ML20009A138

Amend 16 to License DPR-73,implementing App R Criteria in Final Programmatic EIS & Requiring Quarterly Repts Specifying Radiological Releases & Approx Cumulative Population

ML20009A138
Person / Time
Site:	Crane
Issue date:	06/26/1981
From:	Snyder B Office of Nuclear Reactor Regulation
To:
Shared Package
ML20009A137	List: ML20009A136 ML20009A138 ML20009A139 ML20009A140
References
NUDOCS 8107090014
Download: ML20009A138 (18)

Text

{{#Wiki_filter:.,' METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 16 License No. DPR-73 1. The Nuclear Regulatory Comission (the Commission) has found that: A. The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company (the Licensee) dated June 10, 1981, complies with the standards and requirements of the Atomic 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 Order for Modification of License dated July 20, 1979, the Order of February 11, 1980, the Modification of Order dated August 11, 1980, the Amendment of Order dated November 14, 1980, the application for amendment, the provisions of the Act, and the rules and regulations of the Commission. C. There is reasonable assurance (i) 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 Comission's regulations; 1 D. The issuance of this amendment will not be inimical to the comon 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. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, by changing para-graph 2.C.(2) to Facility Operating License No. DPR-73, to read as follows: 2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No,16, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and all Commission Orders, issued subsequent to March 28, 1979, 8107090014 sto626 PDR ADOCK 0500o320 P

PDR,

4 1 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMISSION - --- Y -,A'^ ^ Bernard J. Snyder, gram Director Three Mile Island Program Office Office of Nuclear Reactor Regulation

Attachment:

Revised Technical Specifications Date of Issuance: June 26, 1981

' FACILITY OPERATING' LICENSE NO.'DPR-73 DOCKET NO. 50-320 Replace the following pages of Appendix "B" Technical Specifications with the enclosed pages as indicated. The revised pages contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to main-tain document completeness. Pages 2-1 2-3 2-6 2-7 2-9 2-10 3.2-3 5-7 5-7a (added) 4 I e i l

4 1 2-1 LamAstau cumuis(UN$ FOR~tfERAILLM ~ 2.0 McNIioRIN3 atguixtstnis 2.1 Radioactive Discharges 2.1.1 Liould Effluents Applicability Applies to the controlled release of radioactive liquids from TMI Unit Nos. 1 and 2. Objective Objective To define the limits and conditions To ensure that radioactive liquid for the controlled release of liquid releases from the facility are radioactive affluents to the environs within the limits of Specifications to ensure that these releases are as 2.1.1 a. througn f. I low as practicable. These releases saould not result in radiation exposures to off site areas greater than a few percent of background exposures. The instantaneous releases rate for all effluent discharges should be within the limits specified in 10 CFR Part 20. To assure that the releases of radioactive liquids to off site areas meet the "as low as practic-able" concept, the following oojectives apply: a. The annual total quantity of radioactive materials in liquid ~ waste, excluding tritium and dis-solved gases, should not exceed 5 curies per radioactive waste-producing reactor, and the annual dose to the whole body or any organ of an individual shall not exceed 4' 3 mrem to the total body and shall I be less than or equal to 10 mrem to any organ, b. The annual average concentration of radioactive materials in the i effluent from the Mechanical Draft l Cooling Towers prior to dilution in the Susqueharat Airer, excluding I tritium and dissolved gases, should not exceed 2 x 10-8 uC1/ml. l Amendment No. 16 l 0 e --,~,- -,. - - - _ -,, _ _ _ ._y 7 -4 --y- ,-3 ,--.1,v

I 2-2 LIJGUNG CCNDITION5 FOR CPERATICN 2.0 M)HITORING RECUIR&975 i Objective (Cont'd)

c. The annual average concentration of tritium in Itcuid wasta prior to dilution in the enviroment should not exceed 5 x 3-6 uC1/m1.

