Text

Amends 99 & 91 to Licenses NPF-2 & NPF-8,respectively, Changing TSs to Relocate Procedural Details of Radiological Effluent Technical Specifications to ODCM & Procedural Details for Solid Radioactive Wastes to PCP
	ML20057C361
Person / Time
Site:	Farley
Issue date:	09/20/1993
From:	Bajwa S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20057C362	List: ML20057C361; ML20057C364;
References
	NUDOCS 9309280269
	Download: ML20057C361 (115)
	v • d • e

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UNITED STATES 8 'y

.7,7 NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20555

%.... /

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated June 23, 1992, as supplemented November 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license 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 accordance with 10 CFR Part 51 of the Commission'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. NPF-2 is hereby amended to read as follows:

9309280269 930920 PDR ADOCK 05000348

-l['/

P PDR

4 e (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

i 3.

This license amendment is' effective as of its date of issuance and shall be implemented by December 31, 1993.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 20, 1993 9

9

s ATTACHMENT TO LICENSE AMENDMENT NO, 99 TO FACIllTY OPERATING LICENSE NO. Sir-2 DOCKF7 au. 5u-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revisr.d areas are indicated by marginal lines.

Remove Pages Insert Paaes 1

I IV IV XI XI XVI XVI XIX XIX XX XX l-3 1-3 1-4 1-4 1-5 1-5 1-6 1-6 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 3/4 3-63 3/4 3-64 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-67 3/4 3-67 3/4 3-68 3/4 3-68 3/4 3-69 3/4 3-69 3/4 3-70 3/4 3-70 3/4 3-71 3/4 3-71 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 3/4 11-8 3/4 11-8 3/4 11-9 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-17 3/4 11-17 3/4 11-18 3/4 11-18

)

3/4 11-19 3/4 11-19 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7

s Continued:

ATTACHMENT TO LICENSE AMENOMENT NO. oo TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Paaes Insert Paaes 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-10 3/4 12-11 3/4 12-11 8 3/4 3-5 B 3/4 3-5 B 3/4 11-1 B 3/4 11-1 B 3/4 11-2 B 3/4 11-2 8 3/4 11-3 8 3/4 11-3

~

B 3/4 11-4 B 3/4 11-4 8 3/4 11-5 B 3/4 11-5 B 3/4 12-1 B 3/4 12-1 B 3/4 12-2 B 3/4 12-2 6-15 6-15 6-15a 6-15b 6-15c 6-17 6-17 6-18 6-18 6-19 6-19 6-21 6-21 6-21a 6-21a 6-23 6-23 i

6-24 6-24 i

e i

i INDEX DEFINITIONS SECTION 31[

1.0 DEFINITIONS 9

1.1 ACTION.........................................................

1-1 1.2 AXIAL FLUX DIFFERENCE..........................................

1-1 1.3 CHANNEL CALIBRATION.............................................

1-1 1.4 CHANNEL CHECK..................................................

1-1 i

1.5 CHANNEL FUNCTION TEST..........................................

1,

1.6 CONTAINMENT INTEGRITY..........................................

1-2 1.7 CONTROLLED LEAKAGE.............................................

1-2 1.8 CORE ALTERATION................................................

1-2 1.9 DOSE EQUIVALENT I-131..........................................

1-2 f

1.10 E-AVERAGE DISINTEGRATION ENERGY................................ 1-3 l.11 ENGINEERED SAFETY FEATURES RESPONSE TIME.......................

1-3 1.12 FREQUENCY NOTATION.............................................

1-3 1.13 EASE 0WS-RA9 WASTE-TREATMENT-SYSTEM (Deleted)....................

1-3 1.14 IDENTIFIED LEAKAGE.............................................

1-3 l

1.15 EIQWID-RADWASTE-TREATMENT-SYSTEM (Deleted)..................... 1-4 1.16 MAJOR-EHANGES-TO-RADIGAETIVE-WASTE-TREATMENT-SYSTEMS (Deleted).1-4 1.17 0FFSITE DOSE CALCULATION MANUAL (ODCM).........................

1-4' 1.18 OPERABLE - OPERABILITY.........................................

1-4 1.19 OPERATIONAL MODE - MODE........................................

1-5 1.20 PHYSICS TESTS..................................................

1-5 1.21 PRESSURE BOUNDARY LEAKAGE......................................

1-5 1.22 PROCESS CONTROL PROGRAM (PCP)..................................

1-5 1.23 PURGE - PURGING................................................

1-5 1.24 QUADRANT POWER TILT RATIO......................................

1-5 1.25 RATED THERMAL POWER............................................ 1-6 1

1.26 REACTOR TRIP SYSTEM RESP 0 HSE TIME..............................

1-6 1.27 REPORTABLE EVENT...............................................

1-6 1.28 SHUTDOWN MARGIN................................................

1-6 1.29 SOEIBIFIEATION (Deleted).......................................

1-6 1

1.30 SOURCE CHECK................................................... 1-6 1.31 STAGGERED TEST BASIS...........................................

1-6 1.32 THERMAL POWER..................................................

1-7 1.33 UNIDENTIFIED LEAKAGE...........................................

1-7 1.34 VENTILATION EXHAUST TREATMENT SYSTEM...........................

1-7 1.35 YENTING........................................................

1-7 TABLE 1.1 OPERATIONAL MODES.........................................

1-8 TABLE 1.2 FREQUENCY NOTATION........................................

1-9 FARLEY-UNIT 1 I

AMENDMENT NO. 57, 99 i

i 6

o 1

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

+

SECTION f.sGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE.................................

3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR.........................

3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR..................

3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO............................

3/4 2-11 3/4.2.5 DNB PARAMETERS.......................................

3/4 2-14 3/4.3 INSTRUMENTATION 3/4.3.1 R[ACTORTRIP5YSTEMINSTRUMENTATION..................

3/4 3-1 3/4.3.2 EHGINEERED SAFETY FEATURE ACTUATION SYSTEM i

INSTRUMENTATION....................................

3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Rtdiation Monitoring.................................

3/4 3-38 l

Me,vabl e Incore Detectors.............................

3/4 3-42 Seisnic Monitoring Instrumentation...................

3/4 3-43

]

Meteorological Instrumentation.......................

3/4 3-46 Remote Shutdown Instrumentation......................

3/4 3-49 Chlorine Detection Systems...........................

3/4 3-52 l

High Energy Line Break Sensors.......................

3/4 3-53 Accident Monitoring Instrumentation..................

3/4 3-56 Ftpe-Detection-Instrumentation (Deleted).............

3/4 3-59 Radleactive-Elquid-Effluent-Monitoring (Deleted).....

3/4 3-61 Waste Gas Monitoring.................................

3/4 3-66 3/4.3.4 TURBINE OVERSPLED PROTECTION.........................

3/4 3-72 FARLEY-UNIT I IV AMDOMENT NO. #I, 76, 99 i

i i

'A O

-i INDEX

)

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS i

3/4.11.1 LIQUID EFFLUENTS Concentration (Deleted).............................

3/4 11-1 Dese (Deleted)......................................

3/4 11-5 Liquid-Waste-Treatment (Deleted)....................

3/4 11-6 Liquid Holdup Tanks.................................

3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS Bese-Rate (Deleted)................................

3/4 11-8 Dese-Neble-Gases (Deleted)..........................

