ML20031D568
| ML20031D568 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/02/1981 |
| From: | Axtell C CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20031D553 | List: |
| References | |
| ISSUANCES-OLA, NUDOCS 8110130440 | |
| Download: ML20031D568 (42) | |
Text
i TESTIMONY OF CHARLES E. AXTELL CONCERNING CHRISTA-MARIA'S CONTENTION 2 AND O'NEILL CONTENTION II.A My names is Charles E. Axtell. I have been employed for approximately twenty years at Consumers Power Company Big Rock Point Nuclear Plant, P. O.
Box 59], Charlevoix, Michigan.
I have held the position of Plant Health Physicist for the last thirteen years.
(Resume attached.)
In this position I am responsible for radiation protection of plant personnel and the general public, and chemistry aspects of plant operation.
The purpose of my testimony is to respond to Chris :;-Maria's Contention 2 and O'Neill's Contention II.A.~1/
My testimony, together with that of Roger Sinderman and William Bell, demonstrates that the increase in fuel stored in the Big Rock Point Spent Fuel Pool (SFP) will not result in a detectable increase in the amount of radiation released to the environment at the south wall of the SFP, nor exceed the limits imposed by Appendix I to CFR Part 50 on exposures to the general public. Further, my testimony demon-strates that the releases of radioactivity during the installation of new racks, the loading of those racks, and storage of fuel in the racks will not exceed the limits imposed by ]O CFR Part 20 on the exposure of workers.
It may be best to start my testimony by referring to several pictures of the area that will be discussed during my testimony.
Figure 1 is a top view of the reactor icvel and SFP area. This picture was taken from the highest elevation (emergency condenser level) in the containment sphere, looking northeast. On the right is the rectangular spent fuel pool; the circular shape on the left is the reactor shield plug
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If These two contentions are quoted in full subsequently in this testimony.
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l which covers-the reactor. There are two fixed area radiation monitors for this area; one on the nearest corner of the SFP which you can see on this j
Figure, (yellow canister on blue pole), and the other is located on the steam drum wall which is off to the left of this Figure but will be shown on a sub-t j
sequent Figure. Both monitors are calibrated on a monthly basis and are normally set to alarm at 20 mR/hr. An additional "non-fixed" area monitor is located on the blue' handrail at approximately mid-point on the east end of the SFP; equal distance from the north and south edge of the SFP. The monitor itself ia difficult to see on Figure 1 but it reads out on the grey instrument panel on the east side of the pool. The monitor is calibrated on a monthly basis and has an alarm setting of 100 mR/hr. This monitor has an extension cable probe (75 feet) which tllows radiation monitoring along the entire east end of the SFP and portions of tiie north and south area of the SFP.
In addition to these three area monitors, hand-held radiation survey instruments are stationed on the reactor level and SFP area for self-monitoring purposes.
This area of the reactor level and SFP area is a radiologically controlled area. It is surveyed by Health Physics personnel under my supervision and is posted and controlled for workmen protection according-to 1
Federal Law, namely Title 10 to the Federal Code of Regulations, Part 20 (10 CFR 20).
.i The small building toward the top of the picture is,the clothes changing area where a workman, before entering the controlled area on this side of the railing, will remove his street clothes and don protective s-2 l
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n clothing (anti-contamination clothing). The area on the opposite side of the railing from the camera position (north side) is a clean or non-contaminated i
area.
The area in the center of Figure 1 is the SFP which is 20 feet by 26 feet and 30 feet 6 inches deep. The tools and equipment on the east end of the SFP are used mainly for fuel inspection.
The bridge crane that straddles the SFP allows for the move-ment of fuel within the SFP from one fuel rack position to another position, or to the fuel inspection rack on the east end of the SFP. The fuel movements within the SFP do not require use of the Fuel Transfer Cask because the water in the SFP provides adequate shielding. The large over-head crane which carries the Fuel Transfer Cask is not shown in Figure 1.
Water is supplied to the SFP from the pipe on the north edge of the SFP. The in-coming water exits the pipe near the bottom of the SFP, flows in an upward direction and across the surface of the SFP over to the surge tank. The overflow from the surge tank goes to the fuel pit filter for removal of particulate matter from the water and then on to the fuel pit pump. This pump returns the water to the SFP through the fuel pool heat eschangers to the pipe on the north edge of the SFP. There are two independent spent fuel pool cooling trains, each with its own pump, heat exchanger and associated equipment.
e Figure 2 shows the SFP area from a different angle. We are looking north. The white object at the top of the stairs' is the fuel transfer cask, sitting in its cradled position when not in use.
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We are also looking at the major portion of the south wall of the SFP. The tapering of the south wall can be seen in this figure. The taper starts 8'2" from the right hand endge of the SFP where the wall is 5 feet 9 inches thick and gradually tapers over a distance of 11 feet 9 inches until it
, meets the adjoining wall at which point the thickness of the wall is 3-1/2 2) feet.