l Specification Soecification a. The radioactivity release During release of liquid radioactive concentration in liouid effluents wastes from the. Waste Evaporator from Unit Nos.1 and 2 to the. Condensate Storage tank and the enviroment shall not exceed the Waste Evaporator Condensate Test i values sper.ified in 10 CFR 20 Tank, the following conditions shell Appendix 3 for unrestricted areas. be met. b. The total release of radioactive A. The If ouid gro'ss activity liquid effluent from Unit Nos.1 and monitors (Unit 1: R!t-L6; Unit 2: 2, excluding tritium and noble gases. WOL-4-1311) or sinflar device, and shall not exceed 10 curies per recorder on the radweste effluent radioactive waste-producing reactor line shall be operable. during any calendar quarter. c. The equipment installed in the monitors (Unit 1: Rit-L6; Unit 2: \\ Ifquid radioactive waste system WDL-A-1311) or similar device shall shall be maintained and shall be be set to alarm and automatically operated to process all radioactive close waste discharge valve (Unit 1: liovid wastes prior to this discharge WDL-V-257; Unit 2: WOL-V-99) when the activity release rate will respectively prior to exceeding the exceed 1.25 curies per radioactive limits specified in 10 CFR 20, waste producing reactor, excluding Appendix B for unrestricted areas. trititse and dissolved gases, during any calendar quarter. C. Liould waste radioactivity and ~ flow rate from the waste evaporator d. The maximum radioactivity to be condensate storage tank (Unit 1) contained in one liquid radweste tank, 'd the waste eva orator condensate excluding tritium and dissolved gases, t tank (Unit 2) shall be that can be discharged directly, to continuously monitored and recorded l the environs, shall not exceed 10 during release. If this requirement curies. cannot be met, continued release of liould effluents sna11 be permitted e. When the average release rate of only during the succeeding 48 hours radioactive effluents, excluding provided that during this 48-hour tritium and dissolved gases, exceeds period two independent samples of 2.5 curies per radioact ve waste-each tank shall be analy:ed and two i producing reactor during any calendar station personnel shall independently quarter, the licensee shall notify the check valve line-up prior to the Mtc within 30 days, identifying the di scharge. 4 .m - - - - -.. - -m m. _-_--_.____---.-_,,n..-_,n.,,,, n,,__-- ,,,_.,,,,_n

2-3 LIMILING conUITIUM5 FOR UrtMATIUM Z.0 MONITURING REQUIR mtm43 Specification (Cont'd) Specification (Cont'd) causes and describing the proposed D. Facility records shall be pre ram of action to reduce such maintained of the radioactive release rates, concentrations and volume before dilution of each batch of liquid affluent released, and the average dilution flow and length of time over which each discharge occurred. Estimates of the error associated with each reported ytlue should be included in facilt+f records. E. Radioactive liquid waste sampling and activity analysis "For the purposes of this specifi-shall be perfomed in accordance with Table 2.3-1. Prior to the cation, the MPC, {I68 hour) for release of each batch of liquid Xe-133 is 5 x 10 pC1/ml. The (168 hour) for Xe-135 is effluent, a sangle shall be taken MPC,10-3pC1/m1". from that batch and analyzed for the 1x concentration of each significant gama emitter to demonstrate com-f. The dose or dose comitment from pliance with Specification "a" using liquid effluents shall be less than the flow into which the effluent or equal to 3 mrem total body and is discharged. less than or equal to 10 mrom to any organ for the calendar year. F. The Ifouid effluent radiation monitors RM-L6 and WDL P-1311 shall be calibrated at least quarterly by means of a known radioactive source. RM-L6 and WDL-R-1311 sna11 also have an instrument channel test monthly and a source eneck prior to each oischarge to verify that the read-out device is indicating as expected. G. The ability of WDL-V-257 and WDL-Y-99 to close automatically on receipt of a high radiation alarm signal from RM-L6 and WDL-R-1311 shall be checked annually. Bases Bases Liquid radioactive waste release Specifications A, B, and C, above levels to unrestricted areas should require that suitable equipment to be kept "as low as practicable" and monitor the release of radioactive are not to exceed the concentration materials in liquid effluents are limits specified in 10 CFR 20. The operating during any period these specifications provide reasonable releases are taking place. assurance that the resulting annual exposure to an individual in off The surveillance requirements given site areas will not exceed the design in the remaining specifications pro-objectives of Appendix ! to 10 CFR vide assurance that liquid wastes are Part 50, which were established as properly controlled and monitored reoutrements for the cleanup of during any planned release of radio. TMI-2 in the NRC's Statement of active materials in liquid effluents Policy of April 27, 1981. This assurance is based on the fact that the Susquehanna River will dilute the liquid effluents upon their release from Amenoment No.16 l 1

