ML20210Q941

Amends 132,128 & 103 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Changing Radiological Effluent Tech Specs Per 10CFR50,App I

ML20210Q941
Person / Time
Site:	Browns Ferry
Issue date:	02/05/1987
From:	Muller D Office of Nuclear Reactor Regulation
To:	Tennessee Valley Authority
Shared Package
ML18031B185	List: ML18031B184 ML20209D410 ML20210Q941
References
DPR-33-A-132, DPR-52-A-128, DPR-68-A-103, TAC 63022, TAC 63023, TAC 63024 NUDOCS 8702170288
Download: ML20210Q941 (166)

Text

,

~.

~ UNITED STATES I T

NUCLEAR REGULATORY. COMMISSION <

+-

o-j

a.

wAswewoTow.o.c.zoses' i

~~

~ ~ ~

' " ~ '

t 4.

./

b i

1

-i TENNESSEE VALLEY AUTHORITY

. DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT'1 i-AMENDMENT TO FACILITY OPERATING LICENSE

~ Amendment No.132 License No. DPR-33:

1.

The Nuclear Regulatory Comission (the Comission) has.found that-l A.

The applications for amendment by Tennessee Valley Authority (the' licensee) dated September 30, 1986, comply with the standards _and requirementsoftheAtomicEnergyActof-1954,asamended(theAct),

and the Comission's rules and regulations set forth in 10 CFR

.1 Chapter I-s B..

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1

C.

Thereisreasonableassurance(1)thattheactivitiesauthorizedby j

this amendment can be conducted without endangering the health and-i safety of the public, and (ii) that such activities-will be

{

conducted in' compliance with the Comission's reg"1ations; l

D.

The issuance of this amendment will not be inimical to the common defense and security or to.the health and safety of the public; and l

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have' been satisfied.

2.

Accordingly, the license.is amended by changes to the Technical Specifications ~as indicated in the attachment to'this license amendment 4

and paragraph 2.C.(2) of Facility Operating License No. DPR-33'is hereby amended to read as follows:

f i

8702170288 870205 PDR ADOCK 05000259 '

P PDR-3 u

l i

.,g (2) Technical Specifications

~

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.-132..' are'hereby incorporated in the ~

-license. The -licensee shall operate.the facility i.n accordance_ with the Technical Specifications.

3,-

'This license amendment is effective as of the date of issuance and shall-1 be implemented within 90 days from the date of. issuance.

FOR THE NUCLEAR REGULATORY COMMISSION l k

)

W' y

^

Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing I

Attachment:

Changes to the Technical Specifications Date of Issuance: February 5,1987 i

i

(

w f

ATTACHMENT TO LICENSE AMENDMENT NO.132 '

FACILITY-OPERATING LICENSE NO.~DPR-33 DOCKET NO. 50-259 Replace the following pages of the Appendix A Technica1' Specifications with the enclosed pages.. The revised areas are indicated by marginal lines.

Pages 1

286 11 287 iii 288-iv 289 y

290 vi 290A:

vii-291 viii 291A 7

2918 7A 291C 78 291D 7C-334A 51 337 52 338 54 340 54A 355 76 359 76A 84A 84B 103 103A 108A 108B 115A 118 179 281 282 283 284 285 Revise Appendix B as follows:

Table of Contents 2 pp.

L

~

TABLE OF CONTENTS

-Section Page N$..

Introduction............_..-.

1 1.0-

-Definitions........-..-..........:

2'

. SAFETY LIMITS AND LIMITING SAFETY SYSTEM. '

SETTINGS.

1.1/2.1

. Fuel Cladding Integrity.......'......

8:

1.2/2.2 Reactor, Coolant System Integrity...-......

27 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS-3.1/4.1~

Reactor Protection System 31 3.2/4.2 Protective Instrumentation.'...........

50 A.

Primary ContainmentLand Reactor Building-Isolation Functions 50 B.

Core and Containment Cooling Systems -

Initiation and Control...........

50 C.

Control Rod Block Actuation -........

.51 D.

Radioactive Liquid Effluent Monitoring Instrumentation.~.............

51' E.

Drywell Leak Detection.....

52 F.

Surveillance Instrumentation........

52' G.

Control Room Isolation...........-

52 H.

Flood Protection'..............

53-I.

Meteorological Monitoring Instrumentation 53 J.

Seismic Monitoring Instrumentation.....

54 K.

Radioactive Gaseous Effluent Monitoring-Instrumentation 54 3.3/4.3 Reactivity Control.........

120 A.

Reactivity Limitations...........

120 B.

Control Rods................

121 C.

Scram Insertion Times 124 i

Amendment No. 132 0241p

v

- Section

'Pago'No.

-D.

' Reactivity Anomalies......-...-.........

125

. E. '. Reactivity-_ Control...'...........;.....

126 F.

Scram Discharge Volume.........'....-...'

126

-3.4/4.4

. Standby Liquid Control System 135' A.

Normal System Availability.........-...

.135

~

r B.

Operation with Inoperable Components.....,.-.-

136

. C.

Sodium'Pentaborate Solution 137 3.5/4.5.

Core and Containment Cooling Systems..........-.

143 j

A.

Core Spray System (CSS)............

1.

143 B.

Residual Heat Removal System (RHRS)

]

(LPCI and Containment Cooling).

145.

C.

RHR Service Water System and Emergency Equipment Cooling

• Water-System (EECWS).

151 D.

Equipment Area Coolers...........-...

154' k

E.

High Pressure Coolant Injection System j

(HPCIS) 154 F.

Reactor Core Isolation Cooling System 4

(RCICS) 156 G.

Automatic Depressurization System (ADS) 157 H.

Maintenance of Filled Discharge' Pipe.......

158 I.

Average Planar Linear Heat Generation Rate.....

159

]

J.

Linear Heat Generation Rate (LHGR).

159 l

K.

Minimum Critical Power Ratio (MCPR) 160 L.

APRM Setpoints..................

160A i

M.

Reporting Requirements..............

160A 3.6/4.6 Primary System Boundary 174 A.

Thermal and Pressurization Limitations.......

174 B.

Coolant Chemistry 176 11 Amendment No.132 i

0241p i

x' J

s

~

a Y

- Section Pags No.

Co n Coolant: Leakage

'180-

~

D.

~ Relief Va1ves..............:.

.J.

181

'E.

. Jet Pumps.....~.'..-.-.............

181' F.

Recirculation Pump Operation........-.-...

182-

-G.;l Structural-Integrity...'............~.

183 H.

Seismic Restraints, Supports and Snubbers 185 3.7/4.7 Containment Systems-227 A... Primary Containment 227-B.

Standby Gas Treatment System....;......'...-

236 C.

Secondary Containment 240 D.

Primary Containment Isolation Valves.......-

242 E.

Control Room Emergency Ventilation........

244 F.

Primary Containment Purge System..........

246 G.

Containment Atmosphere Dilution System (CAD)...

248 H.

Containment Atmosphere Monitoring (CAM) System H Analyzer

249, 3.8/4.8 Radioactive Materials 281 A.

Liquid Effluents.................

281 B.

Airborne Effluents.........-.......

283 C.

Radioactive Effluents - Dose...........

286 D.

Mechanical Vacuum Pump..............

286 E.

Miscellaneous Radioactive Materials Sources 287 i

F.,

Solid Radwaste..................

289 3.9/4.9 Auxiliary Electrical System..

292 A.

Auxiliary Electrical Equipment..........

292 B.

Operation with Inoperable Equipment-295 j

C.

Operation in Cold Shutdown.............

298~

I 1

3.10/4.10 Core Alterations..........~

302 i

A.

Refueling Interlocks...............-

302 Amendment-No. 132 -

lii

- 0241p j

Section Page No.

B.

Core Monitoring 305 C.

Spent Fuel Pool Water.

306 D.

Reactor Building Crane.....-.....:....

307 E.

Spent Fuel Cask 307 F.

Spent Fuel Cask Handling-Refueling Floor.....

308 3.11/4.11 Fire Protection Systems

315' A.

High Pressure Fire Protection System..

315 B.-

CO: Fire Protection System..'...........

319 C.

Fire Detectors...........-.......

320 D.

Roving Fire Watch 321 E.

Fire Protection Systems Inspection........

322-F.

Fire Protection Organization...........

322 G.

Air Masks and Cylinders 323 H.

Continuous Fire Watch...~...

323 I.

Open Flames, Welding and Burning in the Cable Spreading Room....

323 5.0 Major Design Features 330 5.1 Site Features 330 5.2 Reactor 330 5.3 Reactor Vessel.......

330 5.4 Containment 330 5.5 Fuel Storage...................

330 5.6 Seismic Design.......

331 6.0 Administrative Controls 332 6.1 Organization...................

332 iv Amendment No.132 0241p

Section-Pags-Noi-6.2 Review and Audit..~...............-

333 6.3 Procedures.....................

338 6.4 Actions to be Taken in the Event of a Reportable Occurrence in Plant Operation.....-.

346

-6.5' Actions to be'taken in the Event.a Safety Limit is Exceeded ~.. '

346 346 6.6 Station Operating Records 2-6.7 Reporting Requirements....,...........~..

.349 4

6.8 Minimum Plant Staffing.................

358 i

't 2

i 1

i I

1 1

4 i

i i

9 1

J 1

v Amendment No.132 0241p

LIST OF TABLES

~

Table Title-

-Page No.-

1.1 Surveillance Frequency Notation 7c

-3.1.A' Reactor Protection System (SCRAM) Instrumentation Requirements...................

33 4.1.A Reactor Protection System (SCRAM) Instrumentation Functional Tests Minimum Functional Test

' Frequencies for Safety Instrumentation and

-Control Circuits.................

37 4.1.B Reactor Protection System (SCRAM) Instrument Calibration Minimum Calibration Frequencies for Reactor Protection Instrument Channels......

40 3.2.A Primary Containment and Reactor Building Isolation Instrumentation 55 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 62 3.2.C Instrumentation that Initiates Rod Blocks 73 j

3.2.D Radioactive Liquid Effluent Monitoring Instrumentation 76 3.2.E Instrumentation that Monitors Leakage Into Drywell.

77 3.2.F Surveillance Instrumentation............

78 1

3.2.G Control Room Isolation Instrumentation.......

81 3.2.H Flood Protection Instrumentation..........

82 1

3.2.I Meteorological Monitoring Instrumentation 83 i

l 3.2.J Seismic Monitoring Instrumentation.........

84 1

3.2.K Radioactive Gaseous Effluent Monitoring Instrumentation 84A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation..

85 i

4.2.B Surveillance Requirements for Instrumentation that Initiate or Control the CSCS.

96 4.2.C Surveillance Requirements for Instrumentation that Initiate Rod Blocks 102 4.2.D Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.....

103 1

4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation......

104 vi Amendnent No.132 0241p

Y s

' LIST OF--TABLES (Cont'd)

Title

..Page No.

Table 422.F Minimum Test ~and Calibrat' ion Frequency for-Surveillance Instrumentation

.z.

105 4.2.G Surveillance Requirements'for Control Room Isolation Instrumentation 106; 4.2.H Minimum Test and' Calibration Frequency for i

Flood Protection Instrumentation..........

107

4. 2.'J Seismic Monitoring-Instrument Surveillance......

108 L4.2.K Radioactive Gaseous Effluent Instrumentation

' Surveillance..............

.c.

.108A j

3.5 Minimum RHRSW and EECW Pump Assignment.......

152a j-3.5.I MAPLHGR Versus Average Planar Exposure........

171, 172, 172a 4

j 3.7.A Primary Containment Isolation V&lves.........

250 1

i 3.7.B Testable Penetrations witn Double 0-Ring Seals....

256 3

j 3.7.C Testable Penetrations with Testable Bellows 257 i

j 3.7.D Air Tested Isolation Valves 258 3.7.E Primary Containment. Isolation' Valves which Terminate below the Suppression-Pool Water Level 262

\\

i 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 Lines........

263 3.7.H Testable Electrical Penetrations..........

265 s

4.9.A.4.C Voltage Relay Setpoints/ Diesel' Generator Start...

298a 3.11.A Fire Protection System Hydraulic Requirements 324 i

6.8.A Minimum Shift Crew Requirements 360 1

1 1

vil Amendment No. 132

- j 4

0241p

b LIST OF ILLUSTRATIONS Figure Title Page~No.

2.1.1 APRM Flow Reference Scram and APRM Rod Block Settings......................

13 2.1 APRM Flow Bias Scram Vs. Reactor Core Flow:.

26

.4.1 Graphic Aid in the Selection of an Adequate-Interval Between. Tests.

1.-

49.

4. 2-l' System Unavailability 119 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements....................

138 3.4-2 Sodium Pentaborate Solution Temperature Requirements...................

139 3.5.K-1 MCPR Limits 172b 3.5.2 Kr Factor 173 3.6-1 Minimum Temperature 'F Above Change in Transient Temperature 194 3.6-2 Change in Charpy V Transition Temperature Vs.

Neutron Exposure..................

195 4.8.la Gaseous Release Points and Elevations 290 4.8.lb Land Site Boundary.................

290A 6.1-1 TVA Office of Power Organization for Operation of Nuclear Power Plant.

361 6.1-2 Functional Organization 362 6.2-1 Review and Audit Function 363 6.3-1 In-Plant Fire Program Organization.........

364 L

1 vill Amendment No. 132 i

l 0241p

1.0 DEFINITIONS (Cont'd) 10.

Logic - A logic is an arrangement of relays, contacts, and other components that produces a decision output.

(a) Initiating - A logic that receive signals from channels and produce decision outputs to the actuation logic.

(b) Actuation - A logic that receives signals (either from initiation logic or channels) and produces decision outputs to accomplish a protective action.

11.

Channel Calibration - Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors. The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test. The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check. 12. Channel Functional Test - Shall be: a. Analog Channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions. b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions. 13. Source Check - Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources. Amendment No. 132 7 0242p

~. 4 s 3 'H 4 y '1.0L DEFINITIONS (Cont'd)- I l W.' Functional Tests - ' A fun'cli'onhllest is the manual [opetition 'or. i initiation of a system,! subsystem? or components to verify that... it. functions within design' tolerances (e.g.,.the manual start.of. .t a core spray pump to verify that;it: runs and that it' pumps'the 7 [,. required volume'of water). l [

X.

. Shutdown:- The reactor is in a shutdownicondition when the- [ reactor mode switch'is in thel shutdown mode position and~no core F ' alterations are being performed. Y.- Engineered Safeguard - An engineered safeguard is a~ safety l [* system the actions of which are essential to a safety action. [ required in response to accidents.. Z. Reportable Event 'A reportable event shall;be any of~those- ] conditions specified in:section 50.73 to.10 CFR Part.50.. L AA. Solidification - Shall be the conversion of radioactive wastes into a form that meets shipping and burial' ground requirements.. BB. -Offsite Dose Calculation Manual (ODCM) - Shall be a manual j describing the environmental monitoring program and the I j. . methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and.and 4 liquid effluents. The ODCM will also provide the plant with j guidance for establishing alarm / trip setpoints to ensure a j technical specifications sections-3.8.A.1 and 3.8.B.1 are not i exceeded. 8 CC. Purge or purging - The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operatingLcondition ~ [ in such a manner that replacement air or gas is' required to i purify the containment. i l DD. Process Control Program Shall contain the' sampling, analysis, l and formulation determination by which SOLIDIFICATION of i radioactive wastes from liquid systems is assured. ) EE. Radiological Effluent Manual (REM) - Shall be a manual j containing the site and environmental: sampling and analysis l programs for measurements of radiation and' radioactive materials i in those exposure pathways and for those radionuclides whica ] lead to the highest potential radiation exposure to individuals 1 from station operation. It shall also specify operating j guidelines for radioactive ~ waste treatment systems and report content. FF. Venting - The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, i humidity, concentration..or other operating condition in such a i manner that replacement air or gas.is not provided or required.- Vent, used in system names, does not imply a venting process.. 4 ii 1 3 J 7A i 0242p E Amendment No.132 - . ~ _ _. _ _ _ _ _ _. _,. _. _ _. _. _ _,_,

w

g

_( ^ ~[ ^, ".1.0 ' I DEFINITIONS (Cont'd) ~ ~ ~ GG..; Site Boundary - Shall be-that-line.beyond which the land;is not owned,-leased, or otherwise controlled by TVA. ~ t HH. Unrestricted Area -.Any area.at.or-beyond;the. site boundary to i ~

which access is not. controlled by the;1icensee.for purposes ofJ c

. protection of individuals from exposure to radiation and. 7 j s radioactive materials. or.any area..within ' the. site boundary t! sed 'for; industrial, commercial,-institutional,'or. recreational =. purposes., II. Dose Equivalent I-131 - The DOSE EQUIVALENT:I-131 shall-be 'the : - concentration of I-131.(in pCi/gm) which alone_would produce: the same' thyroid dose as the quantity _and; isotopic mixture of' I-131, I-132, I-133, 1-134,.and'I-135 actually present..The' thyroid dose conversion factor used for'this calculation shall-be those listed in Table III of: TID-14844 " Calculation of, Distance Factors for Power and Test Reactor Sites".. .JJ. Gaseous Waste Treatment System The charcoal.adsorber vessels. installed on the discharge-of the steam jet-. air ejector to , provide delay to a unit's offgas activity prior to release. KK. Members of the Public - Shall* include all' individuals who by. l virtue of their occupational status have no formal association with the plant. This category shall include non-employees of the licensee who are permitted to use portions of the site for-recreational, occupational, or other: purposes not associated' with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part'of their formal job function, occasionally enter ~ restricted areas. LL. Surve111ance - Surveillance Requirements!shall'be' met during the ~ OPERATIONAL CONDITIONS or'other conditions specified for individual limiting conditions for operation unless'otherwise' stated in an individual Surveillance Requirements. Each surveillance Requirement shall be performed within the specified time interval with, (1) .A maximum allowable extention not to exceed 25% of the-l surveillance interval, but r (2) The combined time entered for any 3 consecutive surveillance intervals shall not exceed 3.25 times the i .specified surveillance interval-l Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and-associated action statements unless otherwise required.by these specifications. Surveillance requirements do not have to be performed on inoperable equipment. 78 0242p Amendment No.132

r*, a u T-b1W 1'.1 ' SURVEILLANCE FREQUENCY NOTATION T ~ NOTATION

FREQUENCY.:

3 - o S (Shift) At least once per-12 hours.. D-- (Daily) ~At 1 east once per normal calendar'. 24 hour

• day (midnight to:Sidnight).

..1 W- ,(Weekly) At least.once per 7 days. M (Monthly) At'least once per 31-days. Q (Quarterly) At least once per 3 months or.92-days.. SA (Semi-Annually At least once per 6 months or 184' days.- Y (Yearly) At least once.per year or 366 days.- R (Refueling) At-least once~per operating ~ cycle. S/U (Start-Up) Prior to each reactor startup. N. A. ' Not applicable.- P (Prior) Completed prior to each release. 4 7C 0242p Amendment No.132.

.n. = -- yy e a, o LIMITING CONDITIONS FOR.0PERATION SURVEILLANCE REQUIREMENTS

3.2.B

Core and ContainmentLCoolinEL

- '412.8.' Core and Containmer$t Coolina ^ -Systems - Initiation & Control-Systems - Initiation-6-Control

are required to.be operable

'shall be considered operable if-they are within the required-surveillance testing frequency and there is no reason"to suspect'that they are inoperable... . C. Control' Rod Block Actuation ~ C. 1 Control Rod Block Actuation a -The limiting conditions'.o1 Instrumentation shall-be . operation for the. instrumentation functionally' tested.. t that initiates control rod block; ' calibrated, and checked ~as. are given in Table 3.2.C. indicated in Table 4.2.C.- n = System logic shall.be. functionally tested as indicated in Table 4.2.C. 3.2.D Radioactive Liquid Effluent 4.2.D: Radioactive Liquid Effluent, Monitorina Instrumentation Monitorina Instrumentation. 1. The radioactive liquid '1. -Each of the radioactive effluent monitoring l liquid effluent monitoring instrumentation listed in instruments shall be Table 3.2.D shall be demonstrated operable by operable with the performance of test in-applicability as shown in. accordance with Table 4.2.D. Tables 3.2.D/4.2.D. Alarm / trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.A.1 are not exceeded. 2. The action required when the number of operable channels is less than the minimum channels operable requirement. is specified'in the notes for Table 3.2.D. Exert best efforts to return thei instrument (s) to ~0PEFABLE status within 30 dayu and if unsuccessful.M xplain in the next Seislannual Ra:iloactive i Effluent-Release Report why the inoperability was not' ) corrected ~in a timely manner. -l .l 51 Amendment No.132 0233p l '.p. m 1

o g' -.c i-' y - s s + LIMITING CONDITIONS FOR OPERATION ' SURVEILLANCE REQUIREMENTS ^ ^ ~3.2.D

Radioactive' Liquid Effluent-4.2.D'

' Radioactive' Liquid Effluent (Con't) -(Con't)- 3. With a radioactive 11iquid ' effluent monitoring channel. alarm / trip setpoint less Lconservative than required: by these~ specific.ations,-

suspend the release without.

. delay, declare the channel m inoperable, or' adjust'the alarm / trip setpoint to. establish the conservatism - required by these: . specifications. 4. The provisions'of- ' specification 1.0.C and= 6.7.2 are not applicable. ~ E. Drywell Leak Detection E. Drywell Leak Detection

The limiting conditions of.

Instrumentation'shall be operation for the instrumentation calibrated and checked as that monitors drywell leak indicated in Table 4.2.E. detection are given in Table 3.2.E. T. Surveillance Instrumentation-T. Surveillance Instrumentation The limiting conditions for the Instrumentation shall be instrumentation that provides- -calibrated and checked as-surveillance information readouts indicated in Table 4.2.F. are given in Table 3.2.F. G. Control Room Isolation G. Control Room Isolation The limiting conditions for Instrumentation 4shall be instrumentation that isolates calibrated and. checked as the control room and initiates -indicated in Table 4.2.G. the control room emergency pressurization systems are given in Table 3.2.G. 52 Amendment No. 132 0233p 1

3, . LIMITING CONDITIONS FOR OPERATION ~ SURVEILLANCE REQUIREMENTS 3.2.J Seismic Monitoring Instrumentation 4.2.J ' Seismic Monitoring Instrumentation 1. The seismic monitoring 1. Each of the seismic instruments listed in monitoring' instruments-Table 3.2.J shall-be shall be demonstrated . operable.at all times. operable by. performance of., tests at _the frequencies- ~ 2. With the number o' seismic listed in Table 4.2.J. Lmonitoring instruments less than the number listed in

2. ~ Data shall be retrieved

' Table 3.2.J. restore the from all' seismic inoperable instrument (s) to instruments' actuated during operable status within a seismic event and. -30 days, analyzed to determine-the magnitude of the vibratory-3. With one or more of the. ground motion.; A Special instruments listed.in Table Report'shall be submitted-l 3.2.J. inoperable-for more to the Commission pursuant-than 30 days, submit a to specification 6.7.3.D l Special Report to the . within 10 days describing l Conunission pursuant to the magnitude, frequency-specification 6.7.3.C within -spectrum,'and resultant the next 10 days describing, effect upon plant features the cause of the malfunction important to safety. ~ and plans for restoring the instruments to operable status. 3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseous-Effluent' Monitoring Instrumentation -Monitoring Instrumentati.on E The radioactive gaseous 1.- Each of the radioactivi 1. effluent monitoring gaseous effluent monitoring instruments listed in instrtur.ents shall be Table 3.2.K shall be demonstrated operable by operable with the performance of testsiin applicability as shown-in accordance with Table 1A.2.K. l Tables 3.2.K/4.2.K. Alarm / J trip setpoints will be set j,'. 1j i in accordance with guidance t given in the ODCH to ensure i that the limits of specification 3.8.B.1 are not exceeded. . + s. <k l 50 t-A Amendment No.132. - ['

0233p,

%y

LIMITING CONDITIONS FOR OPERATION - SURVEILLANCE REQUIREMENTS'

3.2.K Radioactive Gaseous Effluent

'~~' ?4~. 2. K Radioactive Caseous Effluent ~ Monitoring Instrumentation-Monitoring Instrumentation .(Con't) (Con't) 2.-- The action' required when the 4 ~ number of operable channels, - is less'than.the. Minimum Channels Operable requirement is specified in the notes for . Table 3.2.K. Exert best' efforts to return the instruments to' operable status within 30 days and, if unsuccessful,~ explain in the next Semiannual Radioactive 4 ' inoperability was not Release Report why the 3 corrected in a timely manner.. i 3. With a radioactive gaseous effluent monitoring channel alarm / trip setpoint less conservative than required by these specifications,-suspend I the release without delay, declare the channel inoperable, or. adjust the alarm / trip. setpoint.to establish the conservatism required by these specifications. t i -4. Both off-gas treatment monitors may be taken out of. service- - for less than one hour for purging of monitors during SI-performance. 5.. The provisions of-specifications 1.0.C and 6.7.2 are not applicable. l 1 54A Amendment No. 132 0233p --ee e-M s g- .r- --*+mmg y e g +e 4 n -im p m- -p-O T-1r-t 71 ?y- '1---*9 ?~ d++?--5w

TABLE 3.2.D Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument '" Operable Applicability Action 1. LIQUID RADWASTE EFFLUENT ' 1 A, 8 MONITOR (RM-90-130) 2. RHR SERVICE HATER HONITOR 1 C (RM-90-133. -134) 3. RAW COOLING WATER MONITOR 1 D (RM-90-132) 4. LIQUID RADHASTE EFFLUENT I E FLOW RATE (77-60 loop excluding fixed in line rotometer) ' Amendment No.132 76 0240p; = - -

NOTES FOR TABLE 3.2.D ~ ~*At all times

• • During releases via this pathway
    • During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met (1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge. valve before exceeding the limits specified in 3.8.A.1, (2) if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance'with the sampling and analysis program specified in the REM and two qualified station personnel shall independently verify the release rate calculations and check valving before the' discharge. Otherwise, suspend release via this pathway.

