ML20066B544

Radiological ETS & Environ Protection Plan for Amend 58 to License DPR-72

ML20066B544
Person / Time
Site:	Crystal River
Issue date:	10/12/1982
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20066B543	List: ML20066B541 ML20066B544 ML20066B547
References
TAC-48066, NUDOCS 8211080102
Download: ML20066B544 (44)

Text

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APPENDIX B PART I

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FACILITY OPERATING LICENSE NO. DPR-72 CYRSTAL RIVER UNIT,

FLORIDA POWER CORPORATION

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DOCKET NO. '50-302 RADIOLOGICAL ENVIRONMENTAL TECHNICAL SPECIFICATIONS l

1 Amendment No. 58 8211080102 821012

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I TABLE OF CONTENTS Page No.

1.0 DEFINITIONS 1.1 Frequency 1-1 1.2 Gross (3,y) Analysis 1-1 1.3 Deleted 1-1 1.4 Deleted 1-1 1.5 Unit 3 Mixing zone 1-1 1.6 Delet ed 1-1 1.7 Deleted 1-1 1.8 Known Radioactive Source 1-3 1.9 Deleted ~

1-3 1.10 Deleted 1-3 1.11 Deleted 1-3 1.12 Deleted 1-3 1.13 Channel Calibration 1-3 1.14 Channel Checx 1-3 1.15 Channel Functional Test 1-3 1.16 Dose Equivalent I-131 1-3 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Deleted 2-1 2.2 Deleted 2-3 2.3 Deleted 2-3

'.3.1 Deleted 2-3 2

2.3.2 Deleted 2-4 2.4 Radioactive Effluents 2-4 2.4.1 Liquid Waste Effluents 2-5 2.4.2 Gaseous Waste Effluents 2-9 2.4.3 Solid Waste Handling and Disposal 2-16 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Deleted

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3.1.1 Deleted 3-3 3.1.2 Deleted 4 3.1.3 Deleted 3-4 1

1 1.4 Deleted 3-5 3.1.5 Deleted 3-6 3.2 Radiological Environmental Monitoring 3.2.1 Milk and Green Leafy Vegetables Census 3-26 3.2.2 Media Other Than Ey.ternal Radiation 3-27 3-27 3.2.3 External Radiation 3.2.4 Milk and Green Leafy Vegetables 3-27 4.0 Deleted-4-1 4.1 Deleted 4-2 4.2 Deleted 4-2 4.3 Deleted 5.0 ADMINISTRATIVE CONTROLS 5-1 5.1 Organization 5-1 5.2 Responsibility 5-3 5.3 Review and Audit 5.4 Action to Be Taken if Limitino Condition for Operation is Excebded

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5-5 5-5 5.5 Procedures 5-6 5.6 Plant Reporting Requirements 5-6 5.6.1 Routine Reports 5-8 5.6.2 Non-routine Reports 5-11 5.6.3 Changes 5-11 5.7 Records Retention 5-11 5.8 Deleted Amendment No..#f, 58

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2.4-1 Radioactive Liquid Sampling and Analysis 2-17 2.4-2 Radioactive Gaseous Waste Sampling and Analysis Frequency 2-19 2.4-3 PWR-Liquid Waste System:

Location of Process and Effluent Monitors and Samples Required by Technical Specifications 2-21 2.? a PWR-Gaseous Waste System:

Location of Process and Effluent Monitors and Samples

.equired by Technical Specifications 2-22 i

'2.1-5 Gamda and Seta Dose Factors for Crystal River Unit 3 2-23 3.2-1 Summary of 'Preoperational Environmental Surveillance Results 1971-1974 3 ~9 3.2-2 General Pathway Radiological Environmental Monitoring Program 3-15 3.2-3 Critical Pathway Radiological Environmental 3 Monitori,ng Program 3.2-4 Operational Sample Station Locations 3-19 1

i 3.2-5A Detection Capabilities for Environmental Sample Analysis 3-21 3.2-5B Detection Capabilities for Environmental Sample Analysis 3-22 i

Environmental Radiological 2nitoring P'rogram Sumary 5 5.6-1 1

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1.1-1 Deleted 1-2 1.1-2 Deleted 1-4 3-7 3.1-1 Deleted 3.2-1 Environmental Media and Exposure Pathways 3-23 3.2-2 Offsite Operational Radiological Program Sampling Sites 3-24 3.2-3 Onsite Operational Radiological Program Sampling Sites 3.-25 5.1 1 Organization for Implementing and Independent Review and Audit of Radiological Environmental Technical Specifications 5-2 5.3-1 Deleted 5-4 5-12 5.3-1 Deleted Amendment No. y 58

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1-1 1.0 Definitions The following terms are defined for unifonn interpretation of the Radiological Environmental Technical Specificat. ions for Crystal Ri'ver

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Unit 3.