1 k 2-5 LIMITING CON 0l!;CN5 FCR CPERATICN 2.0 MONITCRING JECUIREME975 - Bases (Cont'd1 Bases (Cent'd) the site. The effluents will be di-These surveillance recuirenents cro-luted by a factor of about 250 in the, vide the data for the licensee and region where finfish can exist (with-the commission to evaluate the sta-in a one-quarter mile radius of the tion's :erformance relative to radio-discharge point). At the same time active licuid wastes released to the these specifications permit the flexi-environment. Reports en the cuantities bility of cperation, compatible with of radioactive materials released in considerations of health and safety, tJ If ouid ef fluents shall be furnished to assure that the public is providec a de-the Commission on the basis of Section pendable source of power. under unusual 5.6.1 of these Technical Scecifica-operating conditiens, which may tenoor-tion s. On *he basis of such reports arily result in higher than normal re-and any additional information obtained leases, but still within the concen-from the licensee er others, the Com-tration limis s:ecified in 10CFR 20. mission may recuire the licensee ta It is expected that by using this take appropriate action. operational flexibility under unusual operating ccnditions, and exerting every effort to keep levels of racio-active material in licuid wastes as low as practicable, the annual releases . will not exceed a small fraction of the annual average concentration Ifmits specified in 10CFR 20. Specification a. above recuires the licensee to ifmit the concentration of radioactive materials in licuid effluents from the station to lev-els specified in 10CFR 20, Appendix

8. for unrestricted areas. This specification provides assurance that no member of the ceneral pub-lic can be exposed to licuids con-taining radioactive materials in excess of limits considered per-missible under the ca9 mission's rules and regulations.

Specificatic 1 b. above estaD11shes an upper limit for the release of radioactive 11ould ef fluents, ex-l cluding tritiun and dissolved [ gases, of 10 curies ser unit dur-ing any calendar cuarter. The in-tent of this s:ecification is to permit the licensee the flexibili-ty of operatien to assure thet the puolic is provided a de:endaDie I source of power under unusual I coerating c:nditions, which may temporarily result in releases higher tnan tne levels normally ( i l I l m

26 LiMIilNb GUhDIIIGhh FOR GPERATION 2,0 MUNIIGRING REGUIREMthih Bases (Cont'd) Bases (Cont'd) achievable when the station and the liquid raswasta equipment are func-tiening as designed. Releases of up to 10 curies per radioactive waste-producing reactor during any calendar quarter will result in concentrations of radioactive materials in liquid effluents at small percentages of the limits specified in 10 CFR 20 Specification c. requires that the ~ licensee shall maintain and operate the equipment installed in the liquid radioactive waste system to reduce the release of radioactive materials in 11guld effluents to as low as prac-ticable, consistent with the require-ments of 10 CFR 50.36a. Normal use and maintenance of installed equip-ment in the 11guld radioactive system is expected to result in releases of not more than about five curies per radioactive waste-producing reactor per year, excluding tritium and dis-solved gases, during normal operations. In order to keep releases of radio-active materials as low as practicable, the specification requires, as a minimum, operation of equipment wnenever the rate of release exceeds 1.25 curies per radioactive waste-producing reactor per quarter, excluding tritium and dis-solved

• gases.

