ML20136F659

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Informs of Review of Environ Info in Cj Paperiello Ltr to Jr Schott & Encl Insp Rept.Rept Indicates That Erosion Stabilized According to 840601 Plan Except in Settling Basin.No Further Action Necessary
ML20136F659
Person / Time
Site: 05000000, Zimmer
Issue date: 01/25/1985
From: Ballard R
Office of Nuclear Reactor Regulation
To: Adensam E
Office of Nuclear Reactor Regulation
Shared Package
ML20136E200 List:
References
FOIA-85-362 NUDOCS 8502010504
Download: ML20136F659 (1)


Text

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JAN 2 51985 i ..

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i Docket No. 50-358 MEMORANDUM FOR: Elinor Adensam, Chief

, Licensing Branch #4, DL -

i FROM: Ronald L. Ballard, Chief Environmental & Hydrologic Engineering Branch, DL

SUBJECT:

ENVIRONMENTAL INSPECTION OF ZIMMER NPP SITE We reviewed the environmental information in the letter to J. R. Schott, site manager, Cincinnati Gas and Electric Company, from C. J. Paperiello, Chief Emergency Preparedness and Radiological Branch, NRC, and the attached inspection report conducted by Dr. M. J. Destmann. The report indic ates- that erosion has been stabilized according to the plan submitted June 1, 1984, except in one location, the settling basin. The soil eroding from the banks of the settling basin will remain in the basin and therefore have no offsite impact. We helieve no further NRC action is necessary prior to the utility's withdrawal of their license.

This review was performed by G. LaRoche.

Original signed by Ronald L. Baucrd Ronald L. Ballard, Chief Environmental & Hydrologic Engineering Branch Division of Engineering DISTRIBUTION:

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NUCLEAR REGULATORY COMMISSION j/ .? - ~f , C gj(

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,6../&: 'g MEMORANDUM FOR: W. Crow, Acting Chief E,EC3 ' ~ ~ i.

Uranium Fuel Licensing Branch Q h Division of Fuel Cycle and , . ., y.

g..q Materials Safety, NMSS v.s. t.*;:t:: :- .v m ;;

c. i FROM: C. J. Paperiello, Chief ,.~..

Emergency Preparedness and N: ,$.

Radiological Protection Branch N. . ,' '

SUBJECT:

CONFIRMATORY SURVEY AND LICENSE TERMINATION, SNM-1823 This refers to the memorandum of February 15, 1985, from George Bidinger of

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your staff on the above subject. Enclosed is a copy of our inspection report dated January 11, 1985, for the Zimmer facility. Surveys conducted at that time showed.no radioactivity in the areas surveyed. The incore detectors were in original crates in the warehouse but the warehouse itself was not smear surveyed.

We see no reason to do additional surveys for the sealed sources. However, if needed for public relation purposes, a materials inspector could stop at Zimmer when in the Cincinnati area.

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C.g.p. ap@iello, Chief Emergency Preparedness and Radiological Protecti'on Branch

Enclosure:

Inspection Report 70-2838/84-07 G. Bidinger e-cc w/ enc 1: g f 2] ' " ..,; ',

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JAN il ED5 Docket No. 50-358 Docket No. 30-11989 Docket No. 70-2838 Cincinnati Gas and Electric Company ATTN: J. R. Schott Site Manager 139 East 4th Street Cincinnati, OH 45201 Gentlemen:

This r'efers to the special safety inspection conducted by Dr. M. J. Destmann of this office on December 11-12, 1984, of activities at the William H. Zimmer Nuclear Power Station, Unit 1, authorized by NRC Construction Permit No. CPPR-88 34-07251-04, (Docket No. 50-358), Byproduct Materials License No.and Special Nuclear M (Docket No. 30-11989) and to the discussion of our, findings with'Mr. J. Schott (Docket No. 70-2838), Additional and others of your staff at the conclusion of the inspection.

discussions have been held by telephone v!th Mr. G. Ficke of your staff on December 13, 14, 17, and 18, 1984.