1.1 Frecuency - Terms used to specify frequency are defined as follows:

One per shift - At least.once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

J Daily. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Weekly - At least once per 7 days.

Monthly - At least once per 31 days.

Quarterly - At least once per 92 days.

Semiannually - At least once per 5 months.

A maxi =um' allowable extension for each surveillance requirement shall not exceed 25" of the surveillance interval.

1.2

. Gross (2,Y) Analysis

- Radioactivity measurements of' gross beta or gross oeta in con,) unction with gross gamma as defined in Regulatory Guide 1.21.

1.3 Deleted 0

1.4 Deleted I

1.5 Unit 3 Mixing Zone - The enclosed area of the discharge canal bounded by the eastern end of the canal and the cable chase from Units 1 and 2 by crossing the canal.

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1-3 1.8 Known Radioactive Source - A calibration source which is traceable to the National Bureau of Standards radiation measurement system and is capable of reproducible geometry.

I 1.9 Deleted 1.10 Deleted 1.11 Deleted 1.12 Deleted 1.13 Channel "clibration - The adjustment, as necessary, of the channel output sucn that it responds with necessary range ano accuracy to known values of the parameter which the channel monitors.

The channel calibration shall encompass the entire channel includi.ng the sensor and alarm and/or trip functions, and shall include the channel func-tional test. Channel calibration nay be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

1.14 Channel Check - The qualitative assessment of channel behavior during operation by observat' ion.

This detennination shall include, where possible, comp *arisch 'of' the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

1.15 Channel Functional Test - The injection of a simulated signal into the channel as close to the primary sensor as practicable to verify opera.

bility including alarm and/or trip functions.

1.16 Ocse Ecuivalent I-131 - That concentration of I-131 (uCi/ gram) which alone would procuce the same thryoid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall' be those listed in TID-14844.

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4 2.4 RADI0 ACTIVE EFFLUENTS Objective: To define the limits and conditions for the controlled release of radioactive materials in liquid and gaseous effluents to t

the environs to ensure that these releases are as low as reasonably achievable.

These releases should not result in radiation exposures in unrestricted areas greater than a few percent of natural background exposures.

The concentration of effluent disonarges of racioactiv-ities shall be within the limits specifiec in 10 CFR Part 20.

To ensure that the releases of radioactive material above background to unrestricted areas be.as low as reasonably achievable, the follow-ing design objectives apply:

For liquid wastes:

A.

The annual dose above background to the total body or any organ of an individual from all reactors at a site should not exceed 5 mrem in an unrestritted area.

B.

The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, discharged from each reactor should not exceed 5 C1.

For gaseous waste:

C.

The annual total quantity of noble gases above background dis-charged from the site should result in an air dose due to gamma radiation of le.ss than 10 mrad, and air dose due to beta radiation of less than 20 mrad, at any location near ground level which could be occupied by individuals at or beyond the boundary of the site.

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The annual total quantity of radiofodines and radioactive

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3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING Objective The radiological environmental monitoring program will provide informa-tion which can be used to assist in assessing the type and quantity of radiation exposure in unrestricted areas resulting from plant operation.

Backorcund

,P.reoperaticnal cadiological environmental monitoring programs, to establish baseline environmental concentration values, were initiated in mid-1970.

One program was operated by the State of Florida Department of Health and Rehabilitative Services; another program was operated by the University of Florida.

A summary of the preoperational surveillance results is shown in Table 3.2-1.

This summary includes median values of the observed environmental concentrations and 95 percentile values (i.e., values which exceed 95 percent of all the comparable measured values).

These values will be taken as the preoperational baseline concentrations.

In some cases the values listed are smaller than the Lower Limit of Detection (LLD).

The 95 percentile values indicate the random frequency of high measured values during the operation of the plant contributes negligibly to

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the environmental radioactivity.