In addition to the limiting conditions for operation listed under Specification b., the reporting requirements of Speci-fication e., 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 per radioactive waste-producing reactor during any calendar quarter and describe the proposed program of action to reduce such release rates. This report must be filed within 30 days following the calender quarter in which the 2.5 curies release occurred. Specification f. requires that the dose to offsite personnel be limited to the design objectives of Appendix ! of 10 CFR Part 50. This will assure 'he dose received by the public durir, the cleanup is equivalent to or less ;han that from'a normal operating rewtor. The limits also assure that the environ-mental impacts are consistant with those assessed in the PEIS. Amenement No.16

2-7 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENT 5 2.1.2 Gaseous Effluents Applicability _ Applies to the controlled release of radioactive gases from TMI Unit i Nos. I and 2. Objective Objective To define the limits and conditions To ensure that radioactive gaseous 13r the controlled release of radio-releases from the facility are active gaseous effluants to the environs within the limits of specifications, to ensure that these releases are as low as practicable. These releases sb.ould not result in radiation exposures in offsite areas greater than a few per. cent of background exposures. The instantaneous release rate for all effluent discharges should be within the limits specified in 10 CFR 20 To assure that the release of radio-active gases to offsite areas meet the as low as practicable concept, the following objectives apply: a. The release rate of gaseous effluents shall not result in doses to the public exceeding the design . objectives of App.endix I to 10 CFR Part 50 Specification Specification a. The instantaneous release rate of During release of radioactive gaseous gross gaseous activity except for halo-wastes, the following cei:ditions gens and particulates with half-lives shall be met: longer than eight days shall not ex-ceed: A. During release of gaseous waste from the waste gas decay tanks, the Qi 3 following conditions shall be met: 5 f 1.5 x 10 (MPC)j ec Amendment No. f$, 16 l l I = -*

2-8 LIMITING CONDITION 5 FOR OPERATION 2.0 MONITORING REQUIREMENT 5 Specification (Cont'd) Specification (Cont'1) where 01 is the release rate in 1. Waste gas discharge monitor (Unit 1: RM-A7; Unit 2: WDG-R-1480) uCi/seg)~for isotope i, and MPCj (uC1/mJ is the maximum permis-or similar device, shall be operable, sible concentration of isotope and defined in Appendix B, Table 2. Auxiliary and Fuel Handling II, Column 1. 10CFR 20. Building and Unit Exhaust Vent exhaust gas, iodine and particulate monitor b. The instantaneous release (Unit 1: RM-A8; Unit 2: HP-R-219)or rate of particulates with half-similar device, shall be operable. lives greater than eight days, released to the environs as 3. The waste gas decay tank discharge part of airborne effluents, valves (Unit 1: WDG-V47; Unit 2: WDG-shall not exceed 0.3 uCi/sec. V-30A or 308) shall be operable. c. The release rate of gross 4. The waste gas decay tank discharge gaseous activity shall not ex-valves (Unit 1: WDG-V47; Unit 2: WDG-Vc ceed: 30A or 30B) shall be closed on receipt of any one of the following conditions: 4 *3 Qi f 2.4 x 10 A @ MW @ % W {IMNi waste gas discharge monitor (Unit 1: RM-A7; Unit 2: WDG-R-1480). when averaged over any calendar

quarter, b.

