Text

Application for Amend to Licenses DPR-57 & NPF-5 Revising Tech Specs by Transferring Radiological Effluent Tech Specs from App a to App B,Per 781221 submittal.Marked-up Tech Specs Encl
	ML20080Q151
Person / Time
Site:	Hatch
Issue date:	10/06/1983
From:	Head G; GEORGIA POWER CO.
To:	Stolz J; Office of Nuclear Reactor Regulation
References
	NED-83-482, TAC-08043, TAC-08095, TAC-8043, TAC-8095, NUDOCS 8310120265
	Download: ML20080Q151 (158)
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no o cm.m . NED-83-482 October 6, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactora Branch No. 4 Division of Licensing U. S. M1 clear Regulatory Comnission Washington, D. C. 20555 NBC DOCKEIS 50-321, 50-366 OPERATIN3 LICENSES DPR-57, NPF-5 EIMIN I. HA'ICH NLCLEAR PIANT UNITS 1, 2 RADIGIOGICAL EFFLUENT TECHNICAL SPECIFICATIONS SUBMI' ITAL Gentler n:

In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c) (1), Georgia Power Company (GPC) hereby proposes a complete revision ,

to our subnittal of December 21, 1978. This subnittal is an amendment to l the Edwin I. Hatch Nuclear Plant Units 1 and 2 Technical Specifications (Appendicies A and B to the Operating Licenses) as described in the attachments to this letter. This application would amend the Technical Specifications by transferring the Radiological Effulents Technical Specifications (RETS) from Appendix B to Appendix A. In order to meet our submittal connitment to you, we are enclosing one hand-marked copy of the submittal. The balance of the required copies will be transmitted as soon as they are received from the printers. We anticipate this to be October 17, 1983.

l Both units were licensed with RETS based on activity and concentration l limitations on plant effluents. Subsequent revisions to regulatory philosophy, notably 10 CFR 50 Appendix I, now base the design objectives for effluent control on radiation dose criteria. All the changes submitted herein have previously been discussed with members of the NRC staff (Effluent Treatment Systems Section and Operating Reactors Branch #4) . It is our understanding that this subnittal does not require a formal 10 CFR 50.92 review, since it is an amendmet to a prior submittal.

The Plant Review Board and the Safety Review Board have reviewed the proposed changes and have determined that they do not constitute an unreviewed safety question. These changes do not increase the probability or consequences of accidents or malfunctions of equipment previously analyzed, create new modes of operation or potential for new accidents, or significantly decrease the margin of safety as described in the basis for Technical Specifications. i We would be pleased to meet with you to discuss any questions which you might have at any time during your review of this subnittal.

0 0310120265 831006 PDR ADOCK 05000321 t\

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e Georgia Power sh Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cmmission October 6, 1983 Page 'Ivo If you have further questions, please contact this office.

G. F. Head states that he is a Senior Vice President of Georgia Power Conpany and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEDIGIA POWER COMPANY By: b . b. / N G'. F. Head Sworn to and subscribed before me this 6th day of October, 1983.

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/T- fINo ry Public Notary Pubfic, Georgf., State et targe My Commission Exp;res M/24,1965 Enclosure xc: H. C. Nix, Jr.

Senior Resident Inspector J. P. O'Reilly, (NRC-Region II) t

TABLE OF CONTENTS Radiological Effluent Technical Specifications HNP-Unit 2 Radiological Effluent Technice.1 Specifications HNP-Unit 1 Section 3/4 Bases BNP-Unit 1 and Unit 2 Environmental Technical Specifications HNP-Unit 1 and Unit 2 e

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FIGURE TABLE

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RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS l HNP-UNIT 2 i

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1.0 DEFINITIONS SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analysis, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR 20, 10 CFR 71, federal and state regulations, and other requirements governing the disposal of radioactive wastes.

l SOLIDIFICATION f.

\s SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.

l OFFSITE DOSE CALCULATION MANUAL (ODCM)

An ODCM shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints, and in the conducting of environmental radiological monitoring.

GASEOUS RADWASTE TREATMENT SYSTEM l

The GASEOUS RADWASTE TREATMENT SYSTEM is the offgas holdup I system designed and installed to reduce radioactive gaseous offluents by collecting primary coolant system offgases from the i

primary system and providing for delay or holdup for the purpose l of reducing the total radioactivity prior to release to UNRESTRICTED AREAS.

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HNP-RETS-1

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( 1.0 DEFINITIONS (Continued) i

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VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in affluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or high-efficiency particulate air (HEPA) filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the rolesse to Uh6.ICTED AREAS. Such a system is not considered to have any effect on noble gas effluents.

Engineered safety feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

MEMBER (S) OF THE PUBLIC MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the planc. This category does not include employees of the utility, its contractors, or its t vendors. Also excluded from this category are persons who enter

! f. the site to service equipment or to make deliveries. This is q category does include persons who use portions of the site for i recreational, occupational, or other purposes not associated with the plant.

SITE BOUNDARY l

The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by Georgia Power Company, as shown in figure 3.11-1.

UNRESTRICTED AREA An UNRES'ZRICTED AREA shall be any area at or beyond the SITE l BOUNDARY to which access for purposes of protection of individuals from exposure to radiation and radioactive materials l is not controlled by the licensee. This includes any area

! within the SITE BOUNDARY used for residential quarters or for long term industrial, commercial, institutional, and/or recreational purposes.

DOSE EQUIVALENT IODINE The DOSE EQUIVALENT I-131 shall be that concentration of I-131

( (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, HNP-RETS-2 L

( 1.0 DEFINITIONS (Continued)

I-133, I-134, and I-135 actually present. The thyroid doseconversion factors used for this calculation shall be those listed in table III of TID-14844 or those in Nuclear Regulatory Commission (NRC) Reg'ulatory Guide 1.109, Revision 1, October 1977. '

PURGE - PURGING PURGE or PURGING is the controlled process of discharging air o*r gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the confinement.

VENTING VENTING is the controlled process of discharging air or gr.s from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required during VENTING. The term " vent" used in system

(. names does not imply a VENTING process.

MILK ANIMAL - A' cow or goat that is producing milk for human consumption.

REPORTABLE OCCvuMt.NCE A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications 6.9.1.12 and 6.9.1.13.

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( TABLE 1.2 FREQUENCY NOTATIONS Notation Definition Frequency S Once per shift once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D Daily once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W Weekly once per 7 days M Monthly Once per 31 days Q Quarterly once per 92 days SA Semi-annually Once per 184 days R REFUELING Once per 18 months S/U STARTUP Prior to each reactor startup P Prior Completed prior to f- each release

( NA Not applicable Not applicable l

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INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.9 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.3.6.9-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.

APPLICABILITY As shown in table 3.3.6.9-1.

ACTION

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, declare the

(-. channel inoperable, or change to a conservative value.

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b. With the number of channels OPERABLE less than the minimum channels required by table 3.3.6.9-1, take the ACTION shown in table 3.3.6.9-1.

c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13 (b) are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.6.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in table 4.3.6.9-1.

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( TABLE 3.3.6.9-1 (SHEET 1 OF 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument OPERABLE APPLICABILITY ACTION

1. Gross Radio-activity Monitors Providing Auto-matic Termina-tion of Release Liquid Radwaste Effluent Line 1 (a) 100

2. Gross Radio-activity Monitors not Providing Automatic Ter-mination of Release Service Water k<. System Effluent Line 1 (b) 101

3. Flowrate Measure-ment Devices **

Liquid Radwaste Effluent Line 1 (a) 102 Discharge Canal 1 (a, b) 102

4. Service Water 1 At all times 103 to Closed Cooling Water System Dif-ferential Pressure

- Pump curves may be utilized to estimate flow; in such cases, action statement 102 is not required.

(a) Whenever the radwaste discharge valves are not locked closed.

(b) Whenever the service watcr system pressure is below the closed cooling water system pressure or AP

(~ indication is not available.

HNP-RETS-6 t

( TABLE 3.3.6.9-1 (SHEET 2 OF 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Table Notations ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be continued, provided that prior to initiating a release:

l a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.2.

b. At least two technically qualified individuals independently verify the release rate calculations and

discharge valving.

Otherwise, suspended release of radioactive effluents via i

this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances'shall be included in the next semi-annual effluent release report.

ACTION 101 - With the numbers of channels OPERABLE less '

(( than required by the Minimum Channels OPERABLE requirement, effluent releases via this pa :hway may continue, provided that once per shift grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a Minimum Detectable Concentration of at least 10 pCi/ml. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the

next semi- annual effluent release report.

ACTION 102 - With the number of channels OPERABLE less '

than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 103 - With the number of channels OPERABLE less than

required by the Minimum Channels OPERABLE requirement, assure that the service water system effluent system monitor is OPERABLE. i r

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( TABLE 4.3.6.9-1 (SHEET 1 OF 3)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

. CHANNT:L CHANNEL SOURCE CHANNEL FUNCTIONAL Instrumeng CHECK CHECK CALIBRATION TEST

1. Gross Gamma Radioactivity Monitors Pro-viding Alarm and Automatic Icolation Liquid Rad-waste Efflu-ent Line D* P R Q'1'

2. Gross Gamma Radioactivity Monitors Pro-viding Alarm

/- but not Provid-( ing Automatic Isolation Service Water System Efflu-ent Line D

M R NA

3. Flowrate Measure- "

ment Devices l

Liquid Rad-waste Efflu-ent Line D'8** NA R Q Discharge Canal D'28* NA R Q I

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TABLE 4.3.6.9-1 (SHEET 2 OF 3)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

4. Service Water System to Closed Cooling Water System Differential Pressure D NA R NA t

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( TABLE 4.3.6.9-1 (SHEET 3 OF 3)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Table Notations

During releases via this pathway.

(1) The CHANIEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarn annunciation occurs if any of the following conditions exist

a. Instrument indicates measured levels above the alarm / trip setpoint.

b. Instrument indicates an isolation on high alarm,

c. Instrument controls are not set in operate mode.

(2) CHANNEL CHECK shall consist of verifying indication of flow

. during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, l' or batch releases are made.

(3) The SOURCE CHECK prior to release shall consist of verifying that the instrument is reading onscale.

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INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.10 The radioactive gaseous and effluent monitoring instrrmentation channels shown in table 3.3.6.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.la are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.

APPLICABILITY As shown in table 3.3.6.10-1.

ACTION

a. With a radioactive gaseous or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value that will ensure that the limits of 3.11.2.la are met, without delay restore the setpoint to a value that will ensure that the limits of Specification 3.11.2.la are met or declare the channel C. inoperable.

b. With the number of channels OPERABLE less than the minimum channels required by table 3.3.6.10-1, take the ACTION shown in table 3.3.6.10-1.

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c. The provisione of Specifications 3.0.3, 3.0.4, and 6.9.1.13(b) are.not applicable.

SURVEILLANCE REQUIREMENTS 4.3.6.10 Each radioactive gaseous or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL l

CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in table 4.3.6.10-1.

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TABLE 3.3.6.10-1 (SHEET 1 OF 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum ChanneIs Instrument OPERABLE agmJlcability Pa ramete r 6CTION

1. Main Condenser Orrgas Treatment System Explosive Gas Monitoring System

- % Hydrogen Hydrogen Monitor (1) 106 i

2. Reactor Building Vent Stack Monitoring System

a.

j Noble Gas Activity Monitor (1) Radioactivity Rate 105 Mea surement i

l b. lodine Sampler Cartridge (1) Verify Presence of 107 Cartridge Z c. Particulate Sampler Filter (1)

Verify Presence of 107 y Filter

$ d. Erriuent System Flowrate Measurement Device

104 e-3 (1) System Flowrate tn Measurement I

[ e. Sampler Flowrate Measurement Device (1) Sampler Flowrate 104

. Measurement

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3A. Main Stack Monitoring System

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a.

Radioactivity Rate l Noble Gas Activity Monitor (1) 105 Measurement

b. lodine Sampler Cartridge (1)

Verify Presence 107 of Cartridge J

,- m. ps n TABLE 3.3.6.10-1 (SHEET 2 OF 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minleum ChanneIa Instrument OPERABLE Aeolicability Pa rameter AfrJ198

c. Particulate Sampler Filter (1)

Verify Presence 101,.

or Filter f

d.

System Flowrote 104' Effluent System Flowrate Measuring Devices (1) ' ,

s Measurement

e. Sampler Flowrate Measurlog (1)

Sampler Flowrate 104 Device Measurement lI:

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x' TABLE 3.3.6.10-1 (SHEET 3 OF 4)

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RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations

During releases via this pathway.

- During main condenser offgas treatment system operation.

ACTION 104 - With the number of channals OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,

, effluent releases via this pathway may continue, provided 1 (" grab samples are taken daily and analyzed daily for gross activity.

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If the number of channels OPERABLE remains less than

, required by the Minimum Channels OPERABLE requirement for l over 30 days, an explanation of the circumstances shall be t

included in the next semi-annual effluent release report.

ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels CPERABLE requirement, operation of the main condenser offgas treatment system may continue provided: (a) gas samples are collected once per.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the ensuing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or (b) using a temporary hydrogen analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

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k; TABLE 3.3.6.10-1 (SHEET 4 OF 4) \

RADIOACTIVE GASEOUS EFFLUENT MONITORING' INSTRUMENTATION l

I Table Notations If the number of channels OPERABLE remains less than required by the Minimum Channels. OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

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. . . . , i-s TABLE 4.3.6.10-1 (SHEET 1 OF 3)

RADIOACTIVE GASEOUS EFFL'UENT MONITORING INCTRUMENTATION SURVEILLANCE REQUIREMENTS

i CHANNEL CHANNEL SOURCE CHANNEL FUNCT10NAL Instrument CHECK CHECK CAllBRATION TEST

1. Main Condenser Orrgas Treatment System Explosive Gas Monitoring Hydrogen Monitor D** NA Q(2) M

2. Reactor Building

- Vent Stack Monitoring System i a. Hoble Gas Activ- D* M R NA Ity Monitor h b. Iodine SampIer W'(3) NA NA NA l ,o Ca rt ridge I

g c. Pa rticula te W'(3) NA NA NA Sampler Filter g

3 y d. Erriuent System F lowra te D* MA R Q g

cn Measuring Device

e. Sampler Flowrate D* NA R Q Measuring Device i

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RADIOACTIVE GASEOUS EFFLUENT MONITORIWG ,

INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE PHANNEL FUNCTIONAL Instrument CHECK CHECK CAilBRATION TEST 3/ Main Stack Monitoring System .

a. Noble Gas D* M R NA Activity Monitor

b. Iodine Sampler W'(3) NA NA NA Ca rtridge

! c. Pa rticulate W*(3) NA NA NA j Sampler

d. Flowrate Monitor D* NA R Q

' lr: e. Sampler flowrate D* NA R Q Z Monitor ed I

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( TABLE 4. 3. 6.10-1 ( SHEET 3 OF 3 )

RADIOACTIVE GASEOUS EFFLUENT MONITORI1!G INSTRUMENTATION SURVEILLANCE REQUIREMENT Table Notations

During releases via this pathway.

- During main condenser offgas treatment system operation.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

l a. Instrument indicates measured levels above the alarm / trip setpoint.

b. Circuit failure occurs.

c. Instrument indicates a downscale failure.

/ (2) The CHANNEL CALIBRATION shall include the use of

( standard gas samples containing a nominal:

a. One volume-percent hydrogen, balance nitrogen

b. Four volume-percent hydrogen, balance nitrogen.

( (3) The-CHANNEL CHECK shall consist of verifying the presence of a filter element and sampler flow at the weekly filter changeout. .

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( 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (figure 3.11-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II (column 2) for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 yCi/ml total activity.

APPLICABILITY i At all times.

ACTION

a. With the concentration of radioactive material released from the site to UNRESTRICTED AREAS exceeding the above e limits, without delay restore concentration within the

'( above limits and provide notification to the Commission by including a discussion of the causes and corrective actions taken per Specification 6.9.1.8.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid effluents shall be sampled and analyzed according to the sampling and anslysis program of table 4.11.1-1.

4.11.1.1.2 The result of radioactive analysis shall be used in accordance with the methods of the ODCM to assure that the concentrations at the point of release are maintained within the l

limits of Specification 3.11.1.1.