These 95 percentile values will be used during operation to assess the probability that any observed high concentration value is due to random fluctuations fn measurements rather than to a true increase in environmental. concentrations.

Soecification (Procram)

Environmental media which are sampled and analyzed for radicactivity are shown by the two diagrams on Figure 3.2-1.

Each box in the dia-grams contains the name of an environmental media which is sampled.

The upper diagram shows the critical pathways; the lower diagram shows.

the other monitored pathways.

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22 3-8 The operational radiological monitoring program shall consist of a continuation of the preoperational program of measurements of radio-activity in environmental media which is outlined in Table 3.2-2.

The critical pathway monitoring program which' is included in Table 3.2-2 is also shown in Table 3.2-3.

Sample station locations are described on Table 3.2-4 and shown on maps on Figures 3.2-2 and 3.2-3.

Lower Limit of Detection (LLD) values are given on Tables 3.2-5A and 3. 2-5 B.

Deviations are permitted from the required sampling schedule if speci-mens are unobtainable due to hazardous conditions, vandalism, seasonal If unavailability or to malfunction of automatic sampling equipment.

the latter, every effort shall be made to complete corrective action All deviations from prior to the end of the next sampling period.

the sampling schedule shall be described in the annual report.

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5.0 ADMINISTRATIVE CONTROLS Objective To define the organization, assign responsibilities, describe the environmental surveillance procedures, provide for a review and audit function, and prescribe the reporting requirements in order to insure continuing protection of the environment and implement the Environmental Technical Specifications.

5.1 ORGANIZATION The organization responsible for radiological environmental pro-j taction, radiological environmental monitoring and the implementa-tion of the Radiological Environmental Technical Specifications for Crystal River Unit 3, is shown on Figure 5.1-1.

l 5.2 RESPONSIBILITY I

The responsibility for the conduct of the operational radiological environmental monitoring program described in Section 3 is that of the Nuclear Support Services Department under the direction of the Vice President, Nuclear Operations.

The plant organization is responsible for 'the development of Oper-ating and Surveillance Procedures described generally in Section 5.5.and supplying field data to the Manager, Nuclear Supoort Sar-vices as required by Sections 2 and 3 of the Radiological Environ-mental Techn,cial S pcifications.

The Manager, Nuclear Support Services is responsible for consul-tant contracts, State and local regulatory agreements, assembly of data, preparation and review of reports required by Section 5.6 of these Radiological Environmental Technical Specifications, and L

making recomendations to improve radiological environmental pro-i:

tection practices.

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FIGURE 5.1-1 ORGANIZATION FOR IMPLEMENTING AND INDEPENDENT REVIEW AND AUDIT OF RADIOLOGICAL ENVIRONMENTAL TECHNICAL SPECIFICATIONS Amendment No..,25',58 l

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5.3 REVIEW AND AUDIT l

l 5.3.1 Function The Nuclear General Review Committee shall function to provide independent review and audit of designated activities in the areas of radiological environmental monitoring and surveillance.

5.3.2 Comoo'sition 1

1 The NGRC shall be composed as described in the Crystal River Unit f

3 Technical Specifications, Appendix A, Section 6.5.2.2.

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The Nuclear General Review Comittee members' qualifications shall be as described in the Crystal River Unit 3 Technical Specifica-tions, Appendix A, Section 6.5.2.3.

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4.3.4 Alternates All alternate member's shall be appointed in accordance with the j

Crystal River Unit 3 Technical Specifications, Appendix A, Section 6.5. 2. 4.

5.3.5 Consultants Consultants shall be utilized as provided in the Crystal River Unit 3 Technical Specifications, Appendix A, Section 6.5.2.5.

i 5.3.5 Meeting Frecuency The NGRC shall meet as required by the Crystal River Unit 3 Tech-nical Specifications, Appendix A, Section 6.5.2.6.

i 5.3.7 Ouorum A quorum of NGRC snail be as designated in the Crystal Rive'r Unit 3. Technical Specifications, Appendix A, Section 6.5.2.7.

5.3.8 Review s

The.NGRC shall review':

a. Proposed changes to the Radiological E'nvironmental Technical Specifications and the evaluated impact of the changes.

b.' Proposed changes or modifications to plant systems or equipment and the evaluated impact which would require a change in the procedures described in 5.5.1 below (or which would affect the evaluation of the plant's radiological environmental impact) as determined by the Plant Review Connittee.

c. Reported instances of violations of Radiological Environmental Technical Specifications, the reaching of specified reporting a

levels, and reportable radiological environmental occu'rrences.

d. Proposed special tests or experiments which might involve a change in the Radiological Environmental Technical Specifica-tions or involve an unreviewed increase in radiological <

l ef fluents.