A high radiation signal from the Auxiliary and Fuel Building exhaust d. The release rate of particolates monitor (Unit 1: RM-A8; Unit 2: HP-with half-lives greater than eight R-219). days, shall not exceed: 0.024 uCi/ sec., when averaged over any calen-c. A high flow signal from the Waste dar quarter. Gas Decay Tank discharge flow trans-mitter (Unit 1: FT-123; Unit 2: WDG-e. Radioactive gaseous wastes FT-3923). collected in the gas decay tanks shall be held up to a minimum of d. Observation of loss of flow 45 days, except when the release through the Unit vent. I rate shall not exceed: B. During purge of the Reactor 3 3m Building, the following conditions }Qi 5 3 x 10 shall be met: sec 1, (noble gases) 1. The Reactor Building Purge Exhaust Monitor (Unit 1: RM-A9; Unit 2: HP-R-0" 225 and/or HP-R-226 and HP-R-219) or similar device shall be operable. 2. 0.003 uCi/sec (particulates l with half-lives 2. The Purge Exhaust Valves (Unit greater than AH-VIA and AH-VIB and Dampers; l 8 days) Unit 2: D5129A/DandD5129B/C) shall be operable. I i I Amendment No. 15 t

2-9 LIMITING CONDITION 5 FOR OPERATION Z,J MONITORING REUVIREMENI5 Specification (Cont'd) Specification (Cont'd) f. Radioactive gas and particulates 3. The valves (Unit 1: AH VIA and purged from the reactor building shall AH-V1B and Dampers; Unit 2: 05129 be filtered through the high efficiency A/D and 05129 S/C) shall be inter-particulate air filters. locked to close or recirculate, respectively on receipt of a high l 9. The maximum activity to be con-radiatien signal from the Reacter tained in one gas decay tank shall not Building Exhaust Monitor (Unit 1: exceed 8800 curies (equivalent to RM-A9; Unit 2: HP-R-225 and HP-R-Xe-133). 226) respectively. h. When the release rate of radio-C. The flow rate for radioactive active materials in gaseous wastes, effluent streams and the Auxiliary averaged over a calendar quarter and Fuel Handling Building and the

exceecs, Reactor Building, shall be monitored 3

and recorded. Gaseous effluents }Q g 6 x 10 E the Reactor Building Purge i.xhaust + 3m from the Waste Gas Decay Tanks and i shall be continuously monithred and (noble gas) recorded. or D. Radioactive gaseous waste samling 0.006 uC1/sec (particulates with and activity analysis shall be rar-half-lives greater fomed in accordance with Table 2.3-2. than 8 days) E. The waste gas decay tank effluent the licensee s all notify the NRC with-monitor (Unit 1: RM-A7; Unit 2: iiDG-R-in 30 days, idestifying the causes and 1480) shall be tested using the in-describing the pr. 90 sed program of ac-stalled check source or eouivalent tion to reduce suc release rates, prior to any releasa of radioactive gas from a holcup tank and snall be 1 The air dose due to noble gases in calibrated cuarterly using a re-gaseous effluents sna11 be less than ferenced calibration source in a or ecual to 10 mrad for gantna radiation controlled reproducible geometry. and less than or equal to 20 mrad for beta radiation for the calendar. year. F. During power operation, tne con-densor vacuum pump discharge shall be

j. The dose for radionuclides (other continuously monitored for gross than noble gaseous effluents shall be gaseous activity. The monitor shall less than or equal to 15 mrem to any not be inoperable for more than a organ for the calendar year, week. Whenever this monitor is in-operable, a grab sample shall be taken daily and analyzed for gross radioactivity. ( f,y ).

G. Facility records shall be main-tained of raoicactive concentration, release ratio and volume of each batch of gaseous effluents released. I Amendment No. 25,16

