during the test. The procedure for setting the gamma descrimination level is described in Appendix B. This test procedure resulted in selection of the following electronic equipment settings: e Detector Voltage 3600 e Amplifier Gain 20 e Descriminator Setting 7 volts e 8 i 1-4 u
Section 2 DESCRIPTION OF EQUIPMENT
. REACTOR ,
The Farley reactor is a Westinghouse 800-Megawatt class pressurized water reactor
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located near Dothan, Alabama. The plant has been producing power since late 1977 and, the ' its were conducted during the early days of the second refueling outage. An elevation of the reactor pressure vessel is shown in Figure A-1 of Appendix A. The ves;el is installed in a containment building that includes a minimum thick-ness of three feet of concrete shielding. Although the concrete is provided for other purposes, it affords a substantial shielding against cosmic rays. Figures A-2 and A-3 of Appendix A show, respectively, a more detailed vertical cross-section of the re=-+or vessel head area and a plan view. In Figure A-2 the vertical location of the detectors is shown. It is on top of the vessel head in-sulation at an elevation of approximately 134'9". The plan view shows the initial location of the four units. As noted in the table at the bottom of that drawing, the detectors were originally installed at radial distances outside of the insu-lation ranging from 14 to 26 inches, but on November 11 all were moved to posi-tinns such that the detector centerlines were 14 inches from the surface of the
. insulation. Inis was as close as they could practically be installed. The cir-cumferential locations shown are approximate and, in some cases, were changed slightly when the detectors were moved closer to the centerline.
The proposed final location for the detectors in this plant would be on brackets down and in towards the vessel from the ventilation duct support structure shown aoove and to the left of the detector in Figure A-2. The location would be chosen, subject to the existing physical constraints, to be as close to the centerline as possible, to avoid shadow-shielding by the very thick reactor vessel flange, and to be as low as possible to maximize the counting rate. The many physical inter-ferences will, of course, limit the possible location, and will require a compro-mise of the several parameters.
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DETECTORS The complete set of detectors supplied to Alabama Power Company to be used in the final installation consists of two sets of detectors, one above the reactor and one below, used as described in the section above on the theory of the measurement system. Each set consists of eight 2-inch diameter, 24-inch active length 10BF3 - filled thermal neutron counteis. These detectors are made from stainless steel and are filled to 70 cm. Hg pressure. They are shielded by a 7/16-inch thick lead _ ; sleeve, and they are surrounded by a plastic modarator. An additional -inch lead . shield is provided between the reactor vessel and the detectors. The top set consists of four assemblies, each containing two counters. Each pair of counters, with its plastic moderator and lead shield, is contained in a steel box approximately 0.64 inches thick. Figure A-4 is an assembly drawing for the top detectors showing both the approximate overall dimensions and the arrangement of the parts. The bottom detectors are all contained in a single unit shown in Figure A-5. Alabama Power is investigating to determine if the single unit can physically be installed in the space available. If not, it will be rebuilt into two half-size units. This may eventually be necessary anyway, in order to comply with NRC redundancy requirements. For the top set, these requirements can be met with the present units but with slight modifications to the initial wiring external to the detectors and some additiorr.1 electronics equipment in the control room. Only the top set of detectors was used in the current test program. A separate set of detectors will be provided in the final installation for use during reactor operation. This is necessary because the large detectors are too sensitive for use under such conditions. The set will consist of two small, less sensitive 10B-lined counters, one above and one below the reactor. They will be provided with moderator and shielding similar to that provided for the large de-
- tectors. The geometry will be different and will probably make use of the lead and plastic presently contained in the large detectors. If redundancy require-
. ments make it necessary, two detectors will be furnished for each location. Switch-ing between the large and small detectors will be automatic. These small detec-tors were not included in the present test installation.
ELECTRONICS The electronics used in the test program is a subset of the equipment provided for the complete installation. The basic arrangement planned for the test was modified
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as the program was carried out in order to make operation more convenient, but no changes were made that would make the test less representative of the final ar-rangement. A Tennelec Model TC 175 FET Charge Sensitive Preamplifier was mounted on the end of each of the four detector assemblies. The output signals from the four pre-amplifiers were combined and fed, through abo _t 150 feet of RG-59 cable, to a
' Tennelec Model TC 216 Linear Amplifier and Single Channel Analyzer, located on the 155-foot level in che containment building. The output of the single channel -
analyzee was intially fed to an adjacent scaler, but soon after the test started this was changed so that the SCA fed, through a long cable terminated for impedance-matching purposes in a second amplifier, a separate scaler located in the hot in-strument shop, also on the 155-foot level but outside of containment. This elimi-nated the need for protective clothing for the people operating the counting equip-ment. Low voltage power was provided to the preamplifiers from a power supply located in the NIM bin housing the linear amplifier and single channel analyzer. The high voltage power supply for the counter tube was also housed in this bin and both power supplies were connected to the detectors by appropriate 150-foot long cables. A sketch of the system is shown in Figure A-6. e 9
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Section 3 CHRONOLOGY OF TESTS
. November 8: Set up detectors outside containment ,
Desiccant packages had shorted some terminals
. . Repaired detectors November 9: Ran plateau and threshold curves using background neutrons and gamma source.