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4 TABLE 4.11.1-1 (SHEET 1 OF 2)

RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM Minimum Minimum Liquid Minimum Type of Detectable Release Sampling Analysis Activity . Concen t ra t ionI ,,

1 Tvoe FreauencvId ' Freauency Analysis fu Cl/ mill P P A. Batch Each Batch Each Batch Principal 5 x 10'##I Waste Gamma Release Emitters'I I

Tanks 1-131 1 x 10 One M Dissolved and 1 x 10 Batch /M Entrained Cases P H-3 1 x 10-'

Each Batch M g,y Composite .

DC Gross Alpha _7 S2:

1 x 10 9 P

' 4 Each Batch Q gc3 Sr-89 5 x 10 h Composito S r-90 8

in I Fe-55 2 x 10 4 t M i

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TABLE 4.11.1-1 (SHEET 2 OF 2)

RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM Table Notations

a. The Minimum Detectable Concentration is defined in table notation (a) of table 4.16.1-2 of Unit 1, Specification 4.16.1.1.

. b. For certain radionuclides with low-gamma yield or low energies or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the Minimum Detectable Concentration. Under these circumstances, the Minimum Detectable Concentration may be increased inversely proportional to the magnitude of the gamma yield (i.e.,

5 x 10-7 /I, where: I = photon abundance expressed as a decimal fraction), but.in no case shall the Minimum Detectable Concentration, as calculated in this manner j for a specific radionuclide, be greater than 10% of the Maximum Permissible Concentration value specified in 10 CFR 20, Appendix B, Table II (column 2).

< c. A composite sample is one in which the quantity of

( liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

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d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

e. The principal gamma emitters for which the Minimum Detectable Concentration specification will apply are l

exclusively the following radionuclides: Mn-54, Fe-59, l Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and l Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other measurable and identifiable peaks together with the above nuclides, shall also be identified and reported.

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HNP-RETS-21

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( RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, from the site (figure 3.11-1) shall be limited to:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to l'ess than or equal to 5 mrem to any organ

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem co any organ.

APPLICABILITY At all times.

ACTION of de

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(_ a. With the calculated dose from the release of uid effluents exceeding any radioactivematerialsinliq/ofanyotherreport of the above limits, in lieu required by Specification $.9.1, prepare and submit to the Commission ait.'.i.; 20 % ia, pursuant to Specification 6.9.1.8, semi-annual radioactive effluent release report hich identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the. subsequent three calendar quarters, so that the cumulative dose or dose commitment to a NENBER OF 'mE PUBLIC from these releases is within 3 mrem to the total body-and 10 mrem to any organ. (This speseeri report shall also include: (a) the results of radiological analyses of the drinking water source and (b) the radiological impact on finished drinking water supplies with regard i

to the requirements of 40 CFR 141, Safe Drinking Water Act.)

b. The requirements of Specifications 3.0.3 and 3.0.4 do l not apply.

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i (

l HNP-RETS-22

RADIOACTIVE EFFLUENTS DOSE SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations - Cumulative dose contributions from liquid effluents shall be determined monthly in accordance with the ODCM.

l HNP-RETS-23

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[ NORTH SITEpopNQARY -

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FIGURE 3.11-1 UNRESTRICTED AREA BOUNDARY I

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( RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT .

LIMITING CONDITION FOR OPERK1 ION 3.11.1.3 The liquid radwaste treatment: system as described in the CDCM shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent per unit from the site (figure 3.11-1) when projected for the calendar quarter would exceed 0.18 mrem to the total body or O.62 mrem to any organ.

APPLICABILITY At all times.

ACTION

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission, pursuant to Specification 6.9.1.8, a W report that includes the following information:

f.

\ 1. Identification of the inoperable equipment or subsystems and the reason for inoperability

2. Action (s) taken to restore the inoperable equipment to OPERABLE status

3. Summary description of action (s) taken to prevent a recurrence,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected monthly, in accordance with the ODCM.

k HNP-RETS-25

I

\ RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3 .11.1. 4 c a> The contents within any outside temporary tank shall be limited to $10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY

At all times. This specification does not apply to disposable liners used for shipment of radioactive waste.

ACTION

a. With the quantity of radioactive material in any outside temporary tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents within the limit and provide i notification to the conmission pursuant to Specification 6.9.1.8.

(. b. The provisions of Specification 6.9.1.13(by are not applicable.

SURVEILLANCE REQUIREMENTS l

l 4.11.1.4 The quantity of radioactive material contained I

in any outside temporary tank shall be determined to be within the above limit by analyzing a sample of each batch of radioactive material prior to its addition to the tank.

i l

l

a. An outside temporary tank is not surrounded by liners, dikes, or walls that are capable of holding the tank conterits

/ and not having tank overflows and drains connected to the

(- liquid radwaste treatment system.

HNP-RETS-26

. , , , . - _ _ . _ _ _ _ _ . - . - _ _ , . . _ _ _ _ . _ . . . . . _ _ _ _ _ _ _ . , _ . . . . - .___. _ -_ . . - , _ . . _ . _ ~ ~ --

~ .. .

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate at any time in the UNRESTRICTED AREAS (figure 3.11-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

a. The dose rate limit for noble gases shall be s 500 mrem / year to the total body and s 3000 mrem / year to the skin

b. The dose rate limit for I-131, I-133, tritium, and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be 5 1500 mrem / year to any organ.

APPLICABILITY At all times.

! ACTION With the dose rate (s) exceeding the above limits, without delay j decrease the release rate to comply.with the limit (s) given in Specification 3.11.2.1.

SURVEILLANCE REQUIREMENTS l

l 4.11.2.1.1 The dose rate due to noble gases in gaLeo'us

! effluents shall be determined to be within the above limits in accordance with the methods and procedures described in the ODCM.

4.11.2.1.2 The dose rate due to radioactive materials other than noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures described in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in table 4.11.2-1.

HNP-RETS-27 L

1.._,-,-.-,-...-. _

^

p f*', R TABLE 4.11.2-1 (SHEET 1 OF 3)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Detectable Sampling I Analysis Type or Concentration *3 Caseous Release Tvoe F reauency Freauency Activity Analysis W Ci /m i l A. Environmental MI '3 I M 'I Principa l Camma Emi tters"3 1 x 10*I"3 Release Points G ra b Sample

-6 i

g 1. Main Stack H-3 1 x 10 Z

m 2. Reactor Building i Vent B. All Release Continuous *3I W(al 1-131 1 x i n-12 h Types (as Iisted Cha rcoa i 4-133 1 x 10-30 t in A an64 above) Sample I I Principal Camma Emitters"3 Continuous *3 W *3 1 x 10'"

Pa rt icu la te (1-131, Others) 1 Sample Continuous I*I

~

M Gross Alpha 1 x 10 "

Composite Pa rt icu la te Sample I

Continuous'3 Q Sr-89, Sr-90 1 x 10~

Composite Pa rt icu l a te Sample 1

1 ,

i

( TABLE 4.11.2-1 (SHEET 2 OF 3)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Table Notations

a. Minimum Detectable Concentration is defined in table notation (a) of table 4.16.1-2 of Unit 1, Specification 4.16.1.1.

b. For certain radionuclides with low-gamma yield or low energies, or for certain radionuclide mixtures, it may i not be possible to measure radionuclides in concentrations near the Minimum Detectable

< Concentration. Under these circumstances, the Minimum ~

Detectable Concentration may be increased inversely proportional to the magnitude of the gamma yield (i.e.,

i 1 x 10-*/I, where: I = the photon abundance l

expressed as a decimal. fraction), but in no case shall the Minimum Detectable Concentration, as calculated in this manner for a specific radionuclide, - be greater than 10 percent of the Maximum Permissible l Concentration value specified in 10 CFR 20, Appendix B, I

Table II (column 1).

,k~ c. Analysis shall also be performed following shutdown, '

startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period.

h d. Sampling shall be performed weekly, and analyses shall i

be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). Sampling shall also be

! performed once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for 7 days following each shutdown, startup, or THERMAL POWER. change exceeding 15-percent RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding Minimum Detectable Concentrations may be increased by a factor of 10.

e. The ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by each dose or dose rate calculation made in accordance I with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

f. The principal gamma emitters for which the Minimum l Detectable Concentration specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions; and Mn-54, Fe-59, Co-58, Co-60, Zn-65,

. Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for

( particulate emissions. This list does not mean that HNP-RETS-29 l

l

. . _ . _ - _ . , . - . . .. . . . . .._,. ,._ ... _ __ _ _________ _ _ _ . _ . _ . _ _ _ . _ _ _ _ . ~ . _ _ . , . . - _ _ _ . . . _ . .

TABLE 4.11.2-1 (SHEET 3 OF 3)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Table Notations only these nuclides are to be detected and reported.

Other measurable and identifiable peaks, together with the above nuclides, shall also be identified and reported. Nuclides below the Minimum Detectable Concentration for the analyses should not be reported as being present at the Minimum Detectable Concentration level for that nuclide. When unusual circumstances result in Minimum Detectable concentrations higher than required, the reasons shall -

be documented in the semi-annual effluent report.

]

(,

l HNP-RETS-30

( RADIOACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION (4seet 3.11.2.2 The air dose in UNRESTRICTED AREAS (figure 3.11-1) due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to s 5 mrad for gamma radiation and 5 10 mrad for beta radiation

b. During any calendar year, to 5 10 mrad for gamma radiation and 5 20 mrad for beta radiation. -

APPLICABILITY At all times.

ACTION

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission, pursuant

k. to Specification 6.9.1.8, a report identifying the cause(s) for exceeding the limit (s) and defining the corrective actions taken to reduce the releases and proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.2.

b. The requirements of Specifications 3.0.3 and 3.0.4 do not apply.

SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations - Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM monthly.

k.

HNP-RETS-31

( RADIOACTIVE EFFLUENTS DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to any organ of a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to UNRESTRICTED AREAS (figure 3.11-1) from each reactor unit shall be limited to the following:

i a. During any calendar quarter to s 7.5 mrem to any organ ,

b. During any calendar year to s 15 mrem to any organ.

APPLICABILITY At all times.

ACTION

- a. With the calculated dose from the release of I-131,

(; ^ I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous

, effluents exceeding any of the above limits, prepare

! and submit to the Commission, pursuant to Specification

i. 6.9.1.8, a report identifying the cause(s) for exceeding the limit and defining the corrective actions taken to reduce releases and proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.3.

b. The provisions of Specifications 3.0.3 and 3.0.4 arte not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculatione - Cumulative dose contributions for the current calender quarter and the current calender year shall be determined in accordance with the ODCM monthly.

HNP-RETS-32

( RADIOACTTVE EFFLUENTS as described in the ODO!

GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 1 1

3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY Whenever the main condenser air ejector system is in operation.

ACTION

~

a. With the GASEOUS RADWASTE TREATMENT SYSTEM inoperable for more than 31 days, prepare and submit to the Commission M C.fn 2^ i;5, pursuant to Specification 6.9.1.8, a report which includes the following information:

1. Identification of the inoperable equipment or ,

subsystems and the reason for inoperability

2. Action (s) taken to restore the inoperable equipment (a

to OPERABLE status

3. Summary description of action (s) taken to prevent a recurrence,

b. The requirements of Specifications 3.0.3 and 3.0.4 do not apply.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected monthly, in accordance with the ODCM.

i I

r HNP-RETS-33 I

\. - . . . , _ . . . - , _ -

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION l 3.11.2.5 The dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to 5 25 mrem to the total body or any organ (except the thyroid, which is limited to s 75 mrem) over a calendar year.

APPLICABILITY At all times.

ACTION

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2(a), 3.11.2.2(b), 3.11.2.3(a), or 3.11.2.3(b),

in lieu of any other report required by Specification 6.9.1, prepare and submit within 30 days a special report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D. C.

(<_ 20555, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of i exceeding the limits of Specification 3.11.2.5. This-special report shall include an analysis which

[ estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources (including all effluents pathways and direct radiation) for a 12 l consecutive month period that includes the release (s)

I covered by this report. If the estimated dose (s) l exceeds the limits of Specification 3.11.2.5, and if the release condition resulting in violation of 10 CFR 100 has not already been corrected, the special report shall include a request for a variance in accordance with the provisions of 10 CFR 100 and including the specified information of paragraph 190.11. Submittal '

of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190 and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b. The requirements of Specifications 3.0.3 and 3.0.4 do not apply.

f HNP-RETS-34

(x RADIOACTIVE EFFLUENTS DOSE SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Dose Calculations - Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 3.11.1.2, 3.11.2.3, and the ODCM.

1 HNP-RETS-35

(- RADIOACTIVE EFFLUENTS

- EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION l

3.11.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to 5 4 percent by volume.

APPLICABILITY At all times.

ACTION _

a. With the concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system exceeding the limit, restore the concentration Ap6 within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13(b) are not applicable.

e SURVEILLANCE REQUIREMENTS k

4.11.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be determined to be within the above limits by monitoring the waste gases in the main condenser offgas treatment system with the (hydrogen) monitors required OPERABLE by table 3.3.6.10-1, Specification 3.3.6.10.

O e-HNP-RETS-36

(- RADIOACTIVE EFFLUENTS MAIN CONDENSER LIMITING CONDITION FOR OPERATION 3.11.2.7 The gross gamma radioactivity rate of noble gases measured at the main condenser evacuation system pretreatment monitor station shall be limited to s 240,000 pCi/second.

. APPLICABILITY f At all times.

~

ACTION With the gross gamma radioactivity rate of noble gases at the pretreatment monitor exceeding 240,000 pCi/second, restore the gross radioactivity rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least OPERATIONAL CONDITION 2 within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4 SURVEILLANCE REQUIREMENTS

('~' 4.11.2.7 The gross radioactivity (beta and/or gamma) rate of noble gases from the main condenser air ~ ejector shall be determined to be within the above limit at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the pretreatment monitoring station:

dilution-and/or + - S rg-) n' + - nxi n M-- . . -- m 1r @th

a. Monthly when plant is operating

b. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an evacuation system pretreatment increase of greater than 50 percent, as indicated by the condenser monitor, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady-state fission gas release from the primary coolant.

(

t HNP-RETS-37

( RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 The solid radwaste system shall be used to provide for the SOLIDIFICATION of wet solid wastes and for the "

SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure the meeting of the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY

~

At all times.

J ACTION

a. With the requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend shipments of defective containers of solid radioactive wastes from the site.

b. The requirements of Specifications 5.0.3 and 3.0.4 do not apply.

SURVEILLANCE REQUIREMENTS 4.11.3.1.1 The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of wastes prior to shipment.

l

(

l HNP-RETS-38

( 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING See specification section 3/4.16 for HNP-Unit 1.

f d

C .

l HNP-RETS-39

ART SLIP SHEET c

FIGURE NO.

ZTURN PAGE Z, FULL PAGE I -

_ . FOLDOUT RESPONSIBLE AUTHOR EDITOR / COORDINATOR i

< SPECIAL INSTRUCTICNS .

L; g cdrA of da /, r/ag fers-N 0- Ils61 VERTICAL _

TURN PAGE FIGURE TABLE Form No. 9-405

( NUREG-0473 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS HNP-UNIT 1

- ?

9 e

.+

w

1.0 DEFINITIONS SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analysis, tests, and determinations to be made to ,

ensure that the processing and packaging of solid radioactive _

wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR 20, 10 CFR 71, federal and state regulations, and other requirements governing the disposal of radioactive -

wastes.

SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.

~

OFFSITE DOSE CALCULATION MANUAL (ODCM)

An ODCM shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of l gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints, and in the conducting of environmental radiological monitoring.

GASEOUS RADWASTE TREATMENT SYSTEM The CASEQUS RADWASTE TREATMENT SYSTEM is the offgas holdup I system designed and installed to reduce radioactive gaseous I

effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to UNRESTRICTED AREAS, ~

i l '

t L -

HNP-RETS-1

-N,..

9 l( l.0 DEFINITIONS (Continued)

VENTILATION' EXHAUST TREATMENT SYSTEM i VENTILATION EXHAUST TREATMENT SYSTEM-is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or high, efficiency particulate air (HEPA) filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to UNRESTRICTED AREAS. Such a system is not considered to have any effect on noble gas effluents. Engineered safety feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. ,,

MEMBER (S) OF THE PUBLIC -

t ; .

MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or its vendors. Also excluded from this category are persons who enter. ~

the site to service equipment or to make deliveries. This g category does include persons who use portions of the site for

('- recreational, occupational, or other purposes not associated with the plant.

i l

l- SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, based, or otherwise controlled by Georgis Power _

Company, as shown in figure 3.15-1. - ~

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY to which access for purposes of protection of individuals from exposure to radiation and radioactive materials is not controlled by the licensee. This includes any area within the SITE BOUNDARY used for residential quarters or for long-term industrial, commercial, institutional, and/or recreational purposes.

l i

l

(.

t l

HNP-RETS-2

}

. --.. ---- ,._n,.-,,-..,.-,.n.,,,,.,,,-,,,,_n-,.,.-,,n.-w- ,-

.- . .~ .

( 1.0 DEFINITIONS (Continued) i PURGE - PURGING w

PURGE or PURGING is the controlled process of discharging air or 1

gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the confinement.

VENTING

?

t VENTING is the controlled process of discharging air or gas from _

a confinement to maintain temperature, pressure, humidity, i concentration, or other operating condition in such a manner ~

l that replacement air or gas is not provided or required during I

VENTING. The term " vent," used in system names, does not imply a VENTING process.

MILK ANIMAL - A-cow or goat that is producing milk for -

human consumption. -

DOSE EQUIVALENT ICDINE The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram),,which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose L conversion factors used for this calculation shall be those listed in table III of TID-14844 or those in NRC Regulatory Guide 1.109, Revision 1, October 1977.

l l ACTION l

ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.

HNP-RETS-3

( l.0 DEFINITIONS (Continued)

CHANNEL CHECK A CHAN14EL CHECK shall be the qualitative assessment of channel be-havior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/

on status with other indications and/or status derived from inde-pendent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be: _

a. Analog channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip funccions and channel failure trips.

b. Bistable channels - the injection of a simulat.ed signal into the channel sensor to verify OPERABILITY including alarm and/or trip functiont. ,

l i

l

( .

HNP-RETS-3a 1

[ TABLE 1.2 FREQUENCY NOTATIONS Notation Definition Frequency S Once per shift once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D Daily once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W Weekly once per 7 days M Monthly once per 31 days Q Quarterly once per 92 days .

SA Semi-annually Once per 184 days R REFUELING Once per 18 months S/U STARTUP Prior to each reactor startup P Prior Completed prior to each f relaase k' NA Not applicable Not applicable r

HNP-RETS-4

--- = ,, erw-- -g_ = me - g v- - ---e---r- -s

'( INSTRUMENTATION RADIOACTIVE LIQUID' EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 4

3.14.1 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.14.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance-with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY As shown in table 3.14.1-1.

ACTION

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid i effluents monitored by the affected channel, declare the channel inoperable, or change to a conservative value. .

{,

b. With the number of channels OPERABLE less than the minimum channels required by table 3.14.1-1, take the ACTION shown in table 3.14.1-1.

c. The provisions of Specification 6.9.1.13(b) are not applicable.

d. When the ACTION statementf or other requirements of this LCO cannot be met, steps need not be taken to change the OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.

l SURVEILLANCE REQUIREMENTS 4.14.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations and at the frequencies shown in table 4.14.1-1.

HNP-RETS-S

- ~ . - _ , - _ . _ . .

(.- TABLE 3.14.1-1 (SHEET 1 OF 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument OPERABLE Applicability ACTION

1. Gross Radioactivity Monitors Providing Automatic Termina-tion of Release Liquid Radwaste Effluent Line 1 (a) 100 ,

2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System Effluent Line 1 (b) 101

(~ 3. Flowrate Measure-ment Devices **

Liquid Radwaste Effluent Line 1 (a) 102 Discharge Canal 1 (b) (a) 102

4. Service Water 1 At all times 103 System to Closed Cooling Water System Differential Pressure

- Pump curves may be utilized to estimate flow; in such cases, action statement 102 is not required.

(a) Whenever the radwaste discharge valves are not locked closed.

(b) Whenever the service water system pressure is below the closed cooling water system pressure or AP indication is not available.

I HNP-RETS-6

t t

( TABLE 3.14.1-1 (SHEET 2 OF 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Table Notations 1

l ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be continued, provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 4.15.1.1.2.

i b. At least two technically qualified individuals .

independently verify the release rate calculations and.

discharge valving.

Otherwise, suspended release of radioactive effluents via this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included i in the next semi-annual effluent release report.

ACTION 101 - With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, (C effluent releases via this pathway may continue, provided

that once per shift grab samples are collected and analyzed l

for gross radioactivity (beta or gamma) at a Minimum Detectable Concentration of at least 10-7 pCi/ml. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi- annual effluent release report.

ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 103 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the service water system effluent system monitor is OPERABLE.

HNP-RETS-7 l

e,.,__-- . - . - - - , ,w_ -----.+y---.__._,,,w.3 .,w.,-- ., y. - , -----.-,v,.<.ry,.,- -y<ww.--,,,,,,y ,,.--+m,,w

_p-,_-+- -

-e vv

( TABLE 4.14.1-1 (SHEET 1 OF 2) .

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

1. Gross Gamma Radioactivity Monitors Pro-viding Alarm and Automatic Isolation ,

Liquid Rad-waste Efflu-ent Line D* P'8' R Q'8'

2. Gross Gamma Radioactivity Monitors Pro-viding Alarm (r.

but not Provid-ing Automatic Isolation Service Water System Efflu-ent Line D

M R NA

3. Flowrate Measure-ment Devices Liquid Rad-waste Efflu-ent Line D'8'* NA R Q Discharge Canal D'8'* NA R Q

4. Service Water l System to Closed l Cooling Water l System Differential Pressure D NA R NA 7-l (.' -

HNP-RETS-8 i

~

(' TABLE 4.14,1-1 (SEEET 2 OF 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Table Notations

During releason via this pathway.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

a. Instrument indicates measured levels above the ~

' alarm / trip setpoint.

b. Instrument indicates an isolation or high alarm.

c. Instrument controls are not set in operate mode.

(2) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic,

,, or batch releases are made.

,(-

(3) The SOURCE CHECK prior to release shall consist of

verifying that the instrument is reading onscale.

I.

1

'( ,

HNP-RETS-9

l- INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.14.2 The radioactive gaseous and effluent monitoring instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of' Specification 3.15.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in-accordance with the ODCM.

APPLICABILITY f

~

As shown in table 3.14.2-1.

. ACTION

a. With a radioactive gaseous or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value that will ensure that the limits of 3.15.2.1 are met, without delay restore the setpoint to a value that will ensure that the limits of Specification 3.15.2.la, are met or declare the channel inoperable.

b. With the number of channels OPERABLE less than the minimum channels required by table 3.14.2-1, take the ACTION shown in table 3.14.2-1.

c. The provisions of Specification 6.9.1.13(b) are not applicable.

d. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the OPERATIONAL CONDITICN of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the

. ACTION statement are satisfied.

SURVEILLANCE REQUIREMENTS 4.14.2 Each radioactive gaseous.or effluent monitoring i instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations and at the frequencies shown in table 4.14.2-1.

BNP-RETS-10

TABLE 3.14.2-1 (SHEET 1 OF 4) t

. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

. Minimum f

Channeis Instrument EfRABLE epolicabill.ty Pa rameter ACTION

1. Main Condenser Orrgas Treatment i System Explosive cas Monitoring System 5 Hydrogan Monitor (1) ** % Hydrogen 106

2. Reactor Building Vent Stack Monitoring System

a. Noble Cas Activity Monitor (1)

Radioactivity Rate 105 Measurement D:

i Z b. todine Sampler Cartridge (1)

Verify Presence of 107 y Ca rt ridge i

' % c. Particulate Sampler Filter (1)

Verify Presence or + 107 s Filter la i d. Effluent System Flowrate H Measurement Device

H (1) System Flowrote 104

] Measurement i

e. Sampler Flowrate Measurement Device (1)

Sampler Flowrato 104 Measurement

3. Recombiner Building Ventilation

Monitoring System A

a. Noble Gas Activity Monitor (1)

Radioactivity Rate 105

{ Measurement

b. lodine Sampler Cartridge (1)

Verify Presence of 107 Ca rtridge 3 c. Particulate Sampler Filter (1)

Verify Presence of 107 1 Filter i

.. d. Sampler Flowrate Measurement (1)

Sampler Flowrate 104 i Device Measurement i

i

p ,

O A TABLE 3.14.2-1 (SHEET 2 OF 4) i RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMEN'JATION Minlaum .

ChanneIs I nst rument OPERABLE Acolicability Pa rameter ACTION l 4. Main Stack Monitoring System

a. Noble Gas Activity Monitor (1)

hadioactivity Rate 105 Measurement

b. lodine Sampler Cartridge (1)

Verify Presence of 107 .

Cartridge

c. Particulate Sampler Filter (1)

Verify Presence of 107 Filter

d. Effluent System Flowrate i Measuring Devices (1)

System Flowrate 104

x: Measurement 2:

N e. Sampler Flowrate Measuring (1)

Sampler Flowrate 104 I Device Measurement b

e in I

tJ l

I i

.l I

l i

d i

(- TABLE 3.14.2-1 (SHEET 3 OF 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations

During releases via this pathway.

- During main condenser offgas treatment system operation.

ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab samples are taken daily and analyzed daily for gross 4

activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

{( .

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided:

(a) Gas samples are collected once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the ensuing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or (b) Using a temporary hydrogen analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

HNP-RETS-13 l.-__._.____. _ _ _ . _ . _ _ . - . . . _ . _ . _ _ _-_ _ _. _ .__ _ _ _ ._ _ ., _ _ ,

h TABLE 3.14.2-1 (SHEET 4 OF 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations ACTION 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided .

samples are continuously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed-within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for -

over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

HNP-RETS-14

r

[

TABLE,4.14.2-1 (SHEET 1 OF 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CAllBRATION TEST

1. Main Condenser Offgas Treatment System Explosive Cas Monitoring System Hydrogen Monitor D** NA Q(2) M

2. Reactor Building Vent Stack Monitoring System

a. Noble Gas Activ- D* M R NA .

2: ity Monitor i

Z T b. Bodine Sampler W'(3) NA NA NA 8

Ca rt ridge J

h c. Pa rt icu la te W'(3) NA NA NA

>3 (t) Sampler Filter I

[ d. Effluent System D* NA R Q Flowrate Measuring Device

e. Sampler Flowrote D* NA R Q Measuring Device e

[., ,P .^

TABLE 4.14.2-1 (SHEET 2 OF 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING '

ESTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCT10NAL I ns t rtiment CHECK CHECK.. CAllBRATION TEST

3. Recombiner Building Ventila tion Monitoring System

a. Noble Cas D* M R Activity Monitor Q(1) i b. Bodine Sampler W'(3) NA NA NA Cartridge

c. Pa rt icul a te W'(3) NA NA NA g Sample Filter h d. Sampler Flowrate D* NA R Q Measuring Device j

4. Main Stack j

$ Monitoring System h

m

a. Noble Gas D* M R HA

Activity Monitor 4

b. Bodine Sampler W"(3) NA NA NA

c. Pa rt icul a tu W"(3) NA NA NA Samp le r

d. Flowrate Monitor D* NA R Q i

e. Sampler Flowrate D* NA R Q

Monitor l

1 l

7

( TABLE 4.14.2-1 (SHEET 3 OF 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Table Notations

During releases via this pathway.

- During main condenser offgas treatment system operation.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

~

a. Instrument indicates measured levels above the alarm / trip setpoint.

b. Circuit failure occurs.

c. Instrument indicates a downscale failure.

(2) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

k a. One volume-percent hydrogen, balance nitrogen

b. Four volume-percent hydrogen, balance nitrogen.

(3) The CHANNEL CHECK shall consist of verifying the presence of a filter element and sampler flow at the weekly filter changeout.

HNP-RETS-17

( 3/4.15 RADIOACTIVE EFFLUENTS 3/4.15.1 LIQUID EFFLUENTS CONCENTRATION

' LIMITING CONDITION FOR OPERATION 3.15.1.1 The concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (figure 3.15-1) .

shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II (column 2) for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-*

pCi/ml total activity. .

APPLICABILITY At all times.

ACTION

a. With the concentration of radioactive material released from the site to UNRESTRICTED AREAS exceeding the above r limits, without delay restore concentration within the

(, above limits and provide notification to the Commission by including a discussion of the causes and corrective actions taken in the next report per Specification 6.9.1.8.

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.

SURVEILLANCE REQUIREMENTS 4.15.1.1.1 Radioactive liquid effluents shall be sampled and analyzed according to the sampling and analysis program of table 4.15.1-1.

4.15.1.1.2 The result of radioactive analysis shall be used in accordance with the methods of the OFFSITE DOSE CALCULATION MANUAL (ODCM) to assure that the concentrations at the point of release are maintained within the limits of Specification 3.15.1.1.

ENP-RETS-18

J 9

n 3 o I" leit11 # ' ,

40 M mba1 0 0 0 ~0 0 _0 A uar9 mtt/

1 1 1 1 1 1 1 R i cnl x x x x x x x G neeC i

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l.

M e n (M Do 6

P C S

I S

Y L s

)

A ) e 2 N e ds A C na

. aG a F h D # dd p O N ys l

a s ee l A mrti p r vn A 1 uois i e li m vy cat 1 oa s 90 5 G ieil nmt 3 sr s 89 5 T N npta imi 1 st 3 o rr e

E i yc n ram - in - r E I MTAA PCE 1 DE H G SS F H L P

S M

(

A 1 S

- T ) )

1 h go g N y c e 5 E sc t t t U min a I i 1 use B s s L ilmyua o op F h p 4 F nae c m m inr a o o E E MAF M MC QC L D .

B I A b T Q 3 I d h h I h L gc v c t

c t

nn e M a a E ie S / B B V l u pa h h

c h h I me c et c c T ar SF E a

POB na PE a

PE a

C A

[OD A e R s heas ctek e tsl n aaea idsae BWRT ueo ql v eT .

iLR A

4*

x yjgm m

( TABLE 4.15.1-1 (SHEET 2 OF 2)

RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM Table Notations

a. The Minimum Detectable Concentration is defined in table notation (c) of table 4.16.1-2, Specification 4.16.1.2.

b. For certain radionuclides with low-gamma yield or low energies or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the Minimum Detectable Concentration. Under these circumstances, the Minimum Detectable Concentration may be increased inversely _

proportional to the magnitude of the gamma yield (i.e.,

5 x 10-'/I, where: I = photon abundance expressed as a d'cimal e frsction), but in no case shall the Minimum Detectable Concentration, as calculated in this manner for a specific radionuclide, be greater than 10% of the Maximum Permissible Concentration value specified in 10 CFR 20, Appendix B, Table II (column 2).

c. A composite sample is one in which the quantity of

(- liquid sampled is proportional to the quantity of liquid

( waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated and then thoroughly mixed by a method described in the CDCM to assure representative sampling.

e. The principal gamma emitters for which the Minimum Detectable Concentration specification will apply are

! exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other measurable and identifiable peaks together with the above nuclides, shall also be identified and reported.

I I

l HNP-RETS-20

( RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.15.1.2 The dose or dose commitment to a MEMB2R OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, from the site (figure 3.15-1) shall be limited to:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrom to any organ

~

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY At all times.

ACTION a, With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission wiRii. 00 whmsr, pursuant to Specification 6.9.1.8, a section in the semi-annual effluent report which identifies the a cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of

, radioactive materials in liquid effluents during the i remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the Q !

cumulative dose or dose commitment to in individsel from j these releases is within 3 mrem to the total body and 10 h l mrem to any organ. (This spee6et report shall also include (1) the results of radiological analyses of the h drinking water source and (2) the radiological impact on C finished drinking water supplies with regard to the o requirements of 40 CFR 141, Safe Drinking Water Act.)

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the

, OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may i

be made if, as a minimum, the requirements of the ACTION statement are satisfied.

l .

I ENP-RETS-21

(' RADIOACTIVE EFFLUENTS DOSE (Continued)

SURVEILLANCE REQUIREMENTS 4.15.1.2 ' Dose Calculations - Cumulative dose contributions from liquid effluents shall be determined monthly in accordance with the ODCM.

t

(

(-

HNP-RETS-22

f'. ,D p

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i. * ..

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NORTH - plTE GOWNPARY .

' tuNetSTRKTER AREA 800NDA4YI ' i l A .

i ;

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) FLOOO PLAIN FOREST / '

j d .geon DLD 48ETE0#0LQ90 CAL TOWER

)\

) Leouse oeSCHARGE 5$ EDWIN O.HATCN NucLEAM PpMT g k T M WRE e9 .

p. MAIN STAclC .

