ML20210E125

Amend 82 to License NPF-43,relocating Existing Procedural Details of Current RETS to ODCM & Procedural Details for Solid Radioactive Wastes to Pcp.Also Incorporates Programmatic Controls Into AC Section of TS

ML20210E125
Person / Time
Site:	Fermi
Issue date:	06/09/1992
From:	Marsh L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210E131	List: ML20210E125 ML20210E145
References
NUDOCS 9206180364
Download: ML20210E125 (61)

Text

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UNITED STATES 3

YS NUCLEAR REGULATORY COMMISSION o

WASHINoTON D C. 20tE4

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DETR0li EDISON COMPANY Q.0CKET NO. 50-341 EERMI-2 AljENDMENT TO FACILITY OPERATING LICENS1 Amendment No. 82 License No. NPF-43 1.

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

A.

The application for amendment by the Detroit Edison Company (the licensee) dated November 26, 1991, 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 (1) that the activities authorized by this amendnent can be conducted without enJangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D,

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicabie 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-43 is hereby amended to read as follows:

lechnigal Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 82, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

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

9206100364 920609 PDR ADOCK 05000341 P

PDR

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3.

This license amendment is effective as of the date of its issuance, i

With full implenntation within 60 days of the date of issuance, FOR THE NUCLEAR REGULATORY COMMISSION

^

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L. B. Marsh, Director i

Project Directorate 111-1 Division of Reactor Projects 111/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: June 9, 1992 r

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AT;TACHMENT TO LICERSE AMENDB[NT NO. 81.

[&ClllTY OPERATING LICENSE NO NPF,3 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Tecinical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

~

REMOVE JU11El 11 11 v

v i

xi xi xiii xiii xvil xvii xviii*

xviii*

xix xix i

xx xx xxiv-xxiv xxv xxv 1-3*

l-3*

1-4 1-4 1-5 1-5 1-7 1-7 1-8 1-8 3/4 3-61a 3/4 3 61a 3/4 3-71 3/4 3-71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 3-75 3/4 3-76 3/4 3-76 3/4 3-77 3/4 3-77 3/4 3-78 3/4 3-78 3/4 3-79 3/4 3-80 3/4 3-80 g

3/4 3-81 3/4 3-81 3/4 3-82 3/4 3-82 3/4 3-83

-3/4 3-84 3/4 3-84 l

3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-4

• 0verleaf page provided to maintain document completeness.

No changes contained in these pages.

-._____...___._-__.___________;,.___.__.~._--..._.._-_.__.-.~._-

ATTA WMENT..10 LICENSE AMUfDB WJ_jiO J 1.

FAClllTY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 i

Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

REMOVE JNSERI 3/4 11-5 3/4 11-6 3/4 11-7*

3/4 11-7*

3/4 11-8 3/4 11-8 3/4 11-9 3/4 11-10 3/4 11-11 3

3/4 11-12 e

-3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16 3/4 11-17 3/4 11-17 3/4 11-18 3/4 11-18 3/4 11-19 3/4 11-20 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-11 3/4 12 ----

3/4_12-13 3/4 12-14 B 3/4 3-5 8 3/4 3-5 t 3/4 3-6 8 3/4 3-6 E 3/4 11-1 B 3/4 11-1 B 3/4 11-2 8 3/4 11-2 8 3/4 11-3 8 3/4 11-3 8 3/4 11-4 8 3/4 11-4 B 3/4 11-5 B 3/4 11-5

• 0verleaf page provided to maintain document completeness.

No changes contained in these pages.

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i ATTACHMENT TO llCENSE AMENDMENT NO. 82._

FACILITY OPERATING LICENSE NO. NPf-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT B 3/4 11-6 B 3/4 11-6 B 3/4 12-1 8 3/4 12-1 B 3/4 12-2 B 3/4 12-2 6l 6-1 6-15*

6-15*

6-16 6-16 6-16a 6-16b 6-17' 6-17*

6-18 6-18 6-19 6-19 6-20 6-20 6-22 6-22 6-23 6-23 6-24 6-24 6-25 6-25

• 0verleaf page provided to maintain document completeness.

No changes contained in these pages.

4 E08 i

DEFINITIONS l

SECTIQB DEFINITIONS (Continued) ffM

{

l.26 OPERATIONAL CONDITION CONDIT 10N..........................

14 1.27 PHYSICS TESTS..............................................

1-4 1.28 PRESSURE B0UNDARY LEAKAGE..................................

14 1.29 PRIMARY CONTAINMENT INTEGRITY..............................

1-4 1.30 PROCESS CONTROL PR0 GRAM....................................

15 1.31 PURGE-PURGING..............................................

15 1.32 RATED THERMAL P0WER........................................