The floor of the SFP consists of 5 feet 9 inches of concrete and 2 inches of Icad.
The small white crane and rope pulley near the bottom of Figure 2 is used by plant operators to remove and replace the filter media (filter socks) in the fuel pit filter tank. The opening over the fuel pit filter is directly be.ow the small crane and pulley. The filter media replacement is accomplished by plan operators with long handled extension tools and the work platform is shielded with lead due to ALARA considerations for radiation coming from the filter tank. This is normally a two man operation which usually results in approximately 35 man millirem of radiation exposure. The fic.er media after removal is placed in a lead shielded cask for transport to low-level on-site storage vaults.
Figure 3 shows the upper portion of the south wall of the SFP but from a different camera angle.
2).
The minimum wall thickness of the south wall is 2 feet. As Figure 2 shows, this extends downward 7 feet from the reactor level deck.
The lowest portion of the 2 foot thick wall is approximately 23 feet above the SFP floor or approximately 17 feet above the top of stcred fuel bundles. Radioactive shine through this 2 foot thick wall is of no concern because of the large amount of water shielding between the stored spent fuel and this portion of the wall. Moreover, the outside of this 2 foot thick section of the wall is ytot accessible to plant personnel.
Therefore, the thinnest portion of the SFP wall near the stored spent d
fuel is the tapered portion of the south wall described above and in Christa-Maria Contention 2.
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The fourth figure (looking southwest) was taken from the clean (or noncontaminated) side of the reactor level and shows the SFP, reactor shield plug over the reactor and the second fixed area monitor mounted on the steam drum wall (yellow canister). The large overhead crane and hook toward the top of this Figure is used to move the fuel transfer cask to various locations on the reactor level and in the SFP. During use over the reactor or SFP, the cask is lowered by the overhead crane into the water and the trap door at the bottom of the cask is swung open. A stainless steel cable, on the end of which is attached a fuel bundle grappling tool, is lowered from the inside of the cask and attached to a fuel bundle under water. The fuel bundle is raised into the cask and the trap door is shut. The cask is raised from the water and the fuel bundle can safely be moved to a desired location in the reactor or SFP. The small hook on the overhead crane toward the right of Figure 4 is used to transfer new fuel from the storage location (directly north of the reactor cavity) to the reactor. Since new fuel is not intensely radioactive, it can be moved in air without lead shiciding of any sort.
The fifth Figure looking due south shows the interior of the SFP and the spent fuel racks. The rack on the right is for storage of fuel channels and the rack in the middle is the fuel leaker rack with several cylindrical icaker cans positioned in the rack.
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e Figure 6 shows the lower portion of the SFP south wall. The tank toward the right of the figure is the fuel pit filter tank and the object sitting on the pedestal near the tank is the cradle for 1 cad shielded cask shich was discussed earlier. This is a radiologically controlled area which is noted with the yellow and magenta tape on the floor, a sturdy chain across the entrance to the area, and proper posting with signs according to 10 CFR Part 20.
The floor elevation in front of the SFP south wall in this slide is at the same elevation as the floor in t'ic SFP. The spent fuel stored in the SFP is at this same elevation but on the other side of this wall. The small metal container to the left is used to store a pre-coat material.
The pre-coat is applied to the filter media in the fuel pit filter tank to increase the efficiency of the filter media.
The seventh Figure (looking due southeast) shows the entire north wall of the SFP. The stairs lead up to the reactor deck level and SFP area. This elevation is the same as Figure 6 but taken from the oppo..te side of the SFP area.
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e Figure eight shows the fuel pit pump room with the pumps In the background and the heat exchangers in the middle of the Figure (marked I rad 2).
The fuel pit pump room is located dirsetly under the SFP.
CHRISTA-HARIA'S CONTENTION 2:
"The increase in fuel stored in the Big Rock pool will result in an increase in the amount of radiation released to the environment at the south vall of the storage pool where there is less shielding, according to the licensee's Description and Safety Analysis. This increment in the level of radiation released to the environment enhances the risks to the health and safety of the public in the vicinity of the plant."
RESPONSE TO CHRISTA-MARIA'S CONTENTION 2 According to the calculations performed for Consumers Power Company by NUS Corporation and described in the testimony of William Bell, the dose rate outside the pool walls and floor based upon the increased fuel storage capacity will be less than 2.0 mrem /hr except outside the portion of the south wall that tapers to 3 feet 6 inches in thickness where the dose rate (assuming 2 day decayed fuel) could be as high as 2300 mrem /hr. This dose rate can he reduced to less than 38 mrem /br if spent fuel, which has been stored in the pool for approximately one year, is stored along the rows of the rack closest to the tapered south wall. The NUS dose rates are based on the assumption that spent fuel can be physically located at the thinnest portion of the south wall.