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, j , eLDG VENT- e

i f WellT 2 flyACTOM -

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l

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RivERFLow - '

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., cs. ! .!I k .! l' i ! .in cAurtwG $l l

> M T l ,

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! FIGURE 3.15-1 UNRESTRICTED AREA BOUNDARY l

i j .

4

m. -

( RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT as described in the 0004 LIMITING CONDITION FOR OPERATION s

3.15.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (figure 3.15-1) when averaged over the calendar quarter would exceed 0.18 mrem to the total body or O.62 mrem to any organ.

1 APPLICABILITY At all times.

ACTION

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission, pursuant to Specification 6.9.1.8, a section in the semi-annual effluent report that includes the following information:

k~ 1. Identification of the inoperable equipment or subsystems and the reason for inoperability

2. Action (s) taken to restore the inoperable equipment to OPERABLE status ,

3. Summary description of action (s) taken to prevent a recurrence.

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.

SURVEILLANCE REQUIREMENTS 4.15.1.3.1 Doses due to liquid releases shall be projected monthly in accordance with the ODCM.

HNP-RETS-24

RADIOACTIVE EFFLUENTS

((

LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.15.1.4<a> The contents within any outside temporary tank shall be limited to s10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY At al'1 times. This specification does not apply to disposable liners used for shipment of radioactive waste.

ACTION

a. With the contents within any outside temporary tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents within the limit' and 'p'rovide notification to the Connission pursuant to '

Specification 6.9.1.8.

b. The provisions of Specification 6.9.1.13l(b) are not h- applicable.

SURVEILLANCE REQUIREMENTS i

4.15.1.4 The -conteatrwithin-any outside temporary tank shall bedeterminedtobewitljintheabovelimitbyanalyzingasample

(

of each batch of radioactive material prior to its addition to the tank.

quantity of radioactive material contained in

a. An outside temporary tank is not surrounded by liners,

, dikes, or walls that are capable of holding the tank contents i and not having tank overflows and drains connected to the liquid radwaste treatment system.

HNP-RETS- 25 l

_ . . - - ..,r---- . _ , , , , , , , , . . . , , , ., .-m.r.._ry -

m . ,__--. ,. ,_,,.y ,m ,, - - - , _ . , .-. , , . _ , , . _ _ . _m,

1

( RADIOACTIVE EFFLUENTS 3/4.15.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.15.2.1 The dose rate at any time in the UNRESTRICTED AREAS (figure 3.15-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

a. The dose rate limit for noble gases shall be s 500 mrem / year to the total body and s 3000 mrem / year to .

the skin

b. The dose rate limit for I-131, I-133, tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days shall be s 1500 mrem / year to any organ.

APPLICABILITY

/ At all times.

k.

ACTION With the dose rate (s) exceeding the above limits, without delay decrease the release rate to comply with the limit (s) given in Specification 3.15.2.1.

SUR7EILLANCE REQUIREMENTS 4.15.2.1.1 The dose rate due to noble gases in gaseous affluents shall be determined to be within the above limits in accordance with methods and procedures described in the ODCM.

4.15.2.1.2 The dose rate due to radioactive materials other

! than noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures described in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in table 4.15.2-1.

HNP-RETS-26

r C\ f TABLE 4.15.2-1 (SHEET 1 OF 3)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Minimum Detectable Sampling Analysis Type or Concent ra t ion g,3 Caseous Release Tvoe Freauency Freauency Activity Analysis (yCi/ml)

MI *I MI 'I Principal Camma EmittersM A. Envi ronmenta l 1 x 10-* I*I Release Points Grab Sample

1. Main Stack 4 H-3 1 x 10

2. Reactor Building Vent

3. Recombiner Building vent

8. All Release Continuous I*I W I#I l-131 1 x 10'I' g Types (as listed Cha rcoa l g in A acd"J above) Sample 1-133 1 x 10-I '

Continuous I*I W(al Principal camma Emitters 1 x 10'I' '

g Pa rticula te Sample (I-131, Others) g 4

f Continuous I*I M Gross Alpha 1 x 10-II b) Composite

-J Pa rticula te Sample Continuous I*I

~

Q Sr-89, Sr-90 1 x 10 *

Composite Particulate .

Sample }

i I

f

i

(~ TABLE 4.15.2-1 (SHEET 2 OF 3 )

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Table Notations l a. Minimum Detectable Concentration is defined in table l notation (a) of table 4.16.1-2, Specification 4.16.1.1. '

, b. For certain radionuclides with low-gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the Minimum Detectable Concentration. Under these circumstances, the Minimum !

Detectable Concentration may be increased inversely propertional to the magnitude of the gamma yield (i.e.,

. 1 x 10-*/I, where: I = the photon abundance expressed as a decimal fraction), but in no case shall the Minimum Detectable concentration, as calculated in this manner for a specific radionuclide, be greater than 10 percent of the Maximum Permissible Concentration value specified in 10 CFR 20, Appendix B, Table II (column 1).

c. Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent i (.t of the RATED THERMAL POWER within a 1-hour period.

l I

d. Sampling shall be performed weekly, and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). Sampling shall also be performed 7 once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15-percent RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding Minimum Detectable Concentrations may be increased by a factor of 10.

l

e. The ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by each dose or dose rate calculation made in accordance l

with Specifications 3.15.2.1, 3.15.2.2, and 3.15.2.3.

l

f. The principal gamma emitters for which the Minimum Detectable Concentration specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions; and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other -

measurable and identifiable peaks, together with the above nuclides, shall also be identified and HNP-RETS-28

( TABLE 4.15.2-1 (SHEET 3 OF 3 )

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Table Notations reported. Nuclides below the Minimum Detectable Concentration for the analyses should not be reported as being present at the Minimum Detectable Concentration level for that nuclide. When unusual circumstances result in Minimum Detectable Concentrations higher than required, the reasons shall be documented in the semi-annual effluent report.

e e

d HNP-RETS-29 e - - - - > - - - .~,,,,m,,,_--,y ..m_.-,.*-,-,n . v, . _,g+-q.. , , . , ,_4,, 9 y,,,7 y -,.g. --q.-, 7w 9. - -, --. ------%,, -,.*w a-g% y --

i

( RADIOACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION 3.15.2.2 The air dose in UNRESTRICTED AREAS (figure 3.15-1) due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to 5 5 mrad for gamma radiation and 5 10 mrad for beta radiation

b. During any calendar year, to s 10 mrad for gamma radiation and s 20 mrad for beta radiation. ,

+a APPLICABILITY At all times.

ACTION

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above r-: limits, prepare and submit to the Commission, pursuant tg. to Specification 6.9.1.8, a section in the semi-annual effluent release report identifying the cause(s) for exceeding the limit (s) and defining the corrective i actions taken to reduce the releases and proposed corrective actions to be taken to assure that subsequent

! releases will be in compliance with Specification 3.15.2.2.

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.

SURVEILLANCE" REQUIREMENTS 4.15.2.'2.1 Dose Calculations - Cumulative dose contributions for the. total time period shall be determined monthly in accordance with the ODCM.

L /. ,

\f ,;

c, HNP-RETS-30

- , __ ~ . _ - - _ _ . . _ . -_ _ _ _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _-_ _ _

~

RADIOACTIVE EFFLUENTS DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 1

l 3.15.2.3 The dose to any organ of a MEMBER OF THE PUBLiC from '

I-131, I-133, tritium, and materials in particulate form with half-lives greater than 8 days in gaseous effluents released to UNRESTRICTED AREAS (figure 3.15-1) from each reactor unit shall be limited to the following:

a. During any calendar quarter to 5 7.5 mrem to any organ

b. During any calendar year to s 15 mrem to any organ.

APPLICABILITY At all times.

l ACTION

a. With the calculated dose from the release of I-131,

,e I-133, tritium, and all radionuclides in particulate

'( form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the_ Commission, pursuant to Specification 6.9.1.8, a section in the semi-annual effluent report identifying the cause(s) for exceeding the limit and defining the corrective actions taken to reduce releases and proposed corrective actions to be taken to assure that subsequent releases will be in compliance with-Specification 3.15.2.3.

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, - as a tMticum, the requirements of the ACTION statement are ar' 10 fied.

SURVEILLANCE REQUIF';j~g g ,

4.15.2.3.1 Dose Calculations - Cumulative dose contributions for the current calendar quarter and the current calendar year shall be determined monthly in accordance with the ODCM.

HNP-RETS- 31 l

- .- .-.. . . _ - . - . - ---.--.- - - ,.- __- _ - .. ~.- -..._-,-._

( RADIOACTIVE EFFLUENTS as described in the ODCM I GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION

\

3.15.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY Whenever the main condenser air ejector system is in operation.

ACTION

a. With the GASEOUS RADWASTE TREATMENT SYSTEM inoperable for more than 31 days, prepare and submit to the Commission +1H= G -4 , pursuant to Specification 6.9.1.8, a semi-annual effluent release report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability

2. Action (c) taken to restore the inoperable equipment (r

to OPERABLE status

3. Summary description of action (s) taken to prevent a recurrence.

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the

, OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.

l SURVEILLANCE REQUIREMENTS 4.15.2.4.1 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected monthly in accordance with the ODCM.

l HNP-RETS-32

4

/

, ( RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.15.2.5 The dose or dose commitment to a MEMBER OF THE PUBLIC I from all uranium fuel cycle sources is limited to s 25 mrem to the total body or any organ (except the thyroid, which is limited to s 75 mrem) over a calendar year.

APPLICABILITY At all times.

ACTION

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.15.1.2(a), 3.15.2.3(a), or 3.15.2.3(b), in lieu of any other report required by Specification 6.9.1, prepare and submit within 30 days a special report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, which

{.

defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.15.2.5. This special report shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources (including all effluents pathways and direct. radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated condition resulting in violation of 40 CFR 190 has not already been corrected, the special report shall. include a request for a variance in accordance with the provisions of 40 CFR 190, including the specified information of paragraph 190.11. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190 and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical

specification.

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the OPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.

HNP-RETS-33

( RADIOACTIVE EFFLUENTS DOSE (Continued)

SURVEILLANCE REQUIREMENTS 4.15.2.5.1 Dose Calculations - Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 3.15.1.1, 3.15.1.2, and the ODCM.

e e

9 l

HNP-RETS-34

! _. ~ -._..__- _ _____ _ _, _._ _ _ _ . . . _ _ _ _ . _ _ _ . _ _ - . _ _ _ . . _ _ _ . . _ - _ _ _ . . - . - . _ _ .

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to s 4 percent by volume.

APPLICABILITY At all times.

ACTION -

a. With the concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system exceeding the limit, restore the concentration -to-within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. The provisions of Specification 6.9.1.13 (b), are not applicable. ,

SURVEILLANCE REQUIREMENTS 4.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be determined to be within the above limits by monitoring the waste gases in the main condenser offgas treatment system with the (hydrogen) monitors required OPERABLE by table 3.14.2-1, Specification 3.14.2.

I

(

L

, HNP-RETS-35 l

RADIOACTIVE EFFLUENTS i MAIN CONDENSER l

LIMITING CONDITION FOR OPERATION 3.15.2.7 The gross gamma radioactivity rate of noble gases measured at the main condenser evacuation system pretreatment monitor station shall be limited to 5 240,000 pCi/second.

I APPLICABILITY At all times.

l ACTION _

With the gross gamma radioactivity rate of noble gases at the pretreatment monitor exceeding 240,000 pCi/second, restore the gross radioactivity rate to within its. limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least OPERATIONAL CONDITION 2 within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS kf 4.15.2.7 The gross radioactivity (beta and/or gamma) rate of noble gases from-the main condenser air ejector shall be determined to be within the above limit at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the pretreatment monitoring station: '

a. Monthly when plant is operating

b. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an evacuation system l pretreatment increase of greater than 50 percent, as indicated by the condenser monitor, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady-state fission gas release from the primary coolant.

l

( .

HNP-RETS-36

RADIOACTIVE EFFLUENTS 3/4.15.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.15.3.1 The solid radwaste system shall be used to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure the meeting of the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY At all times.

ACTION

a. With the requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend shipments of defective containers of solid radioactive wastes from the site.

b. When the ACTION statement or other requirements of this LCO cannot be met, steps need not be taken to change the

(.- CPERATIONAL CONDITION of the Unit. Entry into an OPERATIONAL CONDITION or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.

SURVEILLANCE REQUIREMENTS 4.15.3.1 The PROCESS CONTROL PROGRAM shall be used to verify l the SOLIDIFICATION of wastes prior.to shipment.

1 1

HNP-RETS-37 I

t

4 1

, RADIOLOGICAL ENVIRONMENTAL MONITORING

3/4.16.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.16.1 The radiological environmental monitoring program shall be conducted as specified in table 3.16.1-1.

APPLICABILITY At all times.

ACTION

a. Any deviations in conducting the radiological environmental monitoring program ca> from that as specified in table 3.16.1-1 shall be documented in the Annual Radiological Environmental Surveillance Report; the reasons for these deviations and any appropriate plans for preventing a recurrence shall be stated.

(Deviations are permitted frou: the required sampling schedule if specimens are unobtainable due to hazardous conditions, unavailability, in lement weather, malfunction of equipment, or other just reasons. If k/ deviations are due to equipment malfunction, strenuous efforts shall be made to complete corrective action prior to the end of.the nexc sampling period).

b. With the confirmedsb> , measured level of radioactivity in an environmental sampling medium as specified in table 3.16.1-1 exceeding the reporting levels of table l 3.16.1-2 when averaged over any calendar quarter, submit to the Commission within 30 days from the end of the affected calendar quarter or after confirmation, whichever is later, a report pursuant to Specification 6.9.1.13. When more than one of the radionuclides in table 3.16.1-2 is detected in the sampling medium, this report shall be submitted if:

a. The requirements for radiological environmental monitoring are the same for both units at the site. Thus, a single program including monitoring, land use survey, and quality assurance serves both units.

b. Defined as a confirmatory reanalysis of the original, a duplicate, or a new sample, as appropriate. The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis.

HNP-RETS-38

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.16.1 MONITORING PROGRAM (Continued) concentration (1) + concentration (2) + ...>1.0 limit level (1) limit level (2)

When radionuclides other than those in table 3.16.1-2 are detected and are the reault of plant effluents, this report shall be submittad if the calculated quarterly dose to an individual is equal to or greater than the calendar quarter limits of Specifications 3.15.1.2, 3.15.2.2, and 3.15.2.3. This report is not required if the measured' level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be described in the Annual Radiological -

Environmental Surveillance B.eport. The levels of naturally occurring radionuclides need not be reported.

c. If adequate samples of milk or grass (during the growing season) from any of the sample locations required by table 3.16.1-1 can no longer be obtained or the availability is frequently or persistently wanting, efforts shall be made to find replacement locations.

The cause of the unavailability and identification of

( the affected locations and the locations (if any) for

\ obtaining replacement samples shall be submitted to the Commission in the next semi-annual radioactive effluent release report. The locations from which samples became unavailable may be deleted; however, any locations from which suitable replacement samples are available shall be added to the program.

d. The requirements of Specification 6.9.1.13(b) do not apply.

SURVEILLANCE REQUIREMENTS 4.16.1 The radiological environmental monitoring samples shall be collected, pursuant to table 3.16.1-1, from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirements of tables 3.16.1-1 and 4.16.1-1.

/

HNP-RETS-39

p A i

I TABLE 3.16.1-1 (SHEET 1 OF 2)

' RADIOLOGICAL ENVIRONMENTAL MONI.TORING PROGRAM !

1 I Exposure Pathway Approximate Number Sampling and and/or Sample of Sample Locations gy Collection Freauency Tvos of Analysis and Freauency

1. Airborne l

t a. Radiolodine and 5 Continuous operation of sampler Radiolodine canister.1-131 weekly.'

Pa rt icu la tes with sample collection as required weekly.

Particulate sampler. Ana lyze for gross beta radioactivity not less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter ,

change and ana lyze for I-131 weekly. Perform gamma Isotopic analysis on affected sample when gross beta activity is >10 times the yearly mean of control

.I: samples. Composite (by location) 4 for gamma Isotopic analysis y qua rte rly.

$ 2. Direct Radiation 35 Qua rterly Comma dose quarterly.

H (n , 3. Wa te rbo rne O a. Surface 2 Composit[samplecollected Gamma isotopic analysis monthly.

monthly. Composite (by location) for tritium analysis quarterly.

b. Ground 2 Qua rterly Tritlue analysis quarterly,

c. Sediment 1 Yea rly. Comma isotopic analysis sarple yearly.