ACTION B With a radioactive liquid effluent monitoring channel / alarm trip'setpoint less conservative than required by these specifications, suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm / trip setpoint to establish the conservatism referred by these specifications. ACTION C During operation of an RER loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored. If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours and an analysis of at least an LLDof IE-7 pCi/ml (gross) or < applicable MPC ratio (y isotopic-) shall be used to monitor the effluent. ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided that a temporary monitor is installed or,-at least once per 8 hours, grab samples are collected and analyzed for radioactivity'with an LLDof 1E-7 pCi/ml (gross) or < applicable MPC ratio (y isotopic). ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continuea provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. ACTION F Alarm / trip setpoints will be calculated in accordance with the guidance given in the Offsite Dose Calculation Manual (ODCM). (1) See REM, TABLE NOTATIONS - TABLE C-1, for the definition of LLD. 76A Amendment No. 132 0242p

_ ~ _ i TABLE 3.2.K Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Channels /' Instrument Devices Operable Applicability Action 1. STACK (RM-90-147A & B) a. Noble Gas Monitor (1) A/C

• ~

b. Iodine Cartridge (1) B/C-' c. Particulate Filter (1) 8/C d. Sampler Flow Abnormal (1) D-e. Stack Flow (FT, FM, (1) .D FI-90-271) 2. REACTOR / TURBINE BLDG VENTILATION (RM-90-250) a. Noble Gas Monitor (1) A/C. b. Iodine Sampler' (1) .B/C c. Particulate Sampler (1) B/C d. Sampler Flowmeter (1) D 3. TURBINE BLDG EXHAUST. (RM-90-249, 251) a. Noble Gas Monitor (1) A/C-b. Iodine Sampler (1) .B/C

c.. Particulate Sampler (1).

B/C d. Sampler Flowmeter (1) D 4. RADHASTE BLOG VENT (RM-90-252) a. Noble Gas Monitor (1) A/C b. -Iodine. Sampler -(1) B/C: c. Particulate.-Sampler '(1)- .B/C d. -l Sampler Flowmeter .(1) O OFF GAS HYDROGEN ANALYZER 5. (H,A, H28); (1) E 6. OFF GAS POST TREATMENT a. Noble Gas Activity Monttor . F -(RM-90-265, 266) -(1) b. Sample flow Abnormal' (PA-90-262) (1) .D: " '" "* I 0240"p~

NOTES FOR TABLE 3.2.K

• At all times
  • During releases via this pathway
    • During main condenser offgas treatment system operation ACTION A With the number of channels OPERABLE less_than required by the Minimum Channels Operable requirement, effluent releases via the affected pathway may-continue provided a temporary monitoring system is installed or grab samples-are taken and analyzed at least once every 8 hours.

ACTION B With a number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed in accordance with the sampling and analysis program specified in the REM within 48 hours after the end of the sampling period. ACTION C A monitoring system may be out of service for 4 hours for functional testing, calibration, or repair without providing or initiating grab sampling. ACTION D With the number of channels OPERABLE less than required-by-the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours and analyzed within the following 4 hours. ACTION F 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 at least once per 8 hours and these samples j are analyzed for gross activity within 24 hours. Purging during SI performance is not considered a loss of monitoring capability. j 1 49 4 i 84B Amendment No. 132 0242p

TABLE 4.2.0. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Functional Instrument Instrument Check Source Check Calibration Test 1. LIQUID RADWASTE EFFLUENT D(4) M R(5) Q(1). MONITOR (RM-90-130) 2. RHR SERVICE WATER MONITOR D(4) M R(5) Q(2)- (RM-90-133. -134) 3. RAW COOLING WATER MONITOR D(4) M R(5) Q(2) (RM-90-132) 4. LIQUID RADHASTE EFFLUENT D(4) NA R' Q(3) FLOW RATE (77-60 loop) k l i ^**" **" 0240p_

NOTES FOR TABLE 4.2.D (1) The channel functional. test shall also demonstrate that' automatic isolation of this pathway and control room annunciation occurs if any of -l the following conditions exist: a'. Instrument-indicates measured l'evels above the alarm / trip setpoint b. Instrument indicates an inoperative /downscale failure c. Instrument controls not set in operate mode (2) The channel functional test shall also demonstrate that control room annunciation occurs if any of the following conditions exist: Instrument-indicates measure'd levels above the alarm / trip setpoint .a. b.' Instrument indicates an inoperative /downscale failure c. Instrument controls not set in operate mode (3) This functional test shall consist of measuring rate of tank decrea'se over a period of time.and comparing this value with flow rate instrument reading. (4) INSTRUMENT CHECK shall consist of verifying indication during. periods of release. INSTRUMENT CHECK shall be made at least once per 24 hours on days ~which continuous, periodic, or batch releases are made. (5) The CHANNEL CALIBRATION shall include the use of a known (traceable to National Bureau of Standards Radiation Measurement System) radioactive source (s) positioned in a reproducible geometry with respect to the-sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS). 103A Amendment No.132 0242p

TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Channel Functional Instrument Instrument Check Source Check Calibration Test 1. STACK a. Noble Gas Monitor D M R Q8 b. Iodine Cartridge H NA NA NA c. Particulate filter H NA NA NA d. Sampler Flow Abnormal D NA R Q e. Stack Flowmeter D NA R. Q 2. REACTOR / TURBINE BLDG VENT a. Noble Gas Monitor D. M R Q b. Iodine Sampler H NA. NA NA c. Particulate Sampler H NA NA NA d. Sampler Flowmeter D NA. R Q 3. TURBINE BLDG EXHAUST a., Noble Gas Monitor D M R Q b. Iodine Sampler H ' NA - NA NA c. Particulate Sampler .H NA NA NA. d. Sampler Flowmeter .D NA R Q 4. RADHASTE BLDG VENT j a. Noble Gas Monitor' D M R' Q b. Iodine Sampler H NA NA NA c. Particulate Sampler. H NA, NA NA d. Sampler Flowmeter D. NA R. Q~ S. OFF GAS HYDROGEN ANALYZER-(H,A, H,B) D NA R Q'** 6. Off GAS POST TREATMENT 'S' a. Noble Gas Activity Monitor D M R Q'** b. Sample flow Abnormal .0 NA R Q 108A 0240p. Amendment No.132

NOTES FOR TABLE 4.2.K (1) The CHANNEL CALIBRATION shall include the'use of a known (traceable to .the' National Bureau.of. Standards Radiation Measurement System) radioactive source (s) positioned in a reproducible geometry with respect to the sensor or using standards that have obtained from-suppliers that participate in measurement assurance activities with the National Bureau of Standards. (2)' The CHANNEL FUNCTIONAL TEST shall also demonstrate that con' trol 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. inoperative /downscale failure. Instrument controls not set in operate mode,(stack only). c. (3) The channel calibration shall include the use of standard gas samples containing a nominal: Zero volume percent hydrogen (compressed air) and, a. b. One volume percent hydrogen, balance nitrogen. (4) The channel functional test shall demonstrate that automatic isolation of this pathway and control room annunciation' occurs if'any of the following conditions exists: a. Instrument indicates measured level above the alarm / trip setpoint. b. Instrument indicates an inoperative /downscale failure. c. Instrument controls not set in operate mode. The two channels are arranged in a-coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale wi11' isolate the offgas line. (5) The noble gas monitor shall have a LLD of IE-5 (Xe 133 Equivalent). (6) The noble gas monitor shall have a LLD of IE-6 (Xe 133 Equivalent). 1 r 108B Amendment No.132 i 0242p

'The~ radioactive gaseous effluent instrumentation is provided to monitor End control, as applicable, the releases of radioactive materials in gaseous j effluents during actual or potential releases of gaseous effluents. ~The alarm / trip setpoints for thest instruments will be calculated in accordance with guidance provided in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR'Part 20. This instrumentation also includes / provisions for monitoring the concentration of potentially explosive gas mixtures in the offgas holdup system. The operability and use of this instrumentation is consistent with the requirements of. General Design Criteria a l 60, 63, and 64 of Appendix A to 10 CFR Part 50. 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 guidance provided in the ODCM to ensure that the alarm / trip'will occur prior to exceeding the limits of 10 CFR Part 20 Appendix B, Table.II, Column 2. 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. Amendment No. 132 0242p l

' 4.2 BASES there is no true minimum. -The curve does have a definite knee and very little reduction in system unavailability is. achieved:by-testing at a shorter interval than computed by'the equation'for a-single channel. The best' test procedure of all those examined is to perfectly stagger the tests. That.is,.if the test' interval is four months, test one or the ~ other channel every two months. This is shown in Curve No. 5. The difference between Cases 4 and 5 is negligible..There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error. The conclusions to be drawn are these: 1. A~1 out of n system may be treated the same as a single channel in terms of choosing a test interval; and 2. more.than one channel should not be bypassed for. testing at any one time. The radiation monitors in the refueling area ventilation duct which initiate building isolation ~and standby gas treatment operation are arranged in two 1 out of 2 logic' systems. The bases given for the rod blocks apply here also and were used to arrive at the functional ~ testing frequency. The off-gas post treatment monitors are-connected in a 2 out of 2 logic arrangement. Based on experience with instruments of similar design,-a testing interval of once every three months has been found adequate. The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also. The criteria for ensuring the reliability and' accuracy of th'e radioactive gaseous effluent instrumentation is listed-in Table 4.2.K. The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 4.2.D. Amendment No. 132 0242p

+ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3 '. 6 Primary System Boundary 4.6 Primary System Boundary 6. Whenever the reactor is.

6. -Additional coolant samples-l critical, the. limits on

_shall.be taken.whenever the l activity concentrations in the. reactor activity exceeds one l reactor coolant shall not-percent of the equilibrium' exceed-the equilibrium value concentration specified in i of 3.2 pc/gm of does-3.6.B.6 and one.of the m equivalent.I-131. following conditions are met: ( 4 This limit'may be exceeded (a. _During startup 1-following power transients for' b.~ Following a significant i

a. maximum of 48 hours. During

_ power change **- this activity transient the

c. ~Following an increase in iodine concentrations shall the equilibrium off-gas not exceed 26'pCi/gm.whenever:

. level exceeding 10,000 the reactor is critical.. The .pCi/sec-(at the steam ~ 4 reactor.shall not be operated . jet air ejector) within- 'more than'5 percent of its a 48 hour period. yearly power operation under

d. 1Whenever the equilibrium.

'this exception for the-iodine limit specified equilibrium activity' limits. 'in 3.6.B.6.is exceeded.- i If the iodine concentration ~in l the coolant exceeds 26 pCi/gm, The additional coolant liquid samples shall be -l the reactor shall be shut down, ~ and the steam line isolation taken at 4 hour intervals valves shall be closed. for'48 hours,lor until a. immediately. stable iodine concentration ~ below the limiting valuei (3.2 pCi/gm)-is 1 4 established. However, at least-3 consecutive samples -shall be taken in all cases._ An isotopic analysis .shall be performed for each ' sample, and quantitative I measurements made to determine the dose equivalent I-131 i -concentration. If-the total ~ . iodine activity of the sample is below 0.32-pCi/gm, an isotopic-i analysis to determine. l equivalent I-131.is not required. r

• • For the purpose of this section on i

sampling frequency, a significant I power exchange is~ defined las a-change exceeding 15% of rated power i .in'less than 1 hour. .e ID Amendment No. 132 i 0233p. -. = a

n. f' r LIMITING CONDITIONS FOR OPERATION-SURVEILLANCE REQUIREMENTS .3.8-Radioactive Materials 4.8 'Radioacti'e-Materials v Applicability _ Applicability ' Applies to the release of Applies;to the periodic test and radioactive' liquids and gases

record. requirements and

sampling:

from the facility. and monitoring methods used for ~ facility effluents. Objective Objective .To define the limits and conditions ~for the release.of. To ensure that radioactive radioactive effluents to the-liquid.and gaseous releases-from ~ -environs to assure that any the facility are maintained. e . radioactive releases are as within the limits specified by low as reasonably achievable Specifications 3.8.A and 3.8.B. and within'the' limits,of. 10 CFR Part 20..The specifications Specification except for 3.8.A.1 and 3.8.B.1 are exempt from the. requirements of .A. Liquid Effluents S . definition 1.0.C (Limiting Condition for Operation). fl. Facility records shall-be maintained of Specification-radioactive concentrations and- [ A. Liquid Effluents volume.before dilution of each batch of liquid 1. The concentration of effluent released, and l radioactive material of the average' dilution released at any time from flow and length of time i the site to unrestricted

over which each-areas (see Figure 4.8-1b)

. discharge occurred. shall.be limited to the concentrations specified 2._ Radioactive liquid waste in 10 CFR Part 20, sampling and activity I Appendix B, Table II,: . analysis of each liquid' Column 2 for radionuclides-other than dissolved or . waste batch to be-discharged shall be entrained noble gases, performed prior to l-For dissolved or entrained release in accordance-noble gases, the Jwith the sampling and-concentration shall txe . analysis program limited to 2E-4 pCi/mi specified in the REM. total activity. ) 2-3. The operation of the l 2. If the limits of 3.8.A.1 automatic' isolation. ~ are exceeded, appropriate valves and discharge action shall be initiated tank selection valves .l 'without delay to bring shall be checked the release within : annually. i 281. n

o. 1 32 0233p

l l LIMITING CONDITIONS FOR-OPERATION SURVEILLANCE REQUIREMENTS 3.8' Radioactive Materials - 4.8 Radioactive Materials limits.- Provide prompt 4. The results of the notification to the NRC - analysis of samples pursuant to section 6.7.2. collected from release points-shall be used 3. The doses or dose with the calculational commitment to a member of methodology in the ODCM the public from radioactive to assure that the materials in liquid concentrations at the effluents' released from point of release are. each unit to unrestricted maintained within the areas (See Figure 4.8-1b) limits of specification shall be limi.ted: 3.8.A.1. a. During mar calendar 5. Cummulative quarterly quarter to (1.5 mrem to and yearly dose the total body and <5 contributions from mrem to any organ and, liquid effluents shall be determined as b. During any calendar specified in the ODCM at year to <3 mrem to the least once every 31 days. total body and <10 mrem to any organ 6. The quantity of radioactive material 4. If the limits specified in contained in any outside 3.8.A.3 a & b above are liquid radwaste storage exceeded, prepare and tanks shall be submit'Special Report determined to be within pursuant to Section 6.7.2. the above limit by analyzing a 5. The maximum activity to be representative sample of contained in one liquid the tank's contents at radwaste tank or temporary least once per 7 days storage tank that can be when radioactive discharged directly to the materials-are being environs shall not exceed added to the_ tank. 10 curies excluding tritium and dissolved / entrained noble gas. 6. With radioactive liquid waste exceeding 3.8.A.5 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours, reduce the tank contents to within the limit. Events leading to this condition must be reported in the .next Semiannual Radioactive Effluent Release Report (section F.2 of the REM)- 282 Amendment No.132 - 0233p

l, LIMITING ' CONDITIONS FOR OPERATIOT SURVEILLANCE REQUIREMENTS-s 3.8; Radioactive Materials- '4.'8 Radioactive' Materials + B. Airborne' Effluents B. Airborne' Effluents" .) 1 1. The. dose rate at any time 1. The gross 6/y-and. ~ to areas at-and beyond the particulate activity of j-site boundary (see Figure -gaseous wastes released -4.8-1b)'due to to the environment shall radioactivity released in. -be monitored and. ' gaseous effluents from the. recorded.' ' site shall be~ limited to the following values:_ a. For' effluent. streams 4

having continuous.

a. The dose rate limit monitoring lfor noble gases shall capability, the be <500 mrem /yr:to the activity shall.be. total body and (3000: . monitored and flow mrem /yr to the skin, ' rate. evaluated.and. and -recorded to enable release: rates of-b. The dose rate limit: gross radioactivity ~ for I-131, I-133, H-3, to be determined at and particulates with 1 east:once per shift- .i greater than'eight day using instruments } half-lives shall be specified in table- <1500 mrem /yr to any -3.2.K organ. b.. For effluent. streams 2. If the' limits of 3.8.B.1 without continuous 1 are exceeded, appropriate monitoring l i corrective action shall be_ capability..the. j immediately initiated to. activity shall'be . bring the release.within! monitored and limits. Provide prompt -recorded and the notification to the NRC release _through 1 1 pursuant to section 6.7.2. these streams controlled to within -i 7 the limits specified t --in 3.8.B. I 2. Radioactive gaseous. I waste sampling and activity analysis shall-be performed in! 3 accordance with'the-sampling and analysis - i . program specified in the j j. REM. Dose rates shall-l 4 be determined to be within limits of 3.8.B using methods _ contained in the ODCM. l Amendment No. 132 L O233p_ l .I

LIMITING CONDITIONS FOR 0PERATION- ~ SURVEILLANCE REQUIREMENTS ~

3. yThe air' dose to aress at ?~~'

3. Cumulative-quarterly and' and beyond.the site yearly dose boundary (see Figure. contributions from ' 4.8-lb) due to noble gases. sgaseous releases shallt ~ - released in gaseous-be determined using-. effluents per unit-shall. methods contained in the be limited to the ~ODCM at leastionce every-following: 31 days.: - a. -During;any calendar- ~ quarter, to 15 mrad " 4 for ganna. radiation and 110 mrad for beta radiation;- b b. During any' calendar-year, to 110 mrad for gamma radiation and. <20 mrad for beta radiation.

4..If the calcu' lated air' dose exceeds the. limits

} . specified in 3.8.B.3 above, l prepare and submit a special report' pursuant to: section 6.7.2.1 s 5. The dose to a member.of the public from radioiodines, radiosctive ~ materials in particulate-form, and radionuclides other than noble gases with half lives' greater-than 8 days in gaseous effluent released per unit ' to areas at and beyond the ~ site boundary (see Figure 4.8-lb) shall be limited e to the following: a. To any organ during any calendar quarter-to 17.5 mrem; b. To any organ during any calendar year to 115 mrem;; i ) i 284-Anendment No'.132 4 0233p ~ -9 y-4 -y -~ ,gg m- + w

y c- .n. + s p N LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS' 6. Ifithe calculated ' doses ~ 4. During operation above ' exceed the' limits of 25% power,.the position 3.8.B.5 above, prepare ~ .of;the charcoal. bed and submit a special bypass. valve will;be ~ report pursuant to. verified daily. section 6.7.2.. 7; During operation above 5.

The concentration of 25% power the discharge hydrogen downstream of the recombiners shall be'

~ of the SJAE must be ~ -routed through_the determined to be within. charcoal adsorbers.. the limits of 3.8.B.9'by-continuously monitoring'

8.. With gaseous waste being the offgass.whenever the discharged for.more than-SJAE is in s'ervice using' 7-days without treatment instruments described in' i

through the charcoal-Table 3.2.K. -Instrument- -adsorbers, prepare and. surveillance-, submit a special report requirements are. . pursuant to section specified.in Table 4.2iK. 6.7.2.' 9. Whenstver the SJAE is in~ service, the' concentration of hydrogen in the-offgas downctream of the recombiners shall be limited to 14% by volume. t 10. With-the concentration of ~ hydrogen exceeding the i limit of 3.8.B.9 above, restore the concentration i to within the limit within-48 hours. t 4 4 4 Amendment No. 132. 285 1 4 - 0233p i ,--.. _ ~ -.._.-

+ lW LIMITING ^ CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS E3[8.C. Radioactive-Effluents"- Dose 4.8.C RadioacIt"ve Effluents - Do"se? 1. The, dose or dose -1.

Cumulative dose-commitment :to a real ~

contributions from individual from all ' liquid and' gaseous .' uranium fuel cycle: sources effluents shallibe is limited to <25 mrem to ' determined in accordance 'the-totalkbody or any. . with specifications; organ (except-the, thyroid,. 3.8.A.3, 3.8.B.3, and-which is' limited to <75 3.8.B.5 and the. methods mrem) over a period of one' ~in the ODCM.z calendar. year. ~ 2. With the calculated dose from the release of-radioactive materials in

liquid or gaseous effluents exceeding ~twice the limits of specification 3.8.A.3, 3.8.B.3 -or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specification 6.7.2 and limit the subsequent.

releases such that the limits of 3.8.C.1 are not exceeded. 3.8.D M_echanical Vacuum Pump 4.8.D Mechanical Vacuum Pump 1. Each mechanical vacuum pump At least.once during each ~ shall be capable of being operating cycle verify automatic automatically isolated and securing and isolation of the secured on a signal or mechanical vacuum pump. high radioactivity in the steam lines whenever the main steam isolation ^ valves are.open. 2. If the limits of 3.8.D are not met, the vacuum pump-shall be isolated. l Amendment No. 132 286 -0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 Radioactive Materials f4.8.C Radioactive Materials E. Miscellaneous Radioactive' E. Miscellaneous Radioactive ' Materials Sources Materials Sources ~ 1- ' Surveillance Requirement-1. Source Leakage Test Each sealed source Tests for leakage and/or containing radioactive _ ._ contamination shall be material either in excess performed by the' of 100 microcuries of beta licensec or by other and/or gamma emitting persons specifically material or 5 microcuries authorized.by the of alpha emitting material LCommission or an-shall be free of > 0.005 agreement State, as. microcurie of removable-follows: . contamination. Each sealed souce with removable a. Sources in Use contamination in excesc of the above limit shall be Each sealed source, immediately withdrawn from excluding startup use'and (a) either sources and flux 1 decontaminated and detectors previously repaired,-or (b) disposed subjected to-core of in accordance with flux, containing Commission regulations. radioactive material, otherithan Hydrogen 3, with a t half-life greater. than thirty days and in any form other-than gas shall be tested for leakage and/or contamination at least once per six months. The leakage test shall be' capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. 287 Amendment No.132 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.8.E -Miscellaneous Radioactive Materials Sources- .1..' Surveillance Requirements b. Stored Sources Not-In Use-Each sealed source and fission detector' not previously subjected to core-flux.shall be tested prior to use or. transfer to another licensee unless tested within the previous six months. Sealed sources and fission detectors transferred without a certificate indicating the last-test date shall be tested prior to use. c. Startup Sources and Fission Detectors Each sealed startup source and fission detector shall be tested prior to being subjected to - core flux and following repair or maintenance to the source. 2. Reports A report shall be prepared-and submitted-to the Commission on an annual basis if sealed sources or fission detector leakage tests reveal the presence of greater than or equal to-0.005 microcuries of removable contamination. Amendment No. 132 0233p

M., ,~ " LIMITING ^ CONDITIONS FOR OPERATION ~ SURVEILLANCE REQUIREMENTS 3.8 _ Radioactive Materials -4.8 Radioactive' Materials-: F. Solid Radwaste F. ' Solid Radwaste. 1.- The solid radwaste system 1...The' Process Control Program shall.' include: shall be operated' ins ~ surveillance: check's. accordance with a process ~ s necessary.to demonstrate control. program, fortthe.. ~ ' compliance with 3.8.F.1.. solidification and packaging of wet radioactive 'astes~to w ensure meeting-the' requirements:of 10 CFR 20 and 10 CFR 71.and burial ground requirements prior-to shipment of radioactive wastes from the site.-

2.. With the packaging'

~ requirements'of 10 CFR 20 or burial ground requirements and/or 10 CFR 71 not satisfied, suspend shipments.of. defectively packaged solid radioactive wastes from the site. I f i 4 i t )_ 289 4 Amendment No.-132 I- . 0233p . c.

h i l l q 9 j ^ na ( F ts ] ua h x E d g S n N r n o~ O a i) i I y dm t T h l2 a' A r c i3 l' V t u( i E i B t' w g L S n E e n e n i

• g V

D i d n N b l i g A r i d n u u l i) S T B i d m T u l0 N e B i4 a I n u( l O i r B P b o */ 8 0 r r E 9 t u c T a t .4 S 2 o A e c e E R a r L e u E e R g R c. e. i i tg F S vg bd U rd l O el UB E SB S J A G g 2 n 3 ei 1 cd il fi o fu N OB tnem d ne m I ) A m 08 ( 1 ( k c a t S i I

t c

.~

Figure 4.8-lb ) LAND SITE BOUNDARY 3 i ..-t: d \\/ l g

4,.*

'. ) * .g !:\\ ' \\- N r j.. 3. i M..w-1 3, _ ji : :, ,.q. .e i /

• ,%',P

~ Nyw* *r Liquid Discherme f,.,.g'. (ottraser Fireal ^ '~~ f.TC 'r'~ ~ i.u, \\ \\ l \\ \\ s \\ )

.u,.

