ML19290A414

Tech Spec Change Request 26 to DPR-50,App B Re Sampling Frequency for Individual Gamma Emitters.Certificate of Svc Encl

ML19290A414
Person / Time
Site:	Three Mile Island
Issue date:	12/12/1975
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19290A409	List: ML19290A408 ML19290A414
References
NUDOCS 7911070593
Download: ML19290A414 (9)

Text

~

.

.

METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION LHIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 26 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix B to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix B are also included.

METROPOLITAN EDISON COMPANY ll .

'

By Vice Pre'sfrent-Generation Sworn and subscribed to me this /2 day of, 'm.4 , 1975

'

k Notary Public R:CH A.7D 1. RUTn Nctar; Puth , Mncear: Tr.; , Berks Co.

My Commiss:cn Ex;:res Septem:er 23,1973 1555 343

791107089 7

_

THREE MILE ISLAND NUCLEAR STATION UNIT 1 (TMI-1)

OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Licensee requests that certain changes, as herein-after described, be made in Appendix B of the TMI-l Technical Specifications. A copy of the affected pages with these changes indicated is attached.

-TECHNICAL SPECIFICATION CHANGE REQUEST NO. 26.a.-

Change Request Page 17, Section 2.3.1, Liquid Effluents. Add a paragraph f. to the Specification to read as follows:

-3 "The MPCy (168-hour) for Xe-133 uCi/ml; the MPC y (168-hour)forXe-135is1x10gs5x10 pC1/ml.

Reason for Change Request 10 CFR 20 presently does not provide any MPCy values for xenon but requires that the very restrictive value calculated for unknown mixtures of radio-nuclides be used. The reason for requesting the proposed change is to avoid having to use this very restrictive and technically unjustifiable value and to avoid the costs involved in installing a gas stripping system or in packaging the wastes.

Environmental Analysis Justifying Proposed Change The proposed MPCy values for xenon were derived by a rigorous interpretation of ICRP and NRC guidelines; therefore, it is believed that their adoption will not cause undue risk to either the health or safety of the pu'olic.

Cost-Benefit Analysis Justifying Proposed Change There ara no additional costs associated with the proposed change. The principle benefit will be a cost savings to be derived from removal of the need to either install a gas separation system or have high-xenon-concentration wastes hauled off site so that the MPCy value for unknown mixtures of radionuclides will not be exceeded. A conservative cost estimate for installation of a gas stripping system, including expansion of the waste gas handling system, would be $500,000. The other alternative would involve a cost to package this waste of approximately $600,000 per year.

-TECHNICAL SPECIFICATION CHANGE REQUEST NO. 26.b.-

Change Request Page 23, Section 2.3.1, Liquid Effluents. Add the following paragraph to the Bases:

1555 344

.

"The MPCw values for xenon were calculated from the fundamental formulas found in ICRP 2. All pathways were taken into considera-tion, including swimming and shoreline shine. The pathway doses were calculated from ALAP (WASH-1258) models. The drinking water pathway was found to be the limiting pathway."

Reason for Change Request The reason for requesting the proposed change is to provide the basis for Change Request 26.a. above.

Environmental Analysis Justifying Proposed Change Because the proposed change only serves to provide the b asis for a specifi-cation and does not alter any of the requirements of the. Technical Specifi-cations, its adoption will have no adverse effect on tue environment.

Cost-Benefit Analysis Justifying Proposed Change See the cost-benefit analysis for Change Request 26.a. above.

-TECHNICAL SPECIFICATION CHANGE REQUEST NO. 26.c.-

Change Request Pages 28 and 29, Table 2, Item C, Sampling Frequency for Individual Gamma Emitters. Reference a Footnote (5) instead of Footnote (3) and add a Footnote (5) to read as follows:

The analysis shall be performed following each refueling period, startup, or similar operational occurrence which could alter the mixture of radionuclides unless such an analysis was performed during the previous one-month period.

Reason for Change Request The reason for requesting the proposed change is to eliminate the cost of having to perform redundant analyses of the discharge from the condenser vacuum pump. Specifically, in addition to the monitoring requirenents of Footnote (3), the following analyses of this discharge are already being performed;

1. the discharge is continuously monitored for gaseous activity by radiation monitor RMA-5, and

2. monthly surveillance requirements include a gamma isotopic analysis and a tritium analysis.

Thus, even with the proposed change in effect it is believed that the mixture of radionuclides expected to occur at the condenser vacuum pump discharge will still be adequately monitored.

1555 345

Environmental Analysis Justifying Proposed Change The proposed change, if implemented, will not have any adverse impact on the environment in that the vacuum pump discharge will still be continuously monitored and monthly tritium and gamma scan analyses will be performed.

Cost Benefit Analysis Justifying Proposed Change No additional cost will result f rom implementation of the proposed change, and by making this one monitoring requirement more flexible, fewer man-hours will have to be spent collecting and analyzing gas samples. This reduction in man-hours is expected to result in a cost savings of $2,500 annually.

.

1JJs

-

s7s

.