November 10: Measured background inside containment Set detectors on reactor head Measured gamma level at detectors Connected amolifier analogue output to descriminator in hot instrument lab Counted during night November 10-11 Due to discrepancy in liquid manometers, level was reduced during night, but no change on counters November 11: Moved detectors closer to center of head Remeasured gamma levels Took single 1000 second counts at two foot intervals
- Data were erratic Novembe.* 11-12: Connected pulse output from amp-discriminator in containment to counter in hot instrument room to eliminate double count errors Obtained first reliable data night of November 11-12 November 12: Found that highe:t level (with some water above detectors) gave anomolous high reading ,
Meeting at 0900 on results and program included Dr. Pat Bailey, EPRI; J. J. Thomas, APCo; W. H. Hill, Southern Company Services; Dr. Tom Albert, SAI; S. Untermyer, NNC; L. Kornblith, NNC. Recommendations: Bailey - provide complete data and run lower discriminator to get more counts. Albert - provide raw data and check for streaming, run one detector. Thomas - provide addition shielding around detectors.
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Following the meeting, about six inches saturated boronated water in plastic bottles was placed on sides and top of the detectors. Operation of detectors .as checked with an 8 curie Pu Be neutron source in a shielded cask. This source in a cask gave many counts even at long distances. Obtained data with shields on detectors Anomolous effect with completely full vessel was eliminated and counts were generally lower, indicating lower background. November 12-13: Continued counts - During the night, workmen damaged a cable from one preamp to
. junction box. This increased pulse height from remaining de-tectors, introducing gamma counts and raising count levels.
. In morning, a discriminator check showed the damage which was repaired, and counting war resumed.
Experiment showed neutron source in storage contributed slightly to background counts. November 13-14: Counting was continued In early morning, Operations increased boron level in reactor about 50%, decreasing startup detector counts about 50% with-out changing top detector counts November 14: Removed detectors from reactor head to new position in containment at level 155 Placed detectors to provide maximum mutual radiation self shielding. Counted detectors with and without water shield bags As elevator had failed, could not remove Pu-Be neutron source, but measurements with additional shield in front of this source showed effect to be small November 14: Conclusion of test e t l 3-2
Section 4 TEST RESULTS RELATIONSHIP OF COUNT RATE AND WATER LEVEL . A sumary.of test data, prepared by J. J. Thomas is shown on Figure 4-1. This figure clearly shows the ' increase in count rate as the water level is lowered, as wel.1 as the reduction in count rate with time after shutdown. The point at 136 elevation with unshielded detectors is believed to be high due to the.effect of water above the detectors. m d E* CInitial test run 11-11,12, 1980 det. unshielded 88: V Second test run 11-12,13, 1930 det shielded 3 C Third test run 11-13,14, 1980 det. shielded 260
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200 N.' ~_*~ _ _ ~ r 183 $ i y E E Mm W W ad a 160 "5 SE sS E Ed aE E e SW 140 h 123 124 125 126 127 128 129 130 131 132 133 134 135 136 RCS ELEVATION (FT) Figure 4-1. Farley Unit 1 NIRVLMS test data - count rate versus'RCS .'wel data obtained via FNP-1-ETP-192 on November 11-14, 1980 l u 4-1
The single, averaged curve 4-2 was prepared as foll s:
- 1. The 136 elevation point with unshielded detectors was not used.
- 2. 12 additional points not included in the APCo data sheets, but re-corded by NNC were added to the compilation.
- 3. The three curves were adjusted to allow for decay.
- 4. Data was averaged and error bars were added. !