3/4 11-12 Dese-Radiotodines,-Particulate,-and-Radienuclides-Gther-than-Neble-Gases (Deleted).....

3/4 11-13 Gaseous-Radwaste-Treatment (Deleted)................

3/4 11-14 Waste Gas Monitoring................................

3/4 11-15 Gas Storage Tanks...................................

3/4 11-16 3/4.11.3 RA9 WASTE-SQLIBIFIEATION (Deleted)...................

3/4 11-17 3/4.11.4 TOTAL-DOSE (Deleted)................................

3/4 11-19 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING i

3/4.12.1 MONITORING-PROGRAM (Deleted)........................

3/4 12-1 3/4.12.2 LAND-USE-CENSUS (Deleted)..........................

3/4 12-10 3/4.12.3 INTERLABORATORY-COMPARISBN (Deleted)................

3/4 12-11 i

I i

FARLEY-UNIT 1 XI AMENDMENT NO. 26, 99 l

i r

- _ _,. ~ _

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INDEX

?

BASES SECTION M

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.................................

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.................................

B 3/4 11-2 3/4.11.3 RA9 WASTE-SQLIBIFICATION (Deleted).................

B 3/4 11-5 3/4.11.4 TOTAL-DOSE (Deleted)..............................

B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING-PROGRAM (Deleted)......................

B 3/4 12-1

nt 3/4.12.2 LAND-USE-EENSUS (Deleted).........................

B 3/4 12-1 3/4.12.3 INTERLABORATORV-COMPARISON-PROGRAM (Deleted)......

B 3/4 12-2 FARLEY-UNIT 1 XVI AMENDMENT NO. 26, 99

i e-

'i INDEX i

ADMINISTRATIVE CONTROLS SECTION g

j i

Review.....................................................

6 '

Audits.....................................................

6-11 Authority..................................................

6-12 Records....................................................

6-12 i

r 6.5.3 TECHNICAL REVIEW AND CONTROL i

Activities.................................................

6-12 Records....................................................

6-13 6,6 REPORTABLE EVENT ACTION......................................

6-14 6.7 SAFETY LIMIT VIOLATION.......................................

6-14

(

6.8 PROCEDURES AND PROGRAMS......................................

6-14 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS 4

i Startup Report.............................................

6-15c An n u al Re p o rt..............................................

6-16 Annual Radiological Environmental Operating Report.........

6-17 l

~

Semiannual Radioactive Effluent Release Report.............

6-17 Monthly Operating Report...................................

6-19 Radi al Peaking Factor Limi t Report.........................

6-19 Annual Diesel Generator Reliability Data Report............

6-19 Annual Reactor Coolant System Specific Activity Report.....

6-20 i

i Annual Sealed Source Leakage Report........................

6-20

)

6.9.2 SPECIAL REPORTS............................................

6-20

)

6.10 RECORD RETENTION............................................

6-20 6.11 RADIATION PROTECTION PROGRAM................................

6-21a 1

1 6.12 HIGH RADIATION AREA.........................................

6-22 1

1 FARLEY-UNIT 1 XIX AMENDMENT NO. 57, 99 j

i

i o-i 1

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E r

ADMINISTRATIVE CONTROLS i

i l

SECTION g

6.13 PROCESS CONTROL PROGRAM....................................

6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................

6-23 6.15 MAJOR-CHANGES-TO-RADIGAGTIVE WASTE-TREATMENT-SYSTEMS (Deleted)........................

6-24 l

6.16 ENVIRONMENTAL QUALIFICATION................................

6-25

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I I

1 i

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J FARLEY-UNIT 1 XX AMEN 0 MENT NO. 57, 99 L

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DEFINITIONS E - AVERAGE DISINTEGRATION ENERGY 1.10 E shall be the average sum (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling? of +3-average beta and gamma energies per disintegration (in Mev) for tsutor s other than todines, with half lives greater than 15 minutes, making a; t.

least 95% of the total non-iodine activity in the coolant.

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.11 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FRE0VENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

GASEOUS RADWASTE TREATMENT SYSTEM i

1.13 This definition deleted.

Refer to the Offsite Dose Calculation Manual.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTRCLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor coolant system leakage through a steam generator to the secondary system.

FARLEY-UNIT 1 1-3 AMENDMENT NO. 26, 99

DEFINITIONS LIOUID RADVASTE TREATMENT SYSTEM 1.15 This definition deleted.

Refer to the Offsite Dose Calculation Manual.

KAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS l.16 This definition deleted.

Refer to the Offsite Dose Calculation Manual and the Process Control Program.

OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.17 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Surveillance and Semiannual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9.

l OPERABLE - OPERABILITY 1.18 A systes, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, a normal and an emer-gency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystes, train, con-ponent or device to perform its function (s) are also capable of performing their related support function (s).

FARLEY-UNIT 1 1-4 AMENDMENT NO. 26, 99

o o

DEFINITIONS OPERATIONAL MODE - MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Tcble 1.1.

PHYSICS TESTS 1.20 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and

1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAXAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System Component body, pipe wall or vessel wall.

l I

PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; burial ground requirements; and other requirements governing the j

disposal of solid radioactive waste.

I PURGE - PURGING 1.23 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

00ADRANT POWER TILT RATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

FARLEY-UNIT 1 1-5 AMENDMENT NO. 26, 99

1 i

DEFINITIONS 1

RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2652 MWt.

4 REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when l

the monitored parameter exceeds its trip setpoint at the channel sensor until l

loss of stationary gripper coil voltage.

l REPORTABLE EVENT i

5b73 o O CFR P r 5 I

SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which j

the reactor is suberitical or would be subcritical from its present condition

.i assuming all full length rod cluster assemblies (shutdown and control) are fully

)

inserted except for the single rod cluster assembly of highest reactivity worth.

which is assumed to be fully withdrawn.

i i

SOLIDIFICATION l

1.29 This definition deleted. Refer to the Process Control Program.

SOURCE CHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

STAGGERED TEST BASIS i

1.31 A STAGGERED TEST BASIS shall consist of:

j a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, i

b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

FARLEY-UNIT 1 1-6 AMEN 0 MENT NO. 57, 99 P

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INSTRUMENTATION I

i RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

.l This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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B b

5 9

P

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e P

l FARLEY-UNIT.1

.3/4 3-61 AMENDMENT NO. 7, 99 N

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This page intentionally left blank.

3/4 3-63 through 3/4 3-65 Deleted.

FARLEY-UNIT 1 3/4 3-62 AMENOMENT N0. 26, 99

e INSTRUMENTATION HASTE GAS MONITORING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.3.11 The waste gas mo'.11toring instrumentation channels shown in Table 3.3-14 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY: As shown in Table 3.3-14.

ACTION:

With a waste gas monitoring instrumentation channel alarm / trip a.

setpoint less conservative than required by the above Specification, declare the channel inoperable and take the ACTION shown in Table 3.3-14.

b.

With less than the minimum number of waste gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-14.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each waste gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

I FARLEY-UNIT 1 3/4 3-66 AMENDMENT NO. 57, 99

o TABLE 3.3-14 c

h WASTE GAS MONITORING INSTRUMENTATION q

~

MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.

WASTE GAS HOLDUP SYSTEM MONITORING INSTRUMENTATION 38 a.