N \\ \\ \\ \\ \\ \\ \\ \\ l N 290A Amendment No. 132

r 1 -3~.8. BASES- ~~ ~~ , Radioactive waste release;1evels.to unrestricted areas should be kept "as low as reasonably achievable" and are not to exceed.the concentration limits. specified in 10-CFR.Part 20. At the same time, these specifications permit' i .the flexibility of operation, compatible with considerations of health. and safety.to assure'that the.public is provided a' dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20. It is expected.that'by using.this operational flexibility and exerting every effort-to keep levels or. radioactive materials } released as-low as reasonably achievable in accordance with criteria. established in 10 CFR 50. Appendix I, the annual-releases will not exceed a ~ small. fraction of the annual average concentration limits specified-in. .10 CFR Part 20. 3.8.A.' LIQUID EFFLUENTS 1 Specification.3.8.A.1 is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site.to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of-I water outside the site will result in' exposures within (1) the Section'11.A- ~ design objectives of Appendix I, 10 CFR Part 50, to anLindividual and (2) the limits of 10 CFR'Pcrt 20.106(e) to the population.- The concentration limit for noble gases is based upon the assumption that_Xe-135 is the controlling i radioisotope and its MPC in air'(submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. Specification 3.8.A.3 is provided to implement'the dose requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth the Section 11.A of' {. Appendix I. [ Specification 3.8.A.4 action statements provides the required operating ~~ j 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. j in liquid effluents will be kept "as low as is reasonably achiev'tble". Also, for fresh water sites with drinking water supplies which can be potentially ^ affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the l finished drinking water that are in excess of the-requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by. 1 4 291 Amendment No.132 0242p ~

.c

3.8.AcLIQUID EFFLUENTS (cont'd) 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 i- - Releases of Reactor. Effluents for the Purpose of Effluents from Accidentaland Routine Reactor Releases for the Purpose of Implementing Appendix I," April r 1977. NUREG-0133 provides methods for dose calculations. consistent with- -Regulatory Guides 1.109 and.1.113.. i-I ~ 3.8.B AIRBORNE EFFLUENTS V Specification 3.8.B.1 is provided to ensure that the dose rate at anytime at 4-the exclusion boundary from gaseous effluents from all units on the site will be within the annual' dose limits of 10 CFR Part 20.for unrestricted areas. i 'The annual dose' limits are the doses associated with the concentrations of 10 CFR part 20, Appendix B, Table II, Column 1. ~These limits provide ~ reasonable assurance that radioactive material discharged,in gaseous effluents will not result in the exposure of a member of the_public 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 ofL 10 CFR Part 20-(10 CFR Part 20.106(b))._ For. members of the public who may-at-times be within the exclusion area boundary, the occupancy of the member of-l the public will be sufficiently low to. compensate for any_ increase in the-atmospheric diffusion factor above that.for the exclusion area' boundary. t ) 5 4-f-e j 4 1 Il. 291A Amendment No.132 0242p

... - - ~ __ y. m X p ~ y' Q ~ ~3.8.B LAIRBORNE EFFLUENTS-(cont'd) 3 D I i ~ w IThe'specified release ra'te limits restrict, at~allstimes,(the corresponding; l s gamma and bet'a dose rates ~above background to anjindividual at or.beyond the ' c exclusion area boundary to'1500 mrem /ye' r to' the total body; or to- -j a < 3000 mrem / year to the. skin. These release: rate limits also restrict, at all ' times, the corresponding thyroid dcdeirate' above background to an infant via ~ j the cow-milk-infant pathway to 1-1500' mrem / year.for the nearest cow to the plant. 3 f Specification 3.8'.B.2 requires that appropriate correction' action (s) be taken p to reduce gaseous effluent releases if the limits of-3.8.B.1 are exceeded.. t I Specification 3.8.B.5' dose limits is provided to, implement the requirements of Section II.C, III.A,.and-IV of Appendix-I,;10 CFR Part-50.,'The limiting-conditions for operation are the guides set forth in Section II.C of Appendix I. j. s Specification.3.8.B.6 action statement provides 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 materials in gaseous effluents will_ be ~kept '?as low as is reasonably achievable". The ODCM.. calculational methods.specified in the surveillance requirements-implement'the-l requirements 11n'Section IIGA of Appendix I that conformance with the guides t of Appendix I be shown by-calculational proc'edures based on models and data l such that the actual. exposure of an individual through appropriate pathways is unlikely to be substantially, underestimatedV'The.0DCM calculational methods used for calculating the doses due to'the actual release rates of the subject i 4 materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculating of Annual Doses.to.Han from Routine ) Releases of Reactor Effluents foi the Purpose of Evaluating Corepliance with' l 10 CFR Part 50, Appendix I," Revision I,' October 1977, NUREG/CR-1004, "A 1 Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides",' October 197,9, and Regulatory F 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 radiolodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the s existing radionuclide pathways to man, in the unrestricted area. The pathways l-which are examined in the development of these calculations are: j-

1) individu'al inhalation of airborne radionuclides, ?)' deposition of l

. radionuclides onto green leafy vegetation with subsequent consumption by man,

3) deposition onto grassy areas where milk animal and meat producing animals 4

graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. Specification 3.8.B.6 action statement requires that.a special report be prepared and submitted to explain violations of the limiting doses contained-3 in Specification 3.8.B.S. j t 1, 4 291B 'l t Amendment No.132 ? l 0242p [ 1.= - .-.1..-

~. V P iAIRBORNE EFFLUENTS 1 Specification 3.8.B.7 requires that the-offgas charcoal.adsorber beds be used when specified to treat' gaseous effluents prior to their release to thel environment.. This provides reasonable' assurance that the release _of ~ i. radioactive materials in gaseous._ effluents will be kept "as low as.'is reasonably' achievable".. This specification implementsLthe' requirements,of.- 10 CFR'Part 50.36a, 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. 4 The specified limits' governing the use of.appropriat_e portions of 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. t Specification 3.8.B.8 requires that a special. report be prepared and submitted ~ to explain reasons for-any failure to comply with Specification 3.8.B.7. Specification 3.8.B.3 is provided to implement the requirements of Section II.B, III.A. and.IV.A of Appendix I, 10 CFR Part 50 =The Limiting Condition for Operation implements the guide set forth in'Section.II.C of Appendix I. 1 [ Specification 3.8.B.4 action statement provides the required operating l 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 materials in gaseous effluents will be kept "as low as is reasonably achievable". The l Surveillance Requirements implement the requirements in Section.III.A of-Appendix I~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 a member of the public through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the-j ODCM for calculating'the doses due to the actual release rates of radioactive j noble gases in gaseous effluents will 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 j with 10 CFR Part 50, Appendix I," Revision 1 October 1977, NUREG/CR-1004, "A i Statistical Analysis of Selected Paramete'rs for Predicting Food Chain: j Transport and Internal Dose of Radionuclides", October 1979 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion'of l 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.- Specifications 3.8.B.4 requires that a'special report be' prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.3. [ 4.8.A and 4.8.B BASES The surveillance requirements'given'under Specification 4.8.A and 4.8.B provide assurance that_ liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and l-I i i 291C Amendment No. 132 0242p

+ a 4~.8 A rnd 4.8.B BASES Icont'd) ~ 'y J gaseous effluents. These surveillance'requiYeiiienrs provide the data for the licensee.and the Commission.to evaluate the station's performanceErelative to radioactive wastes released to the environment. Reports'on the quantities of radioactive mrterials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications.- On the basis of such reports and any additional information the' Commission may-obtain from the licensee or.others, the Commission may from time togtime require the licensee to take such actions as;the Commission deems appropriate. 3.8.C and~4.8.C BASES 'This-specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and~ submittal of a Special Report whenever the calculated doses from plant radioactive effluents. exceed twice. the design-objective doses of' Appendix I. For sites containing up to four reactors, it is highly ualikely that-the resultant-dose.to a member of the public will exceed tha dose' limits of t.0 CFR 190 if'the' individual reactors remain within the reporting requirement-level.. The Special Report will- -describe a course of action which should result in the' limitation of dose to-a member of-the public for the calendar year to be within-40 CFR'190 limits. For-the purposes of the-Special Report, it may be assumed that the dose-commitment to the member of'the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions.from other nuclear 1 fuel cycle facilities at the same site or within a radius of five miles'must - be considered. 3.8.D and 4.8.D MECHANICAL VACUUM PUMP The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser. 'During an accident, fission products would be transported from the reactor. through ther main steam lines to the condenser. The fission product radioactivity would be sensed.by the main steam line radioactivity monitors which initiate: isolation. 3.8.E and 4.8.E BASES m The limitations on removable contamination for sources-requiring leak testing, I including alpha emitters, based on 10 CFR 70.39(c). limits for plutonium. ~ This limitation will ensure that leakage froml byproduct,' source, and special nuclear material sources will not exceed allowable intake values. sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with~the probability of. damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.. Sealed! sources which are continuously enclosed.within a shielded mechanism (i.e., sealdd' sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism. ) 291D Amendment'No. 132 0242p 1 i--.sd-

'6.0 ADMINISTRATIVE CONTROLS' k. Th2 radiologica1' environmental monitoring program and the ~ results thereof.at least once per-12 months. 1. The performance of activities required by the Quality' Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev. 1, 1974 and Regulatory Guide 4.1, 1975 at least once.per 12 months. m. The performance-of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d) at least once per 12 months. n.- The Offsite Dose Calculation Manual'and impicmenting procedures at least once per 24 months. o. The Process Control. Program and implementing procedures.for solidification of wet radioactive wastes at least once per 24- ~ ' months. p. The Radiological Effluent Manual and implementing procedures at least once per 12 months. 9. AUTHORITY ^ The NSRB shall report to and advise the Manager of Power on thore areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.C. 10. RECORDS Records of NSRB activities shall be prepared, approved and distributed as indicated below: a. Minutes of each NSRB meeting shall be prepared, approved and i forwarded to the Manager of Power within 14 days following each meeting. b. Reports of reviews encompassed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the_ review. l c. Audit reports encompassed by Section 6.2.A.8 above, shall be forwarded to the Manager of Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.. -1 334A Amendment No.132 0242p

q. I

I 6.0 ADMINISTRATIVE CONTROLS j

j. Review' proposed changes to the Radiological Effluent Manual.

j k. Review adequacy of the. Process Control Program and Offsite Dose Calculation Manual at least once every 24 months. 1. Review changes to the radwaste treatment. systems. E m. Review of every unplanned onsite release of. radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and deposition of the corrective action to prevent recurrence to the Director, Nuclear Power and to the Nuclear Safety Review Board. J 5. -Authority The PORC shall be advisory to the plant superintendent. 6. Records Hinutes shall be kept for.'all PORC meetings with copies sent to Director, Nuclear Power; Assistant Director of Nuclear Power (Operations); Chairman, NSRB. 7. Procedures Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of' committee actions, dissemination of minutes, agenda and scheduling of meetings. d 337 0242p. Amendment No 132

v ~ E6.0OADMINISTRATIVE_ CONTROLS 6.3-Procecares ~ ^ 4 'A Detailed written procedures, including applicable checkoff-lists.. ). covering' items listed below shall be prepared, approved and adhered x to.

1.. Normal startup. operation and' shutdown of the reactor and of all.

systems and components involving nuclear safety of the facility. j2. Refueling operations.

3.

Actions.to be-taken to correct' specific and foreseen potential-malfunctions of systems or. components, including responses'to _ ~ alarms, suspected primary system leaks and abnormal reactivity? changes. ~ J k 4. Emergency conditions' involving potential'or actual' release of. radioactivity. - 5. ' Preventive or corrective maintenance operations which could have l an effect on the safety of the reactor. 4.- I 6. Surveillance and testing requirements. E i 7.= Radiation control procedures. 8. Radiological Emergency Plan implementing procedures. -9. Plant security program implementing procedures. 10. Fire protection and prevention procedures. 11. Limitations on the-amount of overtime worked by individuals-performing safety-related functions inLaccordance with the NRC policy statement on working hours (Generic l Letter No. 82-12).- 12. Radiological Effluent Manual implementing procedures. 13. Process Control Program (PCP). 14. Offsite Dose Calculation Manual. B. Written procedures pertaining to those' items listed above:shall be reviewed by PORC and approved by the plant superintendent prior.to + implementation. Tempocary changes to a procedures which do not change the intent of the approved procedure may be made by'a member j of~the plant staff knowledgeable in the area'affected by the procedure except that temporary changes to those items listed above^ except item 5 require the additional approval of a member of the ~ -plant staff who holds a Senior Reactor Operator.. license on.the unit affecte_d. Such changes'shall.be documented and subsequently reviewed by PORC and approved by the. plant superintendent. I i 338 b ' Amendment Nu. 132 0242p w-, s .gr,g -g- -r- .,,<y..---e .,,-..p. ,...,y..9+..,.,, w e & tr s -i,e, e p a ,e w ,i..s.g,, .es7..-

.z' 6.0 ADMINISTRATIVE CONTROLS ~6.3: Procedures + E. Quality Assurance Procedures - Effluent and Environmental Monitoring- -Quality Assurance procedures shall-be' established, implemented, and maintained for effluent.and environmental monitoring, using the guidance in Regulatory Guide:1.21, rev. 1, June 1974 and Regulatory Guide 4.1, rev.-1, April 1975 or Regulatory Guide 4.15, Dec. 1977.- i. ll L i i f J t i i 4 i i 4-i i i i Amendment No.132 0242p 3 u w.e-

~- 6.0:.Adminirtrativa Controla '3; ' Unique Reporting' Requirements' A. - Radioactive-Effluent Release Report- . Dele t ed.' ' (See REM section F.2) ( i l .J ~ f j 4 - i l l L f. l .1 Amendment No.132 0242p f y ,y-- ---p-g 7#~ v

~ ,6.0.. ADMINISTRATIVE COlfIROLS i 6.9 Process Control Program (PCP) ~ ' ~ ~ ~ ^ ~ 1. The PCPLshall be approved by the Commission prior to implementation.

2... Changes to the PCP shall be-submitted to the Commission'in~the'-

E ' semi-annual Radioactive Effluent Release Report forfthe period' In which the_ change (s)._was made. This submittal shall contain: t- .Sufficiently detailed-information to totally support-the-a. change. b. A. determination that the':hange did not change the overall' conformance of_the. solidified product to existing criteria. 3.- Changes to the PCP shall becomefeffective upon review andL acceptance by PORC.. 1 6.10 Offsite Dose Calculational Manual (ODCM)

1..The ODCM shall be approvsd by the' Commission prior to implementation.

2. - Changes to the ODCM shall be submitted to the Commission in the semi-annual Radioactive Effluent. Release Report for the period in which the change (s) was made. This submittal shall contain: Sufficiently detailed information to totally support'the a. change. i 3. Changes to the ODCM shall'become effective upon review'and acceptance by PORC. 4 -6.11 RADIOLOGICAL EFFLUENT MANUAL (REM)- 1. The REM'shall be approved by the Commission ~ prior to implementation. 2. Changes to the REM shall be reviewed by PORC prior to implementation. ] 3. Changes to the REM shall be approved by the Commission' prior to implementation. L 1 i Amendment No.-132 ~ 0242p 4 -m--- c-, -m.

APPENDIX B TECHNICAL SPECIFICATIONS BROWNS FERRY UNITS 1 AND 2 '9 .0242p Amendment No. 132

j a ~ ~ ENVIRONMENTAL' TECHNICAL SPECIFICAITONS FOR-BROWNS FERRY NUCLEAR PLANT. . TABLE OF CONTENTS Page No. 1.0' DEFINITIONS..'.......................................... _. Deleted-2.0 LIMITING CONDITIONS FOR OPERATION...................... Deleted 2.1 Thermal Discharge Limits.......................... _ Deleted '2.2 Chemica1.......................>................... Deleted ~ 2.2.1 Makeup Water Treatment Plant Spent Demineralizer Regerants.................. Deleted 2.2.2 Ch1orine'...........'....................... Deleted 3.0 DESIGN FEATURES AND OPERATING PRACTICES................ Deleted 3.1 Chemical Usage.................................... Deleted 3.1.1 Oils and Hazardous Materials............... Deleted 3.1.2 Othsr Chemicals............... ............ Deleted 3.2 Land Management................................... Deleted 3.2.1 Power Plant Site........................... Deleted-3.2.2 Transmission Line Right-of-Way Maintenance. 1 3.3 Onsite Meteorological Monitoring.................. Deleted 4.0~ ENVIRONMENTAL SURVEILLANCE...................'.......... Deleted 4.1 Ecological Survei11ance........................... Deleted 4.1.1 Abiotic.................................... Deleted 4.1.2 Biotic..................................... Deleted 4.1.3 Special Studies............................ Deleted 4.2 Radiological Environmental Monitoring Program..... Deleted 0242p-Amendment No. 132

~ r. r F ~5.0 ADMINISTRATIVE CONTR0LS................................ Deleted ~5.1 -Responsibility..........................'........... De'eted .I 5.2' Organization...................................... Deleted -5.3 Review and Audit.................................. Deleted 5.4 Action to be Taken if an Environment LCO is Exceeded........................................ Deleted ',5.5. Procedure.'................................ ....... - Deleted .5.6 Reporting Requirements............................ Deleted 5.7 Environmental. Records.........................'... Deleted Tab1es...................................................... Deleted-Figures..................................................... Deleted i 4 t i i t i d i I J l 1 1 i 1 4 i l 9 i 1 I 0242p Amendment. No. 132 4- - = .-g,w. ,-,.,w e n.-eg- ...-w -e ~ -- -

~ -3.2.2 Transmicsion Lina Right'-of-W"y Mnintantnc9 . Objective -The-sole purpose of this section.is to provide. reporting-requirements (to USNRC) on herbicide usage, if any, for purposes'of- ,right-of-way maintenance.regarding only.those transmission lines .under USNRC's' jurisdiction'for-the Browns Ferry: Nuclear Plant. . Specification-r A statement as to whether or not herbicides have.been used in-maintaining rights-of-way for those transmission lines associated; <with the Browns Ferry Nuclear Plant shall be provided.; If. herbicides have been used,-a description of the types,. volumes, concentrations,. manners and frequencies;of application, and. miles or. rights-of-way that have been treated shall'be included. Reporting Requirements .Information as specified above shall be provided in the Annual. . Operating Report (Appendix A, Section 6.7.1(b)). o Bases Vegetation growth on a transmission line right-of-way must.be-controlled in such a manner that it will neither interfere with: safe and reliablefoperation of the'line or impede restoration of service when outages occur. Vegetation growth is' controlled by mechanical cutting and the limited use of herbicides.. Selected chemicals approved by EPA for use as herbicides are assigned (by EPA) label instructions which provide guidance on and procedures.for their use. .. 0242P Amendment No.132

-y Iw L-g gg - - .q- ~ 'o 'f . UNITED $TATES 8 ^ NUCLEAR REGULATORY COMMISSION ~ o 7 WASHINGTON, D. C. 20666 \\g*...*]j [ ? 1 [. TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260-J BROWNS FERRY NUCLEAR PLANT, UNIT 2-AMENDMENT TO FACILITY OPERATING LICENSE I -Amendment-No. 128 i . License No. DPR-52 4 1. The Nuclear Regulatory Comission (the Comission). has found-that: F A. The. applications for amendment by Tennessee Valley Authority'(the l licensee)-dated September 30, 1986, comply with the. standards and. i reouirements of the Atomic Energy Act of 1954, as amended (the Act),' and the Comission's rules and regulations-set.forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations.of-the Comission; C. There is reasonable assurance (1) that the activities authorized by. i this amendment can be conducted without endangering the health and j safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 1 l' D. The issuance of-this amendment will not be inimical'to the common i defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR'Part 51-of the Comission's regulations and all applicable requireme~nts have been satisfied. 2. Accordingly, the license is amended by change's to thi Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility ' Operating License No.' DPR-52 is hereby amended to read as follows: 1 4 1 1' .---L. ._,-,...a---,..-,------,,.--.-_-. ~ _ - _, - ~., .-A.--- .-,4,. ~.--r

1 4 ._ (2) Technical Specifications 'The Technical Specifications contained in-Appendices A and B,-as. revised through Amendment No.128, are hereby incorporated in the license. -The licensee shall operate the facility-in accordance with the Technical Specifications. 3. This license amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION ' g-AI$ U Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: February 5,1987 j 4

ATTACHMENT TO LICENSE AMENDMENT N0.128 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Replace the following pages of the Appendix A Technical ' Specifications with the enclosed pages. The revised areas are indicated by marginal lines.- Pages i 286 11 287 iii 288 iv 289 y 290 vi 290A vii 291 viii 291A 7 2918 7A 291C 78 291D 7C 334A 51 337 52 338 54 340 54A 355 76 359 76A 84A 848 103 103A 108A 108B 115A 118 179 261 282 283 284 285 Revise Appendix B as follows: Table of Contents 2 pp.

TABLE OF~ CONTENTS-Page No. - Section ~ Introduction.................... 1 ~ ~ 1.0 Definitions.....~............-.. 2 SAFETY LIMITS AND LIMITING' SAFETY SYSTEM-SETTINGS 1.1/2.1 Fuel Cladding Integrity 8 -1.2/2.2 ' Reactor Coolant' System Integrity........ 27 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.1/4.1 Reactor Protection System 31 3.2/4.2 Protective Instrumentation-50 A. Primary Containment and Reactor Building Isolation Functions 50 B. Core and Containment Cooling Systems - Initiation and Control. 50 C. Control Rod Block Actuation 51 D. Radioactive Liquid Effluent Monitoring Instrumentation 51 E. Drywell Leak Detection............ 52 F. Surveillance Instrumentation........ 52 G. Control Room Isolation........... 52 H. Flood Protection-.............. 53 I. Meteorological Monitoring Instrumentation 53 ~J. Seismic Monitoring Instrumentation..... 54 K. Radioactive Gaseous Effluent Monitoring Instrumentation 54 3.3/4.3 Reactivity Control..... 120 A. Reactivity Limitatioas........... 120 B. ' Control Rods................ 121 C. Scram Insertion Times 124 i Amendment No. 128 0241p

c ..} N .'%'tr Section-P' age No. 'D. Reactivity Anomalies.............:.... 125I. -E. Reactivity Control.................- 126 F. Scram Discharge Volume....-...:........

126

'3.4/4.4 Standby Liquid Control System 1. 135 A. Normal System Availability..............- 135 B. Opers. tion with Inoperable Components.....-.. 136 C. Sodium Pentaborate Solution 137 3.5/4.5 Core and Containment Cooling Systems...'...... 143 A. Core Spray System (CSS)

143 B.

Residual Heat Removal System (RHRS) i (LPCI and Containment Cooling). 145 C. RHR Service Water System and Emergency Equipment Cooling

• Water

,151 System (EECWS). D. Equipment Area Coolers.............. 154 i 1 4 E. High Pressure Coolant Injection System j (HPCIS)

154, F.

Reactor Core Isolation Cooling System (RCICS) 156' G. Automatic Depressurization System (ADS) 157 H. Maintenance of Filled Discharge Pipe'...... 158 ^ I. Average Planar Linear Heat Generation Rate................'....... 159 l J. Linear Heat Generation Rate (LHGR). 159 K. Minimum Critical Power Ratio (MCPR) 160 t L. APRM Setpoints.................. 160A M. Reporting Requirements............... 160A 1 l 3.6/4.6 Primary System Boundary 174 l l A. Thermal and Pressurization Limitations...... 174 B. Coolant Chemistry 176 11 Amendment No. 128 '0241p

1 - Section Prgo No. C. Coolant Leakage..........;.............- ~180: D. Relief Valves -181 E.. Jet Pumps 181 F. Recirculation Pump. Operation'......;..... 182 .G. . Structural Integrity-.........'....... 183 H. Seismic Restraints, Supports and. Snubbers 185, . 3.7/4.7 Containment Systems 227 A.- Primary Containment-227 B. Standby Gas Treatment System........... 236-C. Secondary Containment 240 ~ D. Primary Containment Isolation Valves....... 242 E. Control Room Emergency Ventilation........ 244 F. Primary Containment Purge System.......... 246-G. Containment Atmosphere Dilution System (CAD) 248 H. Containment Atmosphere Monitoring (CAM) System H Analyzer 249 1 3.8/4.8 Radioactive Materials 281 i. A. Liquid Effluents................. 281 B. Airborne Effluents..............:.. 283 ~i C. Radioactive Effluents - Dose............ 286 D. Mechanical Vacuum Pump.............. 286 A E. Miscellaneous Radioactive Materials Sources 287 F. Solid Radwaste............-...... 289 3.9/4.9 Auxiliary Electrical System 292 4 i A. Auxiliary Electrical Equipment.... 292 J 4 B. Operation with Inoperable Equipment 295 i C. Operation in Cold Shutdown............ 298 i l 3.10/4.10 Core Alterations................... 302 i A. Refueling Interlocks............... 302 III l Amendment No. 128 j 0241p i

Section P ga'No. 305-B.. ' Core Monitoring. :... 7 C.- Spent Fuel Pool Water... 1.z. 305: .D. Reactor Building Crane'.............. 307-E. . Spent Fuel Cask 3075 F. Spent' Fuel Cask Handling-Refueling Flocr...... 308-315 3.11/4.11 Fire Protection Systems A. High Pressure Fire Protection System... 315 B. 003 Fire Protection' System..........-.. 319 C. Fire Detectors....:.............-. 320 D.- Roving Fire Watch 321 E. Fire Protection Systems Inspection......=.. 322 F. Fire Protection Organization.........;... 322 323 G. Air Masks and Cylinders H. Continuous Fire Watch 323 I. Open' Flames, Welding and Burning in the Cable-Spreading Room................... 323. 5.0 Major Design Features 330 5.1 Site Features '330 5.2 Reactor 330 330 5.3 Reactor Vessel................... 330 5.4 Containment 5.5 Fuel Storage................... 330 1 5.6 Seismic Design.................. 331 6.0 Administrative Controls 332 332 6.1 Organizatior. 6.2 Review and Audit. 333 1 '1 Iv Amendment No. 128 0241p.