- 5. A scale was added to show net count rate, based on the background .
measured after the test on level 155. NET CPS 1
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.18 1.10 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 HEIGHT OF WATER OVER CORE Figure 4-2. Average dat, from Figure 4-1 measurements with cool reactor water t
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WIDE RANGE INDICATION AT TEMPERATURE Figure 4-3 shows the net count data on Figure 4-2 replotted on semi-logue paper and extended to lower water levels based on the water level test data. As pointed
. out by Dr. Bailey, the water tank data has a much greater dependence on level than does the shutdown reactor data. Also shown on Figure 4-3 is a curve corrected for the water density at operating temperature, on the assumption that a 10 foot depth of hot water gives the same count rate as 6 feet of room temperature water.
NET , CPS 10 - 8-7t 6= 5-i i \ 4-I
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l I f l l 0 2 4 6 8 10 ' 12 14 16 18 20 l FEET HOT WATER OVER CORE Figure 4-3. Composite curve Farley data corrected to operating density and norma'ized to Farley count rate a$ h i 4-3
O STREAMING OR PHOTONEUTRONS? The temperature correction method used assumes most neutrons travel through the water to the detectors, but SAI has suggested that, in fact, most neutrons straam to the detectors from the core through small openings between the shielding and the reactor vessel. This section attempts to summarize evidence for each of these theories. *
- Evidence For Streaming .
- 1. SAI calculations on similar reactors show streaming contributes most above the reactor.
- 2. There does not appear to be any way for the neutrons or gamma rays to penetrate such large water thicknesses.
- 3. For the same water thicknesses, the water tank tests show much higher count rates with roughly similar neu.. 'n source terms. Also, the effect of water thickness is much greater in the tank tests.
This dif.erence, however, may perhaps be explained by the difference in the gamma energies between primarily fission garnas in the tank test and primarily fission products at Farley. Evidence For photoneutrons
- 1. When measurements were made with unshielded detectors, the 136 foot elevation point with water 00tn below and to the side of the de-tectors showed a higher than exp :ted count rate. This effect disappeared when the detectors were shielded on top and sides.
This can be explained if photoneutrons reached the detectors from both below and from water to the side of the detectors whenever the water level approached er exceeded the detector elevation (about 135 feet).
. 2. At 0340, November 14, Operations increased boron in the reactor from 1040 PPM to 1584 PPM. Randy Marlow (APCo Reactor Engineer) esti-mates this decreased core reactivity 6.75%. As shown in Table 4-1, abstracted from APCo data sheet No. 7 show: that startup detectors (which read fast neutron leakage through the vassel well from the core) decreased about 50%. Nevertheless, vessel top counters did not change appreciably. On the balance, from available evidence, it is believed that neutrons detected above tne reactor do not originate in the reactor core and are produced in the water near the detectors.
DECA) 0F COUNTS AFTER REACTOR SHUTDOWN Data are not accurate enough to provide an accurate estimate of the half-life of the radioactivity which leads to neutron counts in the detectors above the re-actor vessel. Only the second and third runs had identical detector arrangements. l 4-4
Table 4-1 COUNT RATE DATA AS A FUNCTION OF TIME AND BORON CONTENT Boron Startup Counters (CPS) Top Reactor Counters Time Level (PPM) N-31 N-32 (CPS) 0005 125 1040 222 339 0.227 . 0130 123 1040 221 338 0.222
, 0147 123 1040 221 338 0.212 ~
0204 123 1040 221 339 0.214 0221 123.5 1040 222 339 0.229
. 0340 Added Boron 0354 129 1584 118 169 0.219 0411 130 1584 116 167 0.196 0650 134 1584 Not Taken 0.216 0707 135 Diluting Boron
- Not Taken 0.204 0725 136 192 282 0.178 0734 136 194 286 0.185 0759 136 203 298 0.204 0816 136 211 308 0.184 On the average, these runs were made about 20 hours apart. The later run was about 15 counts lower, and the net count rate was about 130. Using these crude values, the mean life would be:
fh0 Xff=7 Days. (5 days half-life)
'ihis is not inconsistent with 12.8 day 1"0Ba- 40 hour 140La mixed with other short-er lived isotopes. .
BACKGROUND COUNT RATE The best background counts were obtained after the test when the detectors were moved to level 155. Detectors were placed clase together to provide mutual shield-ing, and counts were taken both with and without 6" of boronated water shielding. In a previous test, with the detectors on top of the reactor head, (APCo Data Sheet 5) it appeared that the Farley calibration neutron source (8 curies Pu Be estimated 107 N/S) produced more than one sigma increase in count rate when stored outside tne containment (3'9" concrete plus 18" plastic shie'lding). In the back-ground test, due to a broken elevator, it was impossible to store the source be-low ground so counts were taken both with and without an extra-10 gallon plastic l
. . filled bucket between the source and the detectors. ,
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l As counts were taken the last day, after APCo logues were prepared, the data are listed here: Time (Nov. 14F Condition Counts Per 1000 Sec. Average cps 1310 No Water Shields 118, 158, '41, 148 0.141 2 0.006 1426 6" Boronated Water 91, 76, 87 0.085 0.005
-Shields 1500 Baronated Water With 77, 91, 96 0.088 0.006 .