However, it is physically impossible to store fuel in the channel rack which is presently located at the thin portion of the south wall. The channel rack will not be moved during the proposed rack replacement. Storing S
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fuel in the channel rack is impossible because the lower portion of the feel channel contains a round support tube. The channel rack is desi,ne:I to allow insertion of the round support tube but not the square fuel bundles.
Attachment "A" is a portion of an engineering drawing for the channel rack which shows a " top plan" of the channel rack and the square restraint plates over one corner of each storage location. This configuration allows for the storage of the lower round portion (r,apport tube) of the fuel channel but not spent fuel because the maximum diagonal dimension of the storage space is 8-7/16" + 1/16", whereas the diagonal dimension of a fuci bundle is 8-3/4" +
0.005".
Under the proposed expansion, the " leaker rack" shown in Attachment "B" (existing fuel rack location) would be removed and replaced by a new 9' x 9' rack for the storage of spent fuel and located east of the channel rack on a thicker (4'5") portion of the south wall (see Attachment
'C" - propo.ci :uel rack lecation). Therefore, it is obvious that spent fuel cannot be stored along tba south wall (Attachment "C"
) where the wall narrows f rom approximately 4'4" in thickness to 3'6".
Referring to Mr. Bell's testimony, the graphs on pages 50 and 51 of Bell Exhibit I show that the dose rate emanating from the south wall from 1 year old decayed fuel would be reduced t'o approximately 2 mrem /hr due to the shielding properties of 4'5" cf concrete. Jose rates emanating from the south wall with two day old decayed fuel stored in the same leaker cack would be approximately 150 m"./hr.
Consumers Power Company believes that the dose rate of 150 mR/hr would not be As Low As Reasonably Achievable (ALARA) in accordance with 10 CFR Part 20. Therefore, spent fuel decayed less than one 9
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t year will not be stored in the outer three rows of the proposed 9 x9 fuel rack.
As discussed earlier, Figure 6 shows the south wall area including the spent fuel pool.ilter sock tank. Generally, the radiation dose rate at the radiologically controlled area, which is controlled with yellow and magenta tape on the floor and a sturdy chain across the entrance, reads 30 -
40 mrem /hr because of radiation shine from the filter sock tank. This area is infrequently entered (monthly) and therefore does not pose a radiation hazard to plant workmen. Direct radiation emanating through the south wall with 1 year old decayed fuel,ositioned at the thin portion of the south wall (Attachment "C" proposed fuel rack location) could not be detected separate-ly from the direct radiation emanating from the fuel pool filter sock tank.
This is because the contribution at the south wall from the stored fuel (2 mrem /hr) is small compared to the radiation dose rate resulting from the SFP filter sock tank (30 - 40 mrem /hr).
The exposure to the public due to radioactive shine througi, the south wall of the SFP is described in the testimonf of Roger Sinderman.
CONTENTION II.A BY JOHN O'NEILL "The routine releases of radioactivity during the installation of new racks, the loading of those racks, and storage of fuel in the racks will exceed the limits imposed by IC CFR Part 20 on the exposure of workers, as will the releases of radioactivity through the south wall of the pool exceed the limits imposed by Appendix I to CFR Part 50 on exposure to the general public."
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8 RESPONSE TO JOHN 0/NEILL'S CONTENTION II.A I am the Phnt Health Physicist and as such, the individual responsible for ensuring that radiation exposures to workers during and after the proposed rack replacement operation are within 10 CFR Part 20 limits and as low as reasonably achievable (ALARA).
I have twelve individuals working for me at the plant who are qualified and trained in the field of radiation protection who will help me accomplish this objective.
10 CFR lurt 20 radiation limits for an e,ccupationally exposed person per calendar quarter are as follows:
1.
Whole body; head and trunk; active blood-forming organs; lens of eyes; or gonads-1250 mrems 2.
Hands and forearms; feet and ankles-18,750 mrems 3.
Skin of whole body-7500 mrems A licensee may permit an individual in a restricted area to received a total occupational dose to the whole body greater than that permitted under item 1 above provided that during any calendar quarter the total occupational dose to the whole body shall not exceed 3000 mrem, and the dose to the whole
'oody, when added to the accumulated occupational dose to the whole body, shall not exceed 5(N-18) mrem where "N" equals the individual's age in years at his last birthday. The licensee must also determine the individual's accumulated occupational dose on clear and legible form. Therefore, the maximum whole body radiation exposure that an individual is allowed to receive by Federal 10 miO981-2127b123
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8 Law, is 12,000 mrem per year. In addition to these numerical limits, 10 CFR Part 20 requires all licensees to make every reasonable effort to maintain radiation exposures "as low as is reasonably achievable" (AIARA).
The Big Rock Point Plant has an ALARA radiation program which was used to assess the installation of the new racks and the removal, decontamina-tion and storage on-site of the old " leaker rack".