4. Ingestion

a. Milk 4 Bi-weekly Camma Isotopic and 1-131 analyses bi-weekly,

b. fi sh(83 2 Yea rly Camma isotopic analysis on edible portions yearly.

c. Cra ss 3 Monthly during growing Camma isotopic analysis monthly.I*I season.

6

-4

( TABLE 3.16.1-1 (SHEET 2 OF 2)

Table Notations

a. Sample locations are shown on figure and table in the ODCM.

b. Composite samples shall be collected by collecting an aliquot at intervals not exceeding a few hours.

c. Up to three sampling locations within 5 miles and in different sectors will be utilized as available. In addition, one or more control locations beyond 10 miles will be used.

d. Two different commercially or recreationally important _

species shall be sampled.

e. If gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration, a separate analysis for I-131 may be performed.

P

\.

HNP-RETS-41

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.( TABLE 4.16.1-1 (SHEET 2 OF 3)

MINIMUM DETECTABLE CONCENTRATION Table Notations

a. The Minimum Detectable Concentration is the smallest concentration of radioactive material in a sample that will be detected with 95-percent probability with 5-percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

MDC =

E V- 2.22 - Y- exp(-1AT) where:

MDC = the Minimum Detectable Concentration as define pCi per unit mass or volume)

("'

a b

= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E = the counting efficiency (as counts per disintegration)

V = the sample size (in units of mass or volume) 2.22 = the number of disintegrations per minute per picoeurie Y = the fractional radiochemical yield (when applicable) 1 = the radioactive decay constant for the particular radionuclide AT = the elapsed time between sample collection (or end of the sample l

collection period) and time of counting

' (for environmental samples, not plant effluent samples).

(

HNP-RETS-44

( TABLE 4.16.1-1 (SHEET 3 OF 3)

MINIMUM DETECTABLE CONCENTRATION Table Notations The value of sb used in the calculation of the MDC for a detection system shall be based on the actual observed variance of the background coun' ting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the MDC for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present the samples, e.g., _

potassium-40 in milk samples. Typical values of E, V, Y,

, and AT shoul_d be used in the evaluation.

b. This does not mean that only the radionuclides in table 4.16.1-1 are to be detected and reported.

Other measurable and identifiable peaks, together with the above nuclides, shall be identified and reported.

Only manmade radionuclides need be reported.

(

o

(

HNP-RETS-45

RADIOIOGICAL DWIPOWENTAL MONITORIM; 3/4.16.2 IAND USE SURVEY -

(. LIMITING CONDITION FOR OPERATION 3.16.2 A land use survey shall be conducted to identify the location of the nearest milk animal and the nearest permanent residence in each of the 16 meteorological sectors within a distance of 5 miles and the locations of all milk animals within a distance of 3 miles.

APPLICABILITY At all times.

ACTION

a. With a land use survey identifying a location (s) _

yielding a calculated thyroid dose or dose commitment

! greater than the values currently being calculated in Specification 4.15.2.3, submit the new location (s) to the Commission in the next semi-annual radioactive effluent release report. .

b. With a land use survey identifying a location (s)

. yielding a calculated thyroid dose or dose commitment (via the same exposure pathway) 20 percent greater than

( at a location from which samples are currently being

( obtained, add the new location (s) to the program within 30 days if samples are available. The sampling location having the lower calculated thyroid dose may then be deleted from the program. '

c. The provisions of Specification 6.9.1.13(b) , are not ,

applicable.

SURVEILLANCE REQUIREMENTS

[ 4.16.2 The land use survey shall be conducted once per 12 months by door-to-door survey, by visual survey from automobile or aircraft, by consulting local agriculture authorities, or by a combination of these methods as feasible using the information to provide a good survey. Results of the annual survey, as well as any changes in sampling locations, shall be discussed in the annual radiological environmental surveillance report.

i a

HNP-RETS-46

- ~ _ . . _ _. . ___ . , . _ _ _ . _ , . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . _ . . - _ . . _ - . _ _ . _ _ . _ . - .

k RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.16.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.16.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission.

Analyses need to be performed only where the type analysis and sample are the same as that required in table 3.16.1-1.

APPLICABILITY At all times. .

ACTION

a. With analyses not being performed as required above, report the corrective actions taken (to prevent a recurrence) in the Annual Radiological Environmental Surveillance Report.

' b. The provisions of Specification 6.9.1.13(b) are not e applicable.

k SURVEILLANCE REQUIREMENTS 4.16.3 A summary of results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Surveillance Report. In lieu of submission of this data in the annual report, the program code may be provided so that the Nuclear Regulatory Commission may review the data directly.

HNP-RETS-47

ART SLIP SHEET

~

C FIGURE NO.

TURN PAGE FULL PAGE I -

FOLDOUT RESPONSIBLE- AUTHOR EDITOR / COORDINATOR SPECIAL INSTRUCTIONS

(;

fgb bet *U3/4$doa MDP llalb1adIbubD .

_ VERTICAL _ TURN PAGE I

FIGURE -

TABLE s

Form No. 9 405 l

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(

SECTION 3/4 BASES (Similar for Both Units) l l

l l

i i

I l

( INSTRUMENTATION BASES 3/4. 3. 6.9 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the OFFSITE DOSE CALCULATION MANUAL (ODCM) to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, ,

63, and 64 of Appendix A to 10 CFR Part 50.

3 /4.3.6.10 PADIOACTIVE GASEOUS AND EFFLUENT IONI'IORING INSTRINENTATION !

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents., The alarm / trip setpoints for e these instruments shall be calculated in accordance with the

( methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The preewys monitoring instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive c gas mixtures in the main condenser offgas treatment system. The l OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

1

}

l w

l HNP-RETS-1

h RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICIED AREAS l will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within the Section II.A .

design objectives of Appendix I, 10 CFR Part 50, to an individual; and the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope, and its Maximum Permissible Concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

l 3/4.11.1.2 DOSE This specification is provided to implement the requirements of I Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Operation (LCO) implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable" (ALARA). The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I, which state that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision l 1,

'(

i ENP-RETS-2 I

F h RADIOACTIVE EFFLUENTS BASES October 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing that system.

3/4.11.1.3 LIQUID WASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures -

that this system will be available for use whenever liquid effluents require treatment prior to release to UNRESTRICIED AIEAS.

muestretunent. The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept ALARA. This specification implements the requirements of 10 CFR Part 50.36(a), General Design Criterion 60 of Appendix A to 10 CFR Part 50; and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate pottions of the liquid radwaste treatment system (s were specified as a suitable fraction of the guide set forth in i Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix A, Table II (column 2) at the nearest surface water supply in an UNRES'IRICTED AREAS ' ..

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE l

This specification is provided to ensure that at all times the dose rate at the exclusion area boundary from gaseous effluents from all onsite units will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of k

ENP-RETS-3

( RADIOACTIVE EFFLUENTS BASES

. 10 CFR Part 20, Appendix B, Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an UNRESTRICTED AREA, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits _

restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to 5 500 mrem / year to the total body or to s 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to s 1500 mrem / year for the nearest cow to the plant.

This specification applies to the release of gaseous effluents e from all reactors at the site. For units with shared radwaste

( treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to implement therequirements of Sections II.B, III.A, and IV.A of Appendix I, 13 CFR Part 50.

The LCO implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I, assuring that the releases of radioactive material in gaseous effluents will be kept ALARA. The Surveillance Requirements implement the requirements in Section III.A of Appendix I, which state that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substentially underestimated. The dose calculations established in the OFFSITE DOSE CALCULATION MANUAL (ODCM) for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be

?I l(

HNP-RETS-4

( RADIOACTIVE EFFLUENTS BASES consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977; and Regulatory Guide 1.111, Methods for Estimating Atmosphere Transport snd Dispersion of Gaseous Effluents in Routine Releases from Light-Water-cooled Reactors, Revision 1, July

! 1977. The ODCM equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and -

1.111.

t l

l 3/4.11.2.3 DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The LCO implements the guides set forth in Section II.C of l f '. Appendix I. The ACTION statements provide the required

( operating flexibility and at the same time implement the guides i set forth in Section IV.A of Appendix I, assuring that the releases of radioactive materials in gaseous effluents will be kept ALARA. The ODCM calculational methods specified in the i surveillance requirements implement the requirements in Section l III.A of Appendix I, which state that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by the NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision I, October 1977; Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radiciodines, radioactive and

(

e HNP-RETS-5

( RADIOACTIVE EFFLUENTS BASES material in particulate form, and radionuclides other than noble gases are dependent upon the existing radionuclide pathways to man in the UNRESTRICTED AREA. The pathways examined in the development of these calculations are:

a. Individual inhalation of airborne radionuclides

b. Deposition of radionuclides into green, leafy vegetation with subsequent consumption by man

c. Deposition onto grassy areas where milk animals and ,

meat-producing animals graze with consumption of the milk and the meat by man

d. Deposition on the ground with subsequent exposure of man.

3/4.11.2.4 GASEOUS WASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEMS ensures that the systems

(. will be available for use whenever gaseous effluents require treatment prior to release to UNRESTRICTED AREAS. The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA.

This specification implements the requirements of 10 CFR Part 50.36(a), General Design Criterion 60 of Appendix A to 10 CFR Part 50; and design objective Section IID of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions c,f the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3/4.11.2.5 DOSE This specification is provided to meet the reporting i

requirements of 40 CFR 190.

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HNP-RETS-6

i

( RADIOACTIVE EFFLUENTS -

BASES 3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen and oxygen. (Automatic control features are included in the system to prevent the hydregen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners or injection of dilutants to reduce the concentration below the flammability .

-limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60

, of Appendix A to 10 CFR Part 50.

3/4.11.2.7 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total-body k; exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in j the event this effluent is inadvertently discharged without treatment directly to the environment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

3/4.11.3 SOLID RADIOACTIVE WASTE The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to offsite shipping.

This specification implements the requirements of 10 CFR Part 50.36(a) and General Design CriteriaN60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to, ,

waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

HNP-RETS-7

( 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.16 .1- MONITORING PROGRAM The radiological monitoring program required by.this specification provides measurements of radiation and radioactive ~

materials in those exposure pathways and for those radionuclides leading to the highest potential radiation exposures of individuals, resulting from the station operation. This monitoring program thereby supplements the radiological effluent -

monitoring program by measuring concentrations of radioactive materials and levels of radiation that may then be compared with a those expected on the basis of the effluent measurements,and -

modeling of the environmental exposure pathways.

3 / 4. 16 .2 LAND USE SURVEY I

This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made, if required, by the results of l this survey. This survey satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

l( 3/4. 16.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring to '

demonstrate that the results are reasonably valid.

9 e

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k HNP-RETS-8

ART SLIP SHEET c .

FIGURE NO. -

' TURN PAGE FULL PAGE c .

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RESPONSIBLE AUTHOR EDITOR / COORDINATOR

< SPECIAL INSTRUCTIONS

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_ VERTICAL ] TURN PAGE FIGURE TABLE ,

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Form No. 9 405

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ADMINISTRATIVE CONTROLS

( ,, (Similar for Both Units)

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( 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager-Plant Hatch shall be responsible for overall unit operation, except for portions of the Radiological Environmental Monitoring Program as described below and for delegation in writing of the succession to this responsibility during his absence.

"g 6.1.2 The Manager-Environmental Affairs shall be responsible

,c, for sampling the fish and shoreline sediment described in

p. Specification 3/4.16.1 and for conducting the land use survey W described in Specification 3/4 16;2. -

l e 6.1.3 The uni =f Nuvi er "r.gincev shall be responsible for 3 assessing the results of the Radiological Environmental 2 Monitoring Program and for writing the Annual Radiological Environmental Surveillance Report. ,

6 The ...icf Muclear Engineer shall review the proposed changes to g plant systems or equipment, provided that such changes are iden-e tified by the Plant Review Boe.rd (PRB) as having a potential radiological environmental impact.

0 6.1.4 Each of the above mentioned individuals is responsible 8 for the accuracy of the procedures needed to implement his

,]gj responsibilities.

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j 6.2 ORGANIZATION flOFFSITE l *I O

6.2.1 The offsite organization for unit management and

[: technical support shall be as shown on figure 6.2.1-1.

e UNIT STAFF 6.2.2 The unit organization' shall be as shown on figure 6.2.2-1 and as follows:

l a. Each on-duty shift shall be composed of at least the

! minimum shift crew composition shown in table 6.2.2-1.

b. At least one licensed operator shall be in the control room for each reactor containing fuel.

l

(

I HNP-RETS-1

o

( 6.0 ADMINISTRATIVE CONTROLS

c. At least two licensed operators shall be present in the control room for each reactor in the process of startup, for scheduled reactor shutdown, and during recovery from reactor trips.

d. An individual qualified to implement radiation protec-tion procedures shall be onsite when fuel is in either reactor.

e. All CORE ALTERATIONS shall be directly supervised by either a licensed senior reactor operator or senior reac-tor operator limited to fuel handling who has no other ,

concurrent responsibilities during this operation.

f. A fire team of at least five members shall be maintained onsite at all times. The fire team shall not include the minimum shift crew necessary for safe shutdown of Units 1 and 2 or any personnel required for other essential functions during a fire emergency.

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f TABLE 6.2.2-1 (SHEET 1 OF 3)

MINIMUM SHIFT CREW COMPOSITION'A' Condition of Unit 1 and Unit 2 in Reactor Power Operation, HOT STANDBY, or HOT SHUTDOWN Condition Applicable License Category OPERATIONAL CONDITIONS 1, 2, 3 4&5 SOL <c t 2 2

OL < c > 3 2 -

Nonlicensed 3 3 Shift Technical Advisor 1 1 Condition of Unit 1 and Unit 2 in COLD SHUTDOWN Condition or Refuel Mode Applicable License Category OPERATIONAL CONDITIONS 1,2,3 4&5 SOLcc> . 2 1

OLec) 2 2 Nonlicense 3 3 Shift Technical Advisor 1 dbne l

l' l

ENP-RETS-5

( TABLE 6.2.2-1 (SHEET 2 OF 3)

MINIMUM SHIFT CREW COMPOSITION Condition of Unit 1 - No Fuel in Unit 2 Applicable License Category OPERATIONAL CONDITIONS 1, 2, 3 4&5 SOL 1 1cb>