2.0 LIMITING CONDITIONS FOR OPERATION Specification (cont'd) Specification (cont'd) gases, exceeds 2 5 curies during any Facility records shall be maintained of the calendar quarter, the licensee shall radioactive concentrations and volume before notify the Director, Directorate of dilution of each batch of liquid effluent Licensing within 30 days, identifying released, and of the average dilution flow h the causes and describing the proposed and length of time over which each discharge program of action to reduce such release occurred.

rates. '

Radioactive liquid vaste sampling and activity

f. The MPC y (168-hour) for Xe-133 is 5 x 10-3 analysis shall be performed in accordance with the MPCy (168-hour) for Xe-135 is Table 1. In addition, prior to the release of pCi/m133 each batch of liquid effluent, a sample shall be 1 x 10 pCi/ml ,

taken from that batch and nyalyzed for the concentration of each significant gamma emitter to demonstrate compliance with Specification a using the flow into which the effluent is discharged.

The liquid effluent radiation monitor RF-L6 shall be calibrated at least quarterly by nenns of a known radioactive source. RM-L6 sha21 also have g and instrument channel test monthly and a sensor check daily to verify that the read-out device is indicating as expected.

The ability of WDG-V-257 to close automatically ty, on receipt of a high radiation signal from RM-L6 shall be checked annually.

u 4

N

2.0 LIMITING CONDITIONS FOR OPERATION

-

bases (cont'd)

In addition to the limiting conditions for operation listed under Specification b, the gg reporting requirements of Specification e, in addition to the requirements of Section 5.6.2, delineate that the licensee shall identify the cause whenever the rate of radioactive effluents, excluding tritium and noble gases, exceeds 2 5 curies during any calendar quarter and describe the proposed program of action to reduce such release rate. This report must be filed within 30 days following the calendar quarter in which the 2 5 curies release occurred.

The MPC y values for xenon were calculated frcm the fundamental formulas found in ICRP 2. All pathways were taken into consideration, including swimming and shoreline shine. The pathway doses were calculated from ALAP (WASH-1258) models. The drinking water pathway was found to be the limiting pathway.

2.3.2 Gaseous Effluents Applicability

-

ty, Applies to the controlled release of radio-tj, active gases from TMI Unit 1.

U7 Objecti"e Objective

-

u 43, To define the limits and conditions for the controlled To ensure that radioactive gaseous releases C33 release of radioactive effluento to the environs to from the facility are within the limits of ensure that these releases are as low as practicable. These releases specifications.

TABLE 2 RADI0 ACTIVE GASEOUS WASTE SAMPLIllG AND AllALYSIS Sample Type Sampling Frequency Type of Activity Analysis Detectable Concentration A. Waste Gas Decay Tank Release Gas Each Tank 11 - 3 106 pCi/cc Release Individual Gamma Emitters

~

10 pCi/cc }

B. Reactor Building Purge Releases Gas Each Purge 11 - 3 106 pci/cc

~

Individual Ganma Emitters 10 pCi/cc C. Condenser Vacuum Pump Releases Gas Monthly 11 - 3 106 pCi/cc Monthly (5) Individual Gamma Emitters

~

10 pCi/cc }

D. Auxiliary and Fuel llandling Building Exhaust Vent and Reactor Building Purge Vent Release Points O

Gas Continuous Gross (6,y) 10~ll pCi/cc Monthly 11 - 3 106 pci/cc

"

tn Charcoal Weekly (4) I-131 10 12 pC1/cc Ul Ln Ba-140, La-140, I-131 10~1I pCi/cc One Weekly Sample U Per Month (4} I-133, I-135 10 10 pCf/cc 4

W

(

.

TABLE 2 (Cont'd)

Sample Type Sampling Frequency Type of Activity Analysis Detectable Concentration Particulates Monthly Composite of Sr-89 10~l1 pCi/cc the Samples for the Month Quarterly Composite of Sr-90 10-11 pCi/cc the Samples for the Quarter Monthly Composite of Gross a 10 11 pCi/cc the Samples for the Month (1)The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.

( For certain mixtures of gamma emitters, it may not be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher level.

g Under these circumstances, it will be more appropriate to calculate the levels of such radio-nuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurable.

-

g (3) Analysis shall also be performed following each refueling period, startup or similar operational u occurrence which could alter the mixture of radionuclides.

The iodine and particulate collection device shall be analyzed to determine the release rate increase g for iodines and particulates daily, when the average daily gross radioactivity release rate equals u or exceeds that given in 2.3.2 Specification C or when the steady state gross radioactivity release o rate increases by 50% over the previous correspondinb power level steady state release rate.

(5)The analysis shall be performed following each refueling period, startup, or similar operational oc,currence which could alter the mixture of radionuclides unless such an analysis was performed during the previous one-month period.

'

.

,1*

/\'

ofv' :

,

D -

a.

..

"-

UNITED STATES OF AMERICA .

'

NUCLEAR REGULATORY C0FDiISSION

'

.

IN THE MATTER OF DOCKET No. 50-289 OPERATING LICENSE NO. DPR-50 METROPOLITAN EDIS0N COMPANY This is to certify that a copy of Technical Specification Change Request No. 26 to Appendix B of the Operating License for Three Mile Island Nuclear S tation, Unit 1, dated December 12, 1975, and filed with the U.S. Nuclear Regulatory Commission December 14, 1975, has this 12th day of December,1975, been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania, and of Dauphin County, Pennsylvania, by deposit in the United States Mail, addressed as follows:

Mr. Weldon B. Arehart, Chairman Mr. Charles P. Hoy, Chairman Board of Supervisors of Board of County Commissioners of Londonderry Township Dauphin County R.D. #1, Geyers Church Road Dauphin County Courthouse Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COIPANY r

By Vice President-Generation 1555 351

, .,

a .. v