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e. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commiss' ion.

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f. Descriptions of changes, tests or experiments, and the results thereof, as described in 5.5.3.a.

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Audits of the radiological environmental monitoring and sur-veillance program.

5.3.9 Audits Audits of facility activities shall be performed under the cognizance of the NGRC.

These audits shall encompass:

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Implementation of the rad'iological environmental monitoring a.

and surveillance programs at least once per twelve months.

b.

Conformance to procedures and RETS requirements at least once per twelve months.

Contractor radiological environmental monitoring and sur-c.

veillance activities at least once per twelve months.

5.3.10 Records Records of NGRC activities shall te pre' pared, approved anc

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distributed as indicated below:

Minutes of each'NGRC meeting shall be prepared, approved a.

and forwarded to the Senior Vice President Engineering and Construction within 14 days follmving each meeting.

Reports of reviews encompassed by Section 5.3.8 above, shall b.,

be prepared, approved and forwarded to the Senior Vica President Engineering an'd Construction within 14 days fol-lowing the completion of the review.

Audit reports encompassed by Section 5.3.9 above, shall be c.

forwarded to the Senior Vice President Engineering and Con-struction and to the management positions responsible for the areas audited within 30 days" after completion of the audit.

5.3.11-Authority The NGRC shall report to and-advise the Senior Vice President -

Engineering and Construction on those areas of responsibility specified in Sections 5.3.8, 'S.3.9 and 5.3'.10 (see Figure 5.1-1). j 2

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i 5-5 5.4 ACTION TO BE TAKEN IF LIMITING CONDITION FOR OPERATION IS -

EXCttDED.

l 5.4.1 Immediate remedial adtions as permitted by these Radiological 1

Environmental Technical Specifications shall be implemented until such time as the lief ting condition for operation is met.

3 5. 4.'2 The occurrence shall be iromptly reported to the Chairman of, the Nuclear General' Review Comittee and investigated as specified in Sect, ion 5.3.

5.4.3-The Nuclear General Review Comittee shall prepare and submit a report for each occurrence in accordance with Section 5.3.10.

5.4.4 The Vice President, Nuclear Operations, or his designee, shall report the occurrence to the NRC as specified in Section 5.6.2.

5.5 PROCEDURES f

5.5.1 Explicit written procedures, including applicable check-off lists and instructions, saall be prepared for the im'plementation of the monitor'ing requirements described in Sections 2 and 3, approved as specified in Section 5.5.2, and adhered to for operation of all systems and components involved in carrying out the effluent release and environmental radiological monitoring programs.

Pro-1 l

cedures shall include sampling, instrument calibration, analysis, and action to be taken when. limits are approached or exceeded.

Calibration frequencies and standards for instruments used in per-forming the measurements shall be included. Testing frequency of c.

alarcts shall be included.

These freqCencies shall be determined from experience with.similar instruments in similar environments and from manufacturers' tecnnical mansls.

i 5.5.2 Each procedure in 5.5.1 above, and changes tha.eto,< shall be reviewed and approved prior to implementation -ss foilows:

a.

Except as noted in b:

c 1.

All procec'ures and changes thereto shall be subjected to f

a. review by aMualified Reviewer within the responsible o

dapartment,' iaterdisciplinary' review by Qualified Rriviewers wf thin interf acing departments as speci.fied in Administrative procedures, and the responsible s6perin-tendent or Plant Mansger as specified in Administrative P rocedures.

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The training and qualification of reviewers shall be governed by Administrative Procedures with final certification by the Nuclear Plant Manager. Recertification will be required on a periodic basis and upon transfer between departments. As a

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minimum, all Qualified Reviewers shall. meet the requirements of ANSI N18.1-1971 Section 4.2, 4.4, or 4.6, or the equivalent.

3.

All precedure revision records, including the reviews required by 10 CFR 50.59, shall be reviewed by the Plant Review Comittee within 14 days, and forwarded to the Nuclear General Review Comittee.

b.

Temporary changes may be made to procedures required by Section 5.5.1 providedt.

1.