OL 2 1 Nonlicensed 2 1 Shift Technical Advisor 1 None ,

C

a. Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to accommodate unexpected absence of onduty shift crew members, provided immediate action is taken to restore the shift crew composition to within the minimum requirements of table 6.2.2-1.
b. Does not include the licensed senior reactor operator or senior reactor operator limited to fuel handling, supervising CORE ALTERATIONS.
( c. Assumes each individual is licensed on both units.
HNP-RETS-6
( TABLE 6.2.2-1 (SHEET 3 OF'3)
MINIMUM SHIFT CREW COMPOSITION Table Notations OPERATIONAL CONDITION Definition 1 Run mode 2 Start and Hot Standby Mode 3 Shutdown Mode, HOT SHUTDOWN Condition 4 Shutdown Mode, COLD SHUTDOWN Condition 5 Refuel Mode o
4 HNP-RETS-7
l 1
l l
ADMINISTRATIVE CONTROLS
(
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager of Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55.
6.4.2 A training program for fire protection shall be main-
. tained under the direction of the Senior Regulatory Specialist and shall meet or exceed the requirements of Section 27 of the
(- NFPA Code-1975, except for fire protection training sessions which shall be held quarterly.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)
FUNCTION 6.5.1.1 The PRB shall function to advise the General Manager-Plant Hatch on all matters related to nuclear safety.
I COMPOSITION 6.5.1.2 The PRB shall be composed of the:
Chairman <a> General Manager-Plant Hatch l Member Deputy General Manager-Plant Hatch Member Superintendent of Operations Member Superintendent of Maintenance Member Health Physics Superintendent Member Superintendent of Quality Control
a. General Manager to designate chairman from voting PRB membership as necessary.
HNP-RETS-8
ADMINISTRATIVE CONTROLS Member Superintendent of Plant Engineering and Services Member Superintendent of Regulatory Compliance -
Member Representative of Site Quality (Non-Voting) Assurance Department ALTERNATES
! 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB .
activities at any one time.
I MEETING FREQUENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate.
QUORUM 6.5.1.5 The minimum quorum of the PRB necessary for the perform-
-ance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman and -
three members, including alternates. -'
RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:
a. Review of all procedures required by Specification 6.8 and changes thereto, and any other proposed procedures t or changes thereto as determined by the General Manager-Plant Hatd) l to affect nuclear safety.
b. Review of all proposed tests and experiments that affect nuclear safety. ,
c. Review of all proposed changes to Appendix A Technical Specifications.
d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.
e. Investigation of all violations of the Technical Speci-fications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager-Nuclear Generation HNP-RETS-9
( ADMINISTRATIVE CONTROLS or the Vice' President and General Manager-Nuclear Generation and to the Safety Review Board (SRB).
f. Review of events requiring 24-hour written notification to the Commission.
g. Review of unit operations to detect potential nuclear isafety hazards.
h. erformance of special reviews, investigations or an-g lyses, and reports thereon as requested by the c==== 2 e r or the SRB.
$ ~
g 1. Review of the Security Plan and implementing procedures y and submit recommended changes to the SRB.
m h j. Review of the Emergency Plan and implementing procedures g and submit recommended changes to the SRB.
k. Review of any unplsnned onsite release of radioective s material to the environs when such release is in excess 8' '
of 1 Ci, excluding dissolved and entrained gases and
( 8 8
tritium for liquid effluents, and in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous ,
ff p zLts_. _ Also included is the preparing and forward-to the 0;neral-Manager and the SRB reports covering
[ evaluation, recommendations, and disposition of the corrective action to prevent recurrence.
1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL (ODCM).
m. Review of proposed change (s) to plant systems and equip-ment to determine whether the proposed change has a potential radiological environmental impact. Such change (s) will be reported to the Chief Nuclear Engineer.
Manager-Nuclear Engineering and 6.5.1.7 The PRB shall:
a. Recommend in writing to the General Manager-Plant Hatch approval or disapproval of items considered under 6.5.~1.6, (a) through (d),
f
b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6, (a) through
( (e), constitutes an unreviewed safety question.
HNP-RETS-10 i
. . . _ - - ~ ~ _ _ _ _ _ _ . . _ _ . . . _ . _ . . _ _ . _ , _ _ . . , _ . . - . . . . ,
( ADMINISTRATIVE CONTROLS
c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Manager-Nuclear Generation or the Vice President and General Manager-Nuclear Generation and SRB of b !
k disagreement however, the between the PRB and General Menage the Oer.eral MouYwr; all have the responsibility for resoluti @on of those disagreements
s pursuant to 6.1.1. t, I RECORDS @
4 H
6.5.1.8 The PRB shall maintain written minutes of each PRB meeting that, at a minimum, document and the results of all PRB k, activities performed under the responsibility and authority x provisions of these Technical Specifications. Copies shall be 4 provided to the Manager-Nuclear Generation or the Vice President gj and General Manager-Nuclear Generation and the SRB. 6.5.2 SAFETY REVIEW BOARD -
FUNCTION
, 6.5.2.1 The SRB shall function to provide independent review
(; and audit of designated activities in the areas of:
a. Nuclear power plant operations
b. Nuclear engineering
c. Chemistry and radiochemistry
d. Metallurgy
e. Instrumentation and control
f. Radiological safety
g. Mechanical and electrical engineering
h. Quality assurance practices.
COMPOSITION j 6.5.2.2 The SRB shall be composed of a minimum of seven persons t
who as a group provide the expertise to review and audit the I operation of a nuclear power plant. The Chairman, Vice Chair-l man, and other members shall be appointed by the Executive Vice President-Power Supply or designee. The composition of the SRB shall meet the requirements of ANSI N18.7-1976.
,(
HNP-RETS-11 i
I
( ADMINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 All alternate representatives shall be appointed in writing by the absent member to serve on a temporary basis; however, no more than two alternates shall participate in SRB activities at any one time. Alternate representatives shall not have voting privileges.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRB Chairman or Vice Chairman to provide expert advice to the SRB. ,
MEETING FREQUENCY 6.5.2.5 The SRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.
QUORUM f- 6.5.2.6 The minimum quorum of the SRB necessary for the
( performance of the SRB review and audit functions of these Technical Specifications shall consist of the Chairman or Vice Chairman and at least three SRB members. No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW -
6.5.2.7 The SRB shall review:
a. The safety evaluations for changes to procedures, equipment, or systems; and for tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not constitute an unreviewed safety question.
b. Proposed changes to procedures, equipm ent, or systems involving an unreviewed safety question as defined in Section 50.59, 10 CFR.
c. Proposed tests or experiments involving an unreviewed safety question as defined in Section 50.59, 10 CFR.
d. Proposed changes to Technical Specifications or this
! Operating License.
k HNP-RETS-12
ADMINISTRATIVE CONTROLS
e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or internal procedures or instructions having nuclear safety significance.
f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g. Events requiring 24-hour written notification to the Commission.
l
h. Recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect
( nuclear safety.
i. Reports and moeting minutes of the PRB.
AUDITS
(; 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRB. Each inspection or audit shall be per-s:
formed within the specified time interval with:
1. A maximum allowable extension not to exceed 25 percent of the .d.nspection or audit interval.
2. A total maximum combined interval time for any three consecutive inspection or audit intervals not to exceed l 3.25 times the specified inspection or audit interval.
These audits shall encompass:
a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions annually.
l b. The performance, training, and qualifications of the unit staff annually.-
c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety semi-annually.
d. The performance of activities required by the Operational Quality Assurance Program to meet the
( criteria of Appendix B of 10 CFR 50 annually.
HNP-RETS-13
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ADMINISTRATIVE CONTROLS
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e. The Emergency Plan and implementing procedures annually.
f. The Security Plan and implementing procedures annually. j
g. Any other area of unit operation considered appropriate by the SRB or the Executive Vice President-Power Supply.
h. The Fire Protection Program and implementing procedures bi-annually.
i. An independent fire protection and loss prevention in-spection and audit shall be performed annually utilizing -
either qualified offsite licensee personnel or an out-side fire protection firm.
j. An inspection and audit.of the fire protection and loss prevention program shall be performed by an outside qual-ified fire consultant at intervals no greater than 3 years. During the year in which the inspection or audit occurs, the requirements of 6.5.2.8 (i) can be affected concurrently. Specification
( '
k. The Radiological Environmental Monitoring Program and the results thereof annually.
AUTHORITY 6.5.2.9 The SEB shall report to and advise the Executive Vice President-Power Supply on those areas of responsibility spec-ified in sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of SRB activities shall be prepared, approved, and distributed as indicated below:
a. Minutes of each SRB meeting shall be prepared, approved, and forwarded to the Executive Vice President-Power Supply within 14 days following each meeting.
b. Reports of reviews encompassed by section 6.5.2.7 shall be prepared, approved, and forwarded to the Executive Vice President-Power Supply within 14 days following completion of the review.
c. Audit reports encompassed by section 6.5.2.8 shall be forwarded to the Executive Vice President-Power Supply and to the management positions responsible for the
(' areas audited within 30 days after the audit completion.
ENP-RETS-14
( ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
a. The Commission shall be notified and/or a report submit-ted pursuant to the requirements of Specification 6.9./,
b. Each REPORTABLE OCCURRENCE requiring 24-hour notifica-tion to the Commission shall be reviewed by the Plant Review Board and submitted to the SRB and the Vice President and General Manager-Nuclear Generation. ,
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
, a. The unit shall be placed in at least HOT SHUTDOWN within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
(' b. The safety limit violation shall be reported to the Commission, the Vice President and General Manager-Nuclear Generation and to the Safety Review Board (SRB) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
c. A safety limit violaticn report shall be prepared. The report shall be reviewed by the Plant Review Board.
This report shall describe applicable circumstances preceding the violation; effects of the violation upon facili'ty components, system, or structures; and corrective action taken to prevent recurrence,
d. The safety limit violation report shall be submitted to the Commission, the SRB, and the Manager-Nuclear Gener-ation or the Vice President and General Manager-Nuclear Generation within 14 days of the violation.
! 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978
b. Refueling operations i
HNP-RETS-15 i
ADMINISTRATIVE CONTROLS
c. Surveillance and test activities of safety-related equipment
d. Security Plan implementation 4
e. Emergency Plan implementation
f. Fire Protection Program implementation
g. PROCESS CONTROL PROGRAM implementation ha h. OFFSITE DOSE CALCULATION MANUAL implementation -
E y 6.8.2 Each procedure of 6.8.1 (above) and changes thereto shall 3 be reviewed by the Plant Review Board (PRB), approved by the 7 Cer.erel "irr;cr prior to implementation, and reviewed <
gI periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 may be made E provided:
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( 0 a. The intent of the original procedure is not altered. u
(' E 8 b. The change is approved by two members of the plant -
{
management staff, at least one of whom holds a Senior [
Reactor Operator's License on the affected unit. ,
e
c. The change is documented, reviewed by the PRB, and M approved by t M enemel Menagee within 14 days of 3 implementation. w 3
x 6.8.4 Proposed changes to procedures for implementing the u responsibilities specified in section 6.1.2 shall be reviewed 75 and approved by the Manager-Environmental Affairs. Proposed changes to procedures for implementing the responsibilities E specified in section 6.1.3 shall be reviewed and approved by the C A hiEf-Nuc1TRr-Engineer. When deemed appropriate by the
( Manager-Environmental Affairs or the Ghiof Wuvia.s Engin , .h i
such proposed changes shall also be reviewed by the Safety g Review Board prior to implementation. -
3 6.9 REPORTING REQUIP _EMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES h
, 6.9.1 In addition to the applicable reporting requirements of
'( Title 10 CFR, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement, E
unless otherwise noted.
HNP-RETS-16
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( ADMINISTRATIVE CONTROLS i
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following receipt of an operating i license; unendment to the license involving a planned increase in power level; installation of fuel that has a different design or has been manufactured by a different fuel supplier; and modifications that may have significantly altered the nuclear,' .
l thermal, or hydraulic performance of the plant. l l 1 6.9.1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report and shall include .
a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifi- '
l cations. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within 90 days following completion of the startup test program; 90 days kf following resumption or commencement of commercial power operation; or 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test l program, the resumption or coma.encement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS <as 6.9.1.4 Annual reports covering the activities of the unit, as described below, for the previous calendar year shall be sub-mitted prior to March 1 of each year.
6.9.1.5 Reports required on an annual basis shall include:
I
a. A tabulation on an annual basis of the number of station, utility, and other personnel, including l
contractors, who receive exposures greater than 100 l mrem / year and their associated man rem exposure according to work and job functions, e.g., reactor operations and surveillance, inservice inspection,
a. A single submittal may be made for a multiple-unit station.
( '
The submittal should combine those sections common to all units at the station.
HNP-RETS-17
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( ADMINISTRATIVE CONTROLS 1
l routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measure-ments. Small exposures totaling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole-body dose received from external sources shall be assigned to specific major work functions.
b. Any other unit-unique reports required on an annual basis. ,
i ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT
6.9.1.6 Routine radiological environmental surveillance reports covering the radiological environmental surveillance activities related to the plant during the previous calendar year shall be submitted prior to May 1 of each year. A single report may ful-fill this requirement for both units.
6.9.1.7 The Annual Radiological Environmental Surveillance (7 '
! Report shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental I
surveillance activities for the reporting period, including (as appropriate) a comparison with preoperational studies, opera-tional controls, previous environmental surveillance reports, and an assessment of any observed impacts of the plant operation on the environment. The reports shall also include the results of the land use surveys required by Specification 3,16.2 and the results of licensee participation in the interlaboratory compari-son program required by Specification 3.16.3.
The Annual Radiological Environmental Surveillance Report shall include summarized and tabulated results in the format of table 6.9.1.7-1 of all radiological environmental samples taken during the report period, with the exception of naturally occurring ra-l dionuclides which need not be reported. In the event that some results are not available for inclusion with the report, the re-port shall be submitted, noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as practicable in a supplementary report.
The reports shall also include the following:
a. Summary description of the radiological environmental l
monitoring program
'( .
b. Map of all sampling locations as keyed to a table indicating distances and directions from main stack.
HNP-RETS-18
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(- ADMINISTRATIVE CONTROLS
c. Results of the licensee participation in the Inter-laboratory Comparison Program.
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTsa>
6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of opera-tion shall be submitted within 60 days after January 1 and July 1 of each year.
Any changes to the ODCM shall be submitted with the next semi-annual report in which the change (s) was made effective. .
In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the monthly operating report for the period in which the evaluation was reviewed and accepted by the Plant Review Board.
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a. A single submittal may be made for a multiple-unit station.
. The submittal should combine those sections that are common to
(' all units at the station; however, the submittal shall specify the releases of radioactive material from each. unit.
ENP-RETS-19 e
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r~. p ,n TABLE 6.9.1.7-1
' ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Edwin 1. Hatch Nuclea r Plant Docket No. 50-321. 50-366 Location of Facility Applina County. Georola Reporting Period Location of Highest Annual Mean Medium or Type and Pathway Sampled Total Number Minimum All Indicator Name, Control Number of i
(Unit or of Analyses Detectable Location Distance, Mean Locations REPORTABLE Mea surement ) Pe rfo rmed Concent ra t ionI *I MeanRangegI and Direction Rance I*I Mean ptance OCCURRENCES m
2:
m 8
b d
in 8
M o
a. Minimum Detectable Concentration is defined in table notation a of table 4.16.1-1, Spect ricat!on 4.16.1 of Unit 1
b. Mean and range based upon detectable measurements only. Fraction or detectable measurements at specirled locations is indicated in parentheses, a
( ADMINISTRATIVE CONTROLS 6.9.1.9 The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous ef-fluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Ra-dioactivity in Solid Wastes and Releases of Radioactive Mater-ials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June 1974, with data summa-rized on a quarterly basis following the format of Appendix B thereof.
The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall include an annual summary of meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction atmospheric stability and
precipitation (if measured) on magnetic tape or in the form of joint frequency distributions of wind speed,-wind direction, and ,
atmospheric stability. This same report shall include an assess- -
ment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. All assumptions used in making these assessments, i.e., specific activity, exposure time, and loca-k'. , tion, shall be included in these reports. Historical annual average meteorological conditions or meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and mea-surement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The Radioactive Effluents Release Report shall include the following information for each type of solid waste shipped offsite during the report period:
a. Container volume
b. Total curie quantity (specify whether determined by measurement or estimate)
c. Principal radionuclides (specify whether determined by measurement or estimate)
d. Type of waste, e.g., spent resin, compacted dry waste, evaporator bottoms
e. Type of container, e.g., LSA, type A, type B, large quantity k f. Solidification agent, e.g., cement.
