ML20209D514

Forwards RAI Re 981019 Application & Suppl Dtd 990216,which Requested Review & Approval of Revised Rc Allowable Dose Equivalent I-131 Activity Limit with Max Dose Equivalent Limit of 1.0 Uci/Gram.Response Requested within 30 Days

ML20209D514
Person / Time
Site:	Three Mile Island
Issue date:	07/08/1999
From:	Colburn T NRC (Affiliation Not Assigned)
To:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
References
TAC-MA3951, NUDOCS 9907130151
Download: ML20209D514 (5)

Text

, Mr. Jim >]s W. Leng:nbich, Vics Presid:nt July 8, 1999

" end Director - TMl l GPU Nuclitr, Inc.

P. O. Box 480 Middletown, PA 17057

SUBJECT:

TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) 272 - REACTOR i COOLANT SYSTEM ACTIVITY - REQUEST FOR ADDITIONAL INFORMATION I FOR THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 (TAC NO. MA3951)

Dear Mr. Langenbach:

The NRC staff has reviewed your application dated October 19,1998, as supplemented by letter dated February 16,1999, which requested review and approval of a revised reactor coolant allowable dose equivalent lodine 131 activity limit with a maximum dose equivalent limit of 1.0 microcurie / gram. The staff has determined it will need the additionalinformation identified in the enclosure in order to complete its review. In order for the staff to support your requested review completion schedule, please provide the requested information within 30 days of receipt of this letter. The information in the enclosure and this request and the scheduled l response date have been previously discussed and agreeo spon with Mr. P. Wells of GPU l

Nuclear, Inc., and a copy of this letter is being faxed to Mr. Wells.

l If you have any questions, please contact me at (301) 415-1402.

Sincerely, l ORIGINAL SIGNED BY:

Timothy G. Colburn, Sr. Project Manager, Section 1 Project Directorate I ,

Division of Licensing Project Management j Office of Nuclear Reactor Regulation l

Docket No. 50-289 l

Enclosure:

Request for AdditionalInformation "

g cc w/ encl: See next page j DISTRIBUTION:  !

Docket File TClark SBlack TColburn JLee PUBLIC OGC PEselgroth, RI MReinhart PDI R/F l ACRS

\ \

l DOCUMENT NAME: G:\PDI-1\TMI-1\RAl3951.WPD y9 fo\

To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attach, ment / enclosure "N" = No copy 0FFICE PM:P01 _

(

lE LA:P01 % Q g(f l 7 SC:PD1 .m l l l NAME TColburn F M0*Brienjp M (M SBajwa MR

• / / 7 /99

DATE P'/ T '/99 ~ 7/ f /99

~ Official Record dopy 9907130151 990700 PDR ,,TCK 05000209 P PDR _

l

7.

n arc s

ye lt UNITED STATES g

p '*

j NUCLEAR REGULATORY COMMISSION l WASHINGTON. D.C. 20555-0001 l

%.....# July 8, 1999 I

l Mr. James W. Langenbach, Vice President )

and Director - TMI l GPU Nuclear, Inc.

! P. O. Box 480 Middletown, N 17057 ]

l

SUBJECT:

TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) 272 - REACTOR COOLANT SYSTEM ACTIVITY - REQUEST FOR ADDITIONAL INFORMATION FOR THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 (TAC NO. MA3951)

Dear Mr. Langenbach:

The NRC staff has reviewed your application dated October 19,1998, as supplemented by letter dated February 16,1999, which requested review and approval of a revised reactor coolant allowable dose equivalent iodine 131 activity limit with a maximum dose equivalent limit of 1.0 microcurie / gram. The staff has determined it will neect the additional information identified in the enclosure in order to complete its review. In order for the staff to support your requested review completion schedule, please provide the requested information within 30 days of receipt of this letter. The information in the enclosure and this request and the scheduled response date have been previously discussed and agreed upon with Mr. P. Wells of GPU Nuclear, Inc., and a copy of this letter is being faxed to Mr. Wells.

If you have any questions, please contact me at (301) 415-1402.

Sincerely, b'

Timothy G. Colburn, Sr. Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

Request for Additional Information cc w/ encl: See next page l

l l

l i

y ,

O Three Mile Island Nuclear Station, Unit No.1 cc:

Michael Ross Robert B. Borsum Director, O&M, TMl B&W Nuclear Technologies GPU Nuclear, Inc. Suite 525 P.O. Box 480 1700 Rockville Pike Middletown, PA 17057 Rockville, MD 20852 John C. Fornicola David J. Allard, Director Director, Planning and Bureau of Radiation Protection Regulatory Affairs PA Dep. of Environmental Protection GPU Nuclear, Inc. P.O. Box 8469 e

100 Interpace Parkway Harrisburg, PA 17105-8469 Parsippany, NJ 07054 Dr. Judith Johnsrud Jack S. Wetmore National Energy Committee Manager, TMI Regulatory Affairs Sierra Club l GPU Nuclear, Inc. 433 Orlando Avenue P.O. Box 480 State College, PA 16803 Middletown, PA 17057 Peter W. Eselgroth, Region i Ernest L. Blake, Jr., Esquire U.S. Nuclear Regulatory Commission Shaw, Pittman, Potts & Trowbridge 475 Allendale Road 2300 N Street, NW. King of Prussia, PA 19406 Washington, DC 20037 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 - I l

Chairman I Board of Supervisors I of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 i

Wayne L. Schmidt Senior Resident inspector (TMI-1)

U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 Regional Administrator Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

l . \

l l Reauest for AdditionalInformation l

Technical Specification Chanae Reauest (TSCR) 272 Reactor Coolant System Activity

Reference:

GPU Nuclear letter to the NRC dated October 19,1998 (1920-98-20210) titled, ,

" Technical Specification Change Request (TSCR) No. 272." i

1. In the " Flashing and Evaporation to Dryness Calculation" in Enclosure 4 (page 6 of 20) to the above referenced letter, you used an equation derived in NUREG/CR-5950 (equation 15 on page 13) to determine the primary coolant lodine partition coefficient.  !

l This equation was developed for use in determining an iodine partition coefficient in a  !

quiescent water pool and is not applicable for the once through steam generator l (OTSG) primary coolant flashing into the secondary side. The primary coolant which leaks into the shell side of the OTSG will flash to. steam and iodine in the leaked primary coolant will be immediately vaporized and become airborne due to the flashing and atomization.

The staff sssumes an iodine partition coefficient of 1 (no iodine partition) for the primary coolant leaked to the OTSG since the secondary side of the OTSG will contain no water during the MSLB accident. The staff requests that you recalculate the radiological consequence with no iodine partitioning.

2. In the " Flashing and Evaporation to Dryness Calculation" in Enclosure 4 (page 10 of

20) to the above referenced letter, you used iodine volatility values provided in a table contained in NUREG/CR-5732 (Table 3.8 in page 28) to determine primary coolant iodine decontamination by evaporation to dryness on the OTSG tube surfaces.

These figures are only applicable to iodine evaporation in a quiescent state and only up to 95'C (this reference used evaporation of iodine solution in a beaker to dryness i on an hot plate). These figures are not applicable for the OTSG primary coolant  !

flashing into the secondary side. The staff believes that atomized primary coolant will i not be able to settle on the OTSG tubes to be evaporated. Instead it will vaporize '

instantaneously and become airborne. The staff requests that you recalculate the radiological consequence with no iodine decontamination due to evaporation to  ;

dryness on the OTSG tubes. l l

3. In the " Flashing and Evaporation to Dryness Calculation"in Enclosure 4 (page 15 of l

20) to the above referenced letter, you used NUREG/CR-2713 to determine vapor deposition velocity of iodine on the OTSG tube surfaces.

Enclosure

L I

j  :. .

l ,

\

l The iodine deposition velocity measurement provided in the NUREG has limited

{ application since it was performed on a simple and limited scope as stated in the i

NUREG. The staff believes this experiment is not applicable for estimating iodine deposition velocities on the surfaces of the OTSG tubes. In addition, you have indicated that this iodine deposition velocity becomes only important late in the l cooldown period when the tube surface temperaturo drops below on or about 300* F l

(about 11.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the accident). Justify the applicability of the iodine 1

deposition velocity measurement provided in NUREG\CR-2713 for estimating iodine deposition velocities on the surfaces of the OTSG tubes.

The above questions are necessary in order for the NRC to evaluate radiological consequences from a main steam line break accident to ensure that the resulting 2-hour doses at the exclusion area boundary and the 30-day dose at the low population zone will be a small fraction of the 10 CFR Part 100 dose limit and that control room operator dose will be within the criterion specified in General Design Criterion (GDC) 19 of 10 CFR Part 50.

i l