ML20140D090
| ML20140D090 | |
| Person / Time | |
|---|---|
| Site: | 05000142 |
| Issue date: | 03/21/1986 |
| From: | Wegst W CALIFORNIA, UNIV. OF, LOS ANGELES, CA |
| To: | Berkow H Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8603250577 | |
| Download: ML20140D090 (13) | |
Text
,
4 UNIVERSITY OF CALIFORNIA, LOS ANGELES UCLA e
A
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QL senmn oms nuiu un 4sc m s antaunt. sss naco sis m sasco sms esnesar s4su cacz COMMUNITY SAFETY DEPARTMENT OFFICE OF RESEARCll & OCCUPATIONAL SAFETY IDS ANCELES. CAUFORNIA 90024 March 21, 1986 Herbert N.
Berkow, Director Standardiztion and Special Projects Directorate.
Division of PWR Licensing-B U.S Nuclear Regulatory Commission Washington, DC 20555 Docket No. 50-142
Subject:
Answers to Questions 1 - 8 Concerning UCLA's Reactor Dismantling Plan.
Dear Mr. Berkow:
Enclosed are UCLA's answers to the first eight (8) questions of your staff regarding our reactor facility dismantling plan.
We were most happy to receive these questions as we have been patiently waiting for 4h months to begin work on dismantlement of our old reactor facility.
As indicated in your letter of March 12, 1986, the information requested by questions 9 - 15 will be provided as part of the report UCLA will submit at the conclusion of Phase 1, dismantling operations.
We would appreciate your immediate attention to our answers so that we can begin work as soon as possible.
I'm sure you know that it is difficult and expensive to keep a competent, trained staff intact when they have little to do.
Very Truly Yours, we.-u+:aunessaw:mapas;
'l jf D OHIC AL SEAL 3
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Walter F. Wegst, PhD.
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Director, Research &
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Occupational Safety Enclosure cc:
As indicated on next page STATE OF CALIFORNIA
)
COUNTY OF LOS ANGELES
)
On March 21, 1986, before me, the undersigned, a Notary Public in and for said County and State, personnally appeared WALTER F. WEGST, known to me to be the person whose name is subscribed to the within instrument and acknowledged to me that he executed the same.
WITNESS my hand and offical seal
. Wo_.O Notary Public in and for 8603250577 860321 said County and State I8f,8 PDR ADOCK 05000142 P
,f
Enclosure Answers to UCLA Facility Decommissioning Questions 1-8 1.
" Referring to Section 1.5 of the Plan, provide resumes showing the education, training and experience for all positions that are important to safety during the decommissioning (i.e.,
Manager of Operations, Health Physicist, etc.)."
1.
Walter F. Wegst, Director of Research & Occupational Safety.
During dismantlement and decommissioning of the UCLA facility is serving as the Director of all operations.
BS, MS (Nucl..Eng.), PhD; Reactor supervisor at the University of Michigan Ford Reactor; Certified Health Physicist; responsible for overall health and safety at the UCLA reactor since 1979.
Neill C.
Ostrander, Manager, NEL, BS Chemical Engineering, affiliated with the NEL (as Manager) since 1974.
Has participated in past core dismantlement.
James McLaughlin, Radiation Safety Officer, responsible for all radiation safety operations at UCLA.
30 years I
experience in dosimetry,' environmental measurements, management of 10 physicist research group for AEC/ERDA/ DOE laboratory in New York.
Many publications; ANS Fellow; Certified Health Physicist; additional work experience (1 year) involving reactors at Brookhaven and Idaho.
David J. Krueger, Health Physicist, representing the UCLA Radiation Safety Office, BS Nuclear Engineering, affiliated with the University of Illinois reactor program and. Health Physics Office prior to coming to UCLA.
In charge of health and safety at UCLA's NEL since October 1985.
2.
" Describe the method you will use (e.g., GeLi' spectrometer) to identify radioactive nuclides found in swipes, core samples, etc.,
that will be taken during dismantling."
2.
Identification of radionuclides will be performed using various methods including Ge(Li) gamma ray spectroscopy, liquid scintillation counting and half-life determination (when necessary).
These methods and instruments are constantly used during UCLA's campus-wide safety work and are well calibrated and documented.
3.
"The UCLA Plan indicates the use of only one hi-vol air sampler.
The staff finds that one such sampler is not adequate; two will be required.
Please amend your plan accordingly."
3.
UCLA has obtained and will use two hi-vol air samplers, i
whenever airborne particulate activity is likely to be present.
i
4.'
"Page 7, Table P The radiation protection equipment specified in the table does not include survey meters that can be used to measure dose rates down to 5 pr/hr.
Staff criteria for release for unrestricted use of equipment, release of contaminated structures, surfaces, etc., required for termination of a license, is Table I, of Reg Guide 1.86 and 5 tr/hr above natural background at one
/
meter.
Indicate how you assure that the survey meter used in radiation surveys to measure dose rates is energy independent over a wide range of energies.