10 Gal. Case in
. Front of Source
. From these data, and considering the extra shield inherent in the location with-in the reactor cavity, the value of 0.08 CPS was used for background on top of the reactor.
This background is due to alpha. emitters in the counter tubes, cosmic rays, and other miscellaneous neutron background contributions. By comparison, these de-tectors had a background in the NNC unshielded laboratory in California of approx-imately 2 CPS. The following page gives Reuter Stokes estimates for alpha background levels in proportional counters. In the Farley test there were eight stainless steel tubes, 2" diameter, 24" long. Using an average value of 5.3 Counts per hour per 100 cm2: 5.3 x 8 x 2n100 x 24 x 6.45 x 1000 = 114 Counts Per 1000 Seconds x 3600 As this value is higher than the total measured background, Reuter Stokes may have bettered the background levels of their counters. O I l l I l l
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- REUTER STOKES DATA NATURAL BACKGROUND OF PROPORTIONAL COUNTERS A
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Practical materials for the construction of the bodies of these counters are alu-minum, stainless steel, copper or brass. Natu,al background consists of alpha and beta particles generated from the inner surface of the counter. Two compar-isons of materials for the alpha effect are: Alpha Background of Materials Stainless Brass Copper Steel Aluminum 2 6 31 Counts /100cm /hr (1) 6 1 Counts /100cm2
/hr (2) -
1.1 4.8 27 The energy and ionizing efficiency of 3.fla particles is st #ffcient to produce pulses induced by the (na) reaction of thermal neutrons; i.e. alpha emission by the counter body will be indist;nguishable from neutron pulses. The common requirements of I cpm background can be routinely met in one inch diam-eter counters with up-to 1000cm2 internal area. The figures indicate that this requirement can be met in aluminum counters of approximately 200cm2 area. In prac-tice, our counters using 1100 Aluminum have an even lower backgrot.nd than that theoretically derived above. For example, we are supplying BF3 counters with alu-minum bodies with a maximum background of 1.0 cpm where in the counter has an in-ternal surface area of 263.4cm2 . The natural beta activity of materials is: Beta Background of Materials Stainless Brass Cooper Steel Alumumm Counts /100cm2
/hr 16-W 3-6 300 240 The beta particles have low energy and poor ionizing efficiency, and pulses pro-I duced from this source are not suf ficient to significantly effect the neutron pulses since they are buried in the :,ystem noise and/or are below the discriminator level of the counting system.
4-7 '
Section 5 DISCUSSION AND CONCLUSIONS
. APPLICATION TO POWER REACTORS .
- 1. Tests at Farley-conclusively demonstrate that neutron detectors mounted
. above the reactor vessel respond to changes in water level within the vessel.
- 2. Improvements may_be made through better threshold adjustments on the detectors (as suggested by Dr. Bailey) and marked improvement is pos-sible with detector shielding (suggested by J. J. Thomas). Note: B t,C plastic shields for the detectors are now being fabricated.
- 3. Since neutrans above the vessel do not follow the pattern of core shut-down power, a normalizing detector array below the vessel is required to provide good accuracy in water level measurement. Such a detector does not appear needed to provide a warning, only as planned for the Farley 1 initial installation.
- 4. While count rates measured after four days shutdown were very low, the count rates during the critical period shortly after shutdown are esti-mated to be about 100 times higher, which should be ample.
FURTHER AREAS FOR INVESTIGATION l 1. A clear understanding is needed of the mechanism whereby neutrons reach the detectors when the core is covered by 10-20 feet of water.
- 2. Tests, similar to those at LOFT, should yield a better understanding of behavior at lower water levels, at shorter times after shutdown, and under transient conditions.
1 e l 5-1 ;
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ll i i l l l Appendix A EQUIPMENT AND LOCATION DRAWINGS AND DIAGRAMS e 4 4 e
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rr Appendix B EQUIPMENT ADJUSTMENT PROCEDURES
. DETECTOR THRESH 0LD SELECTION '.