Seetion Page No. _c., ~6.3 Procedures................... 338 6.4 Actions to be Taken in the Event of a Reportable Occurrence in Plant Operation.. 346-6.5 Actions to be taken in the Event a Safety Limit is Exceeded 346. 6.6 Station Operating Records 346' 6.7 Reporting Requirements 1 .349 6.8 Minimum Plant Staffing............. 358 1 V Amendment No.128 0241p

LIST OF TABLES Table Title Page No. 1.1 Surveillance Frequency Notation 7c 3.1.A Reactor Protection System (SCRAM) Instrumentation Requirements............... 33 4.1.A . Reactor Protection System (SCRAM) Instrumentation Functional Tests Minimum Functional Test Frequencies for Safety Instrumentation and Control Circuits............ 37 4.1.B Reactor Protection System (SCRAM) Instrument Calibration Minimum Calibration Frequencies for Reactor Protection Instrument Channels.... 40 3.2.A Primary Containment and Reactor Building Isolation Instrumentation 55 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 62 3.2.C Instrumentation that Initiates Rod Blocks 73 3.2.D R>dioactive Liquid Effluent Monitoring Instrumentation 76 3.2.E " Inctrumentation that Monitors Leakage Into Drywell. 77 3.2.F Surveillance Instrumentation.... 78 3.2.G Contcol Room Isolation Instrumentation... 81 3.2.H Flood Protection Instrumentation........ 82 3.2.I Meteorological Monitoring Instrumentation 83 3.2.J Seismic Monitoring Instrumentation......... 84 3.2.K Radioactive Gaseous Effluent Monitoring Instrumentation 84A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation.. 85 4.2.B Surveillance Requirements for Instrumentation that Initiate or Control the CSCS. 89 4.2.C Surveillance Requirements for Instrumentation that Initiate Rod Blocks 102 4.2.D Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements..... 103 4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation.... 104 vi ^ "" '" "O* 0241p

7 c. y + LIST OF TABLFS (Oaat'dF I L- 'Titik Page No. Jable Minimum Test and, Calibration Frequency for 4.2.F 105 Surveillance Instrumentation.........-..~ . Surveillance Requirements for Control. Room .a.2.G Isolation Instrumentation- '106

s >

Minimum Test and Calibration Frequency for a.2.H (107- . Flood Protection Instrumentation.......... 108 Seismic Monitoring' Instrument Surveillance..... a.2.J Radioactive Caseous' Effluent' nstrumentation a.2.K 108A Surveillance........[............. 152ai Minimum RHRSW and EECW Pump Assignment. 3.5-1 171, 172,. 3.5.I MAPLHGR Versus Average Planar Exposure'....... 250 -3.7.A . Primary Containment Isolation Valves......... 256: Testable Penetrations with Double 0-Ring Seals... 3.7.B 257 3.7.C Testable Penetrations with Testable Bellows 258 3.7.D Air Tested Isolation Valves 3.7.E Primary' Containment Isolation' Valves which Terminate below the Suppression Pool Water 262 Level '........ 3.7.7 Primary Containment. Isolation Valves-Located-in Water Sealed Seismic Class 1 Lines......... 263 3.7.H Testable Electrical Penetrations.......... 265 4.9.A.4.C Voltage Relay Setpoints/ Diesel Generator Start. 298a 3.11.A Fire Protection System Hydraulic Requirements 324 360 6.8.A Minimum Shift Crew Requirements Amendment No.128 vil 0241p

LIST OF ILLUSTRATIONS ^ Figure: Title Page No.

2.1.1 APRM Flow Reference Scram and APRM Rod Block

-Settings............_.......... 13 2.1-2 APRM Flow Bias Scram Vs. Reactor Core Flow...'. 26 '4.1-1 Graphic Aid in'the Selection of an idequate Interval Between Tests............'.. 49 4.2-1 / System Unavailability.-.:......_....... 119 3.4-1 Sodium Pentaborate. Solution Volume Concentration? Requirements.................... 138-3.4-2 Sodium Pentaborate Solution Temperature Requirements.......-...........'. 139 3.5.K-1 MCPR Limits 172a 3.5.2 K r Fac t o r..................... - 173 3.6-1 Minimum Temperature *F Above Change in Transient Temperature -194 3.6-2 Change in Charpy V Transition Temperature Vs. Neutron Exposure................. -195 4.8.la Gaseous Release Points and Elevations 290 4.8.lb Land Site Boundary.......... 290A 6.1-1 TVA Office of Power Organization for Operation of Nuclear Power Plant. 361 6.1-2 Functional Organization 362 6.2-1 Review and Audit Function 363 6.3-1 In-Plant Fire Program Organization.._....... 364 l Amendment No.128 yiii 0241p.

^ i 1.0 DEFINITIONS-(Cont'd) Logic-Alogicisanarrangementofrelays.. con 5 cts,'andother 10.

components that produces a decision output--

'(a)' Initiatina - A' logic that receive signals from channels and produce decision outputs to the actuation logic.- (b). Actuation - A logic that receives signals (either from-initiation logic or channels) and produces decision outputs to accomplish a protective! action. ~ -11. Channel Calibration -'Shall.be the adjustment,-as necessary, of'the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel-monitors. The channel calibration shall'encompara the entire ~ channel including alarm and/or trip functions and shall include the channel functional test. The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this requirement, but will be included.in channel functional test and source check. 12. Channel Functional Test - Shall.be: a. = Analog Channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions. b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions. 13. Source Check - Shall be the qualitative assessment of channel response when the channel sensor is exposed to a' radioactive source or multiple of sources. 'k T t i 7 Amendment No. 128 0242p

4, r x -c !1.0'= DEFINITIONS (Cont'd) ~ ^' ~ W.- Functional Tests - A functional' test'is7the manual operation orL initiation of a system.. subsystem,'or components'to verify thatl 'it functions within design tolerances'(e.g., the. manual start of. a core spray pump to verify that-it runs and'that it pumps the- ' required volume of water)..- X. ' Shutdown.- The reactor is in'a shutdown condition when the . reactor mode switch is in-the shutdown mode position'and no core alterations lare being~ performed. .Y.' Engineered-Safeguard - An engineered safeguard is.a safety system the actions of which are essential to a" safety action required in response to accidents. 2. Reportable Event - A reportable event shall'be any'of those conditions specified in section 50.73 to 10 CFR Part 50.1 AA. Solidification - Shall be the conversion'of radioactive wastes into a form that meets shipping ~and burial ground requirements... 9 B5. Offsite Dose Calculation Manual (ODCN) - Shall be a manual' describing the environmental monitoring program and the methodology and parameters used in the calculation of release _ rate limits and offsite doses due to radioactive gaseous"and and liquid effluents. The ODCM will'also provide the plant'with guidance for establishing alarm / trip setpoints to ensure technical specifications sections 3.8.A.1 and 3.8.B.1 are not-j exceeded. CC. Purge or purging - The controlled process of discharging air or gas from the primary containment to' maintain temperature, pressure, humidity, concentration, or other operating condition-in such a manner that replacement air or gas is required-'to purify the containment. t DD. Process Control Program - Shall contain the sampling.. analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured. EE. Radiological Effluent Manual (REM) - Shall be a manual containing the site and environmental = sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those' radionuclides which ~ lead to the highest potentia 11 radiation exposure to individuals from station operation. 'It shall also specify operating guidelines for radioactive waste treatment systems and report content. FF. Venting - The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in'such a manner tbst replacement air or gas is not provided or required. Vent, used in system names, does not imply a venting process. Amendment No. 128 7A 0242p m.

y. _, ~. ~, i i ,y I '1.0 DEFINITIONSL(Cont'd)~ GG. -Site Boundary.- Shall'be that line beyond.which the land'is'not1 owned, leased, or otherwise_ controlled by TVA.' NH. Unrestricted' Area - Any area at or beyond the' site boundary to .which access is not controlled by the licensee for purposes'of I protection of, individuals from' exposure to radiation and-radioactive materials or any area within the site boundary-used I for industrial, commerciali institutional, or recreational purposes.- 4 p II. - Dose Equivalent I-131 - The DOSE. EQUIVALENT I-131 shall be the J concentration of I-131;(in pCi/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of2 I-131, I-132, I-133,-I-134, and I-135 actually present. -The thyroid dose conversion factor used for this calculation shall i be those listed in Table III of TID-14844 " Calculation of Distance Factors for Power;and Test Reactor Sites". i ~ JJ.. Gaseous Waste Treatment System - The charcoal adsorber vessels installed on the discharge of'the steam' jet air ejector to; { j provide delay to a unit's offgas activity prior to release. } l j KK. Members of the Public - Shall* include all individuals.who by j virtue of their occupational status have no formal' association-i with the plant. This category shall include non-employees of-l the licensee who are permitted to use portions of the site for i recreational, occupational, or other purposes'not associated j with plant functions. This' category shall not include non-employees such as vending machine servicemen or postmen who,. i as part of their formal job function, occasionally enter i i restricted areas. l LL. Surveillance - Surveillance Requirements shall.be' met-during the OPERATIONAL CONDITIONS or.other conditions specified for' individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.. Each surveillance Requirement shall be performed within the specified j ~ time interval with, (1) A maximum allowable extention not to exceed'25% of the survelliance interval, but } (2) The combined time entered for,any 3 consecutive i surveillance intervals shall not exceed 3.25 times'the ]- specified surveillance interval [ Performance of a Surveillance Requirement within the.specified' j-time interval'shall constitute compliance and OPERABILITY l requirements for a limiting condition for operation and 1 associated action statements unless otherwise required by these I specifications. Surveillance requirements do not have to be performed on inoperable equipment. l 1 i 1 i t Amendment No. 128 78 i

0242p j

e 4 y T*bl 1.1 [ --SURVEILLANCE FREQUENCY NOTATION i NOTATION: FREQUENCY-S ' (Shift) .At least'once per 12 hours. D, (Daily) At least once per normal calendar ~ 24 hour day (midnight to midnight). i ~ (Week 1y)- At'least once per'7 days. i-W- ( M. (Monthly) 'At least once per 31' days. ~~ + ..-Q-(Quarterly) _At-least once per 3 months'or 92 days. .SA (Semi-Annually At.least once per 6 months or'184 days. 4 i Y (Yearly) At least once per. year or.366 days. R (Refueling) At least once per operating cycle. S/U._(Start-Up) Prior to each reactor startup. N.A. Not applicable. P (Prior) Completed prior to each release. I b Amendment No. 128 7C 0242p t

7 ~

• j Q<

']. ~ ,r. d. LIMITING CONDITIONS-FOR OPERATION' SURVEILLANCE REQUIREMENTS' 13 2.B' ' Core and Containment Coolina,. ~ X 2.5 C6ee~and ContainmeYit Cooling Systems - Initiation & Control Systems - Initiation & Control q ~ ~(: .m, ~ are: required to be operable z_ sc.. shall~be considered operable-if + ithey are within the required: ~ ~ surveillance testing frequency; i ' and there is no reason to suspect that they,are . inoperable.. f y s - C. Control Rod Block Actuation' -C. Control' Rod Block Actuation i Thelimiting'co$ditionEof,

Instrumentation'shall be'

. operation for the instrumentation functionally' tested, that initiates control rod block ' calibrated, and checked as. are given in Table 3.2.C. indicated in Table 4.2.C. System logic shall;be s 4 functionally tested as'. indicated.in Table 4.2.C. 3.2.D Radioactive Liqu'id Effluent 4.2.D kadioactiveLiquidEffluent. Monitorina Instrumentation ' Monitorina Instrumentation c 1. The radioactive liquid l 1.' Each of the radioactive effluent monitoring _ liquid effluent monitoring. Instrumentation listed in - instruments shall be Table 3.2.D shall be demonstrated operable by operable with the performance of. test in applicability as shown in~- accordance with Table 4.2.D. Tables 3.2.D/4.2.D. Alarm / 1 trip'setpoints will be set in accordance with guidance given in the ODCH to ensure that the limits of. specification 3.8.A.1 are i not exceeded. s 2. The action' required when.the number of operable channels is less than the minimum channels operable requirement J is specified in the notes for Tabla *3.2.D. Exert best efforts to return the instrument (s)'to OPERABLE-status within 30 days-and if unsuccessful.. explain =in the next Semiannual Radioactive Effluent Release' Report why the inoperability was not corrected in' a timely manner. s 51 .s Amendment No.128 N'- e 0233p

^m a e ~ a' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS !I 3.2.D ; " Radioactive Liquid Effluent > '4.2.D -Radioactive Liquid Effluent .(Con't)- (Con't) 1 ~3; kith a radioactive liquid effluent monitoring channel- , alarm / trip'setpoint less conservative'than required

by

these specific.ations,

-suspend the release without delay, declare the channel It inoperable, Lor adjust the l ' alarm / trip setpoint to !~ establish the conservatism required by these 4 specifications.. 4. The provisions of . specification 1.0.C and 6.7.2 are not applicable. E. Drywell Leak Detection E. Drywell Leak-Detection l The limiting conditions of Instrumentation shall be operation for the instrumentation calibrated and checked as that monitors drywell leak indicated in Table 4.2.E. detection are given in i Table 3.2.E. F. Surveillance Instrumentation F.: Surveillance Instrumentation l The limiting conditions for the Instrumentation shall be: j' instrumentation that provides calibrated and checked as surveillance information readouts indicated in Table 4~.2.F. are given in Table 3.2.F. G. Control Room Isolation G. Control Room Isolation k i. The limiting conditions for ' Instrumentation shall be instrumentation that isolates-calibrated and checked as the control room and initiates indicated in Table 4.2.G. the control room emergency pressurization systems are given in Table 3.2.G. I 1 Amendment No.128 l' 0233p

c k ' LIMITING CONDITIONS FOR' OPERATION O SURVEILLANCE REQUIREMENTS ' 3.2.J ' Seismic Monitorina Instrumentation 4.2.J SeismifMonitorina Instrumentation

1. 'The seismic monitoring 1.

Each of.the seismic-instruments listed in monitoring instruments Table 3.2.J shall be shall be demonstrated operable at all times, oper&bie by performance of tests at the frequencies-

2. 'With the number of. seismic listed in Table 4.2.J.

monitoring instruments.less-than the' number listed.In .2. Data shall be retrieved Table 3.2.J. restore the from all seismic inoperable instrument (s) to sinstruments. actuated during operable status within a seismic ~ event and 30 days. analyzed to determine the magnitude of the vibratory 3. With one or more of the ground motion. A Special' ~ instruments listed in Table Report shall,be submitted. ) 3.2.J inoperable for more to the Commission pursuant than 30 days, submit a to specification 6.7.3.D Special Report to the within 10 days describing; Commission pursuant.to the magnitude, frequency rpecification 6.7.3.C within spectrum, and resultant: the next 10 days describing effect upon plant features the cause of the malfunction important to safet'y. and plans for restoring the-s instruments to operable status. Aa 3.2.K Radioactive Gaseous Effluent 4.2)K Radioactive Gaseous Effluent Monitoring Instrumentation Monitoring Instrumentation T 1. The radioactive gaseous 1. Each of the'radiodet'ive effluent monit) ring gaseous effluent monitoring d. instruments listed in instruments shall be. J Table 3.2.K shall be demonstrated operable by' # operable.with the performance of tests in i applicability as shown in accordance with Table 4.2.K.. Tables 3.2.K/4.2.K. Alarm / e trip setpoints will be set T I in accordance with guidance 'given in the ODCM to ensure that-the limits of specification 3.8.B.1 are not exceeded. y. ~ ) 54 Amendment No. 128 0233p .n Wi d-

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Caseous Effluent Monitoring Instrumentation Monitoring Instrumentation (Con't) (Con't) 2. The action required when the number of operable channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 3.2.K. Exert best efforts to return the instruments to operable status within 30 days.and, if unsuccessful, explain in the next Semiannual Radioactive Release Report why the inoperability.was not corrected in-a timely manner. 3. With'a radioactive gaseous. effluent monitoring channel alarm / trip setpoint less conservative.than required by ~ these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm / trip setpoint to establish the conservatism required by these specifications. 4. Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance. 5. The provisions of specifications 1.0.C and 6.7.2 are not applicable. Amendment No.128 54A 0233p

1-TABLF 3.2.0 Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument Operable Applicability Action 1. LIQUID RADWASTE EFFLUENT 1 A, B; MONITOR (RM-90-130) 2. RHR SERVICE WATER MONITOR 1 C (RM-90-133. -134) 3. RAW COOLING WATER MONITOR 1 D -(RM-90-132) 4. LIQUID RADWASTE EFFLUENT 1 E FLOW RATE (77-60 loop excluding fixed in line rotometer) ' Amendment No. 128 76 .0240p j

NOTES FOR TABLE 3.2.D '*At.all times

• • During releases via this pathway
    • During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the" following shall be met (1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.1, (2) if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in the REM and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge. Otherwise, suspend release via this pathway.

ACTION B With a radioactive liquid effluent monitoring channel / alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm / trip setpoint to establish the conservatism referred by these specifications. ACTION C During operation of an RHR loop and associated RHR service water system, the effluent fr6a that unit's service water shall be continuously monitored. If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours and an analysis of at least an LLD'**of IE-7 pCi/ml (gross) or < applicable MPC ratio (y isotopic ) shall be used to monitor the effluent. ACTION D t 4 With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided that a temporary monitor is installed or, at least once per 8 hours, grab samples are collected and analyzed for radioactivity with an LLD'*)of IE-7 pCi/ml (gross) or < applicable MPC ratio (y isotopic). ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. ACTION F Alarm / trip setpoints will be calculated in accordance with the guidance given in the Offsite Dose Calculation Manual (ODCM). (1) See REM, TABLE NOTATIONS - TABLE C-1, for the definition of LLD. 76A Amendment No.128 0242p

~.. TABLE 3.2.K Radioactive' Gaseous Effluent Monitoring Instrumentation i Minimum Channels / Instrument Devices Operable Applicability Action. 'lI. STACK (RM-90-147A & B)- a. Noble Gas Monitor (1) A/C b. Iodine Cartridge (1) B/C 1 c. Particulate Filter (1) B/C d. Sampler Flow Abnormal (1) .D l e. Stack Flow.(FT,.FM, (1) D -FI-90-271) 'I 2. REACTOR / TURBINE BLDG VENTILATION (RM-90-250)- a. Noble' Gas Monitor. (1) A/C b. -Iodine. Sampler (1) .B/C c. Particulate Sampler (1) ^ B/C. d. Sampler Flowmeter (1) D 3. TURBINE BLDG EXHAUST (RM-90-249, 251) .a.* Nchle Gas Monitor-(1) A/C b. . Iodine Sampler. (1) B/C.

c.. Particulate Sampler (1)

B/C d. Sampler Flowmeter (1) D 4. RADRASTE BLOG VENT.(RM-90-252) - a. Noble Gas Monitor (1) A/C b. Iodine Sampler. -(l) 'B/C ' c. Particulate Sampler (1) B/C 4

d. -Sampler Flowmeter (1)

D i . 5. OFF GAS HYDROGEN ANALYZER (H,A, H,B) (1) E

6. '0FF GAS POST TREATMENT

-a. ' Noble Gas' Activity Monitor .(RM-90-265, 266) .(1) F . b.. Sample Flow Abnormal .(PA-90-262) (1)' D Amendment No. 128 84A - 0240p-

+ e NOTES FOR TABLE 3.2.K. s

• At all times'
  • During releases via-this pathway

' ***During main condenser offgas' treatment ' system operation ' ACTION A With the' number of channels OPERABLE less than required by the Minimum ~ l Channels Operable requirement, effluent releases via the affected.pathw'ay may continue provided a temporary monitoring system is installed or grab samples. are taken and analyzed at least once every 8 hours. ACTION B With a number of channels OPERABLE less than required ~by the. Minimum Channels ~ Operable requirement, effluent releases via this pathway may continued provided samples are continuously collected with auxiliary sampling equipmen't' for periods on the order of seven (7) days and analyzed in accordance with the sampling and analysis program specified in the REM within 48 hours'after the end of the sampling period. ACTION C' A monitoring system may be out of service for 4 hours for functional' testing. calibration, or repair without providing'or initiating grab sampling. ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours and-analyzed within the following 4 hours. ^ ACTION F 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 at least once per 8 hours and these samples-i are analyzed for gross activity within 24 hours. Purging during SI performance is not considered a loss of monitoring capability. I i Amendment No.128 0242p ~ L u 1 I

1 TABLE 4.2.D. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance. Requirements Channel Functional l Instrument Instrument Check Source Check. Calibration Test 1. LIQUID RADWASTE EFFLUENT D(4) M R(5) Q(1) MONITOR (RM-90-130) 2. RHR SERVICE WATER MONITOR D(4) M R(5) Q(2) (RM-90-133, -134) 3. RAW COOLING HATER MONITOR D(4) M ~R(5) Q(2) (RM-90-132) 4. LIQUID RADWASTE EFFLUENT D(4) NA R Q(3) FLOW RATE (77-60 loop) t- -Amendment No. 128 103 0240p

~ .r m s t - 4 T NOTES'FOR TABLE 4.2.D -(1) The channel functional test lshall also demonstrat'e'thAt' automatic isolation of this pathway and control room annunciation occurs if any of. ~ the.following conditions exist:. a. Instrument indicates measured levels above the alarm / trip setpoint' ~ b.. Instrument indicates an inoperative /downscale failure c. Instrument controls not set in operate mode-(2) The channel functional test'shall also' demonstrate that control room , annunciation occurs if any of-the following conditions exist: Instrument-indicates measured levels above the alarm / trip setpoint a. ib. fInstrument indicates;an' inoperative /downscale failure < - c.--Instrument. controls not set in operate mode (3) This functional test shall consist of-measuring-rate of tank decrease 'over a period of time and comparing this value with flow rate instrument-reading.. (4) ~ INSTRUMENT CHECK.shall consist of verifying indication during periods of release. INSTRUMENT CHECK shall be made at least once.per 24 hours on days which continuous, periodic, or batch' releases are made. (5) The CHANNEL CALIBRATION shall include the use of a known.(traceable to -National Bureau of Standards Radiation Measurement System) radioactive source (s) positioned in a reproducible geometry with respect to the-sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with'the NationalEBereau of Standards (NBS). U3^ Amendment No.128

0242p

1 TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Channel functional Instrument Instrument Check Source Check Calibration Test 1. STACK a. Noble Gas Monitor i D M R Q b. Iodine Cartridge H NA NA NA c. Particulate Filter H NA NA NA d. Sampler Flow Abnormal D NA R Q e. Stack flowmeter D NA R Q 2. REACTOR / TURBINE BLDG VENT a. Noble Gas Monitor '*' D M R Q b. Iodine Sampler H NA NA NA c. Particulate Sampler H NA NA NA d. Sampler flowmeter D NA R Q 3. TURBINE BLDG EXHA'JST a. Noble Gas Monitor D M R Q b. Iodine Sampler H NA NA NA c. Particulate Sampler H NA NA NA d. Sampler Flowmeter D NA R Q 4. RADHASTE BLDG VENT a. Noble Gas Monitor '*' D M-R Q b. Iodine Sampler H NA NA NA c. Particulate Sampler H NA: NA NA d. Sampler Flowmeter D NA R Q 5. OFF GAS HYDROGEN ANALYZER (H,A, H,B) D NA R Q'*' 6. OFF GAS POST TREATMENT a. Noble Gas Activity Monitor D M R Q b. Sample flow Abaormal D NA R Q Amendment No. 128 108A 0240p

NOTES FOR TABLE-4.2.K. (1)'.The CHANNEL CALIBRATION shall include the use of a known (traceable to the National-Bureau of Standards Radiation Measurement System) radioactive source (s) positioned in a reproducible geometry'with. respect to the sensor or using standards that have obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards. (2) 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. Instrument indicates an inoperative /downscale failure. c. Instrument controls not set in operate mode (stack only). (3) The channel calibration shall include the use of standard gas samples containing a. nominal: a. Zero volume percent hydrogen (compressed' air) and, b. One volume percent hydrogen, balance nitrogen. '(4) The channel functional test shall demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exists: a. Instrument indicates measured level above the alarm / trip setpoint. b. Instrument indicates an inoperative /downscale failure. c. Instrument controls not set in operate mode. The two channels are arranged in a coincidence logic such that 2' upscale, or I downscale and I upscale or 2 downscale will isolate the.offgas line. (5) The noble gas monitor shall have a LLD of IE-5 (Xe 133 Equivalent). (6) The noble gas monitor shall'have a LLD of IE-6 (Xe 133 Equivalent). N 4 1 Amendment No. 128 108B 1 l 0242p 1

. ThLr:dioactiva giseous cffluInt instrumentatien is provided to moniter and control, as applicable, the releases o_f. radioactive materials.in gaseous . effluents during actual or potential releases of gaseous effluents. -The alarm / trip setpoints for these instruments will be. calculated in accordance with guidance provided in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentration of potentially explosive. gas mixtures in the offgas holdup system. 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. 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 guidance provided in the ODCM to ensure that the alarm / trip will occur prior-to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 2. 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. i Amendment No. 128 115A 0242p i 9 u-

4 - 4.2 BASES v there is no true minimum. The curve does have-a definite knee and very little reduction in system unavailability is achieved by testing at a ~ -shorter: interval than computed by the equation for a single channel. 2 The best test procedure of all;those' examined is to perfectly stagger-the tests. That is, if the test interval is four months testtone or--the other channel levery two months. 'This.is shown'in Curve No. 5.~ The- . difference between Cases 4 andL5 is negligible. There may be other. arguments,.however,.that more strongly support the perfectly staggered tests, including reductions in human error..' ~ ~ 'The conclusions to be drawn are these: 1 1. A 1 out of n system may be treated the same as a single channel'in terms of choosing a test interval; and 2. more than one channel-should not be bypassed for testing at any one time. The radiation monitors in the refueling area ventilation duct which-initiate building isolation and standby gas treatment operation are arranged in two 1 out.of 2 logic systems. The bases-given for_the rod-blocks apply here also and were used to arrive at the functional testing, frequency. The off-gas post treatment monitors are. connected in a 2 out of 2 logic arrangement. Based on experience.with instruments of similar design, a testing interval of once every three months has been found-adequate. The automatic pressure relief. instrumentation can be considered to be-a 1 i out of 2 logic system and the discussion above applies also. The criteria for ensuring the reliability and accuracy of the radioactive = j gaseous effluent instrumentation-is listed in' Table 4.2.K. l The criteria for ensuring the reliability and accuracy of the radioactive j liquid effluent instrumentation is listed in Table 4.2.D. i Amendment No. 128-118 0242p I .>-~-.-m .-+*,m-. ..... + ,.,, - ~. -, - + - e .w + .y.