1-5 f

1.33 REACTOR PROTECTION SYSTEM RESPONSE TIME....................

16 1.34 REPORTABLE EVENT...........................................

16 1.35 R0D DENSITY................................................

16 1.36 SECONDARY CONTAINMENT INTEGRITY............................

16 1.37 SHUTOOWN MARGIN............................................

1-6 1.38 SITE B0VNDARY..............................................

1-6 1

1 1.40 SOURCE CHECK...............................................

1-7 1.41 STAGGERED TEST BASIS.......................................

1-7 1.42 THERMAL P0WER..............................................

17 1.43 TURBINE BYPASS SYSTEM RESPONSE TlHE........................

1-7

.l.44 UNIDENTIFIED LEAKAGE.......................................

1-7 1.45 UNRESTRICTED AREA..........................................

1-7 i

i 1.47 VENTING....................................................

18 1

FERMI - UNIT 2 ii Amendment No. 82, t

L--

i 1

INDEX llMITING CONDITIONS FOR OPERATION AND SURVElllANCE REQUIREMENTS SEC.II.QN EAq[

3/4.3 INSTRUMENTATION 2

3/4.3.1 REACTOR PROTECTION SYSlEM INSTRUMENTATION...........

3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.................

3/4 3 9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION i

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

3/4 3 23 3/4.3.4 ATWS REclRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION.....................................

3/4 3 32 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION.....................................

3/4 3-36 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION...................

3/4 3 41 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................

3/4 3 47 l

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

3/4 3 51 Meteorological Monitoring Instrumentation...........

3/4 3 54 Remote Shutdown System Instrumentation and Controls.

3/4 3 57 Accident Monitoring Instrumentation.................

3/4 3 60 Source Range Moniurs...............................

3/4 3 64 Traversing In Core Probe System.....................

3/4 3 65 Chlorine Detection System...........................

3/4 3 66 Deleted.............................................

3/4 3 67 Loose Part Detection System.........................

3/4 3 70 Explosive Gas Monitoring Instrumentation............

3/4 3-76 l

3/4.3.9 FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................

3/4 3-86 3/4.3.10 RESERVED................................................

3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION.......

3/4 3-90 FERMI - UNIT 2 v

Amendment No. EJ, ES, E2,7J,gg,

1119EX LIMITING CONDITIONS FOR OPERATION AND SVRVElllANCE Rf0VIREMENTS II.CT10N PMI 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks........................................

3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS I

i Explosive Gas Mixture......................................

3/4 11 16 j

Main Condenser.............................................

3/4 11 17 3/4.12 DELETED 1

i -

FERMI - UNIT 2 xi Amendment No.82

.._._...__,,_.,._._2.,___.._,

IUQEX BASES Siul0N IEE INSTRUMENTATION (Continued) l MONITORING INSTRUMENTATION (Continued)

E Meteorological Monitoring Instrumentation....... B 3/4 3 4 Remote Shutdown S Controls.........ystem Instrumentation and

............................... B 3/4 3 4 Accident Monitoring Instrumentation............. B 3/4 3 4 Source Range Monitors........................... B 3/4 3 4 Traversing in Core Probe System................. B 3/4 3-4 Chl orine Detection System....................... B 3/4 3 5 De l e t ed......................................... B 3/ 4 3 - 5 Loose Part Detection System..................... B 3/4 3 5 l

Explosive Gas Monitoring Instrumentation........ B ?/4 3 6 l

3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEMS ACTUATION INSTRUMENTATION................................. B 3/4 3 6 3/4.3.10 RESERVED 3/4 3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION................................. B 3/4 3-6 3/4.4 REACTOR COOLANT H HfB 3/4.4.1 RECIRCULATION SYSTEM............................

B 3/4 4-1 3/4.4.2 SAFETY /REllEF VALVES............................

B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems....................... B 3/4 4-2 Operation:1 Leakage............................. B 3/4 4 2 3/4.4.4 CHEMISTRY..................................... B 3/4 4-2 3/4.4.5 SPECIFIC / JIVITY.............................. B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE LIMITS.....................

B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES................ B 3/4 4-5 3/4.4.8 ST RUCTURAL INTEGRITY............................ B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REM 0 VAL........................... B 3/4 4-5 FERMI - UNIT 2 xiii Amendment No. /7, JJ, JJ, J/, /J,82

INDEX 1

i BASES SECI193 pffi 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS...................................... B 3/4 11-1 i

3/4.11.2 GASEOUS EFFLUENTS..................................... B 3/4 11-3 3/4.12 DELETED t

FERMI - UNIT 2 xvii Amendment No. 82

,,a

IBDH DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area.............................................

5-1 Low Population Zone........................................

5 1 Site Boundaries............................................