The intent of the original procedure is not altered.

2.

The change is approved by two members of the plant management staff, at least one of which holds a Senior Reactor Operators (SR0) License.

i 3.

The change is documented and reviewed per 5.5.2.a.3, above.

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l 5.5.3 Special Tests or Changes:

The licensee may make changes in station design or operation or perform tests or experiments provided such changes, tests or experiments do not involve an unevaluated radiological impact

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question or involve a. change in these Radiological Environmental Technical Specifications.

l Any change in station design or operation or test or experiment which could involve an unevaluated radiological impact question or involve a change in these Radiological Environmental Technical Specifications shall be submitted to the Nuclear General Review Comittee for review and report to the Vice President, Nuclear l

Operations for resolution prior to implementation.

5.6 PLANT REPORTING REQUIREMENTS i

5.6.1 Routine Reports l

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Radiological Volume i

A report on the radiological environmental surveillance j

programs for the previous 12 months of operatica shall be submitted to the Director of Inspection and Enforce-i ment (with cooy to Director Office of Nuclear Reactor d

Regulation) -by April 1, eacn year. The report shall include sumaries, interpretations, and statistical evaluation of the results of the radiological environ-mental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate) and previous envircnmental surveillance reports, and an assessment of the observed hnpacts of the plant. operation on the environment.

If harmful effects or evidence of irreversible damage are detected'by the monitoring, the licensee shall provide an analysis of the problem and a.

proposed course of action to alleviate the problem. '

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shall oe summarized on an annual basis following the Results of all radiological environmental samples taken I

I format of Table 5.5-1.

In the event that some results are not available by April 1, the report.shall be sub-mitted, noting and explaining the reasons for the miss-ing results.

The missing data shall be submitted as soon as possible in a supplementary report.

I B.

Semiannual Operating Reoort - Radioactive Effluents 1

A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted l

to the Director of the Office of Inspection and Enforcement (with a copy to Director, Office of Nuclear Reactor Regula-tion) as part of the Semiannual Operating Report by March 1 and September 1 each year.

The report shall include a sum-mary of the quantities of radioactive liquid and gasecus effluents and solic waste released from the plant as outlined in USNRC Regulatory Guide 1.21, with data summa'rized. on a y

quarterly basis folicwing the format of Appendix 3 thereof.

I Any unplanned releases of radioactive material from the site will be reported in accordance with Appendix B Section A.6,

" Abnormal Release" of Regulatory Guide 1.21, with the cause of each release identified.

The report shall include a summary of the meterological con-ditions concurrent with the release of gaseous effluents during each quarter as outlined 'in USNRC Regulatory Guide 1.21, witn data summacized on a quarterly basis following the format of Appendis S_thereof.

Calculated offsite dose to humans resulting from the release of effluents and their sub-sequent dispersion in the atmosphere (Regulatory Guide 1.109) shall be reported in accordance with Regulatory Guide 1.21.

5.6.2 Non-Routine Reoorts A.

Limitino Condition for Oceration Exceeded In the event that:

(1) a limiting condition for operation is exceeded, (2) an unplanned release of radioactive material from the site occurs in quantities such that the release rate is greater than 10% of the allowed instantaneous release rate specified in 2.4.1A or 2.4.2A or (3) an event involving a significant adverse radiological environmental impact occurs, a report will be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and tele-graph to the Director of the Office of Inspection ana Enforca-ment followed by a written report with a copy to the Director, Office of Nuclear Reactor Regulation within 15 days.

The telegraph report will quantify the occurrence, its causes and, if aspects of the Crystal River Unit 3 operation are among the Amendnent No.,}6',58

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The written report will fully describe the occurrence and will describe. its causes and corrective action as fully as 4

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k' TABLE 5.6-1 t-ENVIRONMENTAL RADIOLOGICAL MONITORING PRC 3 RAM

SUMMARY

i Nameof Facility Docket No.

f Location of Facility Reporting Period f'-

L (County, State) j

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f Type end Lower Lirnit Nun ber of Locetion with Hiehest Annual Mean l

Medium or Pathway '

Total Number of All Indicator Lgcations Control Loca,tlons Nontout6ne l

Sampled of Analyses Detection" Meanif Name go n (gn Mean (if Reported b

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(Unit of Measurement)

Perforrned (LLD)

Range

. Distence and Direction Range Range Measurements

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Air Particulates (pCi/m )