The inspection was an examination of activities conducted under your licenses as they relate to radiation safety and environmental protection and to compliance with the Commission's rules and regulations and with the conditions of your licenses. Within the areas examined, the inspection contisted of a selective examination o' procedures and representative records, observations, independent measurements, and interviews with personnel.

No items of noncompliance with NRC requirements were identified during the course of this inspection.

In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure (s) will be placed in the NRC Public Document Room unless you notify this office, by telephone, within ten days of the date of this letter and submit written application to withhold information contained therein within thirty days of the date of this letter. Such application must be consistent with the re-If we do not hear from you in this regard within quirements of 2.790(b)(1).the specified periods noted above, a copy of this '

inspection report will be placed in the Public Document Room.

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2 JAN 11 BSS Cincinnati Gas and Electric We will gladly discuss any questions you have concerning this inspection, erely, C. J. Paperiello, Chief Emergency Preparedness and Radiological Branch ,

Enclosure:

Inspection Report No. 50-358/84-07(DRSS)

No. 30-11989/84-01(DRSS)

No. 70-2838/84-07(DRSS) cc w/ encl <

G. C. Ficke, Manager, Nuclear Licensing Department DMB/Docement Control Desk (RIDS)

Resident Inspector, RIII Harold W. Kohn, Ohio EPA ,

MVPP/ CASE James W. Harris, State of Ohio Robert H. Quillin, Ohio Department of Health Thomas Applegate Thomas Devine, Associate Director, Institute for Policy Studies Dave Martin, Office of Attorney General Mark Wetterhahn, Esq.

Jerome A. Vennemann, Esq.

Gretchen Hummel, Ohio Consumers' Counsel James R. Williams, State Liaison Officer, Ohio Disaster Services Agency Paul Ryder, Ohio Governer's Office R. E. Buerger, The Dayton Power and Light Company John B. Shinnock, Esq. ,

D. David Altman, Esq.

Zirmer Area Citizens H. Denton, NRR .

B. J. Youngblood, NRR L. Kintner, NRR C. Barth, ELD RIII RI)

RI RII( II l' u 1.rsb v /1/e fello Oestmann/pg Schumacher Ca 1 o 1/7/85

i U. 5. NUCLEAR REGULATORY COMMISSION REGION III I

Report Nos. 50-358/84-07(DRSS); 30-11989/84-01(DRSS); 70-2838/84-07(ORSS)

J i Licenses Nos. CPPR-88; i

Docket Nos. 50-358; 34-07251-04 30-11989; l SNM-1823 1 70-2838 t

> Licensee: Cincinnati Gas and Electric Company 139 East 4th Street Cincinnati, OH 45201 Facility Name: William H. Zimmer Nuclear Power Station, Unit 1 Inspection At: William H. Zimmer Nuclear Power Station Site, Moscow, OH I

Inspection Cond ted: ecember 11-12, 13, 14, 17, and 18 ,

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  • i Inspector: M. . Destmann

< Approved By:

  • (he:!'s M. C. Schumacher, Chief -
                                                                                                                                                                              // */h4, Date J

Independent Measurements and i Environmental Protection Section ' i , i i 1 1 Inspection Summary l Inspection on December 11-12, 13. 14. 17. and 18 1984(Report i l ! Nos. 50-358/84-07(ORSS): 30-11989/84-01(ORSS): 70-2338/84-07(DRSS) Areas Inspected: Special, announced, safety inspection of: (1) environmental t i ' protection, including implementation of the licenste's site restoration plan;  ; i- (2) radiological protection including: (a) performing an independent 4 radiation survey of the fuel pool area, the high and low level laboratories and counting room and instrument calibration room; and (b) verifying ' the licensee's inventory of radioactive sources. I Results:_ No items of noncompliance were identified. The inspector's tour ' of the site showed evidence of erosion of the banks The of radiation the settling basin survey ,

where the licensee failed to seed. - (Section 3).