5-1 5.2 CONTAINMENT Configuration..............................................

5-1 Design Temperature and Pressure............................

5-1 Secondary Containment......................................

5-1 5.3 REACTOR CORE f u el A s s embl i e s............................................

5 - 5 Con t rol Rod A s s embl i e s.....................................

5 5 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature............................

5-5 Volume.....................................................55 1,5 METEOROLOGICAL TOWER LOCATION..............

5-6 116 FUEL STORAGE-Criticality................................................5-6 Drainage...................................................

5-6 Capacity...................................................

5 6 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT........................

5 6 FERMI - UNIT 2 xviii

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE i

6.1 RESPORSlBIL111...........................................

6-1 6.2 ORGANIZA110N.............................................

61 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS..................

6-1 l

6.2.2 UNIT STAFF........................................

6-1 6.2.3 INDEPENDENT SAFETY ENGINEERING GR0VP..............

6-6 FUNCT10N..........................................

66 COMPOSIT10N.......................................

6-6 RESP 0NSIBILITIES..................................

6-6 AUTHORITY.........................................

66 6.2.4 SHIFT TECHNICAL ADVIS0R...........................

66 6.3 UNIT STAFF OVALIFICAT10NS................................

6-7 6.4 TRAINING.................................................

67 6.5 REVIEW AND AUDIT............................

6-7 6.5.]

ONSITE REVIEW ORGANIZATION (OSRO)

FUNCTION..........................................

6-7 COMPOSITION.......................................

6-7 ALTERNATES........................................

6-8 MEETING FREQUENCY.................................

68 QU0 RUM............................................

68 RESP 0NSIBILITIES..................................

6-8 REC 0RDS...........................................

69 6.5.2 NUCLEARSAFETYREVIEWGROUP(NSRG)................

69 FUNCT10N..........................................

69 COMPOSITION.............................,.........

6-10 ALTERNATES........................................

6 10 CONSULTANTS.......................................

6 10 MEETING FREQUENCY.................................

6-10 QU0 RUM.........................................

6-10 i

f i

1 I

l j

FERMI - UNIT 2 xix Amendment No,82

INDEX ADMINISTRATIVE CONTROLS SECTION

,PAGE REVIEW.....

6-10 AUDITS..............................................

6 11 REC 0RDS.............................................

6-12 6.5.3 TECHNICAL REVIEW AND CONTR0L........................

6 12 ACTIVITIES..........................................

6 12 REVIEW..............................................

5 13 SAFETY EVALUATIONS..................................

6 13 QUAllFICAT10NS......................................

6-13 REC 0RDS.............................................

6 13 6.6 REPORTABLE EVENT ACT10N....................................

6-13 6.7 SAFETY LIMIT VIOLATION.....................................

6-14 6.8 PROCEDURES AND PR0 GRAMS....................................

6-14 6.9 REPORTING RE0VIREMENTS.....................................

6-16b 6.9.1 ROUTINE REP 0RTS.....................................

6 16b STARTUP REP 0RT......................................

6 16b ANNUAL REP 0RTS......................................

6-17 MONTHLY OPERATING REP 0RTS...........................

6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..

6 18 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT......

6 18 l

6.9.2 SPECIAL REP 0RTS.....................................

6 21 6.9.3 CORE OPERATING LIMITS REP 0RT........................

6 21 6.10 RECORD RETENTION..........................................

6-21 6.11 RADIATION PROTECTION PR0 GRAM..............................

6-22a 6.12 HIGH RADIATION AREA.......................................

6-22a

& _.13 PROCESS CONTROL PR0 GRAM...................................

6 23 i

E.14 0FFSITE DOSE CALCULATION MANUAL...........................

6-24 I

i FERMI - UNIT 2 xx Amendment No. JJ, %f,82

INDEX LIST OF TABLES (Continued)

TABLE IEE 3.3.7.9-1 DELETED..........................................

3/4 3 68 3.3.7.12-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION........

3/4 3 77 4.3.7.12 1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................

3/4 3 81 3.3.9 1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.................................

3/4 3 87 3.3.9 2 FEEDWATER/ MAIN TURBINE TRfP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS.......................

3/4 3 88 4.3.9.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......

3/4 3 89 3.3.11-l_

APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION..

3/4 3-91 4.3.11.1-1 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS........

3/4 3-92 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES..........................................

3/4 4-12 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS...............................

3/4 4-12 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS.........

3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM................................

3/4 4-18 4.4.6.1.3 1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHDRAWAL SCHEDULE.............................

3/4 4-22 4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED IN LOCKED HIGH RADIATION AREAS..........

3/4 6-lb 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES............

3/4 6 22 3.6.5.2-1 SECONDARY CONTAINMENT VENTILATION SYSTLM AUTOMATIC ISOLATION DAMPERS.....................