M M LIMITING CONDITIONS FOR' OPERATION-SURVEILLANCE REQUIREMENTS' ~ 7 L 3.6 : . Primary System Boundary 4.6 . Primary 59 stem Boundary

6. lWhenever<the reactor is

~ 6. Additional' coolant samples' fj - critical, the. limits on shall be taken whenever the l activity concentrations in the reactor activity exceeds'one: -l ' reactor' coolant shall not percent of'the~ equilibrium ~ L exceed:the. equilibrium value concentration specified in-of 3.2.pc/gm of does 3.6.B.6~and one of the equivalent.I-131. following conditions are met:- . This limit may be exceeded

a. :During startup-

- following power transients for 1b. 'Following-a significant' a maximum of 48 hours.. During . power-change ** this activity: transient the <c. Following an increase _in' - iodine concentrations shall the equilibrium off-gas not exceed-26 pCi/gm whenever level exceeding-10,000- - the reactor is critical. The-pCi/sec (at the steam reactor shall not;be operated jet air ejector) within-more'than 5 percent of'its. a.48 hour period. yearly. power operation.under. d. Whenever the equilibrium this exception for'the iodine limit specified i-equilibrium activity limits. in 3.6.B.6Lis exceeded. t { If the iodine concentration in the coolant. exceeds 26 pCi/gm, The additional coolant-the reactor shall be shut down, liquid' samples shall be-and the steam line isolation taken:at 4 hour intervals ~ valves shall be clored for 48 hours, or until a immediately, stable iodine concentration below the limiting value -(3.2 pCi/gm) is-established. However, at-least 3 consecutive' samples shall be taken in all. t cases. 'An isotopic analysis shall be performed for each.. sample, and quantitative measurements made to- ' determine the dosei - equivalent I-131-concentration. If the total iodine activity of the sample is below 0.32. pCi/gm, an isotopic. analysis to determine equivalent I-131 is not ~ required.

• • For the purpose of this section onL sampling frequency,-a significant power exchange is defined as a change exceeding 15% ofLrated~ power 4

in less.than 1. hour. 179 Amendment No.!12'8 0233p L - eg ww -e e e r e - = w -e - - + - -+,-~+s-- m

LIMITING CONDITIONS FOR OPERATION SURUEILLANCE REQUI EMENTS' .l 3 '. 8 Radioactive Materials ~ 4.8 -Radioacti've Materials: i ApplicabilityL Applicability-AppliesitoTthe release of Applies to.the' periodic test and- . radioactive. liquids and gases record requirements'and saepling'-. ~ from the facility. 'and monitoring methods used for. facility ~ effluents. Objective Objective To' define the-limits and 3 ~ j conditions for the release off <To' ensure thatLradioactive radioactive effluents ~to the liquid and gaseousfreleases from environs to assure that any .the' facility are maintained. 7 . radioactive releases are as' within the: limits specified by low as reasonably' achievable Specifications 3.8.A and 3.8.B. .and within the limits of ~ 10 CFR Part 20. The specifications Specification except for.3.8.A.1 and 3.8.B.1 are exempt from the requirements of A.. Liquid Effluents e 5 definition 1.0.C (Limiting Condition for Operation). - l'.--Facility records shall e 'be maintained of Specification radioactive concentrations and .A. Liquid Effluents volume before dilution of each batch of liquid-i 1. The concentration of ceffluent released, and radioactive material of the average dilution j released at any time from flow and length of time the site to unrestricted over which each areas (see Figure 4.8-1b) discharge' occurred. shall be limited to the concentrations specified-2. Radioactive liquid waste in 10 CFR Part 20,- sampling and activity-2 Appendix B. Table II :

analysis of each-liquid Column 2 for radionuclides waste batch to be other than dissolved or-

- discharged'shall.be entrained noble gases.- performed prior-to For dissolved or entrained release in accordance t noble gases, the with the sampling and t concentration shall be-analysis program limited to 2E-4 pCi/ml

specified in the REM.

. total activity. 3. The operation'of the-2. If the limits of 3.8.A.1 -automatic isolation are. exceeded, appropriate valves and discharge i action shall.be initiated . tank selection valves without delay to bring _ shall be checked the release within annually. Amendment No. 128 281 10233p ,w h ,--,--,--c.- -,,.n,, w. ,,,,c- ...-.#--w,-. .) u

f n -r-LIMITING CONDITIONS FOR OPERATION ^ SURVEILLANCE REQUIREMENTS ~ 3.8. lRadioactiveMaterials - 4.8' . Radioactive Materials limits. Provide prompt 4.- The results of.the .. notification to the NRC analysis.of samples ~ 1 pursuant to'section 6.7.2. collected from' release -points ~shall be'used' 3. The doses or dose. ,with the calculational" -commitment to a member of methodology in:the ODCM l the public from radioactive te assure.that.the i materials in liquid concentrations'at,the -- ffluents released from point of; release are. e each unit to unrestricted maintained within the -areas (See Figure 4.8-1b) limits'of specification i shall-be' limited: 3.8.A.I. a. During any-calendar ~ 5. Cummulative quarterly-quarter.to <1.5 mrem to .and yearly dose the total body and <5 contributions from arem to any organ and,- liquidLeffluents shall-be determined as b. During any calendar _ specified in.the ODCM atf year to <3 mrem to the least_once every 31 days.- total body and <10 mrem to any organ- .6. The quantity of-radioactive material 4. ~If the limits specified in contained in any outside '3.8.A.3 a & b above are liquid radwaste storage exceeded, prepare and ~ tanks shall be submit'Special Report . determined to-be within pursuant to Section 6.7.2.- the above limit by analyzing a -5. The maximum activity to be representative sample of ' contained in one liquid' the. tank's contents at radwasteitank or temporary least once per 7 days storage tank that can'be when radioactive discharged directly to the materials are being environs shall not exceed added to the tank. 10 curies excluding tritium and dissolved / entrained noble gas. [. 6. With radioactive liquid waste exceeding 3.8.A.5 limits, without delay h suspend all additions of-v l radioactive material to the tank and within 48 hours. reduce.the tank contents to within the limit. Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report -(section~F.2 of the REM) i j 282~ Ame dment No. 128, n

0233p,

,,r,, ,.v, -.,,.,4-,-,*.m.-L_-,. ,,,;.m,, -, .,--,r,3_. --m-,

, ~. (i 4 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 Radioactive Materials

4.8 Radioactive Materials a

B. Airborne Effluents

B.' - ' Airborne ~ Effluents 1.

The dose rate at;any time-1. The gross'B/V and' ) : to areas at and beyond the particulate activity of site boundary (see Figure -gaseous wastes released .4.8-1b) due to to the environment shall-radioactivity _ released in be monitored and -gaseous effluents from:theJ recorded. site shall be limited to the'following values: a.-- For effluent: stream's ohaving continuous a. The dose r' ate limit monitoring for noble gases shall. capability, the be <500 mrem /yr to the activity shall be-total body and'<3000 monitored and flow mrem /yr to the_ skin, rate evaluated'and-t and recorded to enable

release rates of.

b. The dose rate: limit gross radioactivity for I-131, I-133, H-3, to be1 determined.at and particulates with .least once per shift 3 greater than eight day 'using instruments ~ half-lives shall be specified-in table l <1500 mrem /yr to any. 3.2.K. -organ, b.' For effluent streams-2. If the' limits of 3.8.B.1 without. continuous are exceeded, appropriate monitoring ~,_ corrective action shall bel capability,:the immediately initiated to activity shall be ' bring the release within monitored andL limits. Provide prompt . recorded and the. notification-to the NRC release through pursuant to section 6.7.2. these streams -controlled to within the limits specified- .in.3.8.B. 2. Radioactive gaseous 'f ~ waste sampling and~ _ activity analysis.shall be performed in accordance with ;the sampling and. analysis _ program specified.in'the REM.- Dose rates shall l i be determined to be i within' limits of-3.8.B using methods contained in the ODCM. Amendment No. 128 283 0233p ~ -.. ~ i

' LIMITING CONDITIONS'FOR' OPERATION- ~ SURVEILLANCE REQUIREMENTS g o 3. The air. dose to' areas at ~3. -Cumulativel'uarterly and and beyond the site yearly dose-boundary.(see Figure contributions from-4.8-1b) due to noble gases' gaseous releases shall_ released in gaseous. be determined using effluents per unit shall. methods contained in the be limited.to the ODCM at~1 east once every following: 31 days.

a.. During any calendar quarter, to 15 mrad

~ 'for gamma radiation and 110 mrad.for beta radiation;

b.. During any calendar year, to 110 mrsd for gamma radiation and 120 mrad:for beta radiation.

4.. If the calculated air dose exceeds the limits ~*' specified in 3.8.B.3 above, prepare and submit a special report pursuant to section 6.7.2. 5. The dose to a member of the public from' radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than~8 days in gaseous

effluent released per unit-to areas at and beyond the site boundary (see Figure 4.8-lb)'shall be limited to the following

a. To any organ during ~ { any calendar quarter to 17.5 mrem; l

b. 'To any organ during any calendar year to-115 mrem; i.

i 284 Amendment No. 128 0233p

N

1. 7 LIMITINGbONDITIONSFOROPERATION SURVEILLANCE REQUIREMENTS

~ 6. If.the' calculated doses-

4..During operation above; exceed.the limits of-25% power,.the position-3.8.B.5_above, prepare-of the charcoal bed

.and submit a special: . bypass valve will be; { report pursuant to : verified daily.o section 6.7.2. '7. During. operation above 5. The concentration of.- 25% power.,the. discharge' hydrogen downstream of p of the SJAE must be -the recombiners.'shall.be-F ' routed through the . determined to be within'- icharcoal adsorbers.. the_. limits'of 3.8.B.9.by continuously' monitoring;

8.. With gaseous waste.being the offgass,whenever'the.-

dischargad for more than-SJAE is;in service using? ~ 7 days without-treatment instruments described in through the charcoal Table 3.2.K. . Instrument-adsorbers, prepare _and; . surveillance-submit a special. report requirements are pursuant to section -specified in Table 4.2.K. 6.7.2.- i 9. Whenever the SJAE-is in~ service, the concentration of hydrogen in the offgas downstream of the recombiners shall be I limited to 14% by volume. t 4 10. With the concentration ofJ l hydrogen exceeding the-limit of 3.8.B.9 above, L restore the concentration to within the limit within 48 hours. J h 4 i J J E Amendment No. 128: 285 L e 0233p . ~. -

-. _ ~ _ _ _ - _ _ -. _ _ _ _ _ _ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS ,3.8.C Radioactive Effluents - Dose 4.8'.C Radioactive Effluents - Dose 1. The dose or dose 1. CumulativeJdose commitment to a real - contributions from .individua1'from all' ' liquid and gaseous uranium fuel cycle sources effluents shall.be is limited to <25 mrem'to determined in accordance the total body or any with specifications organ (except the thyroid, 3.8.A.3,:3.8.B.3, and which is limited to <75 3.8.B.5 and the methods mrem) over.a period of one in'the ODCM. . calendar year. 2. With the cal'culated dose -from the release of . radioactive materials in i ' liquid or gaseous effluents exceeding twice the limits of specification-3.8.A.3, 3.8.B.3, or 3.8.B.5, 3 prepare and submit a Special Report to the Commission pursuant to ~ ~ specification 6.7.2 and limit the subsequent releases such that the= limits of 3.8.C.1 are not exceeded. l 3.8.D Mechanica1> Vacuum Pump 4.8.D' Mechanical Vacuum Pump. 1. Each mechanical vacuum pump 'At least once during each shall be' capable of being operating cycle verify automatic automatically isolated and securing and isolation'of the secured on a signal or-mechanical vacuum pump. high radioactivity in the steam lines whenever the main' steam isolation valves are open. 4 2. If the limits of 3.8.D are not met, the vacuum pump shall be isolated. 'T A 4 1 Amendment'No. 128 286 l0233p- - - - ~

N ' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS' '4.' 8. C. ' Radioactive Materials 3.8: Radioactive Materials. E.' Miscellsneous Radioactive E.- Miscellaneous Rsdioactive-Materials Sources Materials Sources 1. Source Leakage Test 1.. Surveillance Requirement: i 'Each sealed source- . Tests' for : leakage.and/or: containing radioactive contamination shall be' I material either in excess performed by the. of 100 microcuries of beta licensee or by other and/or gamma emitting

persons specifically material or 5 microcuries

-authorized by the of alpha emitting' material Commission or an shall be free of > 0.005 agreement State,:as microcurie of removable follows: contamination. Each, sealed souce with removable a.- Sources in Use contamination in excess of. the above limit shall be Each sealed source,. i .immediately withdrawn from excluding:startup 4 use and (a)~either sources and flux I decontaminated and ~ detectors'previously repaired, lor (b) disposed subjected to core 2 of in accordance with flux,' containing Commission regulations. radioactive. material, other than . Hydrogen 3, with a half-life greater than thirty. days and in any' form other .than gas shallDbe-tested for leakage and/or contamination-i L at.least once per six months. The' leakage test shall l be capable of' detecting the

presence of 0.005 microcurie of radioactive material

.on the test. sample. i l Amendnen; lb.~ 128 1 287 i-0233p

LIMITING CONDITIONS FOR OPERATION ' SURVEILLANCE REQUIREMENTS 4.8.E Miscellaneous Radioactive Materials Sources 1. Surveillance Requirements b. Stored-Sources Not In Use Each sealed source and fission detector not previously subjected to core flux shall.be tested prior to use or . transfer to another licensee unless tested within the previous _six months. Sealed sources and fission detectors transferred without a certificate 4 indicating the last test date shall be tested prior to use. c. Startup Sources and Fission Detectors Each sealed startup so'rce and fission u detector shall be tested prior to being subjected to core flux and following repair or maintenance to the. source. -2. ' Reports A report shall be prepared and submitted to the i Commission on an annual basis if sealed sources or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination. 288 Amendment No. 128 0233p w e u - &+ er

~. -... d E -LIMITING CONDITIONS FOR OPERATION' ' SURVEILLANCE REQUIREMENTS 3.8 Radioactive Materials; 4.8 Radioactive Materials J F.' ' Solid'Radwaste. -F.. Solid Radwaste-1. The' solid radwaste system

1..The Process Co'ntrol.

shall be operated in

Program shall include-accordance with a process surveillance checks control program, for the ~

necessary to demonstrateL solidification and fcompliance with 3.8.F.1. packaging of wet radioactive wastes'to - ensure meeting the - requirements of 10 CFR 20 and'10 CFR 71 and burial . ground requirements prior to shipment of radioactive . wastes from.the. site. 2. With'the packaging _ requirements of 10 CFR 20 l or burial ground _ ~ requirements and/or j 10 CFR'71 not satisfied, -suspend shipments of defectively packaged solid i radioactive wastes from ^ the site. = i i l l i I l i 1 , l l 289 Amendment No. 128. ] 4 0233p J

~ i 4 y] na F ts h ua h x E =- S d g n N r n o O a i) i I y dm t T h l2 a I r c i3 l V t u( i E i B t L w g n E S 'e n e n i

• g V

D i d n N b l i g A r i d n u u l i) S T B i dm T u l0 N e B i4 a I n u( l O i r B P b o* 0 r t r 8 E 9 u c o 4 S 2 T a A e c e E. R a r l e u E e R~ g R c. e. i tg F S ivg bd U l rd $l O el hB E SB S J A C \\ gn ei cd il fi fu OB )m 0 8 ( 1 ( 8 k 2 c 1 a t S o N tn f em dn e m A~ l l i tl 1 1 t l t ,I j .I l 4 1

i Figure 4.8-lb IA'D SITE BOUNDARY T ~ z @i, y p, /

s-r ;_

/ . >i g .\\ .y. \\ f .H. r..? xy QT = :.: n s .f_

S M,

i.u. 1 \\ i g \\ s

.u.

s, \\ \\ \\ \\ s \\ \\ \\ 290A Amendment No.128

3.8 BASES Radioactive waste release levels to unrestricted areas sh6QId be kept."as low as reasonably achievable" and are not to exceed.the concentration limits specified in 10 CFR Part 20. At the same time, these' specifications permit the flexibility of operation, compatible'with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases-higher:than design objectives but still within the concentration limits specified in 10 CFR Part 20. It is expected that by using this operational - flexibility and exerting every effort to keep;1evels or radioactive materials released as low as reasonably achievable in accordance with criteria established in 10 CFR 50-Appendix I, the annual releases will not. exceed a small fraction of the annual average concentration limits _specified in i 10 CFR Part 20. 3.8.A. LIQUID EFFLUENTS Specification 3.8.A'.1 is provided to ensure.that the concentration of radioactive materials released in' liquid waste effluents from the site'to l unrestricted areas will be less than the concentration levels specified'in 10 CFR Part 20, Appendix B. Table II, Column 2. This limitation provides. additional assurance ~that the levels of radioactive materials in bodies'of water outside the site will re'sult in exposures within (1) the Section 11.A design objectives of Appendix I,10 CFR Part 50,- to an individual and (2) the t limits of 10 CFR'Part 20.106(e) to the population. The concentration. limit i for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope.and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. i Specification 3.8.A.3 is provided to implement the dose requirements of Sections II.A, III.A. and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth the Section 11.A of j Appendix I. Specification 3.8.A.4 action statements provides 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".- Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the I finished drinking water that are-in' excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by i i Amendment No. 128 291 l 0242p a l',#.m,-r.,.ce. y--., m ,,--..w

h 3.8.A,' LIQUID EFFLUENTS (ctnt'd) calculational procedures based cn1 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 Effluents from' Accidental.and Routine Reactor-Releases for'the Purpose of Implementing Appendix I," April 1977. NUREG-0133 provides methods for. dose calculations consistent with. Regulatory Guides 1.109 and 1.113, 3.8.B AIRBORNE EFFLUENTS 4 Specification 3.8'.B.1 is provided to ensure that the dose. rate at anytime'at the exclusion. boundary from gaseous effluents from all' units on the site 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 10 CFR part 20, Appendix B Table II, Column 1. These limits provide reasonable. assurance that radioactive material discharged in gaseous effluents will not result,in the exposure of a member of the public 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 members of the public who may at' times be within~the exclusion area boundary, the occupancy of the member _ of the public will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. .= d f i Amendment No.128 l 291A j l 0242p 1 =

-. 3 4 3.8.B. AIRBORNE EFFLUENTS (cont'd). The specified release rate limits restrict, at all times, the corresponding- ~ gasuna and beta dose rates above background to an, individual at 'or beyond the exclusion area boundary to-1 500: mrem / year.to the total body or to 1 3000 mrem / year to the skin. These' release, rate limits also restrict, at all . times, the corresponding'ithyroid dose rate above background to an infant via the cow-milk-infant pathday to i 1500. mrem / year for the nearest cow to the plant.- 3 4 + t Specification 3.8.B.2' requires that appropriate correction action (s) be taken to reduce gaseous effluent releases if'the limits of 3.8.B.1 are exceeded, t [ Specification 3.8.B.5 dose limits'is pecvided to implement-the requirements of- ^ .Section II.C, III.A, land IV=of-Appendix Is 10 CFR Part'50.. The limiting conditions for operation are the guides set forth in Section;II.C of Appendix I.. ~

Specification 3.8.B.6 action statement provides 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 materials in gaseous effluents will be kept "as low as is reasonably achievable". The ODCM i calculational methods'specified in the, surveillance requirements implement the requirements'in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data sach that the actual--exposure of an_ individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods-used for calculating the' doses due to the'actua', 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-3 Releases of Reactor Effluents for the Purpose of Eve.luating Compliance with' 10 CFR Part 50,, Appendix I," Revision I, October 1977, NUREG/CR-1004, "A { Statistical Analysis of Selected Parameters for Predicting Food Chain j-Transport and Internal Dose of Radionuclides",- October 1979, and Regulatory-t Guide 1.111. "Mathods for Estimating Atmospheric Transport and Dispersion of i 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 s 1 release rate specifications for radioiodines,-radioactive material in i particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.- The pathways which are examined in the development of these calculations are:-

1) individual inhalation of airborne radionuclides,.2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)-deposition onto grassy areas where milk-animal and meat producing animals graze with consumption of_the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

l Specification 3.8.B.6 action sta'tement requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.S. j ns \\ Amendment No.128 4 l ~ ' (. 291B i s s l 0242p d

1. Z$i

.. ~.. Y t P s AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsorber-beds'be used' when:specified to' treat gaseous effluents. prior to-their. release.to the environment. This provides reasonable assurance that the release of-radioactive materials'in gaseous' effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of-- 10 CFR.Part 50.36a, General Design Criterion 60 of. Appendix'A to 10 CFR i Part 50, and design objective Section II.D of Appendix I to 10 CFR Part.50. The specified limits'gcVerning the use of appropriate portions of the systems i were specified as a-suitable fraction of the guide set forth in Sections II.B j .and II.C'of Appendix I, 10 CFR Part 50, for gaseous effluents. 1 Specification 3.8.8.8 requires that a special report be prepared and submitted: to' explain reasons for any failure to comply-with Specification 3.8.B.7. Specification 3.8.B.3 is provided'to implement the requirements of Section.II.B III.A. and IV.A of Appendix I, 10 CFR Part 50. The Limiting. Condition for-Operation implements the guide set.forth in Section II.C of .i Appendix I. Specification 3.8.B'.4 action statement provides the required operating- [ flexibility and at the same time implement the guides set forth in Section j IV.A of Appendix.I to assure that the releases of radioactive materials in " gaseous effluents will'be kept "as low as is' reasonably achievable". The { Surveillance Requirements implement the requirements in Section;III.A of i-Appendix I that conformance with the guides of Appendix I is to be shown by j calculational procedures based on models and data such that the actual l exposure of a member of the public through appropriate pathways is unlikely to be'substantially underestimated. The dose calculations established in the. ODCM for calculating'the doses due to the actual release rates of radioactive' a noble gases in gaseous effluents will 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 1 October 1977, NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides". October 1979 and. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in-Routine Releases from Light-Water-Cooled Reactors," i 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 l consistent with Regulatory Guides 1.109 and 1.111. Specifications 3.8.B.4 requires that a special report be prepared and submitted to explain violations l of the limiting doses contained in Specification 3.8.B.3. 4.8.A and 4.8.B BASES ^ The surveillance requirements given under Specification 4.8.A and 4.8.B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and i i i. 4 h [ 291C l 0242p Amendment No. 128 [

m n x 4i8.A'and4.8.BBASES[(cont'd) ~ ib 7 .r [_ ~ gaseous effluents. These surveillance riqUiiements provide ~the data ~for the i licensee and'the Commission to evaluate the station's performance relative.to radioactive wastes released to the environment.' ' Reports on-the quantities of. radioactive materials released in effluents shall be-fdenishe<' to the Commission on the basis of-Section 6 of these technical-specifications. ~On !q' the basis of such reports and any' additional information the Commission may-obtain from the licensee or'others, the Commission may from time to time

require the. licensee to take-such actions as the Commission deems appropriate.

3.8.C and 4.8.C BASES This specification is The specification requprovided t'o meet-the dose limitations of 40 CFR 190. ires the preparation and submittal of a Special. Report whenever'the calculated doses from plant radioactive effluents exceed twice .the design objective doses of Appendix I. - For sites containing up to four reactors, it is highly unlikely that the resultant dose to a member of~the. public wi11' exceed the dose limits of 40 CFR 190 if the individual reactors s,

remain within the reporting' requirement level. The Special Report will I

t describe a course of action which should result in the limitation 'of dose to i a member of the public.for the calendar year to be within 40 CFR 190 limits. j' For.the purposes of the Special Report, it may-be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from othei nuclear. fuel cycle facilities at the same site or within a radius of five miles mustt + be considered. 3.8.D and 4.8.D MECHANICAL VACUUM' PUMP b ) 4 'Ihe purpose of isolating the mechanical vacuum pump line is to-limit ~the release of activity from the main condenser. During an accic products would be, transported from the reactor through the ma;ent, fission)- in steam 1"nes to the condenser. The fission product. radioactivity would be sensea'by the main steam line radioactivity monitors which initiate isolation. f 3.8.E and 4.8.E BA?E.S gy The limitations on removable contamination for sources requiring leak testing, including' alpha emitters, based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct,' source, and special nuclear material sources will not' exceed allowable intake values. sealed sources are classified into three groups according.to their use, with surveillance requirements commensurate with the. probability of ' damage to a source in that group. Those sources which are frequently handled.are required to be tested more often than those which are not. Sealed sources which are continuously enclosed'within a shielded mechanism (i.e., sealed sources within p radiation monitoring or boron measuring devices) are considered to-be stored. and need not be tested unless they are removed from the shielded mechanism. Amendment No. 128 0242p 1 t " k..

'6.0 ADMINISTRATIVE CONTROLS k. The radiological environmental monitoring prog' ram and the -results thereof at least once per 12 months. 1. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide '4.1, 1975 at least once per 12 months. m. The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d) at least once per 12 months. n. The Offsite Dose Calculation Manual and implementing procedures at least once per'24 months. 'o. The Process Control Program and implementing procedures for solidification of wet radioactive wastes at least once'per 24 months. p. The Radiologica1' Effluent Manual and implementing procedures at least once per 12 months. 9. AUTHORITY The NSRB sha11' report to and advise the Manager of Power on those areas of responsibility specified'in Sections 6.2.A.7 and 6.2.A.8. 10. RECORDS Records of NSRB activities shal1~be prepared, approved and distributed as indicated below: a. Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of. Power within 14 days following each meeting. b. Reports of reviews encompassed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion nf the review. c. Audit reports encompassed by Section 6.2.A.8 above, shall be forwarded to the Manager of Power and to the management positions responsible for the areas audited within 30 days after completion of the audit. Amendment No.128 3343 0242p i

1 6.0 ADMINISTRATIVE CONTROLS.

j. Review proposed changes to the Radiological'5ffluent Manual.

k.. Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.

1. Review changes to the radwaste' treatment systems. I' m. Review of every unplanned onsite release-of radioactive material ~ to the environs including thefpreparation and forwarding of reports covering evaluation, recommendation, and deposition ~of the corrective action to prevent recurrence to the Director, Nuclear Power and to the Nuclear Safety Review Board.

5. -

Authority The PORC shall be advisory to the plant superintendent. 6. Records Minutes shall be kept for all PORC meetings with copies sent to Director, Nuclear Power; Assistant Director of Nuclear Power (Operations); Chairman, NSRB. 7. Procedures Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission.and-content of presentations to the committee, review and approval by members of' committee actions, dissemination of minutes,' agenda and scheduling of meetings. i 3 Amendment No. 128 0242p w - r

---

w l

r [6.0EADMINISTRATIVECONTROLS l' y 6.3 Procedures-4 A., . Detailed written procedures,-' including applicable checkoff' lists-covering' items listed below shall be prepared, approved and adhered -to.- L

1.. Normal startup,' operation and shutdown of the reactor and of all

- systems and components involving nuclear. safety of the facility. - 2. Refueling operations. '3. Actions to be taken-M correct specific ~and foreseen' potential

j' malfunctions of. systems or components, including' responses to L

alarms, suspected. primary system leaks and abnormal reactivity. changes.- 7 4 - Emergency conditions involving' potential or actual release of radioactivity.- 5. Preventive or corrective maintenance operations which could have= an effect on the safety of the reactor. 4 l 6. Surveillance and testing requirements. 7. Radiation control procedures.- 1 8. Radiological Emergency Plan implementing procedures. P I 9. Plant security program implementing procedures. l

10.. Fire protection and prevention procedures.

11. Limitations on the amount of overtime worked by-individuals performing safety-related functions in.accordance with the NRC E policy statement on working hours (Generic Letter No. 82-12). 12. Radiological Effluent Manual implementing procedures. j 13. Process Control Program (PCP). 14. Offsite Dose Calculation Manual. E B. Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant superintendent prior to I implementation. Temporary changes to a procedures which do not ~ change the intent of the approved procedure may be made by a member of the plant staff knowledgeable in-the area affected by the procedure except that temporary changes.to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reactor Operator license on the unit ~. affected. Such changes shall be documented and subsequent 1y' reviewed by PORC and approved by the plant superintendent. i Amendment No. 128-338 t-0242p t el., w-, +, - -, - - <y,--,- ,-,.,-,r ,,---,,vy,--, ,,w-n+c.r > w w-w*-mv e + v w -+-w

6.0 ADMINISTRATIVE CONTROLS 6.3 Procedures E. Quality Assurance Procedures - Effluent and Environmental Monitoring.. Quality Assurance procedures shall be established, implemented. and ~ maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide-1.21, rev. 1,-June 1974 and Regulatory Guide 4.1, rev. 1, April.1975 or Regulatory Guide 4.15, Dec. 1977~. Amendment No. 128 340 0242p

~, 6.0.:Adminintritiv7 Controls. - l, ? 3.' Unique Reporting Requirements'. ~ -I A.~~ Radioactive Effluent Release Report' ^ Deleted.--(See REM section F.2)- L / 4 1 l-1 4 Amendment No. 128 355 i 0242p 1 s

E. e-a (6.0.ADMINISTRATIVECONTROLS 6.9 Process Control Program'(PCP) ~ ~ ' * ~ ~

1. -The PCP shA11'be' approved by the-Commission prior to-s'

- s implementation. I^ 2. Changes to the PCP shall be'~ submitted;to the Commission in-the; -semi-annual ~ Radioactive Effluent Release Report for the period. Ein which the change (s):was1made.--This submittal'shall contain: Sufficiently detailed information to totally support the ~ -a.. ' change. i b. A determination that the-change did not change the overall' .conformance-of the solidified product to existing criteria. 3. Changes to the PCP shall.become effective upon review and- ~ acceptance by PORC.. 6.10 Offsite Dose Calculational Manual (ODCM). 1.. The ODCM'shall:be approved by'the Commission prior to i 4 implementation. 2. Changes to the ODCM shall be submitted to the Commission in the - l-semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made.._This submittal.'shall contain: Sufficiently detailed information to totally support the a. change. 3. Changes to the ODCM shall become effective upon review and acceptance by PORC. 6.11 RADIOLOGICAL' EFFLUENT MANUAL (REM) 1. The REM shall be approved by'the Commission prior to. implementation.

2. - Changes to~the REM shall be reviewed by PORC prior:to-implementation.

4 . ~ 3. Changes to the REM shall be approved-by the Commission prior to implementation. i i 3 \\ ~ j Amendment No.128 359 0242p - i e w- , -, - - - = ,,-i, .a ,,._,,.m -.,m. y-wy. qa-.e,-r-$ ,ma%r ,r%-

f ENVIRONMENTAL TECHNICAL SPECIFICAITONS .-FOR BROWNS FERRY NUCLEAR PLA?Tf P TABLE OF CONTENTS Page No.-- .1.0 DEFINITIONS............................................ Deleted 2.0 LIMITING CONDITIONS FOR OPERATION...................... Deleted 2.1 Thermal Discharge Limits.......................... Deleted 2.2 Chemica1.......................................... Deleted 2.2.1 Makeup Water Treatment Plant Spent Denineralizer.Regerants.................. Deleted 2.2.2 Chlorine................................... Deleted 3.0 DESIGN FEATURES AND OPERATING PRACTICES................ Deleted 3.1 Chemical Usage.................................... Deleted 3.1.1 Oils and Hazardous Materials............... Deleted 3.1.2 Othdr Chemicals............................ Deleted-3.2 Land Management................................... Deleted 3.2.1 Power Plant Site........................... Deleted-3.2.2 Transmission Line Right-of-Way Maintenance. 1 ) i 3.3 Onsite Meteorological Monitoring.................. Deleted 4.0 ENVIRONMENTAL SURVEILLANCE............................. Deleted 4.1 Ecological Survei11ance........................... Deleted 4.1.1 Abiotic.................................... Deleted 4.1.2 Biotic..................................... Deleted 4.1.3 Special Studies............................ Deleted 4.2 Radiological Environmental Monitoring Program..... Deleted Amendment No. 128 0242p

M .1 1 2-- j 1 ^ 5 '.0. ADMINISTRATIVE CONIR0LS...............................N Dele t ed Lj 5.1 Responsibility..................................... Deleted. 5.2 Organization...................................... Deleted .5.3'-Review'and Audit.................................. Deleted ~ 5.4 ' Action to.be Taken if an Environment LCO is Exceeded......................................... Deleted 5.5 Procedure...................'...................... Deleted

5.6~ Reporting Requirements.'...........................

Deleted 517 Environmental Records............................. - Deleted ' Tab1es...................................................... Deleted -Figures...................................................... Deleted 4 i Amendment No.128 0242p n, -a y 4, .we .g-- w e. ya_ --r

+ ^ s [3,2.2 Trrr: mission Lins Right-of-Wry Maintsnr.nce: . Objective- -The sole purpose of this section is to provide reporting .c requirements (to USNRC) on herbicide ' usage, if Lany, for purposes of-- .right-of-way maintenance regarding only thoseLtransmission~1ines .under USNRC's jurisdiction for'the Browns Ferry Nuclear Plant. JSpecification A= statement as to whether.or.notiherbicidesihave been'used in l maintaining.'ights-of-way for those: transmission lines associated' ~ r -with the Browns Ferry-Nuclear Plant shall be providedk. If-herbicides have been used, a description of the. types,, volumes,=, concentrations, manners.and frequencies of application Land miles or rights-of-way that have been treated'shallJbe included.' Reporting Requirements- .Information as specified above shal1 be provided~in the Annual ' Operating Report (Appendix A, Section 6.7.1(b)).- ~ Bases ^ Vegetation growth on a transmission line right-of-way must'be -controlled in such a manner thatiit-will neither. interfere with safe and reliable,peration of the line or impede restoration.of. service when outages occur. Vegetation growth is contro11ed'by mechanical cutting.and:the' limited use of herbicides. Selected chemicals approved by EPA forJ use as herbicides are assigned (by EPA) label instructions which-provide guidance on and procedures'for their use. I I l Amendment No.128 i -1 0242p

'8 ~z UNITED STATES - E NUCLEAR REGULATORY COMMISSION n-WASHINGTON, D. C. 20555 Y,. ,o 4 TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-296 BROWNS FERRY NUCLEAR PLANT,-UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. DPR-68 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The applications for amendment by Tennessee Valley Authority-(the ' licensee) dated September 30, 1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment.is in a:cordance with 10 CFR Part 51 of the Comission's regulations and all ~ applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-68 is hereby amended to read as follows:

- (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103,'are hereby incorporated 'in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of-the date of issuance and shall be implemented within 90 days from the date of-issuance. FOR THE NUCLEAR REGULATORY COMMIS I N 8 g Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: February 5, 1987 i s l i 1

ATTACHMENT TO LICENSE 1. AMENDMENT N0.103 FACILITY OPERATING LICENSE N0. DPR-68 DOCKET NO.'50-296 Replace the following pages of.the. Appendix A Technical Specifications with 4 the enclosed pages. The revised. areas are indicated by. marginal lines. Pages i 307 11 308 iii 300 iv 310 v 311 vi 312' vii .313 viii 314 7 315 '7A 364A 7B. 367 8 368 51 -370 52 385 56A 389 79 79A 87A 878 100 100A 105A 105B 113 116 190 299 300 301 302 303 104 305 306 Revise Appendix B as follows: Table of Contents 2 pp. i .,-,,-_.m__m y

9 TABLE OF CONTENTS i Page No. Section 1 i 1 Int'roduction'..............'...... 1 --1.0 Definitions......-.............. 12 i i SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 Fuel Cladding Integrity............. 9 1.2/2.2 Reactor Coolant System. Integrity...... .u. 26 LIMITING CONDITIONS FOR OPERATION AND -SURVEILLANCE REQUIREMENTS 3.1/4.1 Reactor Protection System.. 31 3.2/4.2 Protective Instrumentation. 49 A. Primary Containment and Reactor Building Isolation Functions. 49 B. Core and Containment Cooling Systems -- j Initiation and Control. 50 C. Control Rod Block Actuation. 50 D. Radioactive Liquid Effluent Monitoring Instruments.................. 51 E. Drywell Leak Detection.'. 53 F. Surveillance Instrumentation........ 53 J G. Control Room Isolation..,........ 53 H. Flood Protection. 54 I. Meteorological Monitoring Instrumentation.. 54 J. Seismic Monitoring Instrumentation...... 56 K. Radioactive Gaseous Effluent Monitoring Instrumentation............... 56A j 3.3/4.3 Reactivity Control. 118 l A. Reactivity Limitations........... 118 r l B. Control Rods................ 122 4 i-1 Amendment No. 103 l 0243p

s A. + bection1 Paste No. LC.. Scram Insertion Times..'...-..'..'.=.. 128:- D.' Reactivity Anomalies....-..-.....'.. 1129.. ~E. Reactivity Control. .-..g. ~129' F. ' Scram Discharge Volume.....'.....'.. 129 - l3.4/4.4 Standby. Liquid Contro1' System.....' 137~ .....=. A. Normal' System Availability.:._...~...:.. 137 4 B. Operation with Inoperable-Components.'...- 139-C. 1 Sodium Pentaborate Solution.'......:.. 139 a - 3.5/4.5 ~ Core and Containment Cooling Systems..'..... 146 A. Core Spray: System.1 ...r....... 146 B. l Residual Heat Removal System (RHRS) ~ '(LPCI and Containment Cooling). 149 C. RHR Service Water System and-Emergency-Equipment Cooling Water System (EECWS) 155 D. Equipment Area Coolers......,.....'. 158 E. High Pressure Coolant Injection System (HPCIS). 159 ~ F. Reactor Core Isolation Cooling' System (RCICS). 160~ G. Automatic Depressurization System (ADS). 161 i H. Maintenance of Filled Discharge Pipe..... 163 I. Average Planar Linear Heat Generation Rate.................... 165 J. Linear Heat Generation Rate......... 166 K. Minimum Critical Power Ratio (MCPR)... 167 L. DAPRM Setpoints................ 167A M. Reporting Requirements.....'...... 167A 3.6/4.6 Primary System Boundary............. 154 A. Thermal and Pressurization Limitations... 184 11 . Amendment No.103 0243p-

~ /' I ,y J .Section, Page No. B. Coolant Chemistry.s. .c.J... -187 C. Coolant Leakage.. .g.;.1r. .~.7 ...f.- 191-D. Relief Valves.........-.. =...-.... 192-E. Jet Pumps...:...............E.... 193 F. Recirculation Pump Operation...:.....:...-

195, G. -Structural: Integrity....

196 'H. . Seismic Restraints, Supports, and' Snubbers ~.........-............- .198~ 3.7/4.7. Containment Systems...,,.......'..:... 231 Primary Containment.. 231-A. -B. Standby Gas Treatment System.. .c. .s. 247[ C. Secondary Containment.. 251 D. Primary Containment Isolation Valves...... 254 E.. Control Room Emergency Ventilation.. .L. 256 F. Primary Containment Purge System...... 258 G. Containment Atmosphere Dilution System (CAD) 260 H. Containment Atmosphere Monitoring (CAM) System B: Analyzer...'........._. '261 3.8/4.8 Radioactive Materials.............. 299 A. Liquid Effluents.............. 299 Airborne Effluents............. 301 B. C. Radioactive Effluents - Dose........- 304 D. Mechanical Vacuum Pumps........... 304 g.. E. Miscellaneous' Radioactive Materials Sources.................... 305 F. Solid Radwaste............... 307 3.9/4.9 Auxiliary Electrical System........... 316 - A. Auxiliary Electrical Equipment 316~ B. Operation with Inoperable Equipment. 321 Amendment No. 103 - 0243p

Section-

Page No.

a .C. ' Operation in Cold Shutdown.......... '326 3.10/4.10 Core Alterations........;........ ~331 A.- Refueling Interlocks.... 331-B. Core Monitoring... 336 .C. Spent Fuel Pool Water...._...:... 337 D.- ' Reactor Building Crane............. 338 E. Spent Fuel Cask. 339 F. Spent Fuel Cask Hindling-Refueling Floor.. 339 3.11/4.11 Fire Protection Systems......... 347 A.. High Pressure Fire Protection System. 347 B. C0 Fire Protection System. 351 C. Fire-Detectors................ 352 D. Roving Fire Watch......-.. 353 E. Fire Protection Systems Inspections.... 354' F. Fire Protection Organization......... 354 G. Air Masks and Cylinders.......... 355 H. Continuous Fire Watch........... 355 I. Open Flames, Welding, and Burning in the Cable Spreading Room....... 355 q. 5.0 Major Design Features.............. 360 5.1 Site Features............... 360 5.2 Reactor.................. 360 5.3 Reactor Vessel. 360 5.4 Containment. 360 5.5 Fuel Storage................ 360 5.6 Seismic Design.......... 361 6.0 Administrative Controls............ 362 6.1 Organization................ 362 Amendment No.103 0243p.

~ e T 4 n ( ~ ~ Section. ~ ' Paste No. j n1 .;6.'2~ Review and' Audit.-... :.... _:..... :... ^ - 6.3-' Procedures....-....-..........'... 368' y T -6.41 Ictions.to"be Taken in the Event of A-2 . Reportable Occurrence in Plant Operation..

376 --

6.5 ' Action to be Taken in the_ Event'a Safety

Limit is Exceeded..

^. 376-- ' 6.6. Station Operating Recor'ds,......... 376- ~ 6.7 Reporting Requirements.._..:........ ~379 s 6.8 ~ Minimum Plant Staffing...-. 388 i t $l t 1 1 4 t 4 i e d 4 i i I' 4 1 4. 1 i Amendment No. 103 4-V t d. __....._0243p_- _ _. _ _ _. -,

-.. ~.....

~ d T LIST OF TABLES Section.. ' Title' Page No. '1.1: . Surveillance Frequency Notation.........- _-8 3.1.A- ' Reactor Protection System (SCRAM) -Instrumentation Requirements...-....... ~32 4.1.A . Reactor Protection System (SCRAM) Instrumentation-Functional Tests Minimum Functional Test Frequencies for Safety 4 Instr. and Control Circuits......... ~36L + l4.1.B Reactor Protection System'(SCRAM) Instrument-i l Calibration Minimum Calibration Frequencies for. . 39 Reactor Protection Instrument Channels... 3.2.A-Primary Containment and Reactor Building Isolation Instrumentation.......'....-. -57 3.2.B Instrumentation that. Initiates or. Controls

the Core and Containment Cooling Systems'...

64 i 3.2.C Instrumentation-that Initiates Rod Blocks....- 76 3.2.D Radioactive Liquid Effluent Monitoring Instrumentation....... 79 3.2.E Instrumentation that Monitors Leakage I l .Into Drywell.... 80 i I' 3.2.F Surveillance Instrumentation........... 81 I 3.2.G Control Room Isolation Instrumentation..... 84 s 1 j 3.2.H Flood Protection Instrumentation........ 85 3.2.I Meteorological Monitoring Instrumentation. 86 h 3.2.J Seismic Monitoring Instrume'ntation....... '87 i ~ 3.2.K Radioactive Gaseous Effluent Monitoring 1 l Instrumentation................ 87A' I 4.2.A Surveillance Requirements for Primary j. Containment and Reactor Building j. Isolation Instrumentation. 88 4.2.B Surveillance Requirements for Instrumentation that Initiate or Control the CSCS....... 92 l 4.2.C Surveillance Requirements for Instrumentation

that Initiate Rod Blocks..........

'a. 99 4.2.D Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirement... 100. vi knendment No. 103 0243p

' Qf. r j -1 . ' 4. 2. E ' ' Minimum Test,and Calibration Frequency for? Drywell Leak Detection Instrumentation...... .101 . 4.2.F ' Minimum Test and Calibration Frequency,for' -Surveillance Instrumentation. 102 ~4. 2.G - Surveillance Requirements for Control Room- ~ Isolation Instrumentation.n. .v.-... 103 i 4.2.M Minimum Test and Calibration Frequency.for Flood Protection Instrumentation...'..... 104 ~ 4.2,.J Seismic Monitoring Instrument Surveillance Requirements.-..............'...... 105-4.2.K~ . Radioactive Gaseous Effluent Instrumentation: Surveillance'.........--......... 105A 3.5.-1 ' Minimum RHRSW and EECW Pump Alignment. .156a-3.5. I - MAPLHGR vs. Average Planar Exposure.:...'. 181,;182, 182a. 182b 3.7.A Primary Containment Isolation Valve....-... 262~ 3.7.B Testable-Penetrations with Double 0-Ring Seals'......' 268 3.7.C Testable Penetrations with Testable Bellows.................... 269 3.7.D Air Tested Isolation Valves........... 270 3.7.E Primary Containment Isolation Valve which Terminate Below the Suppression' Pool: Water Level......... 279 3.7.F Primary Containment Isolation Valve Located in Water Sealed Seismic Class I Lines...... 280 t 3.7.G Deleted 3.7.H Testable Electrical Penetrations........ 283_ 4.9.A.4.c Voltage Relay Setpoints/ Diesel Generator Start. 327 3.11.A Fire Protection System Hydraulic. Requirements.. 353a 6.8.A Minimum Shift Crew Requirements......... '390 Amendment No.103 vii 02433

LIST OF ILLUSTRATIONS Figure Title _ Page No. 2.1.1 APRM Flow Reference Scram and APRM Rod Block Settings.................... 14 2.1-2 APRM Flow Bias Scram Vs. Reactor Core-Flow.-.. 25 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests............. 48 4.2-1 System Unavailability.. 117 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements.................. 141 3.4-2 Sodium Pentaborate Solution Temperature Requirements....-.............. 142 3.5.K-1 MCPR Limits.......-............ 182c 3.5.2. Kr Factor vs. Percent Core Flow. 183 3.6-1 Temperature-Pressure Limitations........ 207 3.6-2 Change in Charpy V Transition Temperature Vs. Neutron Exposure.. 208 4.8.1.a Gaseous Release Points and Elevations...... 308 4.8.1.b Site Boundary...... 309 TVA Office of Power Organization for Operation 6.1-1 of Nuclear Power Plants............. 391 6.1-2 Functional Organization.............. 392 6.2-1 Review and Audit Function... 393 6.3-1 In-Plant Fire Program Organization. 394 Amendment No. -103 viii I 0243p

m; 7- - b? 3 ~ s y' A 'aprotectiNetrip' function. AJtrip system may require one.or more

~

- instrument / channel trip ' signals -relatedito'one -or more. plant. parameters in order to initiate 1 trip system ac't' ion. Initiation.of-protective action may require the tripping of:a' single trip' system 2 cor the coincident' tripping of two trip systems. 17. . Protective Action .'A, action initiated' by'the protective system -when a limit"is reached.1 A protective! action can be"at a-ch?nnel. or system-level.- ~ y 8. Protective Function 1-I system protective. action whish results' from the protective ~ action of;the channels monitoring a particular. ' plant condition. ~ 9. ~ Simulated-Automatic Acutation ISimulated automatic'acutationi means applying a simulated. signal to the' sensor to actuate the . circuit in question. r 10. Logic. - A' logic.is'an arrangement'of relays,. contacts,'and other components'that. produces a decision output.- ~ (a) Initiating - A logic thatEreceives signals from channels and i z produces decision outputs to the actuation logic. (b) Actuation - A logic that. receives signals (either from ~ initiation logic or channels)~and produces decision outputs - to accomplish a protective action. 11. Channel Calibration - Shall be the adjustment, as'necessary,~of the channel output such that'it-responds with necessary range and-accuracy to known values of the parameters which the channel monitors. The channel calibration shall encompass the. entire channel including' alarm and/or trip functions and sha11' include ~ the channel function-test.: The channel calibration may be-performed by any series.of sequential, overlapping or total channel steps such that the entire channel-is calibrated.- Non-calibratable components shall be excluded from.this requirement, but'will be included in channel functional test and source check. 12. Channel Functional Test - Shall be: i ~ a. Analog Channels - the injection of.a simulated signal into the channel as close to the~ sensor as practicable to verify OPERABILITY including; alarm and/or trip functions.; b. Bistable channels - the-injection of a simulated signal into the sensor to verify OPERABILITY ~ including alarm and/or trip functions. 13. Source Check - Shall be the qualitative assessment of channel response when the channel sensor is exposed to a' radioactive source or multiple of sources. 7 Amendment No. 103 0244p +- = - - x.

~ -v.

gs m

s lW.. ' Functional Tests - A functional test:in th2 manuti. operation cet i initiation of a, system, subsystem,;or component-to verify that it'- ~ G functions within design ~ tolerances'(e.g., the manual start of ai ~ l ! core spray' pump to verify-that it runs and that it pumpsIthe . required volume of water).. i 'X. Shutdown - The reactor is in a' shutdown condition when the reactor ~ mode switch'is-in the' shutdown mode position and no core alterations are being performed. i l Y. Engineered Safeguard - An' engineered safeguard is a' safety system the actions of which are essential'to' a safety action required in response to accidents. I Y-Z. Reportable Event -~A reportable event shall be any of.those 4 conditions specified in section 50.73 to 10.CFR Part 50.. AA. Solidification - Shall be the conversion of radioactive-wastes into a form that meets shipping and burial ground requirements.- BB. Offsite Dose Calculation Manual (ODCM) - Shall be:a manual describing the environmental monitoring program and the methodology.and parameters used in'the calculation of release' rate ~ ,F limits.and offsite doses due to radioactive gaseous and liquid i effluents. The ODCM will also provide the plant with guidance for l establishing alarm / trip setpoints-to ensure technical-i specifications section 3.8.A.1 and 3.8.B.1 are not exceeded. CC. Purge or purging - The controlled process of discharging ' air or I gas from the primary containment to maintain temperature,: pressure, humidity, concentration,.or other operating condition in i such a manner that replacement air or gas is required to purify ll the containment. h DD. Process Control Program - Shall contain the sampling, analysis, 4 and formulation determination by which SOLIDIFICATION.of-radioactive wastes from liquid systems is assured. p f EE. Radiological Effluent Manual (REM) - Sha11Tbe a reanual containing j the site and environmental sampling and analysis programs'for measurements of radiation'and radioactive materials in those ) i exposure pathways and for those radionuclides which lead to the . i highest potential. radiation exposure!to' individuals from station operation. It shall also specify operating guidelines for. j radioactive waste treatment systems'and report content. i FF. Venting - The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required. Vent, used in system names, does not imply a venting process. !p 4 i 7A Amendment No.103 0244p ,g 4 ,,,=4%%... ,w.-..,%- ~ + - -.

4,._ , l Al'.0; DEFINITIONS (Cont'd) t ~ GG.': Site Boundary - Shall-be that line'beyond which thellandfis noti

owned, leased, or otherwise controlled by TVA.;

' HH. Unrestricted Area' -; Any -area -at orf beyond' the ' site tioundary to - which access is.not controlled by.the licensee for purposes of-' protection of individuals from exposure to radiation and-radioactive materials or-any area'within the' site boundary.used for industrial, commercial. institutional,'or recreational: purposes. II. Dose Equivalent I-131 - The-DOSE EQUIVALENT'I-131'shall'be'the-concentration of I-131-(in pCi/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, J I-132. I-133, I-134,'and.I-135 actually present. The thyroid dose

conversion factor used for this calculation shall be those listed 4

in Table III of TID-14844'" Calculation of Distance Factors for Power and Test Reactor Sites" JJ. Gaseous Waste Treatment System - The charcoal adsorber vessels installed on the~ discharge of the steam' jet air.ijector to provide. delay to a unit's offgas activity prior to' release. KK. Members of the Public'- Sha11* include all individuals who by' virtue of their occupational status have no formal association with the plant.. This category shall include non-employees of the: licensee who are permitted to use. portions.of the site for? recreational, occupational, or other purposes not, associated with _ plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of: q their' formal job function, occasionally enter restricted areas. LL. Surveillance - Surveillance Requirements shall be met during'the OPERATIONAL CONDITIONS or other' conditions specified for. j_ individual limiting conditions for operation unless.otherwise j-Surveillance Requirement shall be' performed within the specified stated in an individual Surveillance Requirements.- Each' time interval with, (1) A maximum allowable extention not to, exceed 25% of the i surveillance interval, but> (2) The combined time entered for any 3 consecutive surveillance intervals'shall not exceed 3.25 times the j specified surveillance interval i i Performance of a Surveillance Requirement within the specified-time interval shall constitute compliance'and OPERABILITY requirements _for a limiting condition for operation and associated act8on statements unless otherwise required by-these .i specifications. Surveillance requirements do not'have to be I performed on inoperable equipment. I 78 Amendment No. 103 j 0244p t i i v, ,.,,.-...-..,.,.-.v.. ~.. ~,, -. ,..,n..,,,,,-,-- -e~--- ,l

d P '<y Table 1.1 SURVEILLANCE ~ FREQUENCY NOTATION = NOTATION FREQUENCY ~ .S -(Shift) _At least_once per-12 hours. D (Daily) At least once per normal calendar. 24 hour day (midnight to midnight). W' ( eekly) At least once per 7 days. M (Monthly). At least once per 31 days.- Q (Quarterly). At least once per 3 months or 92 days. SA (Semi-Annually) At least,once per 6 months or 184 days. ~ ~ Y (Yearly) At least once per year or'366 days. R-(Refueling) 'At least once per operating cycle. S/U (Start-Up) Prior to each reactor startup. N.A. Not applicable. P -(Prior) Completed prior to each release. Amendment No. 103 8 0244p -,.,.,. ~ y

-LIMITING CONDITIONS FOR OPERATION' SURVEILLANCE REQUIREMENTS 3.2 ~ Protective' Instrumentation ~ ' 4. 2' Protective Instrumentation = 3.2.D - ' Radioactive-Liquid Effluent: 4.2.D! Radioactive' Liquid EffluentT Monitorina Instrumentation MonitorinaIgstrumentation-- '1. The radioactive liquid. 1. Each of!the radioactive' effluent' instrumentation 1 ~-liquid effluentJ listed in Table 3.2.D shall -monitoring instruments -.chall be demonstrated be operable with the. ~ ' applicability as shown in. 3perable by performance- -Table.3.2.D/4.2.D. 1 Alarm /- of test inaccordance . trip setpoints will1be set-with Table.4.2.D.; iin accordance with guidance given in the ODCM ~ to ensure that the limits ~ .of' specification.3.8.A.1 4 are not exceeded. ~2. The action required when the' number of operable channels is less than the minimum channels operable requirement is_specified in the notes for Table 3.2.D. Exert best efforts to return the instrument (s) to OPERABLE status within-30 days and-if-unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. 3. With a radioactive. liquid effluent monitoring, channel alarm / trip setpoint less conservative than required. by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm / trip setpoint to establish the conservatism required by these specifications. 4. The provisions of specifications l'.0.C and 6.7.2 are not applicable. 51 Amendment No. 103 0233p Inw. a

r g . 4; s: g +g g- \\g' 4 i ~ a '..\\ - w ~ cg \\ t 5 % t.- \\ This page_ deleted + V

• 4

\\ s n b r % \\ \\ ) \\ ( s s s,,- '( 4 s ) I 1 I S2 4 024Lp Amendment No.103 i

~ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS ~ ~ 3.2.K Radioactive Gaseous Effluent-4.2.K Radioactiie'CaseouT Effluent -Monitoring InstrumentationE Monitoring Instrumentation ~ 1. The radioactive gaseous 1. Each of'the radioactive effluent monitoring instruments gaseous effluent monitoring listed-in Table 3.2.K shall.be' instruments shall be operable with the applicability -demonstrated operable by as shown in Tables 3.2.K/4.2.K. performance of tests.in-Alarm / trip setpoints will be accordance with Table 4.2.K. set in'accordance with guidance given'in the ODCM to ensure that the limits of specification 3.8.B.1 are not exceeded.: 2. The action required when the number of operable channels is-less than the minimum channels .. operable requirement is 4 specified in the notes for-Table 3.2.K. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful,' explain in the next Semiannual Radioactive Release Report why.the inoperability was not I corrected in a timely manner. 3. With a radioactive gaseous effluent monitoring channel-alarm / trip setpoint less conservative than required by these specifications, suspend 1 the release without delay, declare the channel inoperable, or adjust the alarm / trip setpoint to establish the conservatism required by these specifications. 4. Both off-gas posttreatment monitors may be taken e out-of-service for-less than one hour for purging of ) monitors during SI performance. 5. The provisions of q specifications 1.0.C and 6.7.2 are not applicable. Amendment No. 103 56A 0233p g y-.. r-

i TABLE 3.2.D Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrumeret ' Operable Applicability Action l. LIQUID RADHASTE EFFLUENT 1 A, 8 MONITOR (RM-90-130)

2..RHR SERVICE HATER MONITOR 1

C '(RM-90-133, -134) 3. RAN COOLING HATER MONITOR 1 D (RM-90-132) 4. LIQUID RADHASTE EFFLUENT 1 E~ FLOH RATE (77-60 loop excluding fixed in line rotometer) e N Amendment No. 103 79 '0240p

NOTES FOR TABLE 3.2.D ~

• At all times
  • During releases via this pathway
    • During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the following shall.be met (1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified.in 3.8.A.1, (2).if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in the REM and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge. Otherwise, suspend release via this pathway.-

ACTION B With a radioactive liquid effluent monitoring channet/ alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without' delay, declare the channel inoperable, or adjust the alarm / trip setpoint to establish the conservatism referred by these specifications. ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored. If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours and an analysis of at least an LLDof IE-7 pCi/ml (gross) or < applicable MFC ratio (y isotopic) shall be used to monitor the effluent. ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, at least once per 8 hours, grab samples are collected and analyzed for radioactivity with an LLDof IE-7 pCi/ml (gross) or < applicable MPC ratio (y isotopic). ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided i the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. ACTION F Alarm / trip setpoints will be calculated in accordance.with the guidance giver. in the Offsite Dose Calculation Manual (ODCM). (1) See REM, TABLE NOTATIONS - TABLE C-1, for the definition of LLD. 79A Amendment No.~103 0244p

,m TABLE 3.2'K' Radioactive Gaseous Effluent Monitoring Instrumentation W Minimum Channels /- Instrument-Devices Operable Applicability Action: l 1. STACK (RM-90-147A & B) a. Noble. Gas Monitor (1). JA/C-b. Iodine Cartridge (1) B/Cu c. Particulate Filter (1) B/C- .d. Sampler Flow Abnormal (1) D o 'e. Stack Flow (FT, FM, (1) D FI-90-271) 2. REACTOR / TURBINE' BLDG VENTILATION (RM-90-250) a. Noble Gas Monitor (1) A/C. i b' Iodine Sampler-(1) B/C ~ 'B/C p

c.. Particulate Sampler (1)

=

• d.

Sampler Flowmeter -(1) D.. 3. TURBINE BLDG EXHAUST (RM-90-249, 251) a. Noble Gas Monitor (1) A/C b. Iodine Sampler (1) B/C

c. -Particulate Sampler (1) 8/C:

d. Sampler Flowmeter (1) D 4. 'RADWASTE. BLDG VENT (RM-90-252) A'/C i a.. Noble Gas Monitor. (1) b. Iodine Sampler. (1) 8/C' c. Particulate Sampler (1) =* B/C d. Sampler Flowmeter (1) D 1 5. OFF GAS HYDROGEN ANALYZER' '(H,A, H,B) (1)' -E- + 6. OFF GAS. POST TREATMENT ~ -a. -Noble Gas Activity Monitor .(RM-90-265, 266) (1) F. b. Sample Flow Abnormal. 3 (PA-90-262) (1) D s Amendment No.'~103 87A 0240p ,. -=

s t NOTES FOR TABLE 3.2.K

• At all times i
  • • During main condenser offgas treatment system operation-j
  • During releases via this pathway

.j - ACTION A . i With'the number of channels OPERABLE less th'an required by the Minimum Channels Operable requirement, effluent releases via the affected pathway may continue i provided a temporary monitoring system is installed or grab samples are taken- - and analyzed at least once every 8 hours. i ACTION B i - With a number of channels OPERABLE'less than required by the Minimum Channels j - Operable requirement,' effluent releases via this pathway may continue provided 2 samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed in accordance with the sampling and analysis program specified in the REM within 48 hours after the~end of the sampling period. ACTION C A' monitoring system may be out of service'for 4 hours for functional testin'g, calibration, or repair without providing or-initiating grab sampling.- ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable. requirement, effluent releases via this pathway may continue provided . i. the flow rate is estimated at least once per 4 hours. ACTION E l With the number of channels OPERABLE less'than required by the Minimum Channels-Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours and analyzed within the following 4 hours. ACTION F With the number of channels OPERABLE less than required by the Minimum Channels-Operable requirement, effluent releases via this pathway may continue provided L grab samples are taken at least once per 8 hours and these samples are analyzed for gross activity within 24 hours. Purging during SI: performance is not [ considered-a loss of monitoring capability. l Amendment No. 103 87B 1 0244p nm.- ,,---e n . v,> e,-- + - -.r- ~,, = - - ~ ,.-->w. -m -,v.,,... wen,----- ,a.,r. 4,--

l. TABLE 4.2.D Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel functional Instrument Instrument Check Source Check Calibration Test i 1. LIQUID RADHASTE EFFLUENT D(4) M R(5) Q(1) MONITOR (RM-90-130) 2. RHR SERVICE HATER HONITOR D(4) M R(5) Q(2) (RM-90-133. -134) 3. RAW COOLING HATER MONITOR D(4) H R(5) Q(2) (RM-90-132) 4. LIQUID RADHASTE EFFLUENT. D(4) NA R .Q(3) FLOW RATE (77-60 loop) [ Amendment No. 103 100 0240p

NOTES FOR TABLE 4.2.D (1) The channel functional test shall also demonstrate that' automatic isolation of' this pathway and control room ar.nunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the alarm / trip setpoint b. Instrument indicates an inoperative /downscale failure -c. Instrument controls not set in operate mode (2) The channel functional test shall also demonstrate that_ control room annunciation occurs if any of the following conditions exist: .a. Instrument indicates measured levels above the alarm setpoint. b. Instrument indicates an inoperative /downscale failure c. Instrument controls not set in operate mode (3) This functional test shall consist of measuring rate of tank decrease over .a period of time and comparing this value with flow rate instrument reading. (4) INSTRUMENT CHECK shall consist of verifying indication during periods of release. INSTRUMENT CHECK shall be made at least once per 24 hours on days' which. continuous, periodic, or batch releases are made. (5) The CHANNEL CALIBRATION shall include the use of a known (traceable to National Bureau of Standards Radiation Measurement System) radioactive source (s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS). Amendment No. 103 100A 0244p

y f TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Channel Functional Instrument ' Instrument Chef Source Check Calibration Test 1. STACK a. Noble Gas Monitor 'S' D M R Q b. Iodine Cartridge H NA-NA NA c. Particulate Filter H NA NA NA i d. Sampler Flow Abnormal D NA R. Q e. Stack flowmeter D NA R Q 2. REACTOR / TURBINE BLDG VENT a. Noble Gas Monitor D H R Q b. Iodine Sampler. H NA NA NA c. Particulate Sampler H NA NA NA d. Stack flowmeter D NA R Q 4 3. TURBINE BLDG EXHAUST

a.. Noble Gas Monitor

D M-R Q b. Iodine Sampler H NA NA NA c. Particulate Sampler H NA NA-NA d. Stack Flowmeter D NA' R Q 4. RADWASTE BLDG VENT a. Noble Gas Monitor '*' D M. R Q b. Iodine Sampler H NA. NA-NA

c. ' Particulate Sampler H

NA NA .NA d. Stack Flowmeter. D NA R Q 5. OFF GAS HYDROGEN ANALYZER (H,A, H,B) D NA R Q'*' 6. '0FF GAS POST TREATMENT *** a. Noble Gas Activity Monitor' D M , R Q'** b. Sample Flow Abnormal D NA R Q Amendment No. 103 105A 0240p

r e NOTES FOR TtJBLE 4.2.K ;- + - '1) TheCHANNELCALIBRATIONshallincludethe-use.ofa1knoYn(traceabletothe National Bureau of Standards Radiation Measurement System). radioactive . source (s) positioned in a reproducible geometry with respect to the sensor or using' standards that have obtained from suppliers that participate'in-measurement assurance activities with the National, Bureau of Standards. b (2) 'The CHANNEL FUNCTIONAL TEST shall also. demonstrate that control room alarm i annunciation occurs if any of the following conditions exist: 4 -: ^ J a. Instrument indicates measured-' levels above the alarm / trip setpoint. e lb. Instrument-indicates'an inoperable /downscale failure. c. Instrument controls not.' set in operate mode (stack only).' (3): The' channel calibration sha11 include the use of' standard gas samples containing a nominal: 3 a. Zero volume percent hydrogen (compressed air) and, 'b. One volume percent hydrogen, balance nitrogen.. (4)-'The channel functional test shall demonstrate that automatic isolation'of this pathway'and control room annunciation occurs:if any of the following j conditions exists: a. Instrument indicates measured levels above the alarm / trip setpoint. b. Instrument i'ndicates an' inoperative /downscale failure. D c. Instrument controls not-set in operate mode. The two channels are arranged in a coincidence logic.such that 2 upscale, _or 1 downscale and 1 upscale or 2 downscale will-isolate. the offgas. line. j .(5) The noble gas monitor shall have a LLD of'1E-5 (Xe 133 Equivalent). -i (6) The noble gas monitor shall have a LLP of.1E-6.(Xe 133 Equivalent). - l i-4 1 4 i Amendment No. 103-- 105B L _ 0244p - ... - - +, , - ~ ,.,.w-c,..,-

t -The operability of the seismic instrumentation ensures that sufficient-capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those. features important to safety..This capability is required to permit comparison of.the measured rc;sponse to that used in the design basis for Browns Ferry Nuclear Plant. Tht. instrumentation provided is consistent.with specific portions of the recommendations of Regulatory Guide 1.12 " Instrumentation for Earthquakes". N i 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 6ffluents. The ' alarm / trip setpoints for these instruments will be calculated in accordance with guidance provided in the ODCM to ensure that.the alarm / trip will occur' prior to exceeding the limits of.10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentration of potentially explosive gas. mixtures in the offgas holding system. 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. 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 guidance provided in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 2. The OPERABILITY and use of this instrumentation is ccasistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 1 113 Amendment No. 103 0244p

g-W i The most likely cause would be to stipulate that.one channel be bypassed. __ tested.;and restored, and then immediately following, the.second channel be-bypassed. tested, andtrestored. 'This'is shown by Curve No. 4. Note that:there is no true minimum. The curve does have'a definite knee ~and.very little. reduction in system unavailability is achieved by testing at'a shorter interval than computed by.the. equation for a single channel. The best test procedure-of all those examined is to perfectly stagger.the tests.- That is,'if the test interval is four months, test one or the other-channel every two months.'- This'is shown.in Curve No. 5. The difference between . Cases 4 and 5 is negligible. There may be other arguments, however, that more - strongly support;the perfectly staggered tests, including reductions in human ' error.. The conclusions to be drawn are these: 1.- A 1 out of r, system may be treated the same as a single channel in terms'of1 choosing a test interval; and i 2. more than one channel should not be bypassed.for testing at any one time. 4 The radiation monit' ors in the refueling area ventilation' duct which initiate ~ building iso,lation~and standby gas treatmentLoperation'are arranged in two 1 out of 2 logic systems. The bases given for the rod blocks apply here also and were . used to-arrive at the functional testing frequency. The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement. Based on' experience with instruments of similar design, a testing interval of once every.three months has been found adequate. The automatic pressure relief instrumentation can be considered to be a 1.out of 2 logic system and the discussion above applies.also. The criteria for ensuring the reliability ~and accuracy of the rad'ioactive gaseous effluent instrumentation is listed in Table 4.2.K. L The criteria for ensuring the reliability and accuracy of the radioactive liquid i effluent instrumentation is listed in Table 4.2.D.. 5 i 1 1 Amendment No. 103 116 0244p 1 ..,.-,,,.,,.n,-.. ~, ~

-LIMITING CONDITIONS FOR' OPERATION SURVEILLANCE REQUIREMENTS 3.6 Primary System Boundary -4.6 Primary System Boundary -5.- Whenever the, reactor is. critical, the limits on activity concentrations in the reactor coolant shall. not exceed the equilibrium .value of 3.2 pc/gm of-dose' equivalent I-131. This limit may be exceeded following power transients for a maximumLof.48 hours. During~this activity-transient'the iodine concentrations.shall not i exceed.the. equilibrium. values by'a factor of more than 10 whenever the reactor is critical. The ' reactor shall not be operated more than=

5. percent of its yearly power operation under this exception for the equilibrium activity.

-limits.. If the iodine concentration in the . coolant exceeds the equilibrium limit'by a factor of ten, the reactor shall shutdown, and the steam line isolation valves shall be closed i= immediately. l -1 'l Amendment No.~103 ~ 190 j 0233p'

1 LIMITING CONDITIONS'FOR OPERATION ~- SURVEILLANCE REQUIREMENTS 1 - 3.'8 ' Radioactive Materials-4.8-Radioactive Materials Applicability ' Applicability, Applies to the~ release of . Applies fo the periodic test and' radioactive-liquids and gases record requirements ~and. sampling. from the facility. 'and monitoring methods.used for facility effluents. -Objective s Objective-t To define the limits and conditions for'the release of To ensure that radioactive ' radioactive effluents-to the liquid and gaseous releases from-t l. environs to assure.that any .the-facility are, maintained .. radioactive releases are'as within the limits specified by low as reasonably achievable Specifications:3.8.A'and 3.8.B. and within,the limits of- + 10 CFR Part 20. The specifications Specification except for-3.8.A.1 and 3.8.B.1 are-exempt'from the requirements of A. " Liquid Effluents 4 a definition 1.0.C (Limiting i Condition for Operation).-

1. - Facility records shall i~

be maintained ofy Specification radioactive concentrations and - A. Liquid Effluents' volume-before. dilution of_each. batch'ofoliquid 1. Th'e concentration of effluent released,'and p radioactive material of.the average dilution j released.at any time from . flow and length of time the site to unrestricted over which each areas (see Figure 4.8-1b) discharge occurred. i shall be limited to the-concentrations specified 2.- Radioactive liquid waste, in 10 CFR Pert 20, sampling ~and' activity-j Appendix B, Table.II, ' analysis of each liquid Column 2 for radionuclides waste batch to be; other than dissolved or - discharged shall be entrained noble gases. performed prior to-For dissolved or entrained -release in accordance noble gases, the with the sampling and concentration shall be analysis program limited to 2E-4 pCi/ml 'specified in the REM. ~ total activity. 3. The operation of the 2. If the limits of 3.8.A.1-automatic isolation. are exceeded, appropriate valves and discharge action shall be initiated -tank selection valves without delay to' bring shall be checked" the release within . annually. 1 i L \\ j l' Amendment No. 1031 l 299 4 L I 0233p; + -., -+

4 LIMITING CONDITIONS FOR OPERATION' SURVEILLANCE REQUIREMENTS' -3. 18 - Radioactive Materials 4.8 Radioactive Materials limits. Provide prompt

4. -The results of the notification to-the NRC analysis of' samples-pursuant to section 6.7.2.

collected from release' points shall be used 3. The doses or dose-with-the calculational commitment to a member;of-methodology in the ODCM- -the public from radioactive to assure that the materials in liquid ' concentrations ~at the. -effluents released.from. . point of release-are. each unit'to unrestricted maintained within the, areas'(See Figure 4.8-1b) -limits of specification f; shall be limited: 3.8.A.1.- a.. During_any calendar-5. Cummulative quarterly; quarter to-<1.5 mrem to and yearly dose the total body and-<5 contributions from mrem to any organLand, ' liquid effluents:shall> be determined as. 'b. :During any calendar -specified in the ODCM at-3 year to <3 mrem 1to the least once - every 31' day';. total body and <10. mrem to any organ

6..The quantity of-radioactive material 4

If.the limits specified in contained in any outside 3.8.A.3 a & b.above are ' liquid radwaste storage exceeded, prepare and tanks shall be submit'Special Report determined to be within pursuant to Section 6.7.2. the above limit by analyzing a 5. The maximum activity to be . representative sample of contained in one liquid' the tank's contents.at~ radwaste tank'or temporary least once per 7 days storage tank that can be when' radioactive discharged directly to the materials are being environs shall not exceed added to'the-tank. 10 curies excluding tritium l ~ and~ dissolved / entrained = 4 noble gas. 6. With radioactive liquid I waste exceeding 3.8.A.5-. limits, without delay suspend all additions of-radioactive material to the tank and within 48 hours,. reduce the. tank contents to i within the limit. Events leading to this condition' must be reported'in'the next Semiannual Radioactive y 1 Effluent Release Report. (section F.2 of the REM) ' Amendment No.103 ' 0233p. ~ . ~,

.*I i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREM'ENTS ~ _3.8: ~ Radioactive Materials 4.8' Radioacti e Materials. ~ B. Airborne ~ Effluents 'B. Airborne' Effluents 1. The dose rate at any time '1. The gross B/y and. to areas at and beyond the~ particulate activity of: site boundary.(see Figure gaseous wastes released 4.8-1b) due to ~torthe environment shall ~ radioactivity released in-be monitored'and. gaseous effluents from the recorded. site shall"be. limited to ~ the following values:- a. For effluent streams -having continuous a. The' dose rate limit ~ ' monitoring for noble gases shall. capability, the-be,<500 mrem /yr to the activity shall tm total. body and <3000 ~ ~ monitored and. flow . mrem /yr to the skin,- rate evaluated and and recorded to enable release rates of b. The dose rate limit' gross radioactivity-for I-131, I-133, H-3, to be determined at - and particulates with least once per shift greater than eight day 'using instruments 4 half-lives shall be specified in table <1500 mrem /yr to any 3.2.K. 4 organ. b. For effluent streams 2. If the' limits of 3.8.B.1 without continuous are exceeded,-appropriate monitoring-corrective action shall be capability. the immediately initiated to activity shallibe bring the release within monitored'and I limits. Provide prompt -recorded ~and'the notification to the NRC release through. 4 pursuant to section 6.7.2. these streams controlled to within the limits specified 1 in 3.8.B. . Radioactive gaseous 2. waste sampling and activity analysis shall be performed in accordance with the 'l sampling and. analysis l { program specified in the REM. Dose rates shall be determined to be 3 within limits-of 3.8.B D using methods contained. j in'the ODCH. l Amendment No.103 301 4 0233p-

s o 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 5 3. The air dose to areas at ~3. Cumulative. quarterly and and beyond the site yearly dose .) ' boundary.-(see Figure contributions.from 4.8-1b) due.to noble gases gaseous releases shall released in' gaseous -be determined using effluents per unit shall methods contained in the. be limited to the ODCM at least once every following: 31 days. a. During any calendar quarter, to 15 mrad ~'for gamma radiation and <10 mrad for beta radiation; b. .During any' calendar ' year, to 110. mrad for-e gamma radiation and' (20 mrad for beta radiation.- 4. If the calculated air dose. I exceeds the limits specified,in 3.8.B.3 above, prepare and. submit a special report pursuant to section 6.7.2. f 5. The dose to a member of the public from 1 radioiodines,= radioactive materials in particulate form,.and radionuclides other than noble gases with-half-lives greater i than 8 days in gaseous' effluent released per unit to areas at and beyond the' site boundary (see Figure 4.8-lb) shall be-limited ~ to the following:- a. To any organ during any calendar quarter. .. i to 17.5 mrem; i. b. To any organ during any calendar year to 115 mrem; I 3s i Amendment No. 103 302. L ' 0233p i

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 15. If the calculated doses 4. During operation above exceed the limits of 25% power, the position 3.8.B.5 above, prepare of the charcoal bed and submit a special bypass valve will be report pursuant to verified daily. section 6.7.2. ~ 7. During operation above 5. The concentration of 25% power the discharge' hydrogen downstream'of of the SJAE must be the recombiners shall be routed through the determined to be within charcoal adsorbers. _the' limits of 3.8.B.9 by continuously monitoring 8. With gaseous waste being. the offgass whenever the-discharged for more_than SJAE is in service using 7 days without treatment instruments described in through the charcoal

Table 3.2.K.