This program consists in part of a clear statement of operating philosophy regarding occupational ra-diation exposure which states it,part:
"The Health Physics Department serve. in an advisory capacity to the plant staff. The basic guidelines and Federal Requirements for department operations are " Code of Federal Regulations" (CFR), Title 10, Part 20, entitled Standards for Protection A ainst Radiation, 3
10CFR19, Notices, Instructions and Reports to Workers; Inspection, Plant Technical Specifications, USNRC Regulatory Guide 8.8 Information Relevant to Maintaining Occupational Radiation Exposure As Low As Practicable.
The philosophy ar.d duty of the Health Phyrics Department in to maintain the occupational dose to all personnel as low as is reasonably achievable; (NCRP Report No. 43, Review of the Current State of Radiation Protection Philosophy, January 15, 1975).
However, each person (where applicable) is responsible for acquiring a thorough understanding of radiation and techniques available for protecting himself from unnecessary radiation exposure.
The exposure of personnel to internal and external ionizing radiation, in air and water above natural background levels, shall be limited to the values set forth in Appendix B, Table 1, of 10CFR20.
Every reasonable effort will be made to maintain radiation exposure as far below these vM ues as is reasonably achievable."
The installation of the new spent fuel storage racks will first involve the movement and re-arrangement undervater of fuel assemblies and existing fuel storage racks presently in the pool. Based on plant operating exposure we know this entails minimal radiation exposure to plant workmen 0
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8 since there is adequate water depth in the fuel pool which will shield the radiation from the spent fuel and fuel storage racks to background levels normally seen in this work area. Generally, the radiation level over the 7urface of the SFP is approximately 12 mrem /hr, although for purpose of the estimates provided below we have conservatively assumed a higher dose rate of 20 mrem /hr.
The next step will be to remove and decontaminate the old failed fuel rack. The average dose rate for this operation is expected to be about 200 mrem /hr, based on our experience in removing and decontaminating the "D" spent fuel rack in September, 1973. The SFP rack will be decontaminated by rinsing with water as it is lifted from the SFP vater and may be stored in decontamination room 444 for further decontamination if necessary. Chemical residue from this operation will not enter the SFP water. The radiation levels over the fuel pool are expected to decrease to normal values in a few days by filtering and demineralization if required. Further work, i.e.,
in-stallation of new racks will not commence until background radiation levels are normal.
Installing the new racks and movement of fuel assemblies to their final locations will take work crews consisting of five personnel about 92 hours0.00106 days <br />0.0256 hours <br />1.521164e-4 weeks <br />3.5006e-5 months <br />, working in average background radiation fiel& of less than 20 mrem /hr.
Since the new storaf;a racks are, of course, not radioactive, dose rates in the vicinity of the peol will not be increened over normal background levels during this phase of the operatLon.
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8 The final phase of the operation involves general decontamination and cleaning in the SFP area. Based on our experience with similar cleanup operations after refueling operations this should require a work crew of only two personnel working about 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in average dose levels of less than 20 mrem /hr.
In December of 1979, the NRC staff (NRR) informed Consucers Power Company that the normal background radiation levels over the spent fuel pool at Big Rock Point were higher than at other plants. At the time, the Big Rock Point doses were approximately 15 - 18 mrem /hr while other plants had dose rates of about 2 mrem /hr.
The basic reason for the difference is because most newer plants have a dedicated spent fuel pool demineralizer for the sole purpose of maintaining SFP clarity and maintaining low dose rates.
Big Rock Point relies upon the intermi..;nt use of the radwaste demineralizer to process SFP water. The radwaste demineralizer is mainly used to process other plant liquid streams.
In response to the NRR request concerning possible dose reduction, we implemented a number of dose rate reduction methods which reduced the radiation fields in the vicinity of the SFP by approximately 45% to about 12 l
l mrem /hr.
See attachment "D".
The radiation exposures to plant personnel while working over the spent fuel pool have always been within Federal Law, namely 10CFR20. The j
miO981-2127b123
O question raised by NRR is whether occupational exposures could be further reduced in accordance with the "ALARA" principle. In my opinion, the methods outlinedin Attachment "D" and the resulting 45% reduction in normal background dose rates have accomp'.ished this goal. During the actual rack replacement operation the dose rates in the SFP area will be monitored by Health Physics personnel to ensure that they are consistent with the estimates provided in this testimony and as low as reasonably achievable. The area dose rates will be reduced by the following:
(1) Filtering spent fuel water through spent fuel pool filter to mi.7imize crud buildup; (2) Cycling fuel pool water through radwaste system demineralizer to reduce waterborne doses as required; (3) Reducing disturbance of crud in the pool by minimizing spent fuel movements and movement of racks near the pool floor; (4) 7acuuming pool walls, floor, and existing racks, to remove loose crud as necessary, and; (5) Decontamination, if required, of areas around the spent fuel pool.
Health Physics personnel have the authority to stop work if necessary to reduce dose rates to an acceptable level.