2-10 LIMIiiNG CONDITION 5 FOR OPERATION 2Y MGhliORING REQUIsttMtNih Specification (Cont'd) and the length of time over wnich release occurred. Estimates of the error associated with each reported value should be included in facility records. H. At least annually, automatic initiation and closure of the Waste Gas Decay Tank Discharge valve on alarm of (Unit 1: RM-A7 and RM-A8; Unit 2: WDG-R-1480) shall be verified. I. The Auxiliary and Fuel Handling Butiding and Reactor Building Purge Exhaust gas monitors for TMI-1 (RM-A8 and RM-A9) and the Unit Vent monitors for TMI-2 (HP-R-219, HP-R-225, and HP-R-226), respectively, shall be calibrated at least every eighteen months by means of a known radioactive source. These detectors shall have an instrument channel test at least monthly, and a sensor check at least daily, to verify that the read-out device is indicating as expected. Basa Bases 1 The specified levels provide rea-Specifications A. through I., aoove, sonable assurance that the resulting require that suitable equipment to annual exposure rate from noble monitor the radioactive gaseous gases at any location at the site releases are operating during any boundary will not exceed 10 millirems period these releases are taking per year. At the same time, these place. specifications permit the flexibility of operation, compatible with can. The surveillance requirements given sideration of health and safety, to under the remaining Specifications assure that the public is provided a above, provide assurance that dependable source of power under un. radioactive gaseous effluents from usual operating conditions, which may 2e stat %n are properly controlled temporarily result in higher than the and monito..

• over the life of the design objective levels, but still station. These surveillance within the concentration limits requirements provide the data for specified 10 CFR 20 and within the the licensee and the Consnission to design objectives of Appendix I to evaluate the station's performance 10 CFR 50 It is expected that relative to radioactive gaseous using this operational flexibility wastes released to the environment, under unusual operating conditions, and by exerting every effort to keen Reports on the quantities of radio-levels of radioactive material in active materials released in gaseous gaseous wastes as low as practicable, effluents shall be furnished to the the annual releases will not exceed Commission on the basis of Section a small fraction of the annual con-centration limits specified in 10.CFR 20 and will not result in doses which exceed the fesign objectives of Acpendix I to 10 CFR 50, which were endorsed as limits for the cleanup of TNI-2 by the NRC's Statement of Policy of April 27, 1981.

Amendment No. 16

3.2-3 exceeds the reporting level given in Table 4, a written report skall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 30 days from the end of the quarter. If it can be demonstrated that the level is not a result of plant effluents (e.g., by comparison with control station or preoperational data) a report need not be submitted, but shall be dis-cussed in the annual report. When more than one of the radionuclides in Table 4 are decected in the medium, the reporting level shall have been exceeded if: concentration (2) concentration (1) + + ,, 3 i reporting level (1) reporting level (2) If radionuclides other than those in Table 3.2-4 are detected and are due from plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR Part 50, Appendix I. This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result. c. R3diological Releases and Estimated Dose Report. The following information shall be submitted to the Director of the Regional Of fice. This information shall be submitted on a calendar quarter basis (January-March, April-June, July -September, and October-December) and shall be submitted no later than 30 days following the end of each calendar quarter. (a) Estimates of the amounts and types of radioactivity that were released to the environment during the quarter and during the calendar year. This shall include estimates of the total activity of each nuclide and the time rate of release of each nuclide. (b) Estimates of populations and maximum individual cases which occurred during the calendar quarter and during the calendar year shall be provided. The estimates shall te based on actual hydrological and meteorological conditions which occurred during the releases. Calcu-lational methods shall be those of U.S. NRC Regulatory Guides 1.109 / Revision 1, October 1977), 1.111 (Revision 1, July 1977), 1.112 { Revision 0-R, April 1976)and1.113(Revision 1, April 1977). These calculations shall be based on estimates of actual population dis.tri-butions during the releases and shall take into consideration factors such as boating or fishing recreation. Amendment No. 16 3 ~

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clGURE 3.2-1 THREE MILE !$L/,MO WC' ElR 57174CN l Location of Coerational cladiological E.evironmental Monitoring itations eithin 5 Miles of tne site l

5-7 e. station operation on the environment. If harmful effects or evidence of irreversible damage are suggested by the monitoring or special programs, the licensee shall provide a more detailed analysis of the data and a proposed course of action to alleviate the problem. The Annual Report shall also include a summary of:

1) All ETS noncompliances and the corrective actions taken to remedy them.