Gross # 416 0.003

. 0.08 (200/312)

Middletown 0.10 (5/52) 0.08 (8/104) 1 Iy 3

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- (0.05-2.0) 5 miles 340' (0.08-2.0)

(0.05-1.40)

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7-Spec. 32 h

137Cs 0.003 0.05 (4/24)

Smithville 0.08(2/4)

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Podunk 0.05(2/4) 0.02 (1/8) 1 E

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Mean and range based upon detectable. _ _...,.ts only. Fraction of detectable measurements at specified locatione le Indicated in perentheses. ifl i

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Radiological Reoorting Levels In the event a report level specified below is reached, a report shall be made within the designed time period to the Director of Inspection and Enforcement with a copy to the Director of Office of Nuclear Reactor Regulation.

(I) Radioactive Discharge i

l If.neasured rates of release of radioactivity in the environment, averaged over a calendar quarter, exceed the design objective rates as specified in specifica-tions 2.4.1.H for liquid effluents and in 2.4.2.C for airborne effluents, a report of the causes of the release rates and of a proposed progran of action to reduce the release rates will be submitted within 30 l

days from the end of the quarter during which the celease. occurred.

(2) Radiological Environmental Monitoring If a single measured value of radioacivity concentra-tions in critical pathway environmental medium samples identified in Section 3.2 exceeds ten times the control l

station value as defined in Section 3.2, a written notification including an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result shall be sub-mitted to the Director of the NRC Regional Offic'e (with a copy to the Of ractor, Office of Nuclear Reactor Regu-lation) within 10 days after confirmation.*

• Confirmation is defined in Regulatory Guide 4.8.

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5-11 5.6.3 Changes s

A.

A report shall be made to the Director of Office of Nuclear Reactor Regulation prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have, in the judgment of the licensee, a significant adverse effect on the environ-ment or involves a radiological environmental matter or question not previously reviewed and evaluated by the USNRC.

The report shall include a description and evalua-tion of the change and a supporting benefit-cost analysis.

B.

Request for changes in Radiological Environmental Technical Specifications shall be submitted to the Director of Office of Nuclear Reactor Regulation for review and authorization.

The request shall include an evaluation of the impact on the change and a suoporting benefit-cost analysis.

'5.7 RECORDS RETENTION 5.7.1 Records and logs relative to the following areas shall be retain-ed for the life of the plant:

Records and drawing changes reflecting plant design modifi-a.

cations made to systems and equipment as described in Section 5.6.3.

b.'

Records of radi,ological environmental surveillance data.

Records to " demo'nstrate compliance with the limiting condi-l c.

tions for caeration in Section 2.0.

l 5.7.2 All other records and logs relating to the radiological environ-mental technical specifications shall be retained for five years.

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i APPENDIX B ;_PART II 7

s TO FACILITY OPERATING LICENSE NO. DPR-72 CRYSTAL RIVER UNIT 3 FLORIDA POWER CORPORATION DOCKET NO. 50-302 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

TECHNICAL SPECIFICATIONS l

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1-l 1.0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protection of environmental values during operation and additional construction of the Crystal River Unit 3.

The principe, objectives of the EPP are as follows:

i

.. l 1.

Verify that Crystal River Unit 3 is operated in an environmentally acceptable manner, as established by the Final Environmental Statement j

(FES) and other NRC environmental impact assessments.

2.

Coordinate NRC requirements and maintain consistency with other Federal, State and local requirements for environmental protection.

3.

Keep NRC informed of the environmental effects of Crystal Riv.er Unit 3 operation and additional construction, and of actions taken to control those effects.

Environmental concerns identified in the FES which relate to water quality matters are regulated by way of licensee's NPDES pennit.

I-I Amendment t!o.58

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In the FES-OL, dated May 1973,.iRC staff considered the environmental impacts associated with the operation of Crystal River Unit 3.

Certain environ-mental issues were identified which required study or license conditions to resolve environmental concerns and to assure adequate protection of,

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the environment." The Appendix B Environmental Technical Specifications issued with the license included discharge restrictions and monitoring i

programs to resolve the issues. Prior to issuance of this EPP, the requirements remaining in the ETS were:

1., The need to con, trol the release of heat (temperature) an'd chlorine within those discharge concentrations evaluated.

2.

