ML20154A669

Amend 113 to License DPR-40,allowing Licensee to Use Annual Average (Rather than real-time) Meteorological Dispersion Factors to Calculate Doses & Corrects & Clarifies Some Parts of Tech Specs 2.9.1 & 5.9.4

ML20154A669
Person / Time
Site:	Fort Calhoun
Issue date:	05/04/1988
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154A667	List: ML20154A662 ML20154A669 ML20154A675
References
NUDOCS 8805160087
Download: ML20154A669 (7)

Text

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1. • 'o,, UNITED STATES

. 8 o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C 20555 B ,

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OMAHA PUBLIC P0k'ER DISTRICT DOCKET fiO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDPENT TO FACILITY OPERATING LICENSE Amendment No..ll3-License No. DPR-40

1. The Nuclear Regulatory Commission (the Comission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated February 8, 1988, complies with the standards and requirenents of the Atcric Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Corrission; C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the ecmon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications containn in Appendix A, as revised through Amendment No.113, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective 90 days from the date rf issuance.

FOR THE NUCLEAR REGULATORY COMMISSION u 0. 0c &

Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 4,1988 l

ATTACHMENT TO LICENSE AMEN 0 MENT NO.113 FACILITY OPERATING LICENSE NO. OPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment nurber and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 2-40 2-40 2-41 2 41 2-43 2-43 5-15 5-15

4 2.0 LIMITING CONDITIONS FOR OPERATIONS 2.9 Radioactive Effluents 2.9.1 Liquid and Gaseous Effluents Applicability Applies to the controlled release of radioactive materials in liquid and gaseous effluents from the facility. The provisions of Technical Speci-fication 2.0.1 for Limiting Condition for Operation are not applicable.

Objective To define the limits and conditions for the controlled release of radio-active materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as is reasonably achievable in confo mance with 10 CFR Part 50.34a and 50.30a, and to ensure that these releases result in concentrations cf radioactive materials in liquid and gaseous effluents released to unrestricted areas that are within the limits l spe:ified in 10 CFR Part 20.

To ensure that the releases of radioactive materials above background to unrestricted areas are as low as is reasonably achievable, the followino design objectives apply.

A. Liquid Effluents (1) The dose or dose comitment to a member of the public during any calendar year should not exceed 3_ millirems to the total body.

(2) The dose or dose comitment to a member of the public during any calendar year should not exceed 10 milliremt to any organ.

B. Gaseous Effluents (1) The calculated annual air dose due to gama radiation at any location which could be occupied by individuals in unrestricted areas should not exceed 10 millirads; (2) The calculated annual air dose due to beta radiation at any location which could be occupied by individuals in unrestricted areas should not exceed 20 millirads; and l

(3) The calculated annual total quantity of iodine-131, tritium, and all radioactive raterial in particulate fonn with half-lives greater than 8 days should not result in an annual dose or dose comitnent to any organ of an ir.dividual in an unrestricted area from all pathways of exposure in excess of 15 millirems.

j Amendment No. Ef,113 -

2-40 t

2.0 LIMITING CONDITIONS FOR OPEPATIONS 2.9 Radioactive Effluents (Continued) 2.9.] Liouid and Gaseous Effluents (Continued)

(1) Specifications for Liquid Vaste Effluents

a. (i) The release rate of radioactive material in liquid effluents shall be centro 11ed such that the instan-taneous concentrations for radionuclides, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFP. Part 20, Appendix B, for unrestricted areas. For dissolved or entrained nchle gases, the concentration shall be limited to 2.0 E-04 microCi/ml total activity. I (ii) With the concentration of radioactive material released to unrestricted areas exceeding the above limits, appropriate corrective actions shall be taken imediately to restore concentrations within the above limits,

b. The cumulative dose contributions from redioactive materials in liquid effluents released to unrestricted areas shall be deter-nined, in accordance with the ODCM, on a quarterly basis. If the dose contributions, due to the cumulative release of liquid effluents averaged over a eclendar quarter, exceed one-half of the design objectives, the following course of actions shall be taken:

(i) Make an investigation te identify the causes for such releases.

(ii) Otfine and initiate a progran of action to reduce such releases to the design levels.

(iii) Submit a special report, pursuant to Specification.5.9.3, within 20 days from the end of the quarter during which release occurred, identifying the causes and describing the proposed program of action to reduce such release to the design levels,

c. The equipment or subsystem (s) of the liquid radwaste treatment system as identified in the ODCP shall be operated prior to the discharge of radioactive caterials in liouid wastes. If tt)e radioactive liquid wastes were discharged without treatment by one or nere of the pieces of equipment or subsystem (s) idertified in the ODCM and it appears that one-half of the anrual objective will be exceeded during the calendar quarter, a special report, pursuant to Specification 5.9.3, shall be prepared and subr.itted to the Conrission within 30 days. This report shall include the fo11cwing information:

(i) Identification of equipment or subsysters not operable and reasons for inoperability.