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9 The total estimated man-rem dose for the spent fuel pool rack expansion is about 18.2 man-rem, as shown below.
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8 ESTIMATED MAN-DOSE FOR SPENT FUEL RACK ADDITION lBIG ROCK PPINT PIANT A
Number of Work Time Average Dose Man-Dose Function Personnel (Hours / Worker)
Rate (mR/h)
(Man-Rem)
Phase I A.
Failed fuel rack removal and decontamination.
2 16 200 6.4 B.
Shuffling fuel assemblies and old rack reloca-tion 5
20 20 2.0 Phase II f.
Install new racks 5
72 20 7.2 B.
Shuffling fuel assemblies to final locations.
5 20 20 2.0 Phase III A.
General deconta-mination and cleaning in pool area.
2 16 20 0.6 TOTAL MAN-DOSE FOR SPENT FUEL RACK ADDITION 18.2 0
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S I have reviewed this estimate of total occupational exposure and the assumptions upon which it is based, and in my opinion it is a reasonable estimate. Further, I believe that such occupational exposure is as low as reasonably achievable. The NRC's Safety Evaluation Report reflects an earlier estimate of 23 2an-rem that we provided to them. Further review of the project has led us to reduce our estimate of the total exposete to 18.2 man-rem. This reduction is based on a revised estimate of the number of men and hours required to complete the work.
The estimate of 18.2 man-rem represents the total occupational exposure to all workers involved in the rack replacement operation.
Individual doses will be iraintained below the limts described on pages 11-12 by the following means:
(1) Radiation fields are measured and mapped before workers begin work, and areas of high radiation or local contamination are clearly marked so that they may be avoided.
(2) The time workers spend in radiation fields is measured and controlled to limit exposure.
(3) Workers are issued personal monitoring equipment such as direct-reading pocket dosimeters or pocket alarm meters which permit early evaluation of individual doses.
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8 (4) All workers are also issued ILD badges which are read as required and provide an mccurate and official record of their exposure.
(5) Workers are dressed in appropriate clothing to prevent possible contamination. Although I do not expect their use will be necessary, respirators are available if needed to minimize inhalation of radioactive materials. The need for their use will be determined by air activity analysis with the use of state of the art respiratory protection guidance.
(6) Careful records of occupational exposure are maintained for each worker so that cumulative occupational exposure remains within 10 CFR Part 20 limits. Where contractor personnel are used, they are interviewed and their individual exposure history due to radiation exposure elsewhere is determined so that cumulative exposure will remain within 10 CFR Part 20 limits.
(7) !!calth Physica personnel, equipped with appropriate radiation detection devices will monitor rack replacement operations as necessary to provide additional assurance that individual exposures are ALARA.
(8) As described previously in this testimony, there are area radiation monitors in the SFP area which will detect any abnormally high direct or airborne radiation in the vicinity of 8
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O the spent fuel pool during rack replacement operations. These monitors are tested and calibrated frequently to ensure correct operation.
(9) All workers and contractors' employees receive radiation protection training in accordance with 10 CFR Part 19.
The radiation protection procedures to be used at Big Rock Point Plant during the rack replacaent operations and therafter are fully in compliance with all applicable federal regulations, including 10 CFR Part 20.
Alter installation of the new racks, the storage of additional spent fuel in the spent fuel pool will not increase dose rates above the spent fuel pool surface because of water shielding above the spent fuel.
Continuous circulation of spent fuel pool water through the spent fuel pool filter, and cycling spent fuel pool water through the radwaste system demineralizer, as necessary, will maintain concentration of radioactive materials in spent fuel pool water to the normal background levels previously described in this testimony, regardless of the number of spent fuel assemblies stored in the pool. Moreover[basedon plant operating experience it is clear that refueling operations are the principle cause of occupational exposure to workers from the SFP since little work activity occurs over or near the rpent fuel peal during routine operations. Refueling operations will not change following installation of the new racks. Therefore, occupational exposure will not I
increase due to storage of additional spent fuel in the Big Rock Point SFP.
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9 CONCLUSION Radiation emanating from the thinnest portion of the SFP south wall is of no concern since it is physically impossible to store fuel bundles in the channel rack due to the construction of the rack which allows s,orage of fuel channels and connected support tubes but not spent fuel.
One year old or longer decayed fuel will be sorted in the outer three rows of the new fuel rack while it is located directly east of the channel rack. Under this configuration, the radiation levels emanating from the south wall will be so lov. ey will not be distinguishable from the direct and higher radiation level from the fuel pool filter sock tank. The maximum expected dose rate from the south wall, based on the above conditions, will be less than 2.5 mr/hr whereas the normal radiation level in this area is 30 - 40 mr/br.
The limits imposed by 10 CFR Part 20 on exposure to workers will not be exceeded due to the minimal amount of radiation that will come through the south wall of the SFP. In addition, the radiation exposure received by plant workmen during installation of new racks, the loading of those racks and storage of fuel in the racka will be within 10 CFR Part 20 limits and will be As Low As Reasonably Achievable.