Additionally, the inventory in the table does not lnclude monitors for self examination of extremities, face, clothing, etc. for contamination."
4.
Items to be released to unrestricted areas are screened with a shielded thin window (1.7 mg/cm2) pancake-type G.M.
counter.
This instrument is calibrated with an electronic pulser to read directly in counts per minute.
Check
. sources of known emission rates were used to verify efficiencies.
The values-in Reg. Guide 1.86, Table 1,
" Removable", have been chosen as the release criteria for both fixed and removable contamination, geometric and efficiency factors taken into account; in practice anything which is even suspect of being radioactive is disposed in the radioactive waste.
The criterion of Sjar/hr. at a meter will not be used by UCLA during Phase 1 dismantling since it is not sensitive enough to detect significant radioactive contamination and/or induced radioactivity.
During the final decommissioning phase we will use the 5 determine if in-place concrete shielding /Ar/hr. criterion to floors, walls, etc, can be released for unrestricted disposal or use.
UCLA currently has a high pressure ion chamber instrument capable of measuring at these background levels and we are in the process of obtaining a sensitive, portable scintillation survey instrument to measure dose rates in the pt/hr.' range.
Personnel will use the pancake GM probes for self examination for contamination.
In addition, a hand and l
foot counter (located at the exit from the reactor room) equipped with 8 thin walled G-M's and a "frisker" pancake probe is routinely used by all personnel exiting from the reactor room.
l 5.
" Indicate how you will dispose of the lead and graphite bars that are removed from the core."
5.
Lead and graphite that were activated or contaminated during use of the reactor will be packaged and shipped to either Texas A&M University or the LLW site in Richland, Washington.
All State and Federal regulations concerning packaging, transportation and burial will be followed.
Note that Texas A&M is licensed by the NRC to possess the radionuclides contained in both the lead and graphite.
--2--
.i T
6.'
"Page 6, Section 1.7; Page 9, Section 3.3.1; Page 9, Section 3.3.2 - Please state whether the experienced radiation workers in the three sections specified are the same people.
Explain how they will take a more active role, in the Decommissioning Plan, than training contractor technicians.
Provide details of their experience with respect to the Decommissioning Plan (e.g.,
experience with respiratory protection equipment, large area and volume contamination' control, measurement ofjAr/hr radiation levels, supervising people performing the dismantling and decommissioning function)."
6.
Our original plan was to hire experienced radiation workers from an outside contractor.
Presently, the plan for completion of Phase I is to use.the people listed in Question 1, as well as the following, full time UCLA employees.
Cha rles E. Ashbaugh, Nuclear Engineer, BS, MS in Nuclear Engineering from UCLA, affiliated with the reactor since 1971.
Participated in three core dismantlements.
Mitchell Lanahan, Senior Health Physicist Technician.
San Diego State University course work in math, biology, chemistry and physics 1976 - 1979; practical training and experience in treatment of radioactive waste, detection and control of radioactive contamination, radioactive material inventory control, steam generator mechanical work; experienced in working in high radiation areas, use of
" bubble suits" and respirators.
Raymond Crott, Principal Health Physics Technician.
U.S.
Navy'1976 - 1982; training in nuclear power, electricity and electronics; experienced in control point access watch; corrective and preventive maintenance inside reactor compartment; shutdown reactor operator, radiation worker 1978 - 1982.
Anthony Zane, consultant to dismantling.
Affiliated with the UCLA reactor since 1963, most recently as Reactor Supervisor (1975 - 1985).
Participated in many core dismantlements.
Maurice Thelia, electronics technician with NEL since 1971. Has been involved in previous reactor dismantling operations.
All of these people have had experience in either core dismantlement of UCLA's reactor or in wide ranging health physics measurements and protective proce'dures, including experience at an operating research reactor.
All are familiar with the use of respiratory protection; contamination control techniques; use of survey meters and personnel dosimeters; and all have been briefed on the dismantling plan and the use of radiation work permits to control each step of the operation.
--3--
At this time, we do not plan to use any outside (non-UCLA) personnel except for the concrete care sampling to be done as the last step in Phase 1.
The specialists hired to do the coring will be trained in contamination control procedures and closely supervised by UCLA health physics personnel.
Note that Mr. David Krueger_(see answer number 1) has the authority to veto or modify any operation which is deemed to be hazardous or to be contrary to ALARA considerations.
7.
"We note that student volunteers have been used for dismantling the core for maintenance.
From this, it appears.that volunteers will again be used of core dismantlement.
Please specify how these volunteers have been and will be trained for this work in accordance with 10 CFR 19.12."
l 7.
Student volunteers will not be used to carry out this dismantlement.
However, any person involved will be trained by UCLA health physics personnel in accordance with 10 CFR 19.12.
8.
" Appendix B, Pages 2 & 3 -- Detailed diagrams of the reactor system and environs are needed to follow the Decommissioning Plan.