The need for aquatic monitoring programs to confirm that themal mixing occurs as predicted, and that effects on aquatic biota and water quality due to pla[1t operation are.no, greater than predicted.

3.

The need for special studies to document levels of intake entrainment aild impingement.

Aquatic issues are addressed by the effluent limitations, monitoring requirements and the Section 316(b) demonstration requirement contained in' the effective NPDES pemit issued by EPA-Region IV.

Amendment No. 58 2-1

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3.0 Consistency Requirements 3.1 Crystal River Unit 3 Design and Operation i

l The licensee may make changes in station design or operation or perform i

tests or experiments affecting the environment provided such changes, tests I

or experiments do tot involve an unreviewed environmental question.

Changes in plant design or operation or performance of tests or experiments which

~

do not affect the environment are not subject to this requirement.

t Before engaging in unauthorized construction or operational activities which may affect the environment, the licensee shall perform an environmental evaluation of such activity.* When the evaluation indicates that such activity involves an unreviewed envi.ronmental question, the licensee shall provide a written evaluation of such activities and obtai.n prior approval i

from the NRC.

1 A. proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated l

in the FES, suoplements to the FES, environmental impact appraisals, or in

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I any decisions of the Atomic Safety and Licensino Board; or (2) a sionificant l'

11 l

• Activities are excluded from this requirement if all measurable L

nonradiological effects are confined to the on-site areas previously disturbed during site preparation and construction.

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c,,,,a change in effluents or power level (in accordance with 10 CFR Part 51.5(b)(2));

or (3) a matter not previously reviewed and evaluated in the documents spe'cified in (1) of this Suosection, which may have a significant advene environmental impact.

The licensee shall maintain records of changes in facility design or operation and of tests and ' experiments carried out pursuant to this Subsection. These 2

1 0

records shall incl.ude a written evaluation which provides bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question.

Records of modificati,ons to plant structures, systems and components detemined to potentially affect the continued protection of the environment shall be retained. for the life of the plant. All other records, data and logs relating to this EPP shall be rethined for five years or, where applicable, in accordance with the requirements of other agencies.

Activities governed by Se~ction~3'.3 of this EPP are not subject to the requirements of this section.

3.2 Reporting Related to the NPDES Pemit and State Certification 1.

Violations of the NPDES Pemit or the State 401 Certification Conditions shall be reported to the NRC by submittal of copies of the reports required by the NPDES Pemit or State 401 Certification.

Puendment No. 58 3-2 e

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2.

The licensee shall provide the NRC with a copy of any 316(a) or (b) studies and/or related documentation at the same time it is submitted to the permitting agency.

3.

Changes and additions to the NPDES Pennit or the State 401 Certification i

shall be reported to the NRC within 30 days following the date the change is approved.

If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days fallowing the date the stay is granted.

4.

The NRC shall be notified of changes to the effective NPDES Permit

' proposed by the licensee by providing NRC with a copy of the proposed change at the same time it is submitted to the permitting agency.

The licensee shall. provide the 'RC a copy of the application for N

renewal of the NPDES Permit at the same time the app'lication is submitted to, the permitting agency.

3.'3 Changes Required for Compliance with Other Environcental Regulations Changes in Crystal River 3 design or operation and performance of tests or experiments which are required to achieve compliance with other Federal, State, or local environmental regulations are not subject to the requirements of Section 3.1.

Amendment No,58 3-3 1

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4.0 Environmental Conditions 4.1 Significant Environmental Events Any occurrence of a significant event that indicates or could result in sign'ificant environmental impact causally related to station operation shall be recorded.and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• follcwed by a written report within 30 days. No routine monitoring programs are required to implement this condition.

j The written report shall (a) describe, analyze, and evaluate the event, f

including extent and magnitude of the impact and plant operating ch'a/acteristics, (b) ' describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (a) indicate the agencies notified and their preliminary responses.

i Events reportable under this subsection which also require reports to other Federal, State or local agencies shall be reported in accordance with those i

reporting requirements in lieu of the requirements of this subsection. The

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NRC shall be provided a copy of such report at the same' time it is submitted 1

to the other agency.

• If a significant environmental event occurs over weekends or holidays the report shall be supplied within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the first working day following the weekend or holiday.

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c-The following are examples of significant environmental events: excessive bird impaction events; onsite plant or animal disease outbreaks; mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973; unusual fish kills; and increase in nuisance organisms or conditions.

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