2) Changes made to state and federal permits and certificates. 3) Changes made to the Environmental Program Description Document. 4) Changes in station design which could involve an environmental impact or change the findings of the FSFES.

5) All nonroutine reports submitted per ETS Section 4.6.

6) Changes in ETS. B. Data Reporting Formats Results of analysis of all nonradiological environmental data collected shall be summarized and tabulated on an 2nual basis. In the event that some results are not available by May 1, the report shall be submitted noting and explaining the missing results. The missing data shall be submitted as soon as possible in a supplementary report. C. Quarterly Radiological Releases and Estimated Dose Report _. A quarterly report shall be submitted to the Director of the Regional Office. This report shall be submitted no later than 30 days following the end of each calendar quarter. The report shall include estimates of the amounts and types of radioactivity released each quarter including the time release rate and total activity of each nuclide. Also include estimates of populations and maximum individual doses which occurred j during the quarter and during the calendar year shall be provided. The estimates shall be based on actual hydrological and meteorological con-ditions which occurred during the releases. Calculational methods shall be those of U. S. NRC Regulatory Guides 1.109 (Revision 1, October 1977), 1.111 (Revision 1 July 1977),1.112 (Revision 0-R, April 1976) and 1.113 (Revision 1, April 1977). These calculations shall be based on estimates of actual population distributions during the release and shall take into consideration factors such as boating or fishing recreation. I 5.6.2 Nonroutine Reports A report shall be submitted in the event that a " Limiting Condition for Operation" (Section 2), if applicable, is exceeded, a report level as specified in Section 3, " Environmental Monitoring," is reached or if an I " Exceptional Occurrence" as specified in Section 4.6 occurs. Reports shall be submitted under one of the report schedules described below. Amendment No. 16 L

) 5-7a 5.6.2.a Prompt Report Those events specified as prompt report occurrences shall be reported within 24 hours by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days. 5.6.2.b ' Thirty ~ Day Report Non-routine events not requiring a prompt ~ resort as described in Subsection 5.6.2.a, shall be reported to NRC either wit1in 30 days of their occurrence or within the time limit specified by the reporting requirement of the cor-responding certification or permit issued pursuant to Sections 401 or 402 of PL 92-500, whichever time duration following the non-routine event shall result in the earlier submittal. Amendment No. 16

( 5-8 ,5.6.2.c Content of Nonroutine Reports -Wsitten 30-day reports and, to the extent possible, the premliminary -telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.

5. 7 Changes in Environmental Technical Soecifications and Permits 5.7.1 chance in Environmental Tecnnical Saecifications Request for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 CFR 50.90.

The request shall include an evaluation of the environmental impact of the proposed change and a supporting justification. Implementation of such requested changes in ETS shall not commence prior to incorporation by the NBC of the new specifications in the license. 5.7.2 Changes in Permit and Certifications Changes or additions to required Federal, State, local, and regional. (' authority permits and certificates for the protection of the environment ~ that pertain to the requirements of these ETS shall be reported to the NRC wi' hin 30 days. In the event that tne licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits or values stipulated in any certification or permit issued pursuant to Section 401 or 402 of PL 92-500 which is also the subject of an ETS reporting requirement, NRC shall be notified concurrently with the authorizing agency. The notification to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought. If, during NRC's review of the proposed change, it is determined that a potentially severe environmental impact could result frem the change, the NRC will consult with the authorizing agency to determine the appropriate action to be taken. 5.8 Records Retention Records and logs relative to the following areas shall be made and retained througnout the term of the operating license. These records and logs shall be made available to NRC on request, a. Records and drawing changes detailing station and unit design changes made to systems and equipment which could potentially affect the environment. ( 0 4.m- ,r ,y 7 ,-,v .w, ,,4.m_.,m,~,,my.,,,, om.-,,,-,,--. --e,.,.--v- -, _.,}}