results of the fuel pool area, the high and low level laboratories and counting room show that the NRC guidelines (Enclosure 1) for release to unrestricted use have been met. Two radiation sources (Cs-137) are stored in the Instrument Calibration Room and 63 in-core fission chambers (ne for Low Power Range Monitors (LPRMs) and Transversing Incore Probes (TIPS) are crated and stored in warehouse No. 2. g e-- g, l l Y. '

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j  ! DETAILS ,f I 3

1. Persons Contacted .

1J. R. Schott, Site Manager 1,8 G. E. Ficke, Licensing Manager l i 1J. Stierizt, Radiation Protection Officer l sB. Gott, Field Construction Engineer i S. Fe11haus, Material Handling Specialist i 3 Denotes those present at exit interview on December 12, 1984. j

Denotes those present during telephone conversations on l

1 December 13, 14, 17 and 18, 1984

2. General f

i  ; On August 29, 1984, the Atomic Safety and Licensing Board (ASLB) issued a , Memorandum and Order authorizing the withdrawal of the Zimmer operating l

                       - licgnse application and dismissal of this proceeding subject to the l

implementation of the licensee's site restoration plan submitted to the i l j

  • NRC on June 1, 1984, and verification by the staff that the 28,site 1985. [

restoration has been satisfactorily completed by February  ; 4 The Zimmer Site Restoration Plan consists of:

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1. Removal of trailers and temporary buildings not useful for conversion l ' to a coal fired unit.
2. Limited grading prior to reseeding; I~
  • Addition of crushed rock on bare areas that are not seeded; t

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4. Modification of drainage patterns at two borrow areas; i

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5. Reseeding of bare areas onsite and on transmission line
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right-of-ways., l I

!                                                    18, 1984, the licensee's counsel stated that           <

l By letter dated Octoberrestoration of the Zimmer site as described in the Jul j plan had been completed and requested termination of Construction l i Permit CPPR-88. r

!                            The licensee has transferred or disposed of most of the radioactive l                            sources on site, once all sources are removed, the licensee will               l j

request termination of their byproduct, source, and special nuclear

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l I material licenses.

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3. Observations Durino Site Tour The inspector toured the site to assure the commitments made in the licensee's June 1,1984, Site Restoration Plan had been satisfactorily met, particularly the conditions described in the Dames and Moore Report enclosed in the Plan. The enclosed Figure 2 shows th'e onsite structures, buildings, existing road ways, access roads, parking lots, fence lines, trailer, and drainage lines which existed on January 21, 1984.

The enclosed Figure 3 presents the configuration of plant site facilities at the time of this inspection. Comparison of the two figures show what structures had been removed. The tour of the site included an overview from the roofs of the Auxiliary Building and Office Building and on the ground within and outside the security fence. The following observations were noted:

1. Most of the trailers had been moved to a parking lot north of the Auxiliary Building (designated as "A" in Figure 3) and were being sold by auction during the inspection.
2. Trailers were also located within the security fence parked in a lot south of the cooling tower (designated as "B" in Figure 3).
                    -A licensee representative stated that they also would be sold.
3. Only permanent buildings still remained on the site. The Construction Office Building (Ceardinat9s C-4) and temporary additions to the Carpenters M'.11 Shop (D 6), Weld Test Shop (0-6),

Iron Workers Shop (0/E-6), E*.ectrical Shup (E-7), Pipe Shop (E-6) and Paint Shop (F-7) have been removed. No debris or rubble was visible on the site except for large concrete slabs at a location south of the parking lot (designated is A) near the banks of the Ohio River. A licensee representative stated that they may be of use when . constructic, for a coal fired plant is underway. ,

4. Limited grading prior to seeding and addition of crushed rock to bare areas where seeding was not done, was completed during the summer of 1984 (designated as "C" in Figure 3). The grading eliminated depressions where water could accumulate; smoothed surfaces so vegetation could be maintained; and reduced slopes adjacent to some of the drainage courses subject to high rates of erosion.
5. Modified drainage patterns at the two borrow areas resulted in direct runoff toward the Little Indian Creek and drying up of these areas (as designated in "0" in Plate 1). There was no evidence of severe onsite erosion along the other drainage ditches and conduits located within the security fence. These drainage pathways are shown in Figure 3. .