HNP-RETS-21
( ADMINISTRATIVE CONTROLS i
l The Radioactive Effluent Release Report shall include (on a
quarterly basis) unplanned releases from the site to unre-stricted areas of radioactive materials in gaseous and liquid effluents that'were in excess of 1 Ci, excluding dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous releases.
i
! The Radioactive Effluent Release Report shall include any changes to the PROCESS CONTROL PROGRAM made during the reporting period.
MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Direc-tor, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES l 6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.l.12 and 6.9.1.13 including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occur-rence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date. ,
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and confirmed by telegraph, mail-gram, of facsimile transmission to the* Director of the Regional Office or his designee no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a Licensee Event Report form. Information provided on this form shall be supplemented, as needed, by addi-tional narrative material to provide a complete explanation of the circumstances surrounding the event.
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a. Failure of the reactor protection system or other systems subject to limiting safety system settings to
, initiate the required protective function by the time a
( monitored parameter reaches the setpoint specified as i
HNP-RETS-22
( ADMINISTRATIVE CONTROLS ...
the limiting safety system setting in the Technical i
Specifications or failure to complete the required protective function.
b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least con-servative aspect of the limiting condition for operation established in the Technical Specifications.
c. Abnormal degradation discovered in fuel cladding, reac-tor coolant pressure boundary, or primary containment. ;
d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady-state conditions during power operation greater than or equal to 1-percent Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the Technical Specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned
'( reactivity insertion of more than 0.5-percent Ak/k; or
( occurrence of any unplanned criticality.
e. Failure or malfunction of one or more components that prevents or could prevent, by itself, the fulfillment of the functional requirements of the system (s) used to cope with accidents analyzed in the Safety Analysis i Report.
f. Personnel error or procedural inadequacy that prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the Safety Analysis Report.
g. Conditions arising from natural or manmade events that, as a. direct result of the event, require unit shutdown, operation of safety systems, or other protective measures required by the Technical Specifications.
h. Errorn discovered in the transient or accident analyses or in the methods used for such analyses as described in the Safety Analysis Report or in the Technical Specifications bases that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
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HNP-RETS-23 l
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( ADMINISTRATIVE CONTROLS
1. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the Safety Analysis Report or the Technical Specifications bases; or dis-covery during unit life of conditions not specifically considered in the Safety Analysis Report or Technical Specifications that require remedial action or correc-tive measures to prevent the existence or development of an unsafe condition.
THIRTY-DAY WRITTEN REPORTS 6.9.1.13 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days of the occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the form shall be supplemented, as needed, by additional narrative material to provide a complete explanation of the circumstances surrounding the event.
. a. Reactor protection system or engineered safety feature instrument settings found to be less conservative than those established by the Technical Specifications but not preventing the fulfillment of the functional requirements of affected systems.
b. Conditions leading to operation in a degraded mode per-mitted by a Limiting Condition for Operation or plant shutdown required by a Limiting Condition for Operation.
c. Observed inadequacies in the implementation of admini-strative or procedural controls that threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
d. Abnormal degradation' of systems, other than those specified in 6.9.1.13(c), designed to contain radio-active material resulting from the fission process.
6.9.2 Special reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement within the time period specified for each report.
HNP-RETS-24
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c. TABLE 6.9.2-1 SPECIAL REPORTING REQUIREMENTS Tech Spec Area Reference Submittal Date
.t Primary Containment 4.7.A Within 3 months follow-Leak Rate Tests ca' . , ing conduct of test Secondary' Containment 4.7.C Within 3 months Rollow-Leak Rate Tests <b' ing conduct of te*st Primary Coolant 14.6.C 5 years <c>
Leakage to Drywell .
Inser'vice' Inspection 4.6.K 5 years <c i Evaluation Reactor Coolant 4.6.F Within 30 days of the Radioactivty in occurrence Excess of Specified ,
Limits
Notes:
/.
s a. Each integrated leak rate test of the primary containment shall be the subject of a summary technical report including results of the local leak rate *.ests since the last report.
The report as described in the 10 CFR Part 50, Appendix J,
. Primary Reactor Containment Leakage Testing for, Water-Cooled Power Reactors, shall include data, analysis, 'and interpre-tations of the results that demonstrate compliance in meeting the specified leak rate limits.
b. Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This
report should include data on wind speed, wind direction,
outside and inside temperatures'during the test, concurrent reactor building pressure,'and emergency ventilation flowrate.
c. The report shall be submitted within the period of time' listed based on the commercial service date as the starting period. 9
d. , cords $' gase us j~ anO quid 7ra loactiv7m e rl al' leased to the viron
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HNP-RETS-26
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k ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10 CER, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least 5 years:
a. Records and logs of unit operation covering the time interval at each power level
b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety
c. All REPORTABLE OCCURRENCES submitted to the Commission
d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications
/ e. Records of changes made to the procedures required by Specification 6.8.1
f. Records of radioactive shipments ;
g. Records of sealed source and fission detector leak tests and results
h. Records of annual physical inventory of all sealed -
source material of record. s 6.10.2 The following records shall be retained for the duration -
of the unit Operating License:
a. Records and drawing changes reflecting unit design modifications made to systems and equipssn? described in '
the Final Safety Analysis Report -
b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories
c. Records of radiation exposure for all individuals entering radiation control areas.
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TABLE 6.9.2-1 SPE IAL REPORTING REQUIREMENTS Area Tech S ec Refe nce
/
Submitta Date Primary Cont.inment .7.A Within 3 m/onths follow-Leak RateNT sts <a' in'
< ,/ g conduct of test, S'econdar Containment 4.7.C ,-' Wi 3 months fo'llow-Leak Ra e Tes'ts ,/ n conduct of,,t'est ,
i Prim y Coolan / 4.6. years <c> [
1. _ , _ ' Lea ago to Drywel'1 / p',
~
'I,; J'nservice Inspec lo' .- 6 . K 5 years $' [
/ Evaluation '
s. ~
, ,- ,/
Reactor Cool t 4. . Witl51,n'30 days of Mhe Radioactivt in , occ trence
\- '
Excess of pecified / / .
Limits /
Notes.
[
,ak rate test f the primar containment.'l
a. jEach.inte rated s- - shallihe the su ect of a su ary technica report including result .of the ocal les.k r e hests sine the last report.
The r ort as, described i he 10gCFR P t 50, Append'x J, Prim y Rea [or Containme,n 7 t Leakag T ting for Wate -Cooled Pow r Reae rs,'shall igclude data, alysis, and terpre-ta ions o /the result that demons a't complianc in eting he specifie leak rate 1 its
/ -
b. Each tegrated 1'k rate test f the second y containment shal be the sub ect of a su ary technical eport. This rep rt should clude data o wind speed, ind direction ou side'and i side tempera res s during t
~
tesh concurre,nt
- actor bui ing pressure 'and emergen ventilation lowrate.,'
. The report shall be s mitted wit 'n the period of ime s' ' , listed based on the commercial s9 vice date as the sthrting o_e ri od . (< \
} m.
, d. Records of gaseous and liquid radioactive material released to the environs
e. Records of reactor tests and experiments
( f. Records of training and qualification for current members of the unit staff i
'C HNP-RETS-26
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- g. Records of inservice inspections performed pursuant to these Technical Specifications
h. Records of Quality Assurance activities required by the Quality Assurance Menual
i. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CER 50.59
j. Records of PRB and Safety Review Board meetings.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CER Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH-RADI ATION AREA ' ^_~": ^"J.L )
6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CER 20, each high-
/ radiation area in which the intensity of radiation is greater
\ than 100 mrem / hour but less than 1000 mrem / hour shall be bar-ricaded and conspicuously posted as a high-radiation area, and I; '
entrance thereto shall be controlled by requiring issuance of a o
Radiation Work Permit (RWP).<a> Any individual or group of individuals permitted to enter such areas shall be provided with or r.ccompanied by one or more of the following:
t
a. A radiation monitoring device which continuously
! indicates the radiation dose rate in the area
b. A radiation monitoring dev' ice which continuously inte-grates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after l the dose rate level in the area has been established and personnel have been made knowledgeable of them.
a. Health Physics personnel or personnel escorted by Health Physics personnel, in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement
( during the performance of their radiation protection duties,
!' provided they comply with approved radiation protection
! procedures for entry into high-radiation areas.
j HNP-RETS-27
k' c. An individual qualified in radiation protection pro-cedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the RWP.
6.12.2 The requirements of 6.12.1, shall also apply to each high-radiation area in which the intensity of radiation is
/00D- greater than 100 mrem / hour. In addition, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the shift supervisor on duty or the Plant Health Physicist.
6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT Plant Hatch shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
a. Provisions establishing preventive maintenance and periodic visual inspection requirements
b. System leak test requirements, to the extent permitted by system design and radiological conditions, for each ,
system at a frequency not to exceed refueling cycle intervals. The systems subject to this testing are residual heat removal, core spray, reactor water cleanup, HPCI, and RCIC.
1 j 6.14 IODINE MONITORING I
Plant Hat:h shall implement a program which will ensure the I
capability to accurately determine the airborne iodine concen-tration in vital areasca> under accident conditions. This l program shall include the following:
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a. Training or personnel
b. Procedures for monitoring
c. Provisions for maintenance of sampling and analysis equipment.
a. Areas requiring personnel access for establishing HOT (i EHUTDOWN condition.
HNP-RETS-28
ART SLIP. SHEET FIGURE NO.
ZTURN PAGE j
-I ZFULL PAGE ZFOLDOUT RESPONSIBLE AUTHOR EDITOR / COORDINATOR
( SPECIAL INSTRUCTIONS
} }
Rup-un 1 aa Our Z VERTICAL ZTURN PAGE FIGURE TABLE Form Nc. 9-405
0
' ENVIRONMENTAL TECHNICAL SPECIFICATIONS EDWIN I. HATCH NUCLEAR PLANT UNITS 1 AND 2
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k TABLE OF CONTENTS Section Page 1.0 Definitions 1 2.0 (Section Deleted) 3.0 Environmental Monitoring 3 3.1 Nonradiological Monitoring 3 3.1.1 Abiotic 3 3.1.2 Biotic 3 4.0 Special Surveillance and Study Activities 5 4.1 Erosion Control Inspection 5 4.2 Unusual or Important Events Requirements 5 4.3 Exceeding Limits of Other Relevant Permits 5 5.0 Administrative Controls 7 5.1 Responsibility
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5.1.1 General Manager 7 5.1.2 Manager-Environmental Affairs 7 5.1.3 General Manager-Quality Assurance 7 and Radiological Health and Safety 5.2 Organization 7 5.3 Review and Audit 8 5.3.1 Independent Review 8 5.3.2 Audit Responsibility 9 l
5.4 State and Federal Permits and Certificates 9 5.5 Procedures 9 5.5.1 Environmental Programs Description 10 Document 5.5.2 Quality Assurance of Program 10 Results 5.5.3 Compliance with Procedures 11 5.5.4 Changes in Procedures, EPDD, 11 and Station Design or Operation 5.5.5 Consistency with Initially 12 Approved Programs 5.5.6 NRC Authority to Require Revisions 13 I
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Section Page 5.6 Plant Reporting Requirements 13 5.6.1 Routine Reports 13 5.6.2 Nonroutine Reports 14 5.6.3 Changes in Environmental Technical 15 Specifications and Permits 5.7 Records Retention 16 5.7.1 Life-of-Plant Records 16 5.7.2 Five-Year Records 16 5.7.3 Records Storage 16 r
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a LIST OF TABLES .
Table Number Title 2.1-1 Radioactive Liquid Waste Sampling and Analysis 2.1-2 Radioactive Gaseous Waste Sampling and Analysis 2.1-3 BWR-Liquid Waste System - Location of Process and Effluent Monitors and Samplers Required by Environmental Technical Specifications 2.1-4 BWR-Gaseous Waste System - Location of Process and Effluent Monitors and Samplers Required by Environmental Technical Specifications 2.1-5 Average Energy Per Disintegration 3.2-1 Radiological Environmental Monitoring
( Program 3.2-2 Detection Capabilities for Environmental Sample Analysis 3.2-3 Reporting Levels for Nonroutine Operating Reports l .
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LIST OF FIGURES Figure Number Title 3.2-1 Location of Radiological Environmental Monitoring Stations 5.2-1 Organization Structure Related to Environmental Activities l
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l 1.0 Definitions Aerial Remote Sensing - The measurement or acquisition from aircraft or spacecraft of information on some property of an object or phenomenon by a recording device that is not in physical or intimate contact with the object or phenomenon under study. The technique employs such devices as the camera, radio frequency receivers, and radar system.
Annually - Once per calendar year at intervals of 12 calendar months, 130 days. ;
Biweekly - Once svery 2 weeks, i 4 days. !
I Ground Truth or Ground Data Surveys - Supporting data collected on the ground and information derived therefrom,
, as an aid to the interpretation of a remotely recorded survey, such as aerial imagery. To the extent possible, this should be performed concurrently with the airborne surveys. -
l Infrared, Photographic - Pertaining to or designating that portion of the electromagnetic spectrum with wavelengths just beyond the red end of the visible spectrum; generally defined as being from 0.7 to about 1.0 um or the useful
(. limits of film sensitivities.
Monthly - Once during each calendar month at 30-day intervals, 16 days.
- Normal Operation - Operation of either unit at the station at greater than 5 percent of rated thermal power in other than a safety or power emergency situation.
NPDES Permit - The National Pollutant Discharge Elimination System Permit No. GA 0004120 (or its subsequent revisions) issued by the State of Georgia, Department of Natural Resources, Environmental Protection Division to Georgia Power Company. This permit authorizes Georgia Power Company to discharge controlled waste water from HNP into the waters of the Altamaha River.
Quarterly - Once during each successive 3-month period of i the calendar year, counting from January 1, at 13-week l
intervals, + 14 days.
Scale The ratio of a distance on a photograph or map to its corresponding distance on the ground.
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k. Semi-Annually - Once during each successive 6-month period of the calendar year, counting from January 1, at 6-month intervals, i 21 days.
Spectral Band - A width, generally expressed in wavelength or frequency, of a particula _r portion of the electromagnetic spectrum. A given sensor, e'. g . , radiometer detector or camera film, is designated to measure or to be sensitive to energy received from that part of the spectrum.
Station and Unit - Station refers to HNP-Units 1 and 2.
Unit refers only to HNP 1 or HNP 2, as defined by its usage. Only the individual unit's instrument is applicable to specifications applied to that unit.
Unusual or Important Event - An event that causes
potentially significant environmental impact or that could be of public interest concerning environmental impact from plant operation.
Weekly - Once during each calendar week at 7-day intervals, 12 days.
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i ENP-RETS-2
k 3.0 Environmental Monitoring The objective of the environmental monitoring program is to determine the effect of plant operation on the environment.
'3 .1 Nonradiological Monitoring
.3.1.1 Abiotic 3.1.2 Biotic s
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, 3.1.2.2 Terrestrial I l
3.1.2.2.1 Aerial Remote Sensing Environmental Monitoring Requirement Plant communities of the site shall be aerially photographed to detect and assess the significance of damage, or lack thereof, related to deposition of cooling tower drift.
This monitoring program shall be conducted as specified in the program description developed by the licensee in accordance with l section 5.6.1. The program shall commence at the time of initial commercial operation of Unit 2 and shall continue for at '
least 2 years, after which the licensee may request modification or termination of this monitoring requirement in accordance with section 5.6.3.
! Action i
Results of the monitoring conducted under this program shall be summarized, analyzed, interpreted, and reported in accordance i
with section 5.6.1.
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The licensee shall record the following information for each flight: date and time of photographs, film type, spectral band, and scale of the photographs.
Bases Impacts that cause stress to vegetation may occur as a result of cooling tower drift deposition. Reconnaisance and aerial photographic inspection of plant communities in the drift field are the methods recommended for detecting possible adverse effects of drift deposition on vegetation.
As discussed in the Edwin I. Hatch Nuclear Plant, Unit No. 2, FES-OL, no effects on vegetation have been observed to result from operation of the Unit 1 cooling towers. However, a
, continuation of the current Unit 1 monitoring program will serve to verify the FES-OL conclusion that it is unlikely that drift
effects on vegetation will be observed for Unit 2.
i HNP-RETS-4
4.0 Special Surveillance and Study Activities 4.1 Erosion Control Inspection 4.2 Unusual or Important Events Requirements Requirements The licensee shall be alert to the occurrence of unusual or important events. Unusual or important events are those that cause potentially significant environmental impact or could be of public interest concerning environmental impact from plant operation. The following are examples: unusual or important bird impaction events on cooling tower structures or meteorological towers, onsite plant or animal disease outbreaks, unusual mortality of any species protected by the Endangered Species Act of 1973, fish kills near the HNP site, and significant violations of relevant permits and certifications.
Action Should an unusual or important event occur, the licensee shall make a prompt report to the NRC in accordance with section
(( S.6.2.
Bases Prompt reporting to the NRC of unusual or important events, as described, is necessary for responsible and orderly regulation of the nation's system of nuclear power reactors. The information thus provided may be useful or necessary to others concerned with the same environmental resources. Prompt knowledge and action may serve to alleviate the magnitude of environmental impact or to place it into a perspective broader than that available to the licensee. The NRC also has an obligation to be responsive to inquiries from the public and the news media concerning potentially significant environmental events at nuclear power stations.