Previous experience with these detectors indicated that the operating voltage should be between 3200 and 3800 volts. A test using background neutrons outside the containment was run on November 8 (Figure B-1) and plateaus.were obtained which indicated 3600 volts to be suitable. A test was then run (Figure B-2) which indicated the detectors would count neutrons with a gain of 20 and thresholds as high as 8 volts. A threshold of 7 was used in all tests. METHOD OF ESTIMATING THE REQUIRED GAMMA RAY REJECTION THRESH 0LD If a randomly spaced chain of P uniform length square pulses is received per sec-ond, then if each pulse has a length of T, the rate or counting single pulses will be P, the rate of counting two superimposed pulses will be P (PT) or and the rate of counting X superimposed pulses will (PTE. p These expressions neglect higher order effects, bu't are accurate in the range required. The rate of observing pulses of height greater than X pulses high is then (PT)x p plus negligible higher order terms. Tutting this rate equal to Y; y , (PT)x P l logPT PY = X Tht.s when the logue of the count rate from such a pulse chain is plotted against threshold setting, it results in a straight line. Similar argur.ents indicate that other combinations of pulse pileups result in a straight line when pulse rate is plotted against threshold on similar paper. This e
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THRESHOLD VOLTS 0.1 i . ; 2- 3 4 5 6 7 8 9 Figure B-2. Threshold check in shop with background neutrons
, 3600 HV 6 = 20 100 sec. counts ,
i
~
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fact serves as the basis for setting the threshold bias at the lowest value that will discriminate against gamma rays. l The method'used is shown.on Figure B-3 and B-4. Figure B-3 shows that a thresh-old more than 5 is needed to eliminate 200 MR/H of 60Co gammas in the shop. Figure B-4 curve a shows the count rate from background gamma rays and desired neutrons when the detectors were placed above the reactor where the gamma radiation level 7 was about 300 MR/H. The straight portion of the curve is due to gammas, the de-viation is due to neutrons. Subtracting an estimated neutron count rate of 0.23 per second yields a curve which is due to gammas only, and hence is a straight line on semi-log paper. This shows that the chosen threshold of 7.0, the gamma background is less than 1% of the neutron count rate. On Ncvember 13, curing the course of the experiment, a workman inadvertantly dis-lodged one of the 4 cables lerding from the preamplifiers to the junction box. This reduced the preamplifier output loading from 75 ohms
- 4 to 75 ohms
- 3; in effect lowering the bias to 7 x 3/4 while reducing the counters from 4 to 3. The immediate effect was an increase in the count rate at trir2shold 7, from about 0.2 up to 0.3 CPS. This increase was due to gamma interference at the lower threshold.
The cause was understood as soon as the bias curve b on Figure B-4 was obtained. It can be seen that eat.: point on the gamma line is at a bias level 4/3 higher but at this higher bias there are 3/4 as many counts. The net effect is to in-crease the gamma interference greatly. Such semi-log plots provide a powerful diagrettic tool to set the correct threshold for neutron counting in high gamma fields, r l l
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- i
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. 3 10 4603 518
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FARLEY NUCLEAR PLANT ENGINEERINO TEST PRCCEOCE FNP-1-ETP-192 S A
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1 TNP-1-ETP-192 { FARLEY NUCLEAR PLANT UNIT 1 ENGINEERING TEST PRCCEOURE ETP-192 NON-INVAS!VE REACTOR LF.7EI MEASURING SYS-'EM lEST 1.0 Purpose l.1 The purpose of this procedure is te estahlish end verify the accuracy of the Non-invasive heactor Level Measurement System includ.ng detectors and associated signal processing squipment. 2.0 Acceptance criteria 2.1 Alabama Power Company will evaluate *'-* -asults of this test to determine feasibility of 4 si=ilar system for permanant installation at the plant. At the present time no formal Acceptance Criteria Exist. 3.0 References 3.1 FNP-1-ETP-192 Data Package 3.2 EG & G 0 tec Medel 773 Dual Ocun e:s 2perating and Service Manual 3.3 Tennelec Medel TO 175 Fet Charge-sensitive Preamplifier Instruction Manna. 3.4 Tennelec Model TO 215 Linear Anplifier & SCA Instruction Manual 3.5 Bertan Model NIM 342, 346, 353, 355 Single Wid h High Vcltage Power Supplies Ina ::ti:n Manual 3.6 National Nucles: 00. i. Preliminary Test Procedure 4.0 Test Erli; ment 4.1 Fluke ::igital Multineter, Model 5 20A : Ega: valent 4.2 Tekt : nix Cscill:sc:pe Model 5423 :: Esztvale .: 4.3 St:pwatch 4.4 4 sets of sound pcwered headph:nes and extens;:n cables 1 o
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FNP-1-ETP-192 5.0 Precauti ns and Limitations .