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6. Revegetation from seeding of about 22 acres within the security  ;

fence and the borrow areas was quite evident (as shown by Roman numerals in Figure 3 and in Table 1). Revegetation also was evident i on transmission line right-of-ways, in areas along the access roads to l both meteorological towers, designated as "F" and the borrow areas I - ("D") north of the parking lot "A". l 1  ;

7. .A licensee representative stated that no seeding had been done  !

! around the perimeter of the settling basin or in adjacent areas as stipulated in the licensees Site Restoration Plan. Natural vegeta-l l i l tion on the basin edge was heavy but was sparse on the almost { vertical bank. Erosion was evident, especially on an area of i bank on the south side (area "G" plate 1) where the bank had i ! apparently caved in. Basin water level follows that of Ohio River l from which water enters the basin by intrusion. [ l  ! ! No items of noncompliance were identified.  ; 2 . i

 .'                          Radiation Survey and Radiolonical sources                                                   3
4. .

l The inspector performed a radiation survey and took contamination smears

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of.the fuel pool area in the Reactor Building where the unirradiated fuel f j# was stored, and the high and low level laboratories, counting room and I l instrument calibration room in the Auxiliary Building. The inspector used l j a micro R Meter (Eberline Micro R/h meter, Serial 681, calibrated on ' l November 14, 1984). The smears were counted in the Region III canberra low-level alpha-beta counter Model 2201. The fuel had previously been i  ! shipped to Exxon Nuclear Company Inc. , Richlar'id, Washington 1 The licensee  : had performed a survey of the storage racks and fuel pool floor which ( showed no activity above background. (Minimum detectable levels of l! 104 dpm/100 cm3). !, The smear results and the radiation survey of the fuel pool area and the laboratories and counting room are shown in Table 2 and the > i enclosed Figures 4 and 5. The smear survey results were generally indistinguishable from background at the 95 percent confidence level. l The exceptions were less than one percent of the unrestricted release  : l limits Itated in Enclosure 1 to this report. The radiation survey l indicated background levels of eight microroentgens per hour in most {

areas. The only exception was the Instrument Calibration Room where j two calibration sources (J. L. Shepherd Associated Model No. 4810 containing less than 100 mf11(curies Cs-137 and Model No. 28 Series containing less than 20 curies Cs-137) were located. The licensee is I

planning to transfer the Model No. 4810 (100 act) source to D. C. Cook  ! j J by the end of December 1984.  : i ! L

                                                                                                       .                 j 81nspection Report No. 70 2838/84 06(DR$$)                                     ,

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__ ~ . 1 I l i l Crates containing 53 incore fission chambers (neutron detectors used for The fission chambers LRPMs and TIPS) are stored in warehouse No. 2. contain about 2.7 grams of enriched uranium which is licensed under License , No. $NM-1823. A licensee representative stated that the second Cs-137 source and the incore detectors would be shipped to Richland, Washington, for disposal by the end of December. At that point the licensee will have i transferred or disposed of all licensed radioactive sources. The inspector reviewed the licensee's records of shipment of licensed materials under License No. 34-07251-04 and determined that all transfers and disposals were made in accordance with NRC rules and regulations. The results of the radiation and contamination survey made in the Reactor Building fuel pool area and the Auxiliary Building high and low-level laboratories and counting room show that the NRC guidelines (Enclosure 1) After removal of the for release to unrestricted use have teen met. cesium-137 sources, the licensee plans to perform a closeout survey to I* assure no residual contamination remains. The licensee will then request l i termination of their byproduct and special nuclear materials licenses.