3/4 6 53 3.7.3-1 SURVEY POINTS FOR SHORE BARRIER.................

3/4 7-12 3.7.7.5-1 DELETED..........................................

3/4 7-32 3.7.7.6-1 DELETED..........................................

3/4 7-37 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE..................

3/4 8 8 FERMI - UNIT 2 xxiv Amendment No. /9, ES, EJ, 82

JEDfX llST OF TABLES (Continued)

IAB1f fMI 4.8.2.1-1 BATTERY SURVEILLANCE REQUIREMENTS.............

3/4 8 12 3.8.4.2 1-PRIMARY CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES................

3/4 8-19 3.8.4.3 1 MOTOR 0PERATED VALVES. THERMAL OVERLOAD PROTECTION....................................

3/4 8 21 3.8.4.5 1 STANDBY LIQUID CONTROL SYSTEM ASSOCIATED ISOLATION DEVICES 480 Y MOTOR CONTROL CENTERS..

3/4 8 27 5.7.1 1 COMPONENT CYCLIC OR TRANSIENT LIMITS..........

$7 6.2.2-1 MINIMUM SHlfT CREW COMPOSITION................

6-5 k

FERMI - UNIT 2 xxv Amendment No. M, f//,77. 82

I QB 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

IDLullflED_LLALAg 1.15 IDENTIFIED LEAKAGE shall be:

Leakage into collection systems, such as pump seal or valve packing a.

leaks, that is 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 the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

ISOLATION _ SYSTEM RESEONSE TIME 1.16 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall-include diesel generator starting and sequence loading delays where applicable.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

LIMITING CONTROL ROD PATTERN 1.17 A LIMITING CONTROL R0D PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value for APlilGR, LHGR, or MCPR.

LINEAR HEAT GENIRAT10N RATE 1.18 LINEAR HEAT GENERATION RATE (LiiGR) shall be the heat generation per unit length of fuel rod.

It is the integral of the heat fler over the heat transfer area associated with the unit length.

LOGIC SYSTEM FI)RCT10NAL TEST 1.19 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e.,

all relays and contacts, all trip units, solid state logic elements, etc., of a logic circuit, from sensor through and including the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MAXIMUM FRACTIONJf_LUllTING POWER DEHSILY 1.20 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.

MEMBERIS1 0F THE PI)1LlG 1.21 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant.

This category does not include employees of the utility, its contractors or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons whn use portions of the site for recreational, occupational or other purposes not associated with the plant.

FERMI - UNIT 2 1-3

DEFINLTlQfs._

6fNiMUM CP,iT[(.Al POWER RATIO 1.22 1M MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in ths core.

OF F-q0ij3ELTHENT _ S111LM 1.23 An Off GAS TREATMENT SYSTEM is any system designed and installed to reduce radioactive gasecus effluents by collecting reactor coolant system offgases from tha reactor coolant and providing for delay or holdup for the purpose of reduct:hs the total radioact!vity prior to release to the environment.

OFFSITE 00ffJALQLAT10N MAN'JAL 1.24 The OFF$11E CDSL CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid affluena, in the chiculation of gaseous and liquid ef fluent mon's torir,g Alem/ Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program.

The ODCM shall also contata (1) the Radioactive Effluent Controls ano Radiolog(cal Environmental l

1 Monitoring Programs required by Section 6.8.5 and (2) logical Envirornental descriptions of the information that should be included in the Annual Radio Operatin; and Semiannual Radioactive Effluent Release Reports required by Specifiestions 6.9.1.7 and 6.9.1.8.

DE!BBLE - OPEiLAMLlH 1.25 A system,- LJubsystem, 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, electrical power.

cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

O_P[ RATIONAL CONQlH QU - CONDITIQN P

1.26 An OPERATIONAL CONDITION, i.e.,

CONDITION, shall be any one inclusive combination of mode sW tch position and average reactor coolant temperature as specified in Table 1.2.

PHYSICS TEMS 1.27 PHYSICS 'IESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chaptar 14 of the FSAR, (2) authorized under the provisions of 10 CFR 50.S9, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.28 PRESSURE BOUNDARY LEAKAGE shall be leakage through a nonisolable fault in a reactor coolant system component body, pipe wall, or vessel wall.

!$1}JLARY CONTAINMEf4T INTEGRITY l.29 PRIMARY CONTAINMENT INTEGRITY shall exist when:

a.

All primary containment penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERABLE primary containment automatic isolation system, or FERMI - UNIT ?

1-4 Amendment No. 82

4 DEFINITIONS 2.

Closed by at least one manual valve, blank flange, or deactivated automatic valve secured in its closed position, except as provided in Table 3.6.31 or Specification 3.6.3.

b.