2-41 Amandment No. U , U ,Il3

2.0 LIMITINC- CCKDITIONS FOR OPEPATIONS 2.9 Radioactive Effluents (Continued) 2.9.1 Licuid and Gasecus Effluents (Continued) operable radiation monitor. If both radiation monitors are inoperable, steam generator liquid release may continue provided appropriate grab samples are analyzed for principal gamne enitters at a sensitivity of 5.0E-07 ;JCi/ml and recorded 6t least daily wher. the specific activity of the sample is less than or equal to 0.01 pC1/ gram dose equivalent I-131 and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 JJC1/ gram dose eovivalent I-131. If the radicactivity cannot be recorded autoratically, effluent releases may continue provided the gross radioactivity level is recorded nanually at least once per four hours during actual release.

(?) Specifications for Gasecus Waste Effluents

a. (i) The release rate of radioactive materials in gaseous effluents shall be controlled such that the instan-teneous concentrations cf radionuclides do not exceed the values specified ir 10 CFR Part 20, Appendix P, Table 2 for unrestricted areas. Unrestricted area concentrations shall be calculated based on the annual average Chi /Q.

(ii) With the concentration of radioactive material released to unrestricted areas exceeding the above limits, appro-priate corrective ections shall be taken irrediately to restora concentration within the above linits.

b. The radiatior dose contributions fron radioactive raterials l in gasecus effluents shall be determined, in acccrdar.ce with the ODCM, on a cuarterly t. asis. If the dose contributiers, due tc the cumulative release of gaseous effluents averaged over a calendar quarter exceed one-half of the design objectives, the fo11ovino course of actions sFall be taken:

(i) Fake an investigation to identify the cause for such release rates.

(ii) Define and initiate a program of acticn to reduce such releases to design levcis.

(iii) Suteit a special report, pursuant to Specificatier E.9.3.

within 30 days fron the end of the quarter during which release cecurred, identifying the causes and describing the prereted program of action to reduce dose contribu-tions.

c. The equipment of subsyster(s) of the gaseous radwaste treatment systen as identified in the ODCM shall be operated prior to the discharge of radioactive materials in gasecus wastes. If the radioactive gaseous wastes were discharged without treatr.ent by 2-43 Amendrent No. Pf, 113

5.9.3 Special Reports Special reports shall be submitted to the Regional Administrator of the appropriate NPC Regional Office withir the time period specified for each report. These reports shall be sutmitted covering the activities identified below pursuant to the requirements of the applicable reference specification where apprcpriate:

a. In-service irspection repert, reference 3.3.

b. Tendon surveillance, reference 3.5.

c. Centairrent structural tests, reference 3.5.

d. Special naintenance reports.

e. Containrrent leat rate tests, reference 3.5.

f. Radioactive effluer.t releases, reference 2.0

g. Paterials radiation surycillance specimens reports, reference 3.3.

h. Fuel perfonnance following each refueling cutage.

i. Fire protecticn equipment outage, reference 2.19.

j. Post-accident monitoring irstrumentation, reference 2.21.

5.0.4 Unicue Peportina Requirements

a. Radioactive Effluent Release Perort A report covering the operation of the Fort Calhoun StLtion during the previous six fronths shc11 be submitted within C0 days after January 1 and July 1 of each year per the requir ments of 10 CFR 50.36a. ,

The radioactive effluent release report shall include a sumary cf the quantities of radioactive licuid and gaseous effluents and solid v:aste released from the plant as outlind in Regulatory Guide 1.21, Revision 1.

The radioactivt effluent release report shell include a sumary cf the metecrolocical conditictr concurrert with the release of gascces effluents during each ouarter as outlined in Pegulatory' Guide 1.21, Revision 1.

The radioactive effluent release report shall include an assessrent of radiaticn doses from the radicactive liquid and gasecus effluents released frori the unit during each calendar cuarter as outlinrd in r egulatory Guide 1.21, Pevision 1. In addition, the unrestricted crea boundary maxinun noble gas garra air and beta air doses shall be evaluated. The meteorological ccr.ditions concurrent with the i

5-15 Amendrent No g 7/, 7E, /f, Pf, 110, w - - w -----,.--,--n-..__