ML20195G504

Forwards Pages 6,12,15 & 16 for Placement in Phase II Plan for Former Reactor Facility Sent on 880610.Editorial Changes Made to Pages

ML20195G504
Person / Time
Site:	05000142
Issue date:	06/21/1988
From:	Mclaughlin J CALIFORNIA, UNIV. OF, LOS ANGELES, CA
To:	Alexander Adams NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8806280020
Download: ML20195G504 (6)

Text

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UNWERSITY OF CALIFORNIA,' LOS ANGELES ,, UCLA

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RESEARCil oc OCCUPATIONAL SAFETY /RADI ATION SAFETY AfLO60J CENTER FOR Tile HEALTil SCIENCES IDS ANCELES CALIFORNIA 90024 June 21, 1988 Mr. Alexander Adams U.S. Nuclear Regulatory Commission Washington, D.C. 20555

! Attn: Document Control Desk Docket Number 50-142

Dear Mr. Adams:

Please replace the enclosed four pages in the Phase II. Plan for our former reactor facility, which was sent on June 10, 1988 from J.E. McLaughlin to A. Adams. Some editorial corrections were~made on pages 6, 12, 15, and 16.

Sincerely yours, fM>u/- f h)ce ~/ o James E. McLaughlin aE Acting Director Research & Occup. Safety JEMicm Enclosures se L \

8806200020 880621 E' \

PDR ADOCK 05000142 P PDR;

University of California Docket Noa 50-142 at Los Angeles cc Mr. Neil C. Ostrander, Manager Committee To Bridge The Gap Nuclear Engineering Laboratory 1637 Butler Avenue #203 School of Engineering and Los Angeles, CA 90024 Applied Science University of California Mr. John Bay at Los Angeles 1022 ?eralta Street Los Angeles, CA 90024 Albany, CA 94706 Attorney General Mr. James H. Heelan 1515 K Street Director, Society Services Sacramento, CA 95814 American Nuclear Society 555 N. Kensington Avenue California Department of Health La Grange Park, IL 00525 Attn: Chief. Environmental Radiation Control Unit Roger Kohn, Esq.

Radiological Health Section 524 lith Street 714 P Street, Room 498 Manhattan Beach, CA 60266 Sacramento, CA 95814 Robet't M. Meyers Mr. Daniel Hirson City Attorney 3409 Branciforte Drive Lynn Naliboff Santa Cruz, CA 95065 Deputy City Attorney 1685 Main St. , Room 310 William H. Cormier, Esq. Santa'Monica, CA 90401 Office of Administrative Vice Chancellor Roger Holt, Esq.

University of California Office of City Attorney 405 Hilgard Avenue 200 North Main St.

Los Angeles, CA 90024 City Hall East, Room 1700 Los Angeles, CA 90012 Christine Helwick, Esq.

Glen R. Woods, Esq. U.S. Nuclear Regulatory Commission Office of General Counsel Region V 590 University Hall Office of Inspection & Enforcement 2200 University Avenue 1450 Maria Lane, Suite 210 Berkeley, CA 94720 Walnut Creek, CA 94596-5368 Dean Hansell 302 South Mansrield Ave.

Los Angeles, CA 90036 l

1.3.1 Pipes, Drainlints, and Ductwork The primary water system has also been removed and the reslaual equipment in the process pit consists of a sump, a sump pump and two 290 gallon holding tanks. Tne sink and shower drainlines merge with three other floor drains to empty into the sump. A separate drain from the reactor core also passes to tne sump. Swipes of inlets and outlets of these drainpipes and the accessible points of the exhaust system ductwork when counted on a beta counter, revealed all surface contamination levels below the limits prescribed in Table 1 of USHRC Hegulatory Guide 1.06. However, it is possible that tne pipes ano drainlines may have been activated from neutron streaming. Further surveys will be performed during Phase II as we gain increased acceas.

The sump is a reservoir 24 inches wide, 24 inones long and 61 inches oeep.

At the bottom there is about an inch and a half of sludge covered by approximately 24 inches of water. Samples of the water and the sludge were incividually counted on a high resolution Ge(L1) spectrometry system and a liquid scintillation spectrometer for possible contamination. The results are reported in Table 1.2.

Toole 1.2. Activity of Radioisotopes in the Sump Concrete Isotopes Half-Life Water Activity

• Sediment Activity ** Total (years)  % (uC1)  % (uC1) (uC1)

Co-60 5.27 --- ---

10 3 50.0 50.0 Eu-152 13.6 --- --- 20.0 127.0 127.0 H-3 12.3 100 16 3 52.1 253.8 272.1 C-14 5730.0 --- ---

11.6 56.7 56.7 100 1d.3 100.0 487.5 505.6 3

• Volume of Sump water is approximately equal to 7.83 f t

• Volume of tne sediment is approximately equal to 0.5 ft3. Pensity of the sediment is taken to be that of concrete, i.e., 200 lbm/ft 1.4 The Decommissioning Approach For Phase II, UCLA intends to complete decommissioning of the facility for "unrestricted" use by availing the services of an outside contractor.