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C. E. AITELL, PLANT HEALTH PHYSICIST S Mr. Axtell was assigned as a Senior Chemical Laboratory Technician at the Big Rock Point Nuclear Plant in May 1961.
EDUCATION:
1.
About 2 years of college at Bay City Junior College, Jackson Junior College and North Central Michigan College. Night school, general college.
1958-1973.
2.
International Correspondence School, 1/58 - 1/60 (two years).
Chemistry (completed).
3.
Mathematics Course, Consumers Power Company, General Office, Jackson, Michigan, 5/61 (two weeks).
4.
Jackson Junior College, Jackson, Michigan, 6/61 - 7/61 (eight weeks).
Basic recctor technology; applied reactor physics and health physics; and, use and interpretation of radiation measurement equipment, in-cluding foil irradiation and use of actual monitoring equipment destined for the Big Rock Point Nuclear Plant.
5.
US Public Health Servics, Cincinnati, Ohio,1/62 (two weeks).
Basics of Radiological Health. Subjects covered: major sources of radiation exposure; modes of radiation injury; basic units of termi-nology; standards for radiation protection; and, use, operation and evaluation of monitoring equipment.
6.
US Public Health Service, Cincinnati, Ohio, 2/62 (two weeks).
Pollutants in water; methods and techniques for determination of radiotuclides in the aquatic environment; sud, lectures, problem sessions and laboratory practice.
7.
US Public Ecalth Service, Cincinnati, Ohio, 2/62 (one week).
Pollutants in air; methods and techniques for determination of radio-nuclides in the air environment; and, lectures, problem sessions and
- laboratory practice.
8.
US Public Health Service, Aus. tin, Texas, September 9,1968 (two weeks).
Occupationel 'tadiation Protection.
Subjects covered: beta and gamma shielding der._gn; disposition of radioactive wastes; neutron instru-mentation; protection and biological effects; transportation accidents and regulations; emergercy exposure and concentration guides; emergency planning and management; and evaluation of radiation exposures.
9.
Consumers Power Company, Jackson, Michigan, September 30 - October 4, 1968 (one week).
Basics of Job Management. Some of the sub% cts covered: Company 8
History and Organization; Work Management; Hanagement by Objectives; and Decision Ma'ag.
2 EDUCATION (Contd) 10.
Consumars Power Company, Jackson, Michigan, November 11-15, 1968 (one week).
Basics of Job Management.
Some of the subjects covered:
Equal employment Opportunity Policy; Accounting Records; Rate Making; Union Relations; and Self-Improvemont.
- 11. US Public Health Service, Las Vegas, Nevada, February 24 - March 7, 1969 (two weeks).
Radionuclide Analysis by Camma Spectroscopy. The course covered the theory and operation of a gamma spectrometer; considerations necessary for the selection of a spectrometer; and the procedures for evaluating its performance. The course also covered the consideration of spectral analysis methods, including hand calculation and computer methods.
- 12. US Public Health Service, Winchester, Massachusetts, August 10-14, 1970 (one week).
Management of Radiation Accidents. Major attention was devoted to potential sources and types of accidents, preplanning first stage management and follow-up and public relatious.
Eelected accidents were reviewed in detail. Class and panel discussions enabled the trainee to discuss spec 1'ic problems with other class members, the training staff and consultants. Field exercises were also held.
. 13.
Special Training Division, Oak Ridge Associated Universities, Oak Ridge, Tennessee, February 23 - May 1,1976 (ten weeks).
The Health Physics Course included: Radiation Physics, Spectral Analysis, Counting Statistics. Surrey Instruments, Radiobiology X-ray Production, Neutron Production, Nuclear Medicine, Advanced Absolute Counting, Liquid Scintillation Counting, Radiation Protection Guides, K-ray Fluorescence, Industrial Hygiene, Neutron Activation, Solid State Spectroscopy, Radia-tion Accidents, Film Dosimetry, Radiophotoluminescent and Thermolumine-scence Dosimetry, Emergency Plans and Procedures, Environmental Monitoring, Waste Dispocal, Air Sampling, Laser Safety, Transuranium Health Physics, Accelerator Health Physics, Microwave and Accident Dosimetry.
14.
Respiratory Protection Programs,' conducted by the Los Alamos Scientific Laboratory, Boston, MA, November 3-5,1976.
Air Purifying Respirators, Atmosphere Supplying Respirators, Respiratory Physiology, Oxygen Deficient Atmosphere, Breathing Air Quality, ANSI Standard Z88.2-1969, Minimal Acceptable Respiratory Program, Concept of i
Protection Factors, Fitting of Respirators, Paspiratory Fitting and Training of the Wearer, Medical Surveillance, Inspection and Maintenance, Respirator Use During Emergencies.
PUBLICATIONS 1.