1 4.3 Exceeding Limits of Other Relevant Permits Requirements The licensee shall notify the NRC of occurrences exceeding the limits cpecified in relevant permits and certificates issued by other Federal, State, and local agencies that are reportable to the agency that issued the permit. This requirement shall apply only to topics of NEPA concern within the NRC area of f
responsibility as identified in the Environmental Technical Specifications (ETS).
HNP-RETS-5
This requirement shall commence with the date of issuance of the operating license for Unit 2 and continue until approval for modification or termination is obtained from the NRC in accordance with section 5.6.3.
Action The licensee shall make a report to the NRC in accordance with section 5.5.2 in the event of a reportable occurrence of exceeding a limit specified in a relevant permit or certificate issued by another Federal, State, or local agency.
Bases The NRC is required under NEPA to maintain an awareness of environmental impacts causally related to the construction and operation of facilities licensed under its authority. Further, some of the ETS requirements are couched in terms of compliance with relevant permits, e.g., the NPDES permit, issued by other licensing authorities. The reports of exceeding limits of relevant permits also alert the NRC staff to environmental problems that may require mitigative action.
HNP-RETS-6 l . . _ _ . .. __
5.0 Administrative Controls l This section describes administrative and management centrols established to implement the Environmental Technical Specifications (ETS). Measures specified in this section include assignments of responsibility, review and audit functions, procedures, and reporting requirements.
Corporate responsibility for implementing the ETS and for assuring that the station is operated in such a way as to provide protection for the environment rests with the Executive Vice President-Power Supply.
Responsibilities for compliance with the ETS and for the environmental monitoring program required by the ETS are given below.
Independent audit shall be provided, as discussed in section 5.3.2,.by the General Manager-Quality Assurance and Radiological Health and Safety.
5.1 Responsibility 5.1.1 The General Manager-Plant Hatch is responsible for the
(. environmental monotoring programs. The General Manager-Plant Hatch is also responsible for implementing the special surveil-
-lance activities described in section 4.
5.1.2 The Manager-Environmental Affairs is responsible for the environmental monitoring programs specified in sections 3 and
4. The Manager-Environmental Affairs is responsible for coordinating these programs with appropriate groups.
5.1.3 The General Manager-Quality Assurance and Radiological Health and Safety is responsible for assuring that the periodic' audits of plant operations and the environmental monitoring .
activities to ensure conformance with the ETS are conducted.
5.2 organization A chart showing company organization relative to environmental matters is presented in figure 5.2-1. Changes affecting company organization depicted in figure 5.2-1 will not require NRC approval prior to implementation, but such changes shall be reported to NRC.
HNP-RETS-7 4
,,.,,..--.-------,-.,,_,.-,_,,-,,_.,,n_,,,,,,,,---,--,,,,,,-.-.,.,--.p..-
, ,,--,_,, , ,-,,,,, , , , m , . , , - , - - - . , ,wn,m,
C 5.3 Review and Audit 5.3.1 Independent Review 5.3.1.1 The Manager-Environmental Affairs shall review the following:
a. The conduct of the environmental monitoring programs, on a routine basis, to ensure that the specifications in
sections 3 and 4 are being implemented.
b. Proposed changes to plant systems or equipment, provided such changes are identified by the Plant Review Board (PRB) as having a potential adverse environmental impact.
c. Procedures for implementing the responsibilities specified in section 5.1.2 and proposed changes thereto.
d. Proposed changes to the Environmental Technical Specifications (ETS).
e. Proposed changes to the Environmental Programs Description Document.
('
5.3.1.2 The Safety Review Board (SRB) shall review the following:
a. Proposed changes to the ETS.
b. Violations of ETS to determine whether adequate corrective action is being taken to prevent recurrence.
c. Procedures or changes thereto (which could affect the monitoring of station operation) that may be considered by the Manager-Environmental Affairs or the PRB to be appropriate for SRB review.
5.3.1.3 The PRB shall review the following:
a. Procedures for implementing the responsibilities specified in section 5.1.1 and proposed changes thereto.
b. Proposed changes to the ETS.
HNP-RETS-8
5.3.2- Audit Responsibility 5.3.2.1 The General Manager-Quality Assurance and Radiological Health and Safety is responsible for an audit, conduct _ed -Plant Hatch annually, of the activities of the General Managerfand the Manager-Environmental Affairs, related to compliance with the ETS.
5.3.2.2 Audits of facility activities shall be performed
~
l annually under the cognizance of the SRB to ensure conformance of facility operation to provisions of the ETS.
5.4 State and Federal Permit and Certificates Section 401 of PL 92-500, the Federal Water Pollution Control Act Amendments of 1972 (FWPCA), requires any applicant for a Federal license or permit to conduct any activity that may l result in any discharge into provisions of Sections 301, 302, 306, and 307 of the FWPCA. Section 401 of PL 92-500.further
requires that any certification provided under this section shall set any effluent limitations and other limitations and l monitoring requirements necessary to assure that any applicant for a Federal license or permit will comply with the applicable limitations. Certifications provided in accordance with Section
- - 401 set forth conditons on the Federal license or permit for
!(- which the certification is.provided. Accordingly, the licensee r shall comply with the requirements set forth.in the currently applicable 401 certification, and amendments thereto issued to the licensee by the Georgia Environmental Protection Division. In accordance with the provisions of the Georgia Water Quality Act, the EWPCA and the rules and regulations promulgated pursuant to each of these acts, We Georgia Environmental Protection Division, under authority delegated by the U.S. EPA, issued NPDES permit No. GA 0004120 to the licensee. %e NPDES l permit authorizes the licensee to discharge from HNP Units 1 and 2 to the Altamaha River in accordance with effluent limitations, monitoring requirements, and other conditions stipulated in the permit, effective August 1, 1983, through December 5, 1987.
Subsequent revisions to the certifications will be accommodated in accordance with the provisions of section 5.6.3.
5.5 Procedures Detailed written procedures, including applicable checklists and instructions, shall be prepared and followed for all activities involved in implementing the ETS. 3-r-s c e i n e e s h e l l a p p l y t o -
(
HNP-RETS-9
All procedures shall be maintained in a manner convenient for review and inspection. Procedures that are the responsibility of the General Manager-Plant _ Hatch shall be kept at theylant.
Procedures that are the responsIEility of the Manager-Envirodmental Affairs shall be kept at the Georgia Power Company General Office.
5.5.1 Environmental Programs Description Document Based on these procedures, the licensee shall prepare and follow an Environmental Programs Description document (EPDD) describing i
the monitoring programs that are required by section 3.1. This document shall include descriptions of sampling equipment locations, frequencies and number of replications, sample analyses, data recording and storage, and instrument calibrations where appropriate. These program descriptions shall be approved by the NRC, and subsequent modifications to these programs shall be made by the licensee in accordance with sections 5.5.4 and 5.5.5. .
! 5.5.2 Quality Assurance of Program Results l
Procedures shall be established to assure the quality of ETS program results, including analytical measurements. These
-procedures shall document the program in policy directives; designate responsible organizations or individuals; describe purchased services; e.g., contractual laboratory or other contract services; and provide for audits or results and procedures by licensee personnel. In addition, these quality assurance procedures shall provide for systems to identify and correct deficiencies in technical monitoring programs or related administrative activities, to investigate anomalous or suspect results, and to review and evaluate program results.
l f
l HNP-RETS-10
0 l
5.5.3 Compliance with Procedures In addition to the procedures specified in section 5.5, the station operating procedures shall include provisions to ensure that each unit and all its systems and components are operated in compliance with the conditions established in the Environmental Technical Specifications (ETS).
5.5.4 Changes in Procedures, EPDD, and Station Design or C,eration Changes in the procedures, EPDD, and station design or operation may be made in accordance with section 5.3 and subject to conditions described below:
a. The licensee may make changes in the station design and operation; make changes in the EPDD developed in accordance with section 5.5.1; and conduct tests and experiments not described in the EPDD without prior NRC approval, unless the proposed change, test, or experiment involves either a change-in the objectives of the ETS, an unreviewed environmental question of substantial impact, or affects the requirements of '
section 5.5.5.
(
b. A proposed change, test, or experiment shall be deemed to involve an unreviewed environmental question if it concerns:
I
1. A matter which may result in a significant increase in any adverse environmental impact previously
. evaluated in the final environmental statement, as modified by staff's testimony at the hearing, supplements thereto, environmental impact appraisals, or in initial or final adjudicatory decisions.
2. A significant change in effluents or power level.
i
3. A matter not previously reviewed and evaluated in the documents specified in a. above which may have a significant adverse environmental impact.
i
c. The licensee shall maintain records of changes to the EPDD and to facility design or operation made pursuant to this section. The licensee also shall maintain records of tests and experiments carried out pursuant to paragraph a. of this section. These records shall include a written evaluation that provides the bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question of
( substantive impact, or does not constitute a change in HNP-RETS-11
._ __ _ _ _ _ _ - . _ _ . _ _ _ _ _ _ _ _ _ _ . _ . . _ .__ . _ . - . ~ . _ . _ _ _ _ _ _ . _ . _ _ _
p the objectives of the ETS, or does not affect the requirements of section 5.5.5. The licenses shall furnish to the NRC, annually or at such shorter intervals as may be specified in the license,'a report containing descriptions, analyses, interpretations, and evaluations of such changes, tests, and experiments.
d. Changes in the EPDD that affect sampling frequency, location, gear, or replication shall be reported to the NRC within 30 days after their implementation, unless otherwise reported in accordance with section 5.6.3.
Changes that affect sampling technique or data recording and storage shall be reported to the NRC at the end of the year. These reports shall provide a description of the changes made, the reasons for making the changes, and an evaluation of the environmental impact of these changes.
e. Proposed changes or modifications to plant systems or equipment shall be reviewed in accordance with section 5.3.
f. Proposed changes to procedures for implementing the responsibilities specified in section 5.1.1 shall be reviewed and approved by the Plant Review Board (PRB).
{s Temporary changes to the procedures that do not change the intent of the original procedure may be made with the concurrence of two individuals holding senior reactor operator licenses. Such changes shall be documented and subsequently reviewed by the PRB and approved by the General Manageryon a tinely basis.
-Plant Hatch
g. Proposed changes to procedures for implementing the responsibilities specified in section 5.1.2 shall be reviewed by the staff of Environmental Affairs. Such proposed changes shall subsequently be reviewed and approved by the Manager-Environmental Affairs. When deemed appropriate by the Manager-Environmental Affairs, such proposed changes also shall be reviewed by the Safety Review Board prior to implementation.
5.5.5 Consistency with Initially Approved Programs Any modifications or changes to the initially approved EPDD developed in accordance with section 5.5.1 shall be governed by the need to maintain consistency so that direct comparisons of current and previous data are technically valid. Such modifications or changes shall be justified and supported by adequate comparative sampling programs or studies that demonstrate the comparability of results or provide a basis for making adjustments that would permit direct comparisons.
t.
ENP-RETS-12
{
l These demonstrations of comparability shall be submitted to the NRC in accordance with sections 5.5.4 and 5.6.1.
5.5.6 NRC Authority to Require Revisions The NRC may require modifications or revisions of the EPDD developed in accordance with section 5.5.1 or may require modification or revision of changes made by the licensee in accordance with section 5.5.4, as a result of NRC reviews of the results of these programs, if such modifications or revisions are judged necessary to maintain consistency with the initially approved program descriptions or with the intent of the ETS.
The NRC also may require modifications or revisionc of the EPDD because of changes in plant operation or changes in environmental conditions or concerns associated with plant operation.
5.6 Plant Reporting Requirements 5.6.1 Routine Reports
( Annual Environmental Surveillance Report A report on the environmental surveillance program for the previous calendar year shall be submitted to.the NRC within 90
, (c days after January 1 of each year. The report shall include l summaries, analyses, and interpretations or statistical l evaluations, where appropriate, of the results of the
environmental monitoring activities for the report period.
l The Annual Environmental Surveillance Report also will include the following:
a. Comparison with preoperational studies, with operational i controls (as appropriate), and with previous i environmental monitoring reports.
l
b. An assessment of the observed impacts of plant operation on the environment.
/
l c. A summary of:
1. All instances of Environmental Technical Specifications (ETS) noncompliance and corrective actions taken to remedy them.
2. Changes to Federal and State permits and certificates made in accordance with section 5.6.3.
k HNP-RETS-13
k 3. Changes to the Environmental Programs Description Document.
I
4. Changes in station design or operation that could involve an environmental impact or change in the findings of the final environmental statement.
l S. Changes in the ETS.
6. Copies of all reports regarding station discharges made in accordance with NPDES permit No. GA 0004120 (and subsequent revisions); these shall include reports made in accordance with Parts 1B and III of the NPDES permit.
If harmful effects or evidence of irreversible damage are detected by monitoring, the licensee shall provide a further analysis of the problem and a proposed course of action to alleviate the problem.
Results of analysis of all nonradiological environmental data collected shall be summarized and tabulated on an annual basis.
In the event that some results are not available within 90 days after January 1, the report shall be submitted, noting and explaining the missing results. The missing data shall be
[ submitted as soon thereafter as possible in a supplementary report.
5.6.2 Nonroutine Reports A report shall be sumitted to the NRC in the event that an unusual or important event occurs, as specified in section 4.2.
Reports shall be submitted under one of the report schedules described below:
a. Prompt Report - Those events requiring prompt reports shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or facsimile transmission and followed within 10 days by a written report.
l b. Thirty-Day Report - Nonroutine events not requiring a l
prompt report, as described in section 5.6.2, shall be reported to NRC either:
1. Within 30 days of their occurrence
! 2. Within the time limit designated in the appropriate specification
3. Within the time limit specified by the reporting requirement of the corresponding certification or permit issued pursuant to Section 401 or 402 of PL 92-500.
HNP-RETS-14
i The report submitted to NRC in accordance with item 3 above will consist of a copy of the report made to the Georgia Department of Natural Resources, Environmental Protection Division.
Written reports and, to the extent possible, preliminary telephone, telegraph, or facsimile reports shall describe, I
analyze,'and evaluate the occurrence, including extent and magnitude of the impact; describe the cause of the occurrence; and indicate corrective action (including any significant changes made in procedures) taken to preclude recurrence and to prevent similar occurrences involving similar components or systems. ,
5.6.3 Changes in Environmental Technical Specifications and Permits
5. 6. 3 .-1 Changes in Environmental Technical Specifications Requests for changes in ETS shall be submitted to the NRC for review and authorization in accordance with 10 CFR 50.90. The request shall incude 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 NRC of the new specifications in the license.
Proposed changes to the ETS shall be reviewed and approved by the Manager-Environmental Affairs, the Plant Review Board, and the Safety Review Board. Prior to approval, the possible impact of the proposed changes will be evaluated. S 5.6.3.2 Changes in Permits and Certificates .
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 the ETS shall be reported to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a request for changes i to any water quality requirements, limits, or values stipulated in any certificate or permit issued pursuant to Section 401 or 402 of PL 92-500, which are also the subject of an ETS reporting requirement, the 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 i requirement, limit, or value being sought.
If, during the NRC's review of the proposed change, it is determined that a potentially severe environmental impact.could result from the change, the NRC will consult with the authorizing agency to determine the appropriate action to be taken.
(
j i HNP-RETS-15
5.7 Records Retention 5.7.1 Records and logs relative to the following areas shall be made and retained for the life of the plant in a manner convenient for review and inspection. These logs shall be made available to the NRC on request.
a. Records and drawings detailing plant design changes and modifications made to systems and equipment as described in section 5.5.4.
b. Records of all data from environmeal monitoring and surveillance programs required by the ETS.
5.7.2 All other records and logs relating to the ETS shall be retained, in a manner convenient for review and inspection, for 5 years following logging or recording.
5.7.3 These records shall be stored at the plant or at the Georgia Power Company General Office, as appropriate, under the control of the responsible organization.
O HNP-RETS-16
- , g i ,
EXECUTIVE
.i
. VICE PRESIDENT .
' l
! POWER SUPPLY . .
j ! . i, . I -
r- . 1 ..i l
i l MNEM MMER QMW j! i
SAFETY REVIEW ASSURANCE AND RADIOL.OQlCAL ','; , i i
'. BOARD (SRB) ,
HEALTH & SAFETY
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1 ;
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I ..
SENIOR SENIOR VICE PRES 80ENT VICE PRESIDENT ENGR CONSTRUCTION POWER GENERATION & PROJECT MANAQER W, '
$. s VICE PRESIDENT
& GENERAL MANAGER VICE PRESIDENT POWER SUPPLY ENGINEERINQ -
! @ NUCLEAR GENERATION AND SERVICES (b) ~
g -
U MANAGER CHIEF ENWNEER ) ,.
NUCLEAR GENERATION (a)
. i i i ! ,
i t ;
GENERAL MANAGER MANAGER '
PLANT HATCH ENVIRONMENTAL AFFAIRS .
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I l-a, CURRENTLY VACANT .
PLANT REVIEW -
J
b. CURRENTLY FILLED BY SAME INDIVIDUAL I BOARD (PRB) i FIGURE 5.2-l ORGANIZATIONAL STRUCTURE RELATED TO ENVIRONMENTAL ACTIVITIES
-__

v t e Letter Sequence Request
TAC:08043, (Open) TAC:08095, (Open) TAC:8043, (Open) TAC:8095, (Open)
Initiation Request, Request, Request, Request Acceptance... Administration Meeting, Meeting, Meeting Questions Answers Results Approval... Other: ML20062G268, ML20093C407, ML20101Q731
MONTHYEAR1983-10-06 [Table View]

ML20080Q151

Text

SUMMARY

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