"SAFSTOR" is no longer under consideration. The selected decommissioning alternative is "DECON". After the approval of this plan by the NRC, UCLA will soon distribute a Request for Proposal to potential commercial biddern.

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removal, and transportation of radioactive and non radioactive material

. from the Gate in accordance with all governing regulationso However, UCLA shall oversee and review all tasks during tne decommissioning project.

UCLA will retain overall responsibility for health and safety considerations during. decommissioning.

2.4 Cost Estimate and Funding Tne cost of Phase II. decommissioning is estimated to be $200,000 exclusive of internal personnel costs. This includes the estimated cost of the termination survey. The School of Engineering ana Applied Sciences (SEAS) has approved this cost.

3.0 DISMANTLING AND DECONTAHlNATION TASKS AND SCHEDULES 3.1 Tasks The Contractor's tasks in Phase 11 will include the followir.g:

a. razing the concrete monolith and pedeskal to floor level,

b. excavation of the approximately 52 f 5t of concrete down to about 22 inches below floor level,

c. removal of four large concrete blocks,

d. packaging materials for appropriate land burial,

c. transfer of such material to burial site,

f. decontamination of the reactor room and nearby areas, and

g. final release survey of tne facility.

32 Schedule The schedule for the decommissioning project after approval of tnis plan by the NRC is shown in Table 3.1 12.

r conventional concrete, the remainder in heavy concrete. The monolithic

. .' structures contain reinforcing bar, electrical conduit, three steel beam-port liners (each wing), and a steel plate in the western, conventional concrete, region of each wing. The single drawing that refers to the platc specifies only a 24 inch width. The thickness scales to 1/2 inch, the height is not specified.

3.3.2.4 The Pedestal: The pedestal runs the entire east-west length of the shield at a width of approximately S feet and rises 14 to 16 inches above the floor level. The height and width change in discrete steps to reduce neutron streaming paths.

The pedestal contains the embedded part of the reactor "framework" which supported the control blade system within the core, lt is rectangular in outline consisting of two parallel 5 inch 5.7 lb. channels, each about 76 inches long with 24 inches long end pieces of the same stock. The 21 inches inside distance between the long channels is further fixed by two angles 5 inches x 5 inches x S/16 inenes perpendicular and welded to the channels. One flange of each onannel and one-leg of each of the angles is visibly flush with the top surface of the pedestal. Because of mass and close proximity to the core center, this entity is likely to be the single most radioactive object to be encountered in the demolition work.

The pedestal contains some abandoned aluminum pipe and manifolding, and a centered floor drain which empties to the sump.

3 3 2.5 Removable Blocks: All of the removable blocks are fitted with lifting lugs and are manageable with the 10 ton crane and 4 chain sling.

Tnese blocks are described in Table 3 3 15.

Table 3 3. R; movable Blocks

?- .

Type

• Dimension' Volge Density Mass LxWxH (ft ) (1bm/ft3 ) (tons)

(inches)

C8. -90 x 50 x 30 92.25 207 9.55 Embedded Steel- 1.50 480 0 36-C9 84 x 48 x 30 68.79 247 8.50 Embedded Steel 1.21 480 0.29

< A+B .

66 x 20 x 69 37.93 247 -4 68 Void (15 ports)- 11.88 0 0.00' Embedded Steel '2.13 480 0.51 A + B Port Plugs Concrete 10 32 247 1.27 Steel 1.56 480 0 38 C+D 66 x 10 x 69 42.03 247 5.19 Void (15 ports) 7.46 0 0.00 Embedded Steel 3.21 480 0.77 C + D Port Plugs

-Concrete 6.18 247 0.76 Steel 1.28 480 0 31

• The location of these blocks are shown in Fig. 3.1.

All bl. cks are edged with 2 inches x2 inches x 1/4 inches angle (3.19 lbm/ft p) and contain varying amounts of reinforcing bar. The rebat- !s sometimes terminated by Welds to the center of edge strips. Blocks C-8 and C-9 each contain three cylindrical, vertical steel beam port liners, 35 inches x 3.125 inches x 30 inches in C-8 and 2.5 inches x 2.125 inches x 30 inches in C-9.

Blocks A + B and C + D were cast as four separate entities each 10 inches thick and subsequently welded in pairs along adjacent edge strips to form

.two blocks each 20 inches thick. Block A + B and block C + D each contain 15 rectangular beam ports with matching plugs. The void volumes indicated in the table above are the volumes of the plugs, consequently if the plugs are regarded as a portion of the block, they do not contribute incremental volume to the amount of concrete to be removed.

3 3.2.6 Excavation: The volume is tnat of a spherical segment or base radius 49 inches extending to a depth of 22 inches below floor level.

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