R. W. Sinderman and C. E. Axtell. Personnel Radiation Exposure Aspects of Ooeration, Mhintenance and Refueling a Boiling Water Reactor, presente,d,*at the Health Physics Society Mid-Year Topical Symposium, Los Angeles, Cali-8 fornia, January 29-31, 1969.
- In chronological order.
3.
P_UBLICATIONS (Contd) 2.
C. J. Hartman and C. E. Axtell, Unusual Corrosion Problems Associated vi.th a__ Boiling Water Reactor, presented beis:te the National Association of Corrosion Engineers, Houston, Texas, March 10-14, 1969.
3.
R. W. Sinderman and C. E. Axtell, Liquid Radioactive Waste Management, presented before the American Institute of Chemical Engineers, Cincinnati, Ohio, May 16-19, 1971.
4.
C. E. Axtell and B. L. Murri, Methods Utilized to Reduce Radioactive Licuid Discharge, presented at the Health Physics Society Annual Meeting, Las Vegas, Nevada, June 12-16, 1972.
EXPERIENCE:
1.
9/57 - 5/61, Plant Laborato g Technician, J. C. Weadock Steam Generating Plant (614 MWe)
Assisted in chemical ar.alysis and control; instrument calibration and repair; and plant efficiency analysis.
2.
9/61 - 10/61 (10 weeks), Vallecitos Atomic Laboratory.
Assigned to the Radiochemistry Section of Vallecitos Atomic Laboratory.
Participated in all phases of radiochemical analysis and control associated with a boiling water reactor.
3.
3/62 - 1/68 Assigned to the Big Rock Point Nuclear Plant as Senior Chemical and Radiation Protection Technician.
4.
2/68, Big Rock Point Nuclear Plant Assigned the title of Supervisor, Chemical and Radiation Protection.
5.
Secretary-Elect, Power Reactor Health Physicist Group, 1972-1973.
6.
Member, Health Physics Society.
7.
Three-week (120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />) course,1975. Conducted Basic Health Physics Course for six Chemical and Radiation Protection Techaicians. The course covered such topics as: Mathematics, Basic Physics, Radioactivity, Radiation and Contamination, Biological Effects, Units, Protection Against Radiation and Contamination, Standards and Guide Values Detection and Measurement of
, Radiation and Contamination, Personnel Monitoring, Survey Techniques, Plant Monitoring of Radiation and Contamination, Decontamination, Waste Disposal, Environmental Safety, Emergency Actions, Shielding Calculations, 10CFR19, 10CFR20, Radiation and Respiratory Protection Program, Hazards Associated with Certain Isotopes, Portable Survey Instrument Calibration, Process Monitors, Detector Fundamentals. Technical Specification Requirements Air Sampling, Shipment of Radioactive Materials, Site Emergency Pinn, and Plant Procedures Manual.
8.
3/76 - Assigned the present title of Plant Health Physicist.
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l'EAxtel d'A.
rnon Consumers De.t c July 2h,1980 pDgg[
heaccr BIG ROCK POINT PLANT -
RADIATION LEVELS OVER THE SPENT RIEL POOL INTERNAL
! l '-
- Cometseonotwcc CEA 80-34 cc GLFox Access Cont:ol Control Room Shift Supervisor Office Attached _ are c everal_ survey.s,of_the. spent fuel.poo,1 area and all readings
. vere taken at vaist height.
The initial rurvey was conducted December 12, 1979 and shortly after the fuel pool was placed on recycle through the radvaste demineralizer to reduce the radiation levels. Although the fuel pool was not kept on recycle con-tinuously because of radvaste operations, it is estimated,that recycle occurred for approximately 1.6.vceks.pince the initial recycle.
Representative radiation su ey locations were tabulated from the attached survey sheet and are listed below; Date Fuel Pool Location (s) in mR/hr 12/12/79 West end (14)
Middle'-(lk )
East end (28)'
' Over Surge Tank (24)
' Operators water lanced weir and surge tank 02/01/80 West end (10)
Middle (32-)
East end (16)
' Over Surge Tank (14)
Wet secared fuel pool valls for crud build-up. (Very minor activity)
^
06/04/80 West end (12)
Middle (12)
East end (18)
Over Sur6e Tank (17) 07/17/80 West end (8)
Middle (6)
East end (15)
Over Surge Tank (15)
Generally, dose rates over the fuel pool have been reduced by approximately h5%.
Crud and filtrate activity of the fuel pool vater was followed on a weekly basis according to say memo to the Shift Supervisors dated December 19, 1979 A very significant reduction in filtrate activity can be seen while recycling the water through the radvaste demineralizer. Cnid levels remain relatively low with or without recycle.
1 Dased on the above, the Shift Supervisors are asked to continue the fuel pool re-cycle until further notice'. This memo vill be updated as new information becoraes available.
j Attachment "D"
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raoM CEAxtell Consumars Duc Decc=ber 19, 1979 EDWS[
Company BIG ROCK POIHT PLANT -
suoscci DOSE RATES OVER AND AROUND THE SPENT FUEL POOL
- INTcRNAL
, CommesroxocNcc
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cc Control Room Attached are radiation field maps of the fuel pool, I was informed by the NRC
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tha't these dose rates are much higher than at most reactors (they average d 2mR/hr). The following items should redt.ce the radiation field; 1.
Wet smear the fuel pool valls for crud build-up/ dose rates. (CEA)
- 2.
He, cycle fuel pool throus$ radveste demin. (SS)'
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CEAxtell vill. follow weekly lab iu:tivify analysis df water. (Recycle
' N may take several weeks.'),{
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Water lance veir over surce tank.
(SS) 3.
Is. Air lance surge tank (stir-up crud.to be caught by sock filter). (SS)
.i Please start recycle and continue until fur'the~r notice ' Hold off air / water Ian.ce
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- S'1 vse osso August 11, 1980 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Pro,jects Branch No 5 US Nucler.r Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - RESPONSE TO STAFF QUESTIONS ON SPENT FUEL POOL AREA j
l l..:
On December 19, 1979, a telephone discussion between Consumers Power Compa'ny.'
~
~
and the NRC addressed spent fuIel pool area radiation levels and monitoring.
Mr Walter Paulson of your staff informed us on August 6,1980 that responses to two questions resulting from this discussion had yet to be received. These questions involved an investigation into means to reduce radiation levels in the spent fuel pool area and esistance,of area monitors that alarm in the con;-
trol room on lov spent fnl pool vater;1evel; Consumers Power Ccmpany has taken measures to reduce activity leve's in the I
spent fuel pool area. The mea;sures taken -include recycling of.the spent fuel pool coolant.through the radvaste demineraliser, water lancing the veir over the surge tank and air lancing the surge tank. Wet smears on the fuel pool valls were taken for determination of crud buildup and its affect on dose rates.
The vet smears indicated very minor activity-and that cleaning of the spent fuel pool valls vould not f affect ths toverall area activity level's. The dose rates in the spent fuel pool area have been reduced by approximately h5% since December 1979 as shown by the following:
Date Fuel Pool Location (s) - (Dose Rate in mR/hr).
12/12/79 West End (14)
Middle (lk)
East End (28)
Over S' urge Tank (24)
Water lanced veir and surge tank and recycle of fuel pool through radvaste demineralizer 02/01/80 West End (10)
Middle (12)
East End (18)
Over Gurge Tank (1h)
(~'T 06/0h/80 West End (12)
Middle (12)
East End (18)
Over Surge Tank (17)
U 07/17/80 West End ( 8)
Middle ( 6)
East End (15) over Surge Tank (15)
n.- #
i Crutchfic1d Big Rock Point s
8/11/80 2
Spent Fuel Pool Ar -
8 Big' Rock Point has two area radiation monitors f,n the proximity of the spent i
fuel pool. These monit. ors are located near the SW corner of th- 'tr-nt fuel pool and on the steam drum enclosure vall approximately thirty (30) feet from the spent fuel pool. Both monitors alam in the control room at approximately 10 m3/hr activity levels. Indication of high activity levels due to lov spent fuel pool vater level vould be provided by these monitors in the control room.
In addition to these permanent monitors, a portable monitor has been located at the' east end of the spent fuel pool which* has a local alarm set at approxi, '
mately'100 mR/hr.
t David P Hoffman (Signed)
David P Hoffman Nuclear Licensing Administrator CC JGKeppler, USNRC m*
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$I if UNITED STATES OF AMERICA NUCLEAR REGUIATORY COMISSION BEFORE TIE A10MIC SAFE 1Y AND LICENSING BOARD In the Matter of
)
) Docket No. 50-155 OIA OJNSIFERS PCHER (IEPANY
) (Spent Fuel Pool
) Modification)
(Big Rock Point Nuclear Power Plant)
)
AFFIDAVIT OF WIILIAM H. BELL C%ty of Montgcmery )
)
- SS State of Maryland
)
I, Willian H. Bell, Engineer, Process EngineeriIg Department at NUS Corporation, of lawful age, beirg duly sworn, upon my oath certify that the statenents and inforration contained in thc four-page Statement concerning Christa-Maria's Contention 2 and O'Neill Contention II.A, the attached resume, and NU3 File 5148-ri:-A4 the Big Rock Point Fuel Pool Dose Calculation, dated April 1979, are true and correct to the hut of my knchiedge and belief.
Executed nu Rockville, Maryland.
il(ja
(
,f-
)
' a, A t am ' /
J,
(
Subscribed and sworn to before me this 29th day of SepF=Mr,1981.
Awi 3 -r n
~
Notgaff ic in End for Stafe of land and the County of Mcntganery v(~'s n
My ccmnission expires k4 / / 9 th l
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