ML20151U490

Forwards Request for Addl Info Re Occupational Exposure Resulting from Reracking of Spent Fuel Pool.Response Requested within 30 Days of Ltr Date

ML20151U490
Person / Time
Site:	Byron
Issue date:	04/20/1988
From:	Olshan L Office of Nuclear Reactor Regulation
To:	Butterfield L COMMONWEALTH EDISON CO.
References
TAC-62112, TAC-63266, NUDOCS 8805020074
Download: ML20151U490 (4)

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April 20, 1988 Docket Nos.: STN 50-4543 and STN 50-455 DISTRIBUTION Docket File OGC-Roc' NRC & Local PDRs EJorda Mr. L. D. Butterfield, Jr. PDIII-2 Rdg. JPa rtir, <

Nuclear Licensing Manager DCrutchfield ACRS (1, Connonwealth Edison Company GHolahan PDI!!-2 rid.. itle Post Office Box 767 LLuther Chicago, Illinois 60690 L01shan

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - BYRON SPENT FUEL POOL EXPANSION (TAC N0s. 62112 AND 63266)

In our letter dated November 25, 1986, we requested additional information concerning occupational exposure resulting from the reracking of the Byron spent fuel pool. However, at that time you were planning to rerack the pool before it was filled with water. As you noted in your December 22, 1987 letter, the schedule for installation of the racks has been changed because the racks were not delivered on time; thus "dry" reracking is no longer possible.

Enclosed is a request for additional information concerning occupational exposure resulting from "wet" reracking. Provide your response within 30 days of the date of this letter. For any further clarification, please contact me at(301)492-3018.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.

Sincerely, Oriqinal Sianed Rv/

Leonard N. Olshan, Project Manager Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects

Enclosure:

As stated cc: gSO{@@$$$oo 4 See next page p PDIII-2:PM PDIII-2:L6 PDyh%$PD ML01shan:bj LLutherf[ DMuller a/zo/88 y/ao/88 .)/w/88

Byron Station

_ Mr. Henry Bliss Units 1 and 2 Comonwealth Edison Company CC: Regional Administrator, Region III Mr. William Kortier U. S. Nuclear Regulatory Atomic Power Distribution Comission Westinghouse Electric Corporation 799 Roosevelt Road Post Office Box 355 Glen Ellyn, Illinois 60137 Pittsburgh, Pennsylvania 15230 Mr, Michael C. Parker, Chief Michael Miller, Esq. Division of Engineering Sidley and Austin Illinois Department of One First National Plaza Nuclear Safety Chicago, Illinois 60603 1035 Outer Park Drive Springfield, Illinois, 62704 Mrs. Phillip B. Johnson Joseph Gallo, Esq.

1907 Stratford Lane Hopkins and Sutter Rockford, Illinois 61107 Suite 1250 1050 Connecticut Avenue, N.W.

Ms. Lorraine Creek Washington, D. C. 20036 Rt. 1, Box 182 Manteno. Illinois 60950 Douglass Cassel, Esq.

109 N. Dearborn Street Dr. Bruce von Zellen Suite 1300 Department of Biological Sciences Chicago, Illinois 60602 Northern Illinois University DeKalb, Illinois 61107 Ms. Pat Morrison 5568 Thunderidge Drive Mr. Edward R. Crass Rockford, Illinois 61107 Nuclear Safeguards & Licensing Sargent & Lundy Engineers Attorney General 55 East Monroe Street 500 South 2nd Street Chicago, Illinois 60603 Springfield, Illinois 62701 U. S. Nuclear Regulatory Comission Chairman, Ogle County Board

' Byron / Resident Inspectors Offices Post Office Box 357 4448 German Church Road Oregon Illinois 61061 Byron, Illinois 61010

. ESI Review Coordinator Environmental Protection Agency l Region V l 230 S. Dearborn Street i Chicago, Illinois 60604 4

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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION BYRON STATION UNITS 1 AND 2 SPENT FUEL STORAGE 1

1.

Provide a description of fission ar.d corrosion product sources in the spent fuel pool (SFP) water from: (a) introduction of primary coolant into SFP water, (b) movement of fuel from the core into the pool, and (c) defective fuel stored in the pool. Include a listing of the radionuclides and their concen-trations (expressed in uCi/mL) expected O i OP'{3}Cs, ns and3 g fueling.

The radionuclides of interest should include durin88"o*8b C Co, Cs.and 2.

Dose Rates from Fuel Assemblies, Control Rods, and Burnable Poison Rods

a. Provide a description of the dose rate at the surface of the pool water from the fuel assemblies, control rods, burnable poison rods or any miscellaneous materials that may be stored in the pool. Additionally, provide the dose rate from individual fuel assemblies as they are being placed into the fuel racks. Infonnation relevant to the depth of water shielding the fuel assemblies as they are being transferred into the racks i should be specified, If the depth of water shielding over a fuel assembly while it is being transferred to a spent fuel rack is less than 10 feet, or the dose rate 3 feu above the spent fuel pool (SFP) water is greater than 5 mR/hr above ambient radiation levels, then submit a Technical Specification specifying the minimum depth of water shielding over the fuel assembly as it is being transferred to the fuel rack and the measures that will be taken to assure that this minimum depth will not be degraded.

b. Address the dose rate changes at the side of the pool concrete shield walls, where occupied areas are adjacent to these walls, as a result of the modification. Increasing the capacity of the pool may cause spent fuel assemblies to be relocated close to the concrete walls of the pool, resulting in an increase of radiation levels in occupied areas. Please evaluate this potential problem.

3.

Dose Rates from SFP Water Provide information on the dose rates at the surface of SFP water resulting from radioactivity in the water. Include: (1)doseratelevelsinoccupied I areas and along the edges and center of the pool and on the fuel handling (

crane; (2) effects of crud buildup; and (3) based on refueling water activity, l the dose rates before, during, and after refueling, i l

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.- Dose Rates from Airborne Isotopes Based on the source terms, provide the dose rates gom submgrsion and dose comitments from exposure to the concentration of Kr and H.

5.

Dose Assestment from Modification Procedures

a. Discuss the manner in which occupational exposure will be kept A!; ARA during the meditication. Include the need for and the manner in which cleaning of the crud on the SFP walls will be perforined to reduce exposure rates in the SFP area,

b. Discuss vacuum cleaning of SFP floors if divers are used and the distribu-tion of existing spent fuel stered in racks to allow maximum water shield-ing to reduce dose rates to divers.

c. Describe plans for cleanup of the SFP water to minimize radioactive contamination and to ensure fuel pool clarity and underwater lighting acceptance criteria to help ensure good visibility,

d. Discuss underwater radiation surveys that will be made before any diving operation. These surveys should be performed before or after any fuel rovements or movements of any irradiated components stored in the pool.

e. State your intent to equip each diver with a calibrated alanning dosimeter I and personnel monitoring dosimeters, which should be checked periodically to ensure that prescribed dose limits are not being exceeded,

f. Discuss any preplanning of work by divers as required.

, g. Discuss your provision for surveillance and monitoring of the spent fuel l pool work area by Health Physics personnel during the modification. -

6 l Provide an estimate of the total man-rem to be received by personnel occupying i

I the spentfrom resulting fuel p(ool areas

2) (3), andbased on all (5) above. operations Describe in that area the impact of theincluding spent fuelthose storage rack modification on these estimates.

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