Oxygen Monitois 2/recombiner 40 b.

Hydrogen Monitors 1/recombiner w1 w

t t

5 R

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.E

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I TABLE 3.3-14 (Continued)

TABLE NOTATION

{

(Not Used)

(Not Used) l During recombiner operation.

ACTION 35 -

(Not-Used) t i

ACTION 36 -

(Not Used) l l

ACTION 37 -

(Not Used)

ACTION 38 -- With the number of channels OPERABLE one less than required by j

the Minimum Channels OPERABLE requirement, except for testing, 1solate the oxygen supply to the affected recombiner. 'With no channels OPERABLE, addition of waste gas to the waste gas system may continue provided a grab sample is taken from the on-service waste decay tank and analyzed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months j

and the oxygen concentration remains less than 1%.

i i

FARLEY-UNIT.1 3/4 3-68 AMEN 0 MENT NO. 26, 99 l

i t

o TABLE 3.3-14 (Continued)

TABLE NOTATION ACTION 39 -

(Not Used)

ACTION 40 - With no channels OPERABLE, addition of waste gas to the waste gas system may continue provided a grab sample is taken from the on-service waste decay tank and analyzed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the oxygen concentration remains less than 1%.

a 9

t I

FARLEY-UNIT 1 3/4 3-69 AMENDMENT NO. 76, 99

D.

f TABLE 4.3-9 m7 WASTE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS

!iiQ CilANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 1.

WASTE GAS HOLDUP SYSTEM MONITORING INSTRUMENTATION

a. Inlet Hydrogen Monitor D

N.A.

Q(3)

M

b. Outlet Hydrogen Monitor D

N.A.

Q(3)

M

c. Inlet Oxygen Monitor D

N.A.

Q(4)

M

d. Outlet Oxygen Monitor D

H.A.

Q(4)

M w

o 6

P TABLE 4.3-9 (Continued)

-i TABLE NOTATION i

(Not Used) i During recombiner operation.

j (1)

(NotUsed) j i

i 1

(2)

(Not Used) i l

(3) The CHANNEL CALIBRATION shall include the use of standard gas samples containing in accordance with manufacturer's recommendations.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing in accordance with manufacturer's recommendations.

In addition,-

a standard gas sample of nominally four volume percent oxygen, balance nitrogen shall be used for inlet oxygen monitor linearity check.

i i

FARLEY-UNIT 1 3/4 3-71 AMEN 0 MENT NO. 26, 99 i

e 3/4.11 RADIOACTIVE EFFLUENTS j

3/4.11.1 LIOUID EFFLUENTS CONCENTRATION This specification deleted.

Refer to the Offsite Dose Calculation Manual, i

4 4.I FARLEY-UNIT 1 3/4 11-1 AMENDMENT NO. 26, 99 i

t e

This page intentionally left blank.

3/4 11-3 and 3/4 11-4 Deleted.

FARLEY-UNIT 1 3/4 11-2 AMENDMENT NO. 26, 99

a RADIOACTIVE EFFLUENTS D9.51 This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 1 3/4 11-5 ANENDNENT NO. S K 99

RADIOACTIVE EFFLUENTS LIOUID WASTE TREATMENT I

I This specification deleted.

Refer to the Offsite Dose Calculation Manual.

1 t

t i

l FARLEY-UNIT 1 3/4 11-6 AMDEMENT NO. 7, 99

.l

1 o

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE This specification deleted. Refer to the Offsite Dose Calculation Manual.

I n

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a p

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-i 1

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.j FARLEY-UNIT 1 3/4 11-8 AMEN 0 MENT NO. 26, 99-

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j This page intentionally left blank.

3/4 11-10 and 3/4 11-11 Deleted.

7 i

e FARLEY-UNIT 1 3/4 11-9 AMENDMENT NO.26, 70, 99 O

e e

G RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 1 3/4 11-12 AMENDMENT NO. p, 99

RADIDACTIVE EFFLUENTS DOSE - RADIDIODINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM. AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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t FARLEY-UNIT 1 3/4 11-13 AMDEMENT NO. R, 99 I

3

,-w, u,_,

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATNENT This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 1 3/4 11-14 AMENDMENT NO. 57, 99 4

RADIOACTIVE EFFLUENTS WASTE GAS MONITORING LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in any portion of the gaseous radwaste treatment system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration in that portion of the gaseous radwaste treatment system exceeds 4% by volume.

t APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the gaseous radwaste treatment system greater than 2% by volume but less than or equal to 4% by volume, reduce the concentration of oxygen to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the gaseous radwaste treatment i

system greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% within I hour and less than or equal to 2%

l by volume within the following 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrogen or oxygen in the gaseous radwaste treatment system shall be determined to be within the above limits by monitoring the waste gases in the gaseous radwaste treatment system with the hydrogen i

and/or oxygen monitors required DPERABLE by Table 3.3-14 of Specification 3.3.3.11.

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FARLEY-UNIT 1 3/4 11-15 AMENDMENT NO. 26, 99 1

e o-l RADI0 ACTIVE EFFLUENTS 3/4.11.3 RADWASTE SOLIDIFICAI1Qg l

This specification deleted.

Refer to the Process Control Program.

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FARLEY-UNIT 1 3/411-17 AMDOUT NO. f#, 99-O w

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FARLEY-UNIT 1 3/4 11-18 MEN m, 4 g

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RADI0 ACTIVE EFFLUENTS.

3/4.11.4 TOTAL DOSE This specification deleted. Refer to the Offsite Dose Calculation Manual.

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FARLEY-UNIT 1 3/4 11-19 AMDOMDIT NO. 57, 99

s 3/4.12 RADIOLOGICAL FNVIRONMENTAL MONITORIRG 3/4.12.1 MONITORING PROGRAM This specification deleted. Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 1 3/4 12-1 AMENDMENT NO. R, 99

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This page intentionally left blank.

3/4 12-3 through 3/4 12-9 Deleted.

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FARLEY-UNITS 1 3/4 12-2 AMEN 0 MENT NO. 26, 99

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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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FARLEY-UNIT 1 3/4 12-10 AMENDMENT NO. P, 99

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J RADIOLOGICAL ENVIRONMENTAL MONITORING i

.I 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM i

i This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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FARLEY-UNIT 1 3/4 12-11 AMDOMENT NO. 26,' 99

INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION This specification deleted. Refer to the Offsite Dose Calculation Manual.

3/4.3.3.11 WASTE GAS MONITORING INSTRUMENTATION This instrumentation monitors (and controls) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation are consistent with the requirements of General Design Criteria 60 and 63 of Appendix A to 10 CFR Part 50.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

a 4

FARLEY-UNIT 1 B 3/4 3-5 AMENDMENT NO. 47, gg, 99 i

3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification deleted. Refer to the Offsite Dose Calculation Manual.

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3/4.11.1.2 DOSE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 1 B 3/4 11-1 AMEN 0 MENT NO. 26, 99

7 RADI0 ACTIVE EFFLUENTS BASES L

3/4.11.1.3 LIOUID WASTE TREATMENT i

This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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3/4.11.1.4 LIOUID HOLDUP TANKS Restricting.the' quantity of radioactive material contained in the specified i

tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

P

-t 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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FARLEY-UNIT 1 B 3/4 11-2 AMDOIENT NO. 26, 99 y-..._.,

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e RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.2 DOSE - NOBLE GASES This specification deleted.

Refer to the Offsite Dose Calculation Manual.

3/4.11.2.3 DOSE - RADI0 IODINES. RADIOACTIVE MATERIALS IN PARTICULATE FORN AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT I B 3/4 11-3 AMENDMENT NO. 26, 99 I

RADIOACTIVE EFFLUENTS BASES 1

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3/4.11.2.4 GASEOUS RADWASTE TREATMENT This specification deleted.

Refer to the Offsite Dose Calculation Manual.

3/4.11.2.5 WASTE GAS MONITORING This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. An automatic control feature is included in the system to prevent the oxygen concentration I

from reaching these flammability limits.

The automatic control feature includes isolation of the source of oxygen, to reduce the concentration below the flammability limit. Maintaining the concentration of oxygen below the fitanability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

FARLEY-UNIT I B 3/411-4 AMENOMENT NO. 26, 99

..-._1

..n.

RADI0 ACTIVE EFFLUENTS BASES l

..............................................m...............

i 3/4.11.2.6 GAS STORAGE TANKS l

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to an Ddividual at the l

nearest exclusion area boundary will not exceed 0.5 res.

This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".

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3/4.11.3 RADWASTE SOLIDIFICATION

[

t This specification deleted. Refer to the Process Control Program.

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3/4.11.4 TOTAL DOSE This specification deleted. Refer to the Offsite Dose Calculation Manual.

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i FARLEY-UNIT I B 3/4 11-5 AMO DIENT NO.26, 99

, ~,,

e 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM This specification deleted.

Refer to the Offsite Dose Calculation Manual.

3/4.12.2 LAND USE CENSUS This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT I B 3/4 12-1 AMEN 0 MENT NO. 26, 99 i

o RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABOPATORY COMPARISON PROGRAM This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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e FARLEY-UNIT I B 3/4 12-2 AMENDMENT NO. 26, 99

+

ADMINISTRATIVE CONTROLS b.

In-Plant Radiation Monitorino 1

A program which will ensure the capability to accurately determine the airborne iodine concentration in certain plant areas where personnel may be present under accident conditions. This program shall include the following:

(1)

Training of persopr.el, (ii)

Procedures for monitoring, and (iii)

Provisions for maintenance of sampling and analyses equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(1)

Identification of a sampling schedule for the critical variables and the control points for these variables, (11)

Identification of the procedures used to measure the values of the critical variables, (iii)

Identification of process sampling points, including monitoring the condenser hotwells for evidence of condenser in-leakage, (iv)

Procedures for the recording and management of data, (v)

Procedures defining corrective actions for off-control-point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d.

Post-accident Samolino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the training of personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.

e.

Radioactive Effluent Controls Procram A program shall be provided conforming with 10 CFR 53.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as FARLEY-UNIT 1 6-15 AMENDNENT NO. 26, 99

ADMINISTRATIVE CONTROLS reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

i)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 11)

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, iii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the 00CM, iv)

Limitations on the annual and quarterly doses or dose commitment to a w(mber of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas conforming to Appendix ! to 10 CFR Part 50, v) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, vi)

Limitations on the operability and use of the liquid and i

gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce s

releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, vii)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, i

viii)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, FARLEY-UNIY I 6-15a AMENDKENT NO. 26,E?,22,99 i 4

i ADMINISTRATIVE CONTROLS ix) Limitations on the annual and quarterly doses to a member of i

the public from lodine-131, Iodine-133, tritium, and all i

radionuclides in particulate form with half-lives greater than 8 days b qaseous effluents released from each unit to areas beyos d the site boundary conforming to Appendix ! to 10 CFR Part 50, and x) Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

i f.

Radiolooical Environmental Monitorino Proong A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the 4

accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

i) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCN,

11) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, and iii)

Participation in a Interlaboratory Comparison Program to i

ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

g.

Solid Radioactive Wastes Control Procram The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and detarsinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such & way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; burial ground I

requirements; and other requirements governing the disposal of solid radioactive waste.

(

FARLEY-UNIT 1 6-15b AMENDMENT N0. 99

l ADMINISTRATIVE-CONTROLS i

I 6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Commission, pursuant to 10CFR50.4.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license. -(2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel 1

supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

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ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 and 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries.

interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. A single submittal may be made for a multiple unit station.

SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 and 6.9.1.9 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The report shall include a summ;.ry of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. A single submittal may be made for a multiple unit 4

station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

j FARLEY-UNIT 1 6-17 AMENDMENT NO. 2F, 99

f This page intentionally left blank.

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l FARLEY-UNIT 1 6-18 AMENDMENT NO. 26, 15, 99

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i MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Commission, pursuant to 10 CFR 50.4,-

no later than the 15th of each month following the calendar month covered by the report.

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RADIAL PEAKING FACTOR LIMIT REPORT i

RTP i

l 6.9.1.11 The Fxy "imit for Rated Thermal Power (Fxy ) for all core planes containing bank D control rods and all unrodded core planes shall be

-s established and documented in the Radial Peaking Factor Limit Report before i

each reload cycle (prior to MODE 2) and provided to the Commission, pursuant i

to 10 CFR 50.4, upon issuance.

In the event that the limit would be submitted at some other time during core life, it will be submitted upon issuance, unless otherwise exempted by the Commission.

l RTP Any information needed to support Fxy will be by request from the NRC and need not be included in this report.

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ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of failures to start on demand for each diesel generator shall be submitted to the NRC annually. This report shall contain the information identified in Regulatory i

Position C.3.b of NRC Regulatory Guide 1.108, Revision 1,1977.

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I FARLEY-UNIT 1 6-19 AMEN 0 MENT N0. fJ90,82,97,99 f I

ADMINISTRATIVE CONTROLS h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License.

Records and drawing changes reflecting unit design modifications made a.

to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

Records of radiation exposure for all individuals entering radiation c.

control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

Records of transient or operational cycles for those unit components e.

identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

Records of training and qualification for current members of the g.

facility staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

1.

Records of safety-related Quality Assurance activities required by the Operations Quality Assurance Policy Manual (00APM) and not specifically described in Technical Specification 6.10.1.

j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.

k.

Records of meetings of the PORC and the NORB.

1.

Records of secondary water sampling and water quality, Records of analyses required by the radiological environmental m.

monitoring program.

Records of the service lives of all hydraulic and mechanical snubbers n.

in service after 07-01-84 within the scope of 3/4.7.9 including the date at which the service life consences and associated installation and maintenance records.

Records of reviews performed for changes made to the OFFSITE DOSE o.

CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

FARLEY-UNIT 1 6-21 AMENDMENT NO. R,10, 99 l

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered i

to for all operations involving personnel radiation exposure.

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4 ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

1.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.

This documentation shall contain:

a.

Sufficient information to support the chc 3e together with the appropriate analyses or evaluations justifync the change (s) and b.

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2.

Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.

6 14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

1.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.

This documentation shall contain:

a.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2.

Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.

3.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Sesiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the l

area of the page that was changed, and shall indicate the date (e.g.,

month / year) the chtnge was implemented.

FARLEY-UNIT 1 6-23 AMENDMENT NC. $7, 99

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h ADMINISTRATIVE CONTROLS l

6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous, and r

Solid)

This specification deleted.

Refer to the Offsite Dose Calculation Manual and the i

Process Control Program.

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FARLEY-UNIT 1 6-24 AMEN 0 MENT NO. 57, 99

[pm #f Cyg#'o UNITED STATES

[*i

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NUCLEAR REGULATORY COMMISSION g,

E WASHINGTON, D. C. 20555 t

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SOUTHERN NUCLEAR OPERATING COMPANY, INC.

DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. NPF-8 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated June 23, 1992, as supplemented November 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license 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 accordance with 10 CFR Part 51 of the Commission'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. NPF-2 is hereby amended to read as follows:

)

. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

r 3.

This license amendment is effective as of its date of issuance and shall be implemented by December 31, 1993.

FOR THE NUCLEAR REGULATORY COMMISSION 1

S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 20, 1993 t

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ATTACHMENT T0 LICENSE AMENDMENT NO. 91 l

TO FACILITY OPERATING 1.ICENSE NO. NPF-8 l

DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Pages Insert Paoes I

I IV IV XI XI l

XVI XVI XIX XIX XX XX 1-3 1-3 i

1-4 1-4 1-5 1-5 l-6 1-6 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 3/4 3-63 t

3/4 3-64 3/4 3-65 l

3/4 3-66 3/4 3-66 3/4 3-67 3/4 3-67 3/4 3-68 3/4 3-68 3/4 3-69 3/4 3-69 3/4 3-70 3/4 3-70 3/4 3-71 3/4 3-71 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 3/4 11-4 3/4 11-4 3

3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 3/4 11-8 3/4 11-9 3/4 11-8 3/4 11-9 3/4 11-10 3/4 11-11 1

3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-17 3/4 11-17 3/4 11-18 3/4 11-18 3

3/4 11-19 3/4 11-19 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-2 3/4 12-3 3/4 12-4 l

3/4 12-5

Continued:

ATTACHMENT TO LICENSE AMENDMENT NO 91 TO FACILITY OPERATIf1G LICENSE NO, NPF-8 DOCKET f10, 50-364 l

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

r Remove Pages insert Paaes I

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3/4 12-6 3/4 12-7

_i 3/4 12-8

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3/4 12-9 3/4 12-10 3/4 12-10 3/4 12-11 3/4 12-11 i

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B 3/4 11-1 B 3/4 11-1 B 3/4 11-2 B 3/4 11-2 B 3/4 11-3 8 3/4 11-3 I

B 3/4 11-4 8 3/4 11-4 8 3/4 11-5 B 3/4 11-5 B 3/4 12-1 B 3/4 12-1 l

B 3/4 12-2 B 3/4 12-2 6-15 6-15 i

6-15a I

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6-15b 6-15c 6-17 6-17 6-18 6-18 6-19 6-19 i

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6-21a 6-23 6-23 6-24 6-24 j

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INDEX DEFINITIONS SECTION EME 1.0 DEFINITIONS 1.1 ACTION.........................................................

1-1 1.2 AXIAL FLUX DIFFERENCE..........................................

1-1 1.3 CHANNEL CALIBRATION.............................................

1-1 1.4 CHANNEL CHECK..................................................

1-1 1.5 CHANNEL FUNCTION TEST..........................................

1-1 1.6 CONTAINMENT INTEGRITY..........................................

1-2 1.7 CONTROLLED LEAKAGE.............................................

1-2 1.8 CORE ALTERATION................................................

1-2 1.9 DOSE EQUIVALENT I-131..........................................

1-2 1.10 E-AVERAGE DISINTEGRATION ENERGY................................

1-3 1.11 ENGINEERED SAFETY FEATURES RESPONSE TIME.......................

1-3 1.12 FREQUENCY NOTATION.............................................

1-3 l

1.13 GAS EGUS-RA9 WASTE-TREATMENT-SYSTEM (Deleted)....................

1-3 1.14 IDENTIFIED LEAKAGE.............................................

1-3 1.15 LIQUID-RA9 WASTE-TREATMENT-SYSTEM (Del eted).....................

1-4 1.16 KAJOR-ERANGES-TO-RA910AETIVE-WASTE-TREATMENT-SYSTEMS (Deleted).

1-4 1.17 0FFSITE DOSE CALCULATION MANUAL (ODCM).........................

1-4 1.18 OPERABLE - OPERABILITY.........................................

1-4 1.19 OPERATIONAL MODE - MODE........................................

1-5 1.20 PHYSICS TESTS..................................................

1-5 1.21 PRESSURE BOUNDARY LEAKAGE......................................

1-5 1.22 PROCESS CONTROL PROGRAM (PCP)..................................

1-5 1.23 PURGE - PURGING................................................

1-5 1.24 QUADRANT POWER TILT RATIO......................................

1-5 1.25 RATED THERMAL POWER............................................

1-6 1.26 REACTOR TRIP SYSTEM RESPONSE TIME..............................

1-6 l.27 REPORTABLE EVENT...............................................

1-6 1.28 SHUTDOWN MARGIN................................................

1-6 1.29 SOLIBIFIEATION (Deleted).......................................

1-6 1.30 SOURCE CHECK...................................................

1-6 1.31 STAGGERED TEST BASIS...........................................

1-6 1.32 THERMAL POWER..................................................

1-7 1.33 UNIDENTIFIED LEAKAGE...........................................

1-7 1.34 VENTILATION EXRAUST TREATMENT SYSTEM...........................

1-7 1.35 VENTING........................................................

1-7 TABLE 1.1 OPERATIONAL MODES.........................................

1-8 TABLE 1.2 FREQUENCY NOTATION........................................

1-9 FARLEY-UNIT 2 I

AMENDMENT NO. 49, 91

\\

i i

F lliEl

^

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION pfg 3/4.2 POWER DISTRIBUTION LIMITS l

I 3/4.2.1 AXIAL FLUX DIFFERENCE.................................

3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR.........................

3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR..................

3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO............................

3/4 2-11 i

3/4.2.5 DNB PARAMETERS.......................................

3/4 2-14 l

i 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..................

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION....................................

3/4 3-151 3/4.3.3 MONITORING INSTRUMENTATION 4

Radiation Monitoring'.................................

3/4 3-38 i

Movabl e Incore Detectors.............................

3/4 3-42 l

Seismic Monitoring Instrumentation...................

3/4 3-43 Meteorol ogical Instrumentation.......................

3/4 3-46 Remote Shutdown Instrumentation......................

3/4 3-49 l

Chlorine Detection Systems...........................

3/4 3-52 High Energy Line Break Sensors.......................

3/4 3-53 Accident Monitoring Instrumentation..................

3/4 3-56 F.f ra DatecMon.4ostcumentaMon (Del eted).............

3/4 3-59 l

1 Radioactive-Liquid-Effluent-Monitoring (Deleted).....

3/4 3-61 Waste Gas Monitoring.................................

3/4 3-66 3/4.3.4 TURBINE OVERSPEED PROTECTION.........................

3/4 3-72 4

FARLEY-UNIT 2 IV AMEICMENT NO. 88, 91

INDEX BASES SECTION

_PAfd 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS..................................

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.................................

B 3/4 11-2 3/4.11.3 RA9 WASTE-SOLIDIFICATION (Deleted).................

B 3/4 11-5 3/4.11.4 TOTAL-DOS E (Del et ed)..............................

B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING-PROGRAM (Deleted)......................

B 3/4 12-1 3/4.12.2 LAND-USE-GENSUS (Deleted).........................

B 3/4 12-1 3/4.12.3 INTERLABORATORY-EGMPARISBN-PROGRAM (Deleted)......

B 3/4 12-2 J

I r

FARLEY-UNIT 2 XVI AMENDMENT NO. 91

L t

'l INDEX j

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

- t i

SECTION Egag 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS f

Geneentration (Deleted).............................

'3/4 11-1 Dese (Deleted)......................................

3/4 11-5 Liquid-Waste-Treatment (Deleted)....................

3/4 11-6 i

Liquid Holdup Tanks.................................

3/4.11 ?

- i f

3/4.11.2 GASEOUS EFFLUENTS Dese-Rate (Deleted).................................

3/4 11-8 Dese-Neble-Gases (Del eted)..........................

3/4-11-12 Dese-Radieiedinest-Particulater-and-Radienuelides-Other-than-Neble-Gases (Deleted).....

3/4 11 !

Gaseous-Radwaste-Treatment (Deleted)................

3/4 11-14 Waste Gas Monitoring................................

3/4 11-15

-l Gas Storage Tanks...................................-

'3/4 11-16 3/4.11.3 RA9 WASTE-SQLIBIFICATION (Deleted)...................

3/4 11-17 3/4.11.4 TOTAL-90SE (Del e t ed)................................

3/4 11-19 i

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING-PROGRAM (Deleted)........................

3/4.12-1 3/4.12.2 LAND-USE-GENSUS (Del eted)...........................

3/4 12-10 3/4.12.3 INTERLABORATORY-COMPARISBN (Deleted)................

3/4 12-11 FARLEY-UNIT 2 XI AMENDMENT NO. 91

INDEX i

ADMINISTRATIVE CONTROLS SECTION ESAE Review.....................................................

6-10 Audits.....................................................

6-11 Authority..................................................

6-12 Records....................................................

6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities..................................................

6-12 Records....................................................

6-13 6.6 REPORTABLE EVENT ACTION......................................

6-14 6.7 SAFETY LIMIT VIOLATION.......................................

6-14 6.8 PROCEDURES AND PROGRAMS......................................

6-14 6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REPORTS Startup Report.............................................

6-15c An n u al Re p o rt.............................................

6-16 Annual Radiological Environmental Operating Report.........

6-17 Semiannual Radioactive Effluent Releare Report.............

6-17 Monthly Operating Report...................................

6-19 Radial Peaking Factor Limi t Report.........................

6-19 Annual Diesel Generator Reliability Data Report............

6-19 Annual Reactor Coolant System Specific Activity Report.....

6-20 Annual Seal ed Source Leakage Report.......................

6-20 6.9.2 SPECIAL REPORTS............................................

6-20 6.10 RECORD RETENTION............................................

6-20 6.11 RADI ATION PROT ECT ION PROG RAM................................

6-21a 6.12 HIGH RADIATION AREA.........................................

6-22 FARLEY-UNIT 2 XIX AMENDMENT NO 49', 91

i i

I i

t INDEX i

1 ADMINISTRATIVE CONTROLS

-l l

SECTION EAGE l

.i 6.13 PROCESS CONTROL PROGRAM....................................

6-23

.i t

6.14 0FFSITE DOSE CALCULATION MANUAL............................

6-23 t

i 6.15 MAJOR-CHANGES-TG-RADIGACTIVE WASTE-TREATMENT-SYSTEMS (Del eted)........................

6-24 1

P b

t h

i 1

a r

A i

t i

L L

t 3

I FARLEY-UNIT 2 XX AMENDMENT NO. O, 91 kr

~

..n

-..-,,,_w.,.

o o

DEFINITIONS E - AVERAGE DISINTEGRATION ENERGY 1.10 E shall be the average sum (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than todines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.11 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FRE0VENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

GASEOUS RADWASTE TREATMENT SYSTEM 1.13 This definition deleted. Refer to the Offsite Dose Calculation Manual.

4 IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor coolant system leakage through a steam generator to the secondary system.

FARLEY-UNIT 2 1-3 AMENDMENT NO. 91

DEFINITIONS LIOUID RADWASTE TREATHENT SYSTEM 1.15 This definition deleted.

Refer to the Offsite Oose Calculation Manual.

KAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS 1.16 This definition deleted.

Refer to the Offsite Dose Calculation Manual and the Process Control Program.

OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.17 The OFFSITE DOSE CALCULATION KANUAL shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Surveillance and Semiannual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9.

OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, a normal and an emer-gency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing their related support function (s).

FARLEY-UNIT 2 1-4 AMENDMENT NO.91

o DEFINITIONS

.....c,......................................................................

OPERATIOUAL MODE - MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

PHYSICS TESTS 1.20 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and

1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

EBESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System Component body, pipe wall or vessel wall.

PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.

PURGE - PURGING 1.23 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

OVADRANT POWER TILT RATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximus upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

FARLEY-UNIT 2 1-5 AMENDMENT NO. 91 l

o 1

DEFINITIONS j

RATED THERMAL POWER 1

1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2652 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subtritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SOLIDIFICATION 1.29 This definition deleted.

Refer to the Process Control Program.

SOURCE CHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

STAGGERED TEST BASIS 1.31 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

FARLEY-UNIT 2 1-6 AMENDMENT NO. 69, 91 l

e INSTRUMENTATION M DI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION This specification deleted.

Refer to the Offsite Dose Calculation Manual.

t l

FARLEY-UNIT 2 3/4 3-61 AMENDMENT NO. H 91

l This page intentionally left blank.

3/4 3-63 through 3/4 3-65 Deleted.

o FARLEY-UNIT 2 3/4 3-62 AMENDMENT NO. 91

INSTRUMENTATION WASTE GAS MONITORING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.3.11 The waste gas monitoring instrumentation channels shown in Table 3.3-14 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY: As shown in Table 3.3-14.

ACTION:

a.

With a waste gas monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, declare the channel inoperable and take the ACTION shown in Table 3.3-14.

b.

With less than the minimum number of waste gas monitoring instrumentation channels OPERABLE, take the ACTTON shown in Table 3.3-14.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each waste gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

FARLEY-UNIT 2 3/4 3-66 AMENDMENT NO. 49, 91

- r 1

i n

TABLE 3.3-14 E?

WASTE GAS MONITORING INSTRUMENTATION Ei m

MINIMUM CHANNELS i

INSTRUMENT OPERABLE APPLICABILITY ACTION 1.

WASTE GAS HOLDUP SYSTEM MONITORING INSTRUMENTATION a.

Oxygen Monitors 2/recombiner 38 b.

Hydrogen Monitors 1/recombiner i

40

?,

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5

-wme v' ww Td*w'wm e' w w W 4'

ewFw'w4-1NrYu we-T N-LtvwewrNw*w-D%-*

Ei'W-W-'W e

T'*-w*w-*-*V 9'

T e"w s ywr=

w.- Wew t--*9m-to v r 79-WT==T'T'-VV=*VMN+re v='*ve"tv%'-P'"--'w-d

1 9'TT--W'rWver=w***'

a

=-w'-u VTW--"'th1'--

N-c' t-PP t-tTP Wrw-qu au-.

9

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mer7-4

% Coir w

i TABLE 3.3-14 (Continued) l TABLE NOTATION i

(Not Used)

[

(Not Used) l During recombiner operation.

ACTION 35 -

(Not Used) 1 r

ACTION 36 -

(Not Used) i r

ACTION 37 -

(Not Used) t i

i i

ACTION 38 - With the number of channels OPERABLE one less than required by the Minimus Channels OPERABLE requirement, except for testing, i

isolate the oxygen supply to the affected recombiner. With no i

channels OPERABLE, addition of waste gas to the waste gas system may continue provided a grab sample is taken from the on-service waste decay tank and analyzed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the oxygen concentration remains less than 1%.

i FARLEY-UNIT 2 3/4 3-68 AMENDMENT NO. 91

TABLE 3.3-14 (Continued)

TABLE NOTATION

[

t ACTION 39 -

(Not Used) t i.

ACTION 40 - With no channels OPERABLE, addition of waste gas to the waste gas system may continue provided a grab sample is.taken from the on-service waste decay tank and analyzed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i

and -the oxygen concentration remains less than 1%.

i f

a i

i FARLEY-UNIT 2-3/4 3-69 AMENDMENT NO.-91 e

o m

B TABLE 4.3-9 Ay

)(ASTE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS h

CHANNEL MODES IN WilICH m

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED I.

WASTE GAS HOLDUP SYSTEM NONITORING INSTRUMENTATION

a. Inlet Hydrogen Monitor D

N.A.

Q(3)

M

b. Outlet Hydrogen Monitor D

N.A.

Q(3)

M

c. Inlet Oxygen Monitor D

N.A.

Q(4)

M

d. Outlet Oxygen Monitor D

N.A.

Q(4)

H w

5 E-9 5il 5

r 5

W

TABLE 4.3-9 (Continued)

TABLE NOTATION (Not Used)

During recombiner operation.

(1)

(Not Used)

(2)

(Not Used)

(3)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing in accordance with manufacturer's recommendations.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing in accordance with manufacturer's recommendations.

In addition, a standard gas sample of nominally four volume percent oxygen, balance nitrogen shall be used for inlet oxygen monitor linearity check.

FARLEY-UNIT 2 3/4 3-71 AMENDMENT NO. 91

r 3/4.11 PADI0 ACTIVE EFFLUENTS i

3/4.11.1 LIOUID EFFLUENTS CONCENTRATION This specification deleted. Refer to the Offsite Dose Calculation Manual.

r h

FARLEY-UNIT 2 3/4 Il-I AMENDMENT NO. 91 4

I a

L i

This page intentionally left blank.

3/4 11-3 and 3/4 11-4 Deleted.

i T

i FARLEY-UNIT 2 3/4 11-2 AMENDMENT NO. 13, 91

I i

RADIOACTIVE EFFLUENTS DQlE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 2 3/4 11-5 AMENDMENT NO. H, 91

RADIOACTIVE EFFLUENTS LIOUID WASTE TREATMENT This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 2 3/4 11-6 AMENDMENT NO. M 91

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS t

DOSE RATE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

1 9

FARLEY-UNIT 2 3/4 11-8 AMENDMENT NO. 91 i

1 e

This page intentionally left blank.

3/4 11-10 and 3/4 11-11 Deleted.

FARLEY-UNIT 2 3/4 11-9 AMENDMENT NO. 62, 91

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES This specification deleted.

Refer to the Offsite Dose Calculation Manual.

l f

2 d

e FARLEY-UNIT 2 3/4 11-12 AMENDMENT NO. O, 91

m.

o RADIOACTIVE EFFLUENTS DOSE - RADIOIODINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM. AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification deleted.

Refer to the Offsite Dose Calculation Manual.

i i

Y e

f i

3 F

r l

i 2

FARLEY-UNIT 2 3/4 11-13 AMENDNENT NO. O, 91 7

e

.,m i-

-c

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT i

This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 2 3/4 11-14 AMENDr4ENT NO. M. 91

RADIOACTIVE EFFLUENTS WASTE GAS MONITORING LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in any portion of the gaseous radwaste treatment system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration in that portion of the gaseous radwaste treatment system exceeds 4% by volume.

APPLICABILITY: At all times.

ACTION:

With the concentration of oxygen in the gaseous radwaste treatment a.

system greater than 2% by volume but less than or equal to 4% by volume, reduce the concentration of oxygen to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

With the concentration of oxygen in the gaseous radwaste treatment b.

system greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% within I hour and less than or equal to 2%

by volume within the foll' wing 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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

c.

1 SURVEILLANCE REQUIREMENTS The concentration of hydrogen or oxygen in the gaseous radwaste 4.11.2.5 treatment system shall be determined to be within the above limits by monitoring the waste gases in the gaseous radwaste treatment system with the hydrogen and/or oxygen monitors required OPERABLE by Table 3.3-14 of Specification 3.3.3.11.

FARLEY-UNIT 2 3/4 11-15 AMENDMENT NO. 91

e v

2 i

e I

This page intentionally left blank.

FARLEY-UNIT 2 3/4 11-18 AMEN 0 MENT NO. 91

e e

RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 2 3/4 11-19 AMENDMENT NO. H, W, 91

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM This specification deleted.

Refer to the Offsite Dose Calculation Manual.

6

)

i FARLEY-UNIT 2 3/4 12-1 AMENDMENT NO.

O, 91

w This page intentionally.left blank.

3/4 12-3 through 3/4 12-9 Deleted.

FARLEY-UNIT 2 3/4 12-2 AMENDMENT NO.

91

e RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS This specification deleted.

Refer to the Offsite Dose Calculation Manual.

i i

n 9

FARLEY-UNIT 2 3/4 12-10 AMENDMENT NO. fg, 91 I

RADIOLOGICAL ENVIRONMENTAL MONITORING

+

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM This specification deleted.

Refer to the Offsite Dose Calculation Manual, i

t 1

l l

FARLEY-UNIT 2 3/4 12-11 AMENDMENT NO. 91

l INSTRUMENTATION BASES 3/4.3.3.I0 RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION This specification deleted. Refer to the Offsite Dose Calculation Manual.

3/4.3.3.11 WASTE GAS HONITORING INSTRUMENTATION This instrumentation monitors (and controls) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation are consistent with the requirements of General Design Criteria 60 and 63 of Appendix A to 10 CFR Part 50.

3/4.3.4 TURBINE DVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

i

[

b b

i FARLEY-UNIT 2 B 3/4 3-5 AMENDMENT NO. JT2, 91 f

3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS t

3/4.11 CONCENTRATION This specification d'eleted. Refer to the Offsite Dose Calculation Manual.

j i

i k

3/4.11.1.2 DOSE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

i 4

i

?

1 E

i f

I FARLEY-UNIT 2 B 3/4 11-1 AMEN 0 MENT NO.

91 l

4 i

s RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIOUID WASTE TREATMENT This specification deleted.

Refer to the Offsite Dose Calculation Manual.

3/4.11.1.4 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 2 B 3/4 11-2 AMENDMENT NO. 91 l

s RADIOACTIVE EFFLUENTS BASES I

3/4.11.2.2 DOSE - NOBLE GASES This specification deleted. Refer to the Offsite Dose Calculation Manual.

3/4.11.2.3 DOSE - RADIOIODINES. RADIOACTIVE KATERIALS IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN N0BLE GASES This specification deleted. Refer to the Offsite Dose Calculation Manual.

FARLEY-UNIT 2 B 3/4 11-3 AMENDMENT NO. 91

RADIOA, E EFFLUENTS BASES 3/4.11.2.4 GASEOUS RA0 WASTE TREATHEMI This specification deleted.

Refer to the Offsite Dose Calculation Manual.

i 3/4.11.2.5 WASTE GAS MONITORING i

This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. An automatic control feature is included in the system to prevent the oxygen concentration from reaching these flammability limits.

The automatic control feature includes isolation of-the source of oxygen, to reduce the concentration below the flammability limit. Maintaining the concentration of oxygen below the flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

j i

FARLEY-UNIT 2 B 3/4 11-4 AMENDMENT NO. 91 l

o, RADIOACTIVE EFFLUENTS BASES 3/4.11.2.6 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 res. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".

3/4.11.3 RADWASTE SOLIDIFICATION This specification deleted.

Refer to the Process Control Program.

3/4.11.4 TOTAL DOSE This specification deleted.

Refer to the Offsite Dose Calculation Manual.

i i

FARLEY-UNIT 2 B 3/4 11-5 AMENDMENT NO. 91

=

i s

t i

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l

l BASES 2Li.12.1 MONITORING PROGRAM it.is specification deleted. Refer to the Offsite Dose Calculation Manua1.

I i

2 l

3/4.12.2 LAND USE CENSUS-i i

This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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FARLEY-UNIT 2 B 3/4 12-1 AMENDMENT NO. 91

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e RADIOLOGICAL ENVIRONMENTAL MONITORING BASES r

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM t

This specification deleted.

Refer to the Offsite Dose Calculation Manual.

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t FARLEY-UNIT 2 B 3/4 12-2 ANENOMENT NO. 91 i

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ADMINISTRATIVE CONTROLS b.

In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in certain plant areas where personnel may be present under accident conditions. This program shall include the following:

(1) Training of personnel, (ii)

Procedures for monitoring, ar/

(iii)

Provisions for maintenance of sampling and analyses equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i)

Identification of a sampling schedule for the critical variables and the control points for these variables, (ii)

Identification.of the procedures used to measure the values of the critical variables, 1

(iii)

Identification of process sampling points, including monitoring the condenser hotwells for evidence of condenser in-leakage, (iv)

Procedures for the recording and management of data, (v)

Procedures defining corrective actions for off-control-point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required Jo initiate corrective action.

d.

Post-accident Samplino A program which wil; ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the training of personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.

e.

Radioactive Effluent Controls Procram l

A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as l

FARLEY-UNIT 2 6-15 AMENDMENT NO. I3, 91

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3 ADMINISTRATIVE CONTROLS reasonably achievable.

The program (1) shall be contained in the i

ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1 i)

Limitations on the operability of radioactive liquid and i

gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the i

methodology in the ODCM, ii)

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, iii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with i

the methodology and parameters in the ODCM, iv)

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in. liquid effluents released from each unit to i

unrestricted areas conforming to Appendix I'to 10 CFR Part 50, v) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, vi)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce i

releases of radioactivity when the projected doses in a l

31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I i

to 10 CFR Part 50, i

vii) Limitations on the dose rate resulting from radioactive i

material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR 1

Part 20, Appendix B, Table II, Column 1, i

viii)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary conforming to Appendix I to i

10 CFR Part 50, FARLEY-UNIT 2 6-15a AMENDMENT NO. 6, 4, 91 4

ADMINISTRATIVE CONTROLS ix)

Limitations on the annual and quarterly doses to a member of the public from Iodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, and x)

Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f.

Radiolooical Environmental Monitorino Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the affluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

i) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, ii) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, and 111)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the' precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

g.

Solid Radioactive Wastes Control Procram The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.

FARLEY-UNIT 2 6-15b

/#.ENDMENT NO. 91 l

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ADMINISTRATIVE CONTROLS 6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Commission, t

pursuant to 10CFR50.4.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel-supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

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ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 and 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material pr,vided shall be consistent with the objectives outlined in (1) the ODCM and (J Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. A

. agle submittal may be made for a multiple unit station.

SEMIANNUAL RADI0 ACTIVE EFFLVENT RELEASE REPORT 6.9.1.8 and 6.9.1.9 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

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FARLEY-UNIT 2 6-17 AMENDMENT NO. 91

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FARLEY-UNIT 2 AMENDNENT NO. f#, 91

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Commission, pursuant to 10 CFR 50.4, no later than the 15th of each month following the calendar month covered by the report.

RADIAL PEAXING FACTOR LIMIT REPORT RTP 6.9.1.11 The Fxy "imit for Rated Thermal Power (Fxy ) for all core planes l

containing bank D control rods and all unrodded core planes shall be established and documented in the Radial Peaking Factor Limit Report before each reload cycle (prior to MODE 2) and provided to the Commission, pursuant to 10 CFR 50.4, upon issuance.

In the event that the limit would be submitted at some other time durir.g core life, it will be submitted upon issuance, unless otherwise exempted by the Commission.

RTP Any information needed to support Fxy will be by request from the NRC and need 1

not be included in this report.

ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of failures to start on demand for each diesel generator shall be submitted to the NRC annually. This report shall contain the information identified in Regulatory Position C.3.b of HRC Regulatory Guide 1.108, Revision 1,1977.

FARLEY-UNIT 2 6-19 AMENDMENT NO.49,6244,85,91 l

ADMINISTRATIVE CONTROLS h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License.

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

Records of radiation exposure for all individuals entering radiation c.

control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

Records of transient or operational cycles for those unit components e.

identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the facility staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of safety-related Quality Assurance activities required by the Operations Quality Assurance Policy Manual (0QAPM) and not specifically described in Technical Specification 6.10.1.

J.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR53.59.

k.

Records of meetings of the PORC and the NORB.

1.

Records of secondary water sampling and water quality.

m.

Records of analyses required by the radiological environmental monitoring program.

i n.

Records of the service lives of all hydraulic and mechanical snubbers i

within the scope of 3/4.7.9 including the date at which the service life comences and associated installation and maintenance records.

o.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

FARLEY-UNIT 2 6-21 AMENDMENTNO.O,62,91[

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6.11 RADIATION PROTECTION PROGRAM i

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

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FARLEY-UNIT 2 6-21a AMENDMENT NO. 91 a

gW ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Comission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

1.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.

This documentation shall contain:

a.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2.

Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Comission prior to implementation.

6.14.2 Licensee initiated changes to the ODCH:

1.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.

This documentation shall contain:

a.

Sufficient information to sup, ort the change together with the appropriate analyses or evaluations justifying the change (s) and b.

A detenninat:on that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2.

Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.

3.

Shall be submitted to the Comission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM wes made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month / year) the change was implemented.

FARLEY-UNIT 2 6-23 AMENDMENT NO. A7, 91

A0 ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTQLi (Liquid, Gaseous, and Solid)

This specification deleted.

Refer to the Offsite Dose Calculation Manual and the Process Control Program.

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FARLEY-UNIT 2 6-24 AMEN 0 MENT NO. (9. 91

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ML20057C361

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