Instrument adsorbers, prepare and surveillance submit a special report requirements _are pursuant to section specified in Table 4.2.K. 6.7.2. 9. Whenever the SJAE is in service, the concentration of hydrogen in the offgas downstream of the recombiners shall be limited to 14% by volume. 10. With the concentration of hydrogen exceeding the limit of 3.8.B.9 above, restore the concentration to within the limit within 48 hours. u Amendment No. 103 303 0233p .)

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS ~ 3.8.C' Radioactive Effluents - Dose 4.8.C-Radioactive Effluents - Dose L 1.- The dose or dose 1.. Cumulative ~ dose' i. commitment'to a real contributions from individualtfrom all liquid and gaseous uranium fuel cycle sources-effluents shall'be' .is limited to 125 mrem to -determined in'accordance: 'the total body or any 'with specifications- ~ organ (except thel thyroid, 3.8.A.3,,3.8.B.3,'and. J which is limited to <75-3.8.B.5 and the methods mrem) over a period of one. in-the ODCM. calendar. year. 2. With'the calculated dose 1 -from the release of radioactive materials in. liquid or gaseous effluents exceedingLtwice the limits it of~ specification 3.8.A.3, 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the-Commission pursuant to' ~ specification 6.7.2 and limit the; subsequent releases such that the limits of 3.8.C.1 are not exceeded. 3.8.D Mechanical Vacuum-Pump 4.8.D -Mechanical Vacuum Pump - 1. Each mechanical vacuum pump At'least once during~each shall be capable of being operating cycle verify automatic automatically isolated:and-securing and isolation of the secured on a signal or mechanical vacuum pump. high radioactivity.in'the' steam' lines whenever the-main steam isolation valves are open. ~ 2. If the limits of 3.8.D.1 are-not met, the vacuum pump shall be isolated. Amendment No. 103-3o4 0233p. t-

4 ,O 's LIMITING CONDITIONS'FOR OPERATION-SURVEILLANCE REQUIREMENTS 3.8 Radioactive Materials 4.8 ' Radioactive Materials-E. Miscellaneous Radioactive E. ' Miscellaneous RadioactiveI -Materials Sources

Materials Sources-1.

Source Leakage' Test 1. Surveillance Requirement Each sealed source : TestsLfor_ leakage and/or. f ~ ~ containing radioactive-contamination,shall be. l material either in excess- . performed by : the. l -of 100 microcuries of beta . licensee or by other. .and/or gamma emitting persons specifically. material or 5 microcuries authorized by,the of alpha emitting material Commission or an 'shall be free of 1 0.005 agreement-State, as-microcurie of removable follows: contamination. Each sealed source with removable a.- Sources in Use ) contamination in excess of.- the above limit shall be-Each sealed source, immediately withdrawn from excluding startup use and (a) either. sources and flux decontaminated and detectors previously repaired, or (b) disposed subjected to core of in'accordance with flux, containing Commission regulations. ' radioactive

material, other:than I

Hydrogen 3,'with-a ~ half-life greater. i than thirty days and in any form other than gas shall be tested for leakage and/or contamination at least once per six months..'The leakage. test shall -be-capable of detecting the presence of:0.005 microcurie of radioactive ~ material on theitest sample. l Amendment No.- 103 305 0233p. 3 aw g-- -r-. -en + g.. y.

i . LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.8.E Miscellaneous Radioactive Materials Sources 1. -Surveillance Requirements b. Stored Sources Not In Use Each sealed source-and fission detector not previously subjected to_ core flux shall be tested prior to use or transfer to another licensee unless tested within the-previous six months. Sealed-sources and' fission. detectors -transferred without a certificate indicating the last test date shall be tested prior.to_use._ c. Startup Sources and Fission Detectors dach sealed startup source and-fission. detector.shall be tested prior to being subjected to core flux and following repair or maintenance to the source. 2. Reports A report shall be prepared and submitted. to the Commission on an: annual basis if sealed sources or fission'- detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination. Amendment-No. 103 306 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials s F. Solid Radwaste F. Solid Radwaste. 1. The solid radwaste system 1. The-Process Control shall be operated in Program shall include accordance with a process surveillance checks control program, for the necessary to demonstrate solidification and compliance.with 3.8.F.1. packaging of wet radioactive wastes to ensure meeting the requirements of 10 CFR 20 and 10'CFR 71 and burial ground requirements prior -to shipment of radioactive wastes from the site. 2. With the packaging requirements of 10 CFR 20 or burial ground requirements and/or 10 CFR 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from-the site. I l Amendment No. 103 307 0233p

j ] n a ( F ts ] ua hx E d g S r n n N a i) o O y dm i I h i T t l2 c f i3 a A 't u( l w V i B i E w t g L S e n n E e n i

• g V

i d n D b l N i g r i A d n u u l i T B i d ST u l e B i N n a I i u l O r b B P o */ r r 8 8 t a E c 0 o 4 S T a t 3 A e c e E R a r L e u E e R c. e. g R i i tg rd $l F S vg d U el bB O SB E S J A g G n ei cd il + fi fu OB 3 0 1 .o N t )m n 0 e 8 m ( d 1 ( ne k m c A a t S i m 4 1

Figure 4.8-lb LAND SITE BOUNDARY \\ T 'I 's.(: . :i. v-t,! -); .. 4 . L }l; ll 1 ',,. 3 f f y. ,,. v i n 1_. .,*L s/, iO;? ',.i. ti:n. Liquid Discharge (narr.er rice 4 I,}.. .,7 -

,T 'YO

~

=--

l atte / as \\ \\ \\ ~ \\ ? miles \\ g \\ \\ \\ \\ i \\ \\ \\ \\ \\ \\ \\ 309 Amendment No. 103

i l l This page deleted d Amendment No. 103 310 0244p

3.8 BASES Radioactive waste release levels to unrestricted areas should be kept "as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20.. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety,'to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20. It is expected that by using this operational flexibility and exerting every effort to keep levels or radioactive materials released as low as reasonably achievable in accordance with criteria established in 10 CFR 50 Appendix I, the annual releases will not exceed a small fraction of the annual average concentration limits specified-in 10 CFR Part 20. 3.8.A. LIQUID EFFLUENTS Specification 3.8.A.1 is provided to ensure that the concentration of radioactive materials released in. liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) 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 MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. Specification 3.8.A.3 is provided to implement the dose requirements of Sections II.A, III A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth the Section 11.A of Appendix I. Specification 3.8.A.4 action statements provides 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". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in rsdionuclide concentrations,in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by l Amendment No. -103 311 0244p

3.'8.A fLIQUID EFFLUENTS'(cont'd) ~ ) calculational procedures based on sodels and data such that the actual b exposure of an individual through_ appropriate pathways-is'unlikely to be l substantially underestimated. The equations specified in the ODCH 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.l.109, " Calculation of Annual Doses'to' Man from Routine-Releases.of Reactor Effluents for the Purpose of Effluents from Accidental and - Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and-1.113. 3.8.B AIRBORNE EFFLUENTS 1 Specification 3.8.B.1 is provided to ensure that the dose rate at anytime at-the' exclusion boundary from gaseous effluents from all units on the site 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 10 CFR part 20, Appendix B, Table II, Column 1. 'These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result ~in the exposure of a member of_the public 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 members of the public who may at t times be within the exclusion area boundary,' the occupancy of the members of .the public will be sufficiently low to_ compensate for any increase in the ] atmospheric diffusion factor above that for the exclusion area boundary. i i l 4 i T f i knendment No.103 312 '0244p.

3.8.B'-AIRBORNE EFFLUENTS (cont'd) 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 1 500 mrem / year to the total body or to ~ 1 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 i 1500 mrem / year for the nearest cow._to_the plant. Specification 3.8.B.2 requires that appropriate correction action (s)-be-taken to reduce gaseous effluent releases if the limits of 3.8.B.1 are exceeded. Specification 3.8.B.5 dose limits is provided to implement the requirements of. Section II.C, III.A. and IV of Appendix I, 10 CFR Part 50. The limiting-conditions for operation are the guides set forth in Section II.C of Appendix I. I Specification 3.8.B.6 action statement provides 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 materials in gasec as effluents will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the surveillance. requirements implement the requirements in Section III.A of Appendix I 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-0DCM calculational methods used 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, NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979, and 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 i provide for determining the actual doses based upon the historical average l atmospheric conditions. The release. rate specifications for radioiodines, ) I i radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the ) unrestricted. area. The pathways which are examined in the development of these calculations are:

1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and

4) deposition on the ground with subsequent exposure of man.

l Specification 3.8.B.6 action statement requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.S. Amendment No. 103 313 1 0244p

s. ~ 4 { . AIRBORNE EFFLUENTS ~ Specification'3.8.B.7 requires.that the offgas charcoal adsorber beds be used' when specified to treat gaseous effluents prior.to their release to the' environment. This provides reasonable assurance'that'the' release of + radioactive materials in gaseous effluents will be.kept "as low as is-reasonably achievable'.'. This specification implements-the requirements of-10 CFR Part 50.36a, 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~1imits governing the use.of appropriate portions of 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. Specification 3.8.B.8 requires that a special report be prepared'and submitted to explain reasons for any failure to. comply with Specification 3.8.B.7. Specification 3.8.B.3 is provided to implement the~ requirements of -Section II.B III.A and IV.A of Appendix.I, 10 CFR Part 50..The Limiting Condition for Operation implements the guide set forth.in Section II.C of Appendix-I. Specification 3.8.B.4 action statement provides'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 materials in gaseous effluents will-be.'kept'"as low as-is reasonably-achievable". The Surveillance Requirements implement the requirements in Section III.A of Appendix I'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 a member of the public through appropriate pathways is unlikely to-be substantially underestimated.- The dose calculations established in the ODCM for calculating the doses due to the actual release 4 ~ rates of radioactive noble gases in gaseous 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 j Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1 October 1977, NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionoclides", October 1979 and Regulatory Guide 1.111', " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from j 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. Specificaitons 3.8.B.4 requires that a special report be prepared and submitted to explain violations of the' limiting doses contained in Specification 3.8.B.3. 1 4.8.A and 4.8.B BASES The surveillance requirements given under Specification 4.8.A and 4.8.B provide assurance that liquid-and gaseous wastes are properly controlled and 1 ) monitored during any release or radioactive materials in the liquid and i l Amendment No. 103 314 0244p E

a L ..Y4;8.A'an'd 4.8.B BASES (cont'd) t gaseous effluents.' These surveillanceLrequirement's' provide 1the data for the + = . licensee and the Commission.to evaluate the station's performance relative to radioactive wastes released to the environment. Reportsfon the quantities of-radioactive materials released in effluents shall be furnished to.the Commission on the basis.of-Section 6 of these technical specifications. On i the basis of such reports and any additionalcinformation the Commission may-l .obtain-from the licensee or others, the Commission may from time to time. require'the licensee:to take such actions as the Commission deems appropriate. ^ 3.8.C and 4.8.C BASES This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires-the preparation and submittal of a Special Report whenever the calculated' doses form plant radioactive effluents: exceed.twice. the design' objective doses'of-Appendix I. For sites containing up to four' reactors, it is highly unlikely that the resultant dose to a member of the publicLvill exceed the dose limits of 40.CFR 190 if'the' individual reactors i' remain within the reporting-requirement level. The'Special Report will describe a course of action which should result-in the_ limitation of dose'to a member of the public.for_the calendar-year to be within,40 CFR 190 limits. For the purposes of the.Special Report, it may be assumed that the dose .l commitment 1to the member of the.public from other uranium fuel cycle sources 1 is. negligible, with the exception that dose' contributions from other nuclear fuel cycle facilities at the same site or within a radius of five miles must i be considered. i + 3.8.D and 4.8.D MECHANICAL VACUUM PUMP i The purpose of isolating the mechanical vacuum pump line is to' limit the-release of activity from the main 1 condenser. Dut ing an accident,, fission i products would be transported from the reactor through the main steam lines to =the condenser.. The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate. isolation. l 3.8.E and 4.8.E BASES W ii-The limitations:on removable contamination for sources requiring leak testing, j including alpha. emitters, based on 10 CFR 70.39(c) limits.for plutonium. This i limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, with f surveillance requirements commensurate with the probability of' damage to a source in that group. Those sources which are frequently handled are required to be tested more often than-those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitocing or boron measuring devices)'are considered to be stored. and need not be tested unless they are removed from the shielded mechanism. i 315' Amendment No 103 0244p i

s.,.-

~~ .I . H 6.0 EADMINISTRATIVE CONTROI.S= k.- Thefradiological environmental. monitoring ~ program and the. 1 results thereof at least once per 12 months. 1. The performance of. activities: required by the Quality Assurance Program to meet the criteria'of Regulatory Guide 4.15, December 1977 or Regulatory. Guide 1.21,, _ . Rev.1,1974 and Regulatory Guide 4.1,;1975 at least once per 12 months. n m. The performance'of activities required by the Safeguards ~ Contingency Plan.to meet-the criteria of 10 CFR'73.40(d) at . least once per 12, months. ~n. The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months. ~ J J t o. The Process. Control-Program and implementing procedures forc solidification of wet radioactive wastes at least once per 8 24 months. 1 1 p. The Radiologica1' Effluent Manual arui implementing procedures 1 at least once per 12 months. l 4, AUTHORITY The NSRB shall report to and' advise the Manager of Power on those-areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.8. 10. RECORDS Records of NSRB activities shall be prepared, approved and . distributed as indicated belowr 4 1-a. Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14' days ~fo11owing-each meeting. b. Reports of reviews encompassed by Section 6.2.A.7 above,- 6 1 shall.be prepared, approved and forwarded to-the Manager of Power within 14 days following' completion of the review. c. Audit. reports encompassed by Section 6.2.A.8 above,,shall be forwarded to the Manger of Power and to the management-positions responsible for the areas: audited within'30 days after completion of the audit. E i Amendment No. 103 1 364A I ' 0244p-y.,. _a .pr-c ,y 4 ~,,e, .._..p f 4, ..g.

a / 6.0i ADMINISTRATIVE' CONTROLS . ~u .j. . Review proposed changes to the: Radiological Effluent 1 Manual., i k. Review l adequacy of thS' Process' Control' Program and Offsite-Dose Calculation Manual at least.once every 24 months. m 1.- . Review changes to the radwaste treatmentcsystems.: .m. -Review of every unplanned onsite release of radioactive material.to the environs including the preparation and r forwarding ~of reports covering evaluation,; recommendation, and deposition of the corrective action to prevent. i recurtence to the Director, Nuclear. Power and to the Nuclear Safety Review Board. 5. Authority ~ The PORC shall.txe advisory to' the plant superintendent'. 6. Records Minutes shall.be kept for all,PORC meetings with copies sent to Director, Nuclear Power;. Assistant Director of Nuclear. Power (Operations); Chairma.2, NSRB; i 7. Procedures Written' administrative procedures for committee: operation'shall be prepared and maintained describing the method for submission and content of presentations'to the committee, review and approval by members of committee actions, dissemination of. 4: minutes,: agenda and scheduling of meetings. 4 4

l q

' \\ I 1. t., I Amendment No.'103 367 ~ 0244p e ea e -a,- +- ++"t'y*

• +

x e- =

• -r vr

= r

• +

tY t ve ' - I-

. ~- -... .j-s 6.0'? ADMINISTRATIVE CONTROLS 6;3 ' Procedures ~ A. . Detailed written procedures,. including applicable checkoff lists .l.. covering items listed belowLshall be prepared approved,and-adhered to.. e '1. Normal startup,' operation and shutdown of the reactor'and_of all- ' systems and. components' involving nuclear safety,of the facility. .2. Refueling operations. 3... -Actions to be'taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms,' suspected primary system leaks and-abnormal reactivity changes. ~ 4. Emergency conditions involving potential or_ actual release of radioactivity. 5. Preventive.or corrective maintenance operacionsLwhich could have- -an effect'on the safety of the reactor. 6. Surveillance and testing requirements. 4 7. Radiation control procedures, 4 j 8.' Radiological Emergency Plan implementing procedures. 9. Plant security program implementing procedures. 10. Fire protection and prevention procedures. l 11. Limitations on the amount of overtime worked by individuals performing safety-related functions-in i.ccordance with the NRC policy statement on working hours (Generic Letter No. 82-12). 12. Radiological Effluent' Manual implementing procedures'. 13. Process Control Program (PCP). 14. Offsite Dose. Calculation Manual. B. - Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by:the_ plant' superintendent prior to implementation. Temporary changes to-a procedure which do not change the' intent of.the approved procedure may;be made by.a' member of the-plant staff knowledgeable 'in the area 'affected. by the procedure except 'that temporary changes to those.. items listed.above except item.5 . require'the additional' approvalof a member of the. plant staff who . holds a Senior Reactor Operator. license on the unit affected.. Such changes shall be documented'and rubsequently reviewed by PORC and approved by the_ plant superintendent. Amendment No. ~ 103 368 - 0244p -. u

6.0 -ADMINIS'IRATIVE CONTROL ~- 6.3 Procedures E. Quality Assurance Procedures - Effluent and-Environmental Monitoring Quality Acsurance procedures shall be established, implemented,' and maintained for effluent'and' environmental' monitoring..using the_ guidance in Regulatory Guide 1.21, rev. 1, June 1974 and Regulatory Guide 4.1, rev. 1, April 1975 or Regulatory Guide 4.15, Dec.' 1977. 1 1 1 Amendment No. 103 370 0244p

4 J 6.0 ADMINISTRATIVE CONTROLS 3. Unique Reporting Requirements A. Radioactive Effluent ~ Release Report-t Deleted (See REM section F2). r t f c e 4 ( f I i a l Amendment Nc. 103 385 0244p. ,e

a ~ 6~.0 ADMINISTRATIVE CONTROL 6.9. Process Control Program (PCP)' 1. The PCP shall be approved by the Commission prior to implementation. ~ 2. Changes to.the PCP shall be submitted to the Commission in~the semi-annual: Radioactive Effluent Release Report for the;' period -in which the change (s) was made.- This submittal shall contain: -l a. Sufficiently-detailed.information to' totally support.the change.. ~ b. -A determination that the change did not, change the overal1L conformance of the solidified product to existing criteria. -3. Changes to the PCP.shall become effective upon review and. acceptance by PORC. ~ 6.10 0FFSITE DOSE CALCULATIONAL MANUAL (ODCM) 4 .1. The ODCH shal1~be approved by the Commission prior to' implementation. 2 2. Changes to.the ODCM shall be submitted.to the Commission in the semi-annual Radioactive Effluent Release Report for the. period in which the change (s) was made..This. submittal shall contain: Sufficiently detailed.information to totally support the a. change. 3. Changes to the ODCM shall become effective upon review'and acceptance by PORC. 6.11 RADIOLOGICAL EFFLUENT MANUAL (REM) 1. The REM shall be approved by the Commission prior to i implementation. 2. Changes to the REM shall be reviewed by PORC prior to-implementation. 3. Changes to the REM shall be approved by the Commission prior to-implementation. i Amendment No.103 389 0244p' L. ~

~. 1 -1 ENVIRONMENTAL TECHNICAL SPECIFICAITONS r

FOR BROWNS FERRY NUCLEAR PLANT TABLE OF CONTENTS.

[' Page No.' 1.0 DEFINITIONS............................................. Deleted' 2.0 LIMITING CONDITIONS FOR OPERATION...................... Deleted 2.1 Thermal Discharge' Limits......~.......'.~............ Deleted $.2 Chemica1.......................................... Deleted 2.2.1 Makeup Water Treatment' Plant' Spent 'Demineralizer Regerants.................. . Deleted 1 2.2.2 Chlorine................................... Deleted 3.0. DESIGN FEATURES-AND OPERATING PRACTICES................ Deleted ~ 4 3.1 Chemical Usage.................................... Deleted 3.1.1 Oils and Hazardous Materials............... Deleted 3.1.2 Other Chemicals............................ Deleted 3.2 Land Management................................... .. Deleted 3.2.1 Power Plant Site........................... Deleted { 3.2.2 Transmission Line Right-of-Way Maintenance. 1-3.3 Onsite Meteorological Monitoring.................. Deleted 4.0, ENVIRONMENTAL SURVEILLANCE............................. Deleted. 4.1 Ecological Surveillance........................... Deleted j. 4.1.1 Abiotic.................................... Deleted i. 4.1.2 Biotic..................~................... Deleted 4.1.3 Special Studies............................ Deleted 4.2 Radiological Environmental Monitoring Program..... Deleted' 1 4. il 4 f0244p, ' Amendment No.103 .. u.

m-, h s l L2- ' 5.0' ADMINISTRATIVE'C0NTROLS...............................~'... Deleted 5.1~ Responsibility..................................... Deleted 5.2-Organization.......................~............... Deleted a 5.3 ' Review and Audit.................................. Deleted ' Action to'be Taken if an Environment LCO is 5.4 Exceeded........................................ Deleted. 5.5-Procedure.........'................................ ' Deleted 5.6. Reporting Requirements............................ Deleted 5.7 Environmental Records............................. Deleted Tab 1 e s...................................................... - De l e t ed - Figures..................................................... Deleted l l ' 4 1 4 4 - 0244p. Amendment No.103 e a e

2: - .e- -a 3.2.2 Transmission' Line Right-of.-Way Maintenance s Obj ective - ' The sole. purpose of this section;is to provide reporting: requirements (to USNRC) on herbicide usage, iffany, for purposes of ..right-of-way maintenance regarding only.those transmission lines I under USNRC's jurisdiction for the Browns Ferry Nuclear Plant.; Specification i A statement as to whether or not herbicides have been used in ~ s maintaining rights-of-way for those transmission lines associated. with.the Browns Ferry Nuclear Plant'shall.be provided. If- ~ herbicides have been used, a description of the types, volumes; . concentrations,. manners and frequencies of application,-and miles' or rights-of-way that have been. treated shall.be' included. .b,. I Reporting Requirements Information as specified.above shal1 be.provided in the Annual ^- ~ Operating-Report (Appendix ' A,' Section 6.7.1(bD. Bases I l Vegetation growth on a' transmission line right-of-way must'be-controlled in such a manner that'it will neither interfere with safe and. reliable operation of the line or impede restorationLof- ~ service when outages occur. i j Vegetation growth is controlled by mechanical cutting and the i limited use of herbicides.. Selected chemicals approved ~by EPA for i ~ use as herbicides are assigned (by EPA) label instructions which provide guidance on and procedures for their use.~. t i-4 l T .i 1 i-1 Amendment No. 103 _g_ l-0244p; 2 . e -- - - -J - - - = - --+--" ' ~ * " " ~ ~ ~ ' ~ ~ ~ ' ~ ~ ' " ~ ' * ' " "

• }}