All primary containment equipment hatches are closed and sealed.

c.

Each primary containment air tor.k is in compliance with the requirements of Specification 3.6.1.3.

d.

The primary containment leakage rates are within the limits of Specification 3.6.1.2.

e.

The suppression chamber is in compliance with the requirement of Snecification 3.6.2.1.

f.

The sea H 19 rechenfsm associated with each primary containment penetration, e.g., we'is, bellows, or 0-rings, is OFERABLE.

g.

The suppression chamber to reactor bui1 Jing vacuum breakers are in compliance with Specification 3,6.4.2.

IHE PROCESS LONTROL PROGRAM 1.30 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 1

requirements governing the disposal of solid radioactive waste.

l PVRGE : PURGING 1.31 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.

RATED THERMAL POWER 1.32 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3293 MWT.

c FERMI - UNIT 2 1-5 Amendment No. /2,82 1

4 DEFINITIONS 1.39 DELETED i

SOURCE CHECK 1.40 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

STAGGERED TEST BAS 11 1.41 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.

THERMAL POWER l.42 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM RESPONSE TIME 1.43 The TURBINE BYPASS SYSTEM RESPONSE TlHE shall be that time interval from when the turbine bypass control unit generates a turbine bypass valve flow signal until the turbine bypass valves travel to their required positions.

The response time may be measured by any series of sequential, overlapping or total steps such that the er,6 re response time is measured.

UNIDENTIFIED LEAKACE 1.44 UNICENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEitKAGE.

- UNRESTRICTED AREA 1.45 An UNRESTRICTED AREA shall be any area at-or beyond the SITE COUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to ra11ation and radioactive

-materials, or any a~ea within the SITE B0UNDA)Y used for residential quarters or for industrial, commercial, institational, and/or recreational purposes.

FERMI - UNIT 2 1 Amendment No._82

DEftti!TIONS 1.46 DELETEC VENTING 1.47 VENTING shall be 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,eplacement air or gas is-not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

FERMI - UNIT _2' l-8 Amendment No. 82 y-

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ACCIDENT MONITORING INSTRUMENTATION h

MINIMUM APPLICABLE 5

REQUIRED NUMBER CHANNELS OPERATIONAL j-

]

INSTRUMENT-0F CHANNELS OPERABLE CONDITIONS ACTION

13. Standby Gas Treatment System Radiation Monitors i.

SGTS - Nchle Gas (Low-range)#

1/0PERABLE 1/0PERABLE 1, 2, 3 81 a.

SGTS subsystem SGTS subsysten j

b.

SGTS - Noble Gas (Mid-range) 1/0PERABLE l/0PERABLE 1, 2, 3 81 SGTS subsystem SGTS subsystem c.

-SGTS - AXM-Noble Gas (Mid-range) 1/0PERABLE l/0PERABLE 1, 2, 3 81 SGTS subsystem SGTS subsystem i

d..

SGTS - AXM-Noble Gas (High-range) 1/0PERABLE l/0PERABLE 1, 2, 3 81

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SGTS subsystem SGTS subsystem 14.

Neutron Flux 2

1 1, 2 80

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15. Deleted,

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Primary Containment Isolation Valve Position 1/ valve 1/ valve 1, 2, 3 82 i-E3 m

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1. Also included in the OFFSITE DOSE CALCULATION MANUAL.

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jfiSIEI)MENTAT10N PAGES 3/4 3 72 THROUGH 3/4 3-75 HAVE BEEN DELETED FERMI - UNIT 2 3/4 3-71 Amendment No. U, 82

INSUwMENTATION EXPLOSIVE GAS HONITORING INSTRUMENTATION l

llMITING CONDITION FOR OPERATION 3.3.7.12 The explosive gas monitoring instrumentation channel shown in Table 3.3.7.12-1 shall be OPERA 0LE with its alarm setpoint set to ensure that the limits of Specificatice 3.11.2.6 are not exceeded.

APPLICABILITY: As shown in Table 3.3.7.12 1 ACTION:

a.

With an explosive gas monitoring instrumentation channel alarm l

setpoint less conservative tha' required by the above Specification, declare the channel inoperable and take ACTION shown in Table 3.3.7.12 1; or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of explosive gas monitoring l

instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.12 1.

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.

SURVElllANCE RE0VIREMENTS 4.3.7.12 Each explosive gas monitoring instrumentation channel shall be

@monstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.12-1.

FERMI - UNIT 2 3/4 3-76 Amendment No. U, 82

?;

TABLE 3.3.7.12-1 EXPLOSIVE GAS MONITORING IN">TRUMENTATION l

[

e 25 MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.

OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping) 1 a.