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5.1 All reference t data sheets by this ;; cedure is to darr sheets centained in re'-- --a 3.1. *. 5.2 Critical precedure sections and steps are listad en page 1 of the data package used w th this
. procedure and are marked w :t d an asterisk (*)
within the body of this p ce.ure. As each critical step or seenien is cenpleted, initial en the space pr:vided on Table 1 of the data package. 5.3 Cbserve all precautions and linitations listed in FNP-0-DIP-0, General Instrunenta::: and Cent: la Precautions and Linitations.
*6.0 Initial Cenditions 6.1 The Shift Forenan has granted ad=ints :ative authority to perfczn this test and is aware :"
.adications, printouts, and ala =s that will re .r. ult .
6.2 Verify TNP-1-:MP-201.4 9efueling RCS Level P: cedure has besn Inplenented. , 7.C Detailed Test P :cedure
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7.2 As seen as.pcssihie after Reacts: Shu;d:.n, set up equipnent en Elevation 155' in c:n-tainment. Measure neutron c:untrate. Rec::d neutron countrate en data shee 1. 7.3 Place each cf the four top NNC dete:::: assemblies abcve the reac::: vesse' en ' existing rea ::: vessel insulati:n. L ca:e the ass a the Co.....,enbles
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*7.6 observe c:un.s with reacter vessel full of ceci water ( < 200* F ). Take (4) 10C0 sec: d c:t .s to obse:-d trends 4 d stability of cous =g -
system. Record all per.1:ent data on shee 2.
*7.7 Measure Gamma Radiation Level at the detectors.
Rec :d levels c Data Shee 1. . 7.8 A::ange cor.musicatics with the ecst:01 reem (ie: Sound ?cvered Eeadphenes). 7.9 Have plant operatiens personnel lever -le Reacter Vessci wate'. level two (2) feet per nor:nal plant UCP's. Ta'<e a 10C0 sec d c:= . Rec d. all pe-'---- data c data shee: 2. 7.10 'Have plant operaticas perse=e1 lever -le React : Vessel vate: leve' arc her :se (2) feet. Take a 1000 sec::d c:unt. Rec: d all per.=ent data c= data shee: 2. 7,11 Repeat ste; 7.10 un-' ' -a =c :: vessel vate le rel is at centerline of =c::les. Rec::d all per.nent dat: == data sheet 2. 7.12 Eave plant c;erating persensel raise react:: vesse_ vater level rac (2) feet ta'<e a 1000 sec:=d c unt. Record all per.inen: data :: data shee 2. 7.13 Repeat step 7.12 until reacter vessel is full c.! vater.
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*7.14 Repeat steps 7.9 th:: ugh 7.13.las regized by y,,;. . . .
vendo: t: Obta = necessarr data (Maximu= Of 4 ##'*6, cycles). W SIC -
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*7.. o F-es data cella- =d ' h 7.14, calculate the Ratic: steps 7.9 th: ug/
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g ?iM f Record calcula,.icus : dita.,shee: 2
*7.15 ' ,. : calculated rati: (abc. Q s.
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*7.16 Notify Shift 7:: era: Of Tes ::=;'eted. .
*7.17 Disc:::ect & Re=cve all epi;=ent fr:s ::::ai= en:.
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FNP-1-ETP-192 . FARLEY NUCLE.E PLAN"' UNIT 1 i ENGINT. IRING TEST P.E0ZOURE OATA PAC:GGE .O.-192 l NCN INVASIVE RIA.OR LE*TEL ."ASURING - SYS'"ZM 1.0 Purtese This data package is to used in conjunction with procedure FNP-1-ETP-192 to record data. 2.0 References 2.1 National Nuclear Corp. Preli:.inary Test ?:ocedure 3.0 Procedure Sien-Off Sheet and Altera:icn :.cc 3.1 Initial the appr:priate space in Table 1 as each step or section is c mpleted in ETP-192 3.2 Record any te perarf alterations on Table 2 4.0 Test Results 4.1 Test ce=pleted satisfae:::y 4.2 Deficien:ies occurred (see data sheets for e. ,lanatien) 4.3 Tine re:;; ired fer test %e3 P::cedure Re*. used I 4.4 Test PerfcIned by M t..e _ Date /,4 'a p
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