                  ~ No 4tems of noncompliance or deviations were identified, i

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5. Exit interview l

l The inspector met with licensee representatives (Section 1) at telephone Additional the i conclusion of the inspection on December 12,1984. discussions were held with a licensee representative December 13, 14, 17 and 18 1984 and with representatives of the Office of Nuclear Reactor The inspector stated that all l Regulation (NRR) on December 17-18, 1984. the conditions of the Site Restoration Plan appeared to have been met with one possible exception. No seeding had been done around the settling basin periineter and native vegetation on the steep banks  ! appeared inadequate to control erosion. A,1icensee representative stated that no decision had yet been made as to possible use of the basin during construction or operation of the coal fired plant. The licensee l acknowledged the presence onsite of the cesium sources and the incore detectors used in LPRM's and TIPts and acknowledged the need to dispose of  ; the material prior to license termination. i t i e l I l

d Attachments:

1. Enclosure 1 - NRC Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use, or Termination of Licenses for Byproduct Source or Special Nuclear Materfel
2. Figure 2 - Zimmer Plant Site Configuration (January 21, 1984)
3. Figure 3 - Projected Zimmer Plant Site Configuration (End of December 1984)
4. Plate 1 - Dames and Moore Interim Restoration Plan - Zimmer Site, May 1984
5. Table 1 - Areas of Seeding in Acres of Zimmer Site
6. Table 2 - Radiation Survey Results of Smears of Removable Contamination
7. Figure 4 - Radiation Survey of Fuel Pool Area
8. Figure 5 - Radiation Survey of Laboratories and Counting Rooms 1

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GUIDEL1 ties F.DR DECO: iia".11(AT10 ( OF FAC2tli]ES A!iD EQUIP!'.Ili7 FRIOR TO RELEASE F0F, U!iKISTRitTED USE OR TERKiliAT10!i,OF LICEliSES FOT. EYPR3 DUCT, SDURCE, . OR SPECI AL tiUCLEAR 1%TERI A!.

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st ecify the T bt i:.nr . tit. .s ir. this guida , ir. ccr.'.un::i:r. s ith 'iable 1 radic.u:lict: and radiation exposure rate lirits which should bt used in decontamir.stic . and survey of surf aces or prcmises Theand equipment limits in T55'a prior - 3____._...

 -                         to at.andtnmer.1 or release for unrestr1cted use.                                                                                          -

do not apply to premises, equipment, or scrap containir.g induced radio-- activity .for which the radiological considerations pertinent to their use nay be different. The release of such f acilities or items from considered on a cass-ty-case basis. regulatory centro'1 is

1. The licensee shall rate a reasonable effort to eliminate residu ,

contamination. , .

2. Radioactivity on equipment or surfaces shall not be covered by pair.t. p1 sting, or other covering caterial unless contamir.ation levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the
   -                                covering. A reasonable effort must be made to minimize the
                         '         ' contamination prior to use of any covering.                           '
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3. The radioactivity on the interior surfaces of pipes, drain lines, or duttwork shall be determined by . making measurements at all traps, end other appropriate access points, provided that contam- ~

instion at these locations is likely~to be representative of J 2 - - -Cu. contaminat' ion on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such si2e, construction, or location as to make the surface inaccessible for. purposes of ' measurement shall be presumed to be cohtaminated in excess of the limits.

4. Upon request, the Com;.ission may authorize a licensee to relinq possession ur contrri 'i materials of premises, in excess of the equipment, limits specified. o d not be limited to, special circumstances 1 This may include, but +

such as ra2ing of bail: s, transfer of premises to another organization active materials, or conversion of facilities contint'ing work with,r, standby status. Such requests must: to a long-term storage Provide detailec, ific information describing the premises,

a. dioactive contaminants, and the nature, equipment or screp, extent, and degret residual surface contamination.
b. Provide a detailed t..elth and safety analysis which reflects that the residual an.ounts of materials on surface areas, together with other considerations such a unreasonable rist to the health and safety of the-public.
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5. Trio- to re tetit g,3 3) n.31.e a co . pre hensu, t radiE*6.en curvev dit (!"1:

A c: : y t.i cortEr':Etion i5 withir, the 1.r1 E Cg,t ,.f , i r. 1 E !.i e 1 -e]itione,

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and P.iteriti S.,ety. est;Pr.1,'a'shinctong,, ice hEvino jurisdiction, rne. . ,-

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S Ad.injs6rE )e t a t 30 Nys Prior to the plant.ed date The survey report shh11:

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g. 3dentify the premises. ,

Shew that retsor.'able efion t.as been d 2 MW b. residehl contar.ination.

c. Describe the scope of the survey and general pro edures f ollowed.

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                                                 -      d. s    tate     the [ ndings
                                                                                                ,of    the     survey         in. units  specifie                            _
   ,.                                                          the ' instruction.

iii - Following review of the report. the liRC Wili consider visiting , i the facilities to confirm g the survey. 3 . . ..

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                                      *                                                            ,                                                                     -.                             g it.11-235. U-23fl and                                                         15,000 dp1 a/100 cm2                                               1,000 dem /lon                 ,c.-

related decay products 5,000 dpm n/100 cm 2 . 1 e t I isur:nics, lia-226 Ra-228, - 300 dpm/100 cm2 20 dp=/lon c.2 l]O, Th.228, Pa-231, 100 dem/100 cm2 ~ f27,1-125,1'129 _ sat. Th-232, Sr-90, 200 dp=/100 c 2 3000,ripm/100lcm2 f23 Ra-224. U-232, 1-126, 1000 dem/100 cm2 '

31. I-133 .

e garwa emitters (nuclides

  • 4 decay rodes other than
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15,000 dem ny/100 cm2 1000 dem ny/ Inn rei-5000 dpa sy/100 cm2 Na caission or spontaneous . sinn) czcept Sr-90 and ers noted above. cre surface contamination by both alpha- and beta-gama-emitting nucildes exists, the limits estab11shed c11 des should apply independently. - . .

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used in this table, dem (disintegrations per minute) means the rate of emissinn by radioactive materf al as detemined'hy instr.. corre omts per minute observed by'an appropriate detector for background, ef ficiency, and geometric factnrs associated with the

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'asurements of average contaminant should not be averaged nyer more than 1 square meter. , inuld he derived Inr each such nhject. , ie maximum contamination level applies to an area or not more than 100 cm2 . ie amohnt of removable radioactive material per 100 cm2t of of surface Fadinactive area thnold material on be the determined wipe with an_appropr' by wiping late that ins tareaiie~

  • with ef iterbent raper, applying moderate pressure, and attessing the amounmwn ef fIctency. ,When .u removable cont reportionilly and the entire surface should he wiped. .

b not cececil ie average and maximum radiation levels associated with surface contamination resulting from beta-game emitters ter or shou t , 2 mrad /hr at I cm and 1.1) mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centim

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TABLE 1 AREAS OF SEEDING IN ACRES OF ZIMMER SITE ACRES ROMAN NUMERAL I 0.887 II 4.764 III 2.558 IV 1.189 V 0.996 VI 0.659 VII 0.144 VIII 0.142 IX 0.173 X 0.67 XI 0.121 XII 1.381 , XIII 0.216

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Results of Smears of Removable Contamination ' (Counted on Canberra Alpha-Beta Counter on December 13, 1984) ALPHA, dpm/100cm2 BETA, dpm/100cm2 SHEAR LOCATION LOG NO. 84-436 <0.1 <2.8

1. <2.8 84-437 0.310.7
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3. 84-438 84-439 <0.1 <2.8
4. <2.8
5. 84-440 <0.1 84-441 <0.1 <2.8
6. <4.7 84-442 <0.2
7. <2.8 0.711.0
8. 84-443 84-444 <0.1 <2.8
9. 0.410.7 <3.1
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10.- 84-445 84-446 <0.1 <2.8