'Please provide such drawings showing measurements at the locations specified in Tables B-3 and B-4 and relevant areas specified in Section B-3 and B-4 (e.g.,
steel blade drive support bearings and structure, core center void)."
l 8.
Diagrams of pertinent systems and environs are attached as
~
Attachment A to these answers.
The radiation measurements listed in Tables B-3 and B-4 of the dismantling plan (Octooer, 1985) are referenced in figure 5 of Attachment A.
J'
--4--
ATTACHMENT A:
Response to Question 8 Figure 1 illustrates the general arrangement of the reactor core.
The view is from the southeast.
Item 12 identifies three of the six fuel boxes.
Two of the three boxes are shown with the shield plugs (Item
- 13) in place.
Identification of the fuel boxes is useful for orientation of the subsequent drawings.
Items 7,'8, and 9, identify control blade drive shafts, magnesium shrouds, and one of the control blades.
Item 16 is the steel structure that supports the rod drive shaft bearings and the shrouds.
The south beam port (not shown in this figure) is a horizontal penetration of the biological shield with a liner that extends approximately sixteen inches into the core between the shrouds.
The center-line of the liner passes four and one-half inches above the center-line of the rod drive shafts.
Except for some minor piping differences, the north side of the reactor is a mirror image of'the south side shown in this view.
Figure 2 shows a horizontal section at approximately the top of the fuel boxes.
A vertical plane midway between the two rows of fuel boxes is a plane of left-right (north-south) mirror image symmetry.
The cross-hatched region between the two rows of fuel boxes is occupied by vertically oriented graphite bars that are 4" x 4" in cross-section and four feet long.
Fifteen such bars (stringers) are shown end-on in the cross-hatched region of the figure.
The removal of these bars created the center void referred to in Section B-4 of Appendix B of UCLA's dismantling plan dated October, 1985.
The control blade drive shafts and bearing at a depth of about 24 inches below the top of the fuel boxes (just below the south beam port liner extension) are shown on the left side of Figure 2.
Figure 3 is a vertical section, a view from the east, of the control rod drive shafts seen end-on.
The semaphore blade is shown in the dowa position, partially obscuring the south beam port liner extension.
The concrete biological shield occupies the region to the left of the drive shaft and shroud structural support.
The " distance" used in Table B-4 of Appendix B is measured from the interior end of the liner.
Figure 4 is a vertical section showing the rod drive shafts, bearings, and support structure as viewed from the south.
The near-octagon above the end bearings and between the shrouds shows how the graphite stringers were machined to provide a passageway for the south beam port liner extension.
Figures 3 and 4 illustrate the proximity of the liner to various j
metallic parts which may contribute to the radiation field of 2 - 3 r/hr indicated in Table B-4 of Appendix B.
Figure 5 (upper) shows the beam plug in its normal position in the liner.
The plug was removed and samples taken of drillings at the locations identified in the figure and reported in Table B-3 of Appendix B.
Figure 5 (lower) shows the beam port with the plug removed and the liner which extends 16 inches into the core.
The figure shows
--5--
th'e locations at which the radiation levels resorted in Table B-4 of Appendix B were measured.
Note that the scale: ' of the two figures are i
different, i
The following figures are attached:
Figure 1:
Reactor - Core Area Figure 2:
Horizontal Section Near Top of Fuel Boxis Figure 3:
End View of Drive Shafts Showing South Eeam Port Figure 4:
Side View of Shafts, Bearings, and Suppo!t Structure Figure 5:
Beam Port Plug and Liner Figures 2 through 4 are from AMF drawings dated 1957 except for the l
addition of the beam tube liner (Figure 3) and additional notes to identify some of the items relevant to the preceding discussion. Figure 1 is undated but is from the same era as. Figures 2 through 4 Figure 5 was reconstructed from AMF drawings of the beam port plugs.
Because of reactor revisions made subsequent to the era of these drawings, the drawings are not correct in all respects.
In particular, the west beam port passage through the shield tank (Item 4 of Figure 1) no longer exists,_and much of the embedded piping shown in Figures 1, 4
3, and 4, was bypassed and became non-functional in 1970 - 1971.
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Renfo C6ac re /e BNfoyca/.5/rie/d r Core l
1 FIG. 5:
BEAM PORT PLUG (upper) and BEAM PORT with LINER (lower)
(reconstructed from various AMF dwgs)~
l 3
DISTRIBUTION LIST University of California Docket No. 50-142 at Los Angeles c c':
Committee to Bridge the Gap 1637 Butler Avenue Los Angeles, Ca 90025 Daniel Hirsch 3489 Branciforte Drive Santa Cruz, Ca 95065 Mr. Glenn R. Woods, Esq.
Office of the General Counsel 590 University Hall 2199 Addison Avenue Berkeley, Ca 94720 Mr. William H. Cormier, Esq.
2255 Murphy Hall UCLA 405 Hilgard Avenue Los Angeles, Ca 90024 Counsel for NRC Staff Office of the Executive Legal Director US Nuclear Regulatory Commission Washington, DC 20555
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3/20/86 L