Hydrogen Monitor I

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FERMI - UNIT 2' 3/4 3-78 Amendment No,-82

1 -

TABLE 3.3.7.12 1 (Continued)

TABLE NOTATIONS I

• • During main condenser offgas treatment system operation.

ACTION STATEMENTS ii 1

i ACTION 124 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of main condenser offgas treatment system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Otherwise, suspend release of radioactive effluents via this pathway,

- FERMI - UNIT 2 3/4 3-80 Amendment No. //, /J, 82

z TABLE 4.3.7.12-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

C 25 CHANNEL MODES IN WHICH

' -d CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REOUIRED 1.

0FFGAS MONITORING SYSTEM (At the 2.2 minute delay piping)

' Hydrogen Monitor D

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FERMI -. UNIT 2 3/4 3-82 Amendment No. 82

IA.BLE 4.3.7.12-l'(Continued)-

LABLE NOTATIONS l

~Du' ring main condenser offgas treatment system operation.

1 (3I The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One volume percent hydrogen,' balance nitrogen, and 2.-

Four volume percent hydrogen, balance nitrogen.

FERMI - UNIT 2 3/4 3-84 Amendment No. 82

+

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS PAGES 3/4 11-3 THROUGH 3/4 11-6 HAVE BEEN DELETED FERMI - UNIT 2 3/4 11-1 Amendment No. 82 l'

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THIS PAGE HAS BEEN INTENTIONALLY LEFT BLANK r

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- FERMI'- UNIT:2 3/4 11-2 Amendment No. 82,

4 i

RADI0 ACTIVE EFFLUENTS LIOVID HOLDUP TANKS LIMITING _ CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

i

- FERMI - UNIT 2 3/4 11-7

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS PAGES 3/4 11-9 THROUGH 3/4 11-14 HAVE BEEN DELETED

-FERMI - UNIT 2 3/4 11-8 A~endment No. 82

RADI0 ACTIVE EFFLUENTS THIS PAGE HAS BEEN INTENTIONALLY DELETED FERMI - UNIT 2 3/4 11-15 Amendment No. 82

3/4.11 RADIOACTIVE EFFtVENTS 3/4.11.2 GASEOUS EFFLUENTS EXPLOSlVE GAS MIXTURE LIMITING CONDITION FOR OPERATION i

3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.

APPLICABillTY: Whenever the main condenser steam jet air ejectors are in operation.

ACTION:

a.

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

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by continuously monitoring the waste gases in the main condenser offgas treatment system with the hydrogen monitors required OPERABLE by Table 3-.3.7.12-1 of Specification 3.3.7.12.

FERMI - UNIT 2 3/4 11-16 Amendment No. 82

RADIOAC~!yLEffJ.VINLS MAIN CONDENSER LIMITING CONDITION FOR OPERATION 3.11.2'.7 The gross radioactivity rate of noble gases measured at the discharge of the 2.2 minute delay piping shall be limited to 'iess than or equal to 340 millicuries /sec after 30 minute decay.

APPllCABillTY:

OPERATIONAL CONDITIONS 1, 2*, and 3*.

ACTION:

With the gross radioactivity rate of noble gases at the the discharge of the 2.2 minute delay piping exceeding 340 millicuries /sec after 30 minute decay, restore the gross radioactivity rate tt, within its limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP, with all main steam lines isolated, within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVElllANCE REQUIREMENTS 4.11.2.7.1 The radioactivity rate of noble gases at the discharge of the 2.2 minute delay piping shall be continuously monitored in accordance with the ODCH.

4.11.2.7.2 The gross radioactivity rate of noble gases from the main condenser steam jet air ejector shall be determined to be within the limits of l

Specification 3.11.2.7 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the discharge of the 2.2 l

minute delay piping:

a, At least once per 31 days.

1 b.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following an increase, as indicated by the Offgas Radiation Monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady-state fission gas release from the primary coolant.

c.

The provisions of Specification 4.0.4 are not applicable.

1

• When the main condenser air ejector is in operation.

FERMI - UNIT 2 3/4 11-17 Amendment No. f7,82,

~

RADIOACTIVE r, w Nig PAGES 3/4 11-19 AND 3/4 11-20 HAVE BEEN DELETED 4

l-FERMI - UNIT 2 3/4 11-18 Amendment No. 82,

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SECTION 3/4.12 HAS BEEN DELETED

- FERMI - UNIT 2 3/4 12-1 Amendment No. g,

. - -_1

INSTRUMENTATION BASES MONITORI.t[G INSTRUMENTATION (Continued) 3/4.3.7.8 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine and detection system ensures that an accidental chlorine release will be detected promptly and the necessary p.atective actions will be automatically initiated to provide protection for control room personnel. Upon detection of a high concentration of chlorine, the control room emergency. ventilation-system will automatically be placed in the chlorine mode of operation to provide the required protection.