11. 3.113.9 84-447 0.310.7
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13. 84-448 0.711.0 0.310.7 <2.8
14. 84-449 0.711.0 <2.8
15. 84-450 0.7*1.0 -
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16. 84-451
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17. 84-452
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18. 84-453 0.310.7 <2.8
19. 84-454 <5.1
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20. 84-455 <2.8 84-456 <0.1
21. <2.8 84-457 0.711.0 -
22. <0.1 <3.6
23. 84-458 <3.1 84-459 0.410.7
24. <3.9 84-460 1.111.2
24. <0.1 <3.2
26. 84-461 <3.5 84-462 0.310.7
27. 0.3t0.7 <2.8
28. 84-463 0.711.0 <2.8 29.(Blank 84-464 Filter Paper)
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MAR 141985 FCUP:GHB l 70-2838 SNM-1823 Cincinnati Gas k Electfic Company ATTN: Mr. James D. Flynn, Manager Licensing and Environmental Affairs Department P.O. Box 960 Cincinnati, Ohio 45201 , Gentlemen: In-accordance with your letter dated January 11, 1985, Materials License No. SNH-T823 is hereby terminated. Enclosed are four copies of Amendment No. 3 to Indemnity Agreement No. B-85. Please return one signed copy. Enclosed for information is a copy of our Safety Evaluation Report. FOR.THE NUCLEAR REGULATORY COMMISSION MM 8 Signed By: W. 7. Crow W. T. Crow, Acting Chief Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, HMSS

Enclosures:

1. Amendment No. 3 to Indemnity Agreement No. B-85
2. Safety Evaluation Report cc: Andrew B. Dennison, Esq /

DISTRIBUTION Docket File 70-2838< PDR NMSSR/F DWeiss, LFMB FCUP R/F GBennington, SGMT VLTharpe WBrown, SGFF . GHBidinger (2)e SH0 - - ,_ y 21 LCobb, IE . Region III /p' CBarth, ELD / ~ ~ > !.C u.P BMC>.

                             ?.W.f. 4L . . . . . .?  ..C  . U ?. . . . ... .enc.

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                .                                .        =                       _

1 , , y y *' s, "y* R } ~- MAR 141985 DOCKET NO.: 70-2838 LICENSEE: Cincinnati Gas & Electric Company Columbus and Southern Ohio Electric Company Dayton Power and Light Company

SUBJECT:

TERMINATION OF NRC MATERIALS LICENSE NO. SNM-1823 LICENSEE LETTER DATED JANUARY 11,1985

Background

On June 26, 1978, Materials License No. SNM-1r '3 was issued. The license authorized possession of enriched uranium in uairradiated fuel assemblies .- and in neutron detectors. On March 6, 1979, the license was amended to

             . authorize possession of a plutonium neutron source. These materials were intended,for use in the William H. Zimmer Nuclear Power Station.

I Discussion In the January 11, 1985 letter, the licensee requested temination of the license in accordance with the requirements of 10 CFR 70.38. The licensee certified that licensed materials had been transferred to other licensees and provided survey results to show that radiation levels were at or very close to background in all areas. The NRC Region III staff conducted an independent confimatory survey

      -           in December 1984 and reported the res01ts in Inspection Report 70-2838/

84-07(DRSS). By memorandum dated February 25, 1985, Region III raised no objection to termination of the license. Copies of the memorandum and report are' attached. Conclusion /Recomendation The staff concludes that Materials License No. SNM-1823 may be terminated without undue risk to the health and safety of the public or the environment. Termination of the license is recommended.

                                                                                                  . Original signe'd by George H. Bidinger G. H. Bidinger Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Origina1 Signed 3yt                               Material Safety, NMSS
w. T. crov .
                                                                                                                                                                                  .m Approved by:                                                                                                                                       '.'

W. T. Crow, Section Leader , r At t u.hment e . Meno dtd 2 F 3 F FC mie ) . .......1. fro.m. . . . . . . . . . . .. .. . .. ... .. . . . . . . . . . . . . .

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