ML20210K001

Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis

ML20210K001
Person / Time
Site:	Three Mile Island
Issue date:	08/14/1997
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20210K000	List: ML20210J995 ML20210K001
References
NUDOCS 9708190108
Download: ML20210K001 (9)

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Proposed License Revised Pages i

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l 9"98190108 970814 P ,9 ADOCK 05000289 P PDR

5. GPU Nuclear Corporation shall provide routine reporting of the long-term corrosion " lead tests" test results on a quarterly basis as well as more timely uotification if adverse corrosion test results are discovered.

(9) Long Range Planning Program The revised " Plan for the Long Range Planning Program for the Three Mile Island Nuclear Station - Unit 1" (the Plan) submitted by GPUN letter C311-94-2124 dated September 26,1994 is approved.

a. The Plan shall be followed by the Licensee from and after November 28, 1994.

l b. The Category A schedule shall not be changed without prior approval from the NRC. Categories B and C schedules may be changed without prior approval by NRC.

(10) AdditiorrlConditions The Additional Conditions contained in Appendix B, as revised through Amendment No. . are hereby incorporated into this license. GPU Nuclear Corporation shall operate the facility in accordance with the Additional Conditions.

6, This license is effective as of the date ofissuance and shall expire at midnight, April 19,2014.

FOR THE ATOMIC ENERGY COMMISSION Orismal Signed by A. Giambusso A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing

Attachment:

Appendix A Technica, Specifications Appendix B AdditionalConditions Date ofIssuance: April 19,1974 Amendment No.

l APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING I ! CENSE NO. DPR-50 l GPU Nuclear Corporation shall comply with the following conditions on the schedules noted below:

AMENDMENT ADDITIONAL IMPLEMENTATION

! NUMBER CONDITIONS DATE This amendment authorizes the licensee to - Date ofIssuance incorporate in the Updated Final Safety Analysis Report (UFSAR) certain changes to the description of the Steam Line Break accident analysis assumptions and dose consequences.

Implementation of this amendment is the incorporation of these changes as' described in the licensee's application dated August ,

1997, and evaluated in the staff s Safety Evaluation, dated ,1997.

Ameridment No.-

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ENCLOSURE 2 Affected TMI-l Updated Final Safety Analysis Report Pages f *

.. TM1-1/FSAR The analysis ofIntermediate Building environment following a postulatcd main steam break is discussed in Reference 9. The consideration of effects of piping system breaks outside containment is presented in Appendix A. The primary system response is essentially the same for breaks inside or outside containment.

Breaks inside containment pressurize the Containment Building, whereas breaks outside containment can result in Ngher dose rates.

c. Environmental Consequences The environmental consequences from this accident are calculated by assuming that:

1) The unit has been operating with an RCS dose equivalent iodine activity of 1.0 pCi/g for the accident induced iodine spike analysis. This is the limit in Technical Specification 3.1.4, At the onset of the steam line break, the

! release rate ofiodine from the fuel rods to the RCS is assumed to spike by a i factor of 500.

2) Some credit is taken for partitioning and radioactive decay after the break.

3) The steam line break occurs between the Reactor Building and a turbine stop valve.

4) Reactor coolant leakage into the steam generator continues until the Reactor Coolant System can be cooled down and the leakage terminated.

5) The total primary-to-secondary leakage assumption is integrated over the cooldown time to account for accident induced OTSG tube leakage.

The steam line break is assumed to result in the release of the actisity contained in the steam generator inventory, the activitv contained in feedwater, and the activity contained in reactor coolant leakage (see Ta' 14.1-18). Using these assumptions, the total integrated dose to the thyroid and the whole body dose have been calculated and are tabulated in Table 14.1-18 (Reference 77).

14.1-32 UPDATE-

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. TMI-1/FSAR

.- . TABLE 14,1-18 (Sheet 1 of 1)

ENVIRONMENTAL CONSEOUENCES OF STEAM LINE BREAK Accident Induced Spike Activity Released to Environment 1080 (I-131 dose equivalent Ci)

Integrated Primary Coolant Leakage @ 2 hrs 3228 (gallons @ 579 F) l Tetal Integrated Primary Coolant Leakage 9960 (gaiions @ 579 F)

Atmospheric Dispersion coefficient at exclusion distance (sec/m3) 6.80E-04 Atmospheric Dispersion coefficient 2.00E-05 (0-8 hrs)

At LPZ distance (sec/m3) 4.00E-06 (>8 hrs)

Two Hour Dose at Exclusion Distance Total Integrated Thyroid Dose (Rem) 29.7 Whole Body Dose (Rem) 0.12 Thirty Day Dose at LPZ Distance Total Integrated Thyroid Dose (Rem) 8.5 Whole Body Dose (Rem) 0.02 14.1-61 UPDATE-

/98 i

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... TM1-1/FSAR

73. BWNT Document 86-1232708-00,'"RVVV Liquid Spillover Analysis," September 1994.

74. GPUN Document C-1101-211-5450-008, "RCS Boron Concentration with Credit for Vent Valve Liquid Flow," September 19,1994.

75. BWFC Letter, RC-94-786, "TMl-1 Cycle 11 Steam Line Break Evaluation," 12/1/94.

- 76. GPUN SE 135400-022, Rev. 2., "TM1 Cycle 1 I Reload Design / Redesign," 11/10/95.

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77. GPUN Calculation No. C-1101-224-6612-057,"O!! site Doses from OTSG Tube l

Leakage Due to Main Steam Line Break," August 1997, i 1

i 14.3-5a UPDATE-

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9 ENCLOSURE 3 Certificate of Service for TMI-I License Amendment Request No. 269

, , UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION -

IN THE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR, INC, LICENSE NO. DPR-50 CERTIFICATE OF SERVICE This is to certify that a copy of License Amendment Request No. 269 to the License Conditions and new Appendix B of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, .

l Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental l Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as

!_ follows:

Mr. Darryl LeHew, Chair. nan Ms. Sally S. Klein, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R.- D. #1, C:yers Church Road - Dauphin County Courthouse

- Middletown, PA 17057 Harrisburg, PA 17120 ,

Director, Bureau of Radiation Protection

. PA Dept. of Environmental Resources Rachael Carson State Office Building

- P.O. Box 8469 Harrisburg, PA 17105-8469 Att: Mr. Stan Maingi GPU NUCLEAR INC.

BY: .

d#Ao n

q' ice President and Director, TMI DATE: >> M /[/ff7

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