The detection system required by this specification is consistent with the recommendations of Regulatory Guide 1.95 " Protection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release", Revision 1, January, 1977.

3/4.3.7.9 DELETED 3/4.3.7.10 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable-out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

i l

i I

FERMI - UNIT 2 8 3/4 3-5 Amendment No. EE, EE,82, l

=

INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.12 EXPLOSIVE GAS MONITORING INSTRUMENTATION l

The explosive gas monitoring instrumentation is provided to monitor the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is provided to initiate action of the feedwater system / main turbine trip system in the event of a high reactor vessel water level due to failure of the feedwater controller under maximum demand.

3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION The OPERABILITY of the alternative shutdown system ensures that a fire will not preclude achieving safe shutdown. The alternative shutdown system instrumentation is independent of areas where a fire could damage systems normally used to shutdown the reactor. Thus, the system capability is consistent with General Design Criterion 3 and' Appendix R to 10 CFR 50.

i 1

(

l l

FERMI - UNIT 2 B 3/4 3-6 Amendment No. E9, 7J, 82, l

l l

3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11~.1 L10VID EFFLUENTS THIS PAGE HAS BEEN INTENTIONALLY DELETED t

l l-l l:

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i l.,-

l FERMI - UNIT 2 B 3/4 11-1 Amendment No. 82,

EAD10 ACTIVE EFFLI).ENJ1 BASES 3/4.11.1 l!0VID EFFLUENTS i

3/4.11.1.4 L10VID HOLDUP TANKS

-The tanks listed in this specification include all those outdoor radwaste tanks'that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid'radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified tanks provides assu'rance that.in the event of an uncontrolled

. release of the tanks' contents, the resulting concentrations would be less

-than ths-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.

FERMI - UNIT 2 B 3/4 11-2 Amendment No. 82

i RADIOACTIVE EFFLUENTS' BASES 3/4.11.2 GASEOUS EFFLUENTS-i THIS PAGE HAS BEEN INTENTIONALLY DELETED t

l-FERMI - UNIT 2 B 3/4 11-3 Amendment No.82,

RADI0 ACTIVE EFFLUENTS BASES THIS PAGE HAS BEEN INTENTIONALLY DELETED l

FERMI - UNIT 2 B 3/4 11-4 Amendment No. 82,

=

RADIOACTIVE EFFLUENTS BASES I

i a

i 3/4.11.2.6 EXPLOSIVE GAS MIXTURE

-This specification is provided to ensure that the concentration of potentially explosive gas mixture contained in the main condenser offgas system is maintained below the flammability limits of hydrogen and oxygen.

Maintaining the concentration of hydrogen 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.

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

1 i

FERMI - UNIT 2 B 3/4 11-5 Amendment No. 82

RADIOACTIVE EFFLUENTS BASES THIS PAGE HAS BEEN INTENTIONAll DELETED FERMI - UNIT 2 B 3/4 11-6 Amendment No. 82

y g ;,

v

' BASES-t THIS PAGE dAS BEEN INTENTIONALLY DELETED

FERMI + UNIT 2-B 3/4 12-1 Amendment No. 82

? -

5-BASES 4

t THIS PAGE HAS BEEN INTENTIONALLY DELETED FERMI - UNIT 2 B 3/4 12-2 Amendment No. 82;

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit safe operation cnd shall delegate in writing the succession to this responsibility during his absence.

The Plant Manager shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

.6.1.2 The Nuclear Shift Supervisor or, during his absence from the control

. room, a designated individual shall be responsible for tl.e control room command function.

A management directive to this effect, signed by the Assistant Vice President and Manager - Nuclear Production shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATIQN 6.2.1 0FFSITE__AND ONSITE ORGANIZATIONS j

Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.

The onsite and offsite organizations shall include.the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate, in the _ form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the Updated Final Safety Analysis Report.

b.

The Senior Vice President shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support of the plant to ensure nuclear safety, c.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 UNIT staff a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; b.

At least one licensed Operator shall be in the control room when fuel is in the reat. tor.

In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensea Senior Operator shall be in the control room; FERMI - UNIT 2 6-1 Amendment No. JJ,10, S,82,

4 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

- 6.8.2 Each plant-administrative procedure, and changes thereto, shall be reviewed in accordance with Specification 6.5.1.6, and approved by the Plant Manager prior to implementation, and shall be reviewed periodically thereafter as set forth in administrative procedures.

6.8.3 Each plant procedure required by Specification 6.8.1, other than administrative procedures, and changes thereto, shall be reviewed in accordance with 6.5.3, and approved by the Plant Manager prior to implementation and shall be reviewed periodically thereafter as set forth in administrative procedures. The Plant Manager may delegate approval authority in writing for specific types of. procedures to a Section Superintendent.

l 6.8.4 Temporary changes to procedures of Specification 6.8.1 may be made provided:

a.

The intent of the original procedure is not altered; b.

The. change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on Fermi 2; and c.

The change is documented, and reviewed and approved in accordance with either 6.8.2 or 6.8.3 above, as appropriate, within 14 days of implementation.

6.8.5 The following programs shall be established, implemented, and maintained:

a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, reactor water sampling, containw.it sampling, reactor water cleanup, combustible gas control, control rod drive discharge headers, and standby gas treatment systems. The program shall include the following:

1.

Preventive maintenance and periodic visual inspection requirements, and 2.

Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

FERMI - UNIT 2 6-15 Amendment No. JJ, 30

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

c.

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 following:

1.

Training of personnel,

'2.

Procedures for sampling and analysis, and 3.-

Provisions for maintenance of sampling and analysis equipment, d.

Hioh Density Soent Fuel Racks A program which will assure that any unanticipated degradation of the high density spent fuel racks will be detected and will not compromise the integrity of the racks.

e.

Radioactive Efflyent Controls Procram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS-0F THE PUBLIC from radioactive effluents as low as 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:

1)

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, 2)

Limitations on the concentrations of radioactive material l

released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3)

Monitoring, sampling, and analy; s of radioactive liquid and l

gaseous effluents in accordanct :.th 10 CFR 20.106 and with l

the methodology and parameters in the CDCM.

i FERMI - UNIT 2 6-16 Amendment No. E, JJ, JS, 82,

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 4)

Limitations on the annual and quar erly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix ! to 10 CFR Part 50, 5)

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, 6)

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 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, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the I

SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table -11, Column 1,

]

8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from eacn unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, j

9)

Limitations on the annual and quarterly doses to a MEMBER OF I

THE PUBLIC from Iodine-131, Iodine-133, tritium, and all I

radionuclides in particulate form with half-lives greater I

than 8 days in gaseous effluents released from each unit to I

areas beyond the SITE B0VNDARY' conforming to Appendix I to 10-CFR Part 50, 10)

Limitations en ver'ing and purging of the Mark I containment through the Standby Gas Treatment System or the Reactor Building Ventilation System to maintain releases as low as reasonably achievable, 11)

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to I

radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

i l

FERMI - UNIT 2 6-16a Amendment No.82

r ADMINISTRATIVE CONTROLS ERQc100RES AND PROGRAMS (Continued) f.

Radiolooical Environmental Monitorino Prooram 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 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:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2)

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, 3)

Participation in an 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.

6.9 REPORTING RE0VIREMENTS ROUTINE rep 0RTS 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 V

- Regional Administrator of the Regional Office of the NRC unless otherwise noted.

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 unit.

6.9.1.2 The startup report shall address each of the tests identified in Subsection 14.1.4.8 of-the Final Safety Analysis Report and shall include a

-description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to FERMI - UNIT 2 6-16b Amendment No. 8L

ADMINISTRATIVE CONTR0lS STARTUPREPORT(Continued) obtain satisfactory operat.on shall also be described. Any additional s)ecific details required in license conditions based on other commitments.shall se included in this report.

6,9.1.3 Startu) reports shall be submitted within (1) 90 days following completion of tie startup test program, (2) 90 days following resumption or i

commencement of commercial powe,' operation, or (3) 9 monthf following initial criticality, whichever is earliest.

If the startup report does not rover all three events (i.e., initial criticality, completion of startup test program, and resumption or commene.ement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

AfM AL REPAB15 6.9.1.4 Annual reports covering the activities of the urait as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of plant, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,* (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling).

The dose assignments to various duty functions may be estirnted based on

>ocket or thermoluminescent dosimeters (1LD) dos? More er film aadge measurements.

Small exposures totalling ", ss tia - 20% of the individual total dose need not be accounted fu It' W aggregate, at least 80% of the total whole body dose recette) frem external sources should be assigned to specific major work " unctions; and b.

Documentation of all challenges to main steam line safety / relief valves, and c1 A summary of ECCS outage data including:

1.

ECCS outage dates and duration of outages, 2.

Cause of each ECCS outage, 3.

ECCS systems and com>onents in the outage, and 4.

Corrective action ta<en, d.

The reports shall also include the results of specific activity analysis in which the prima y coolant exceeded the limits of Specification 3.4.5.

Ik n.110 wing infi.mation shall be included:

• This tabulation supplements the requirements of 920.407 of 10 CFR Part 20.

FERHI - UNIT 2 6-17 Amendment No. 11

ADMINISTRATIVE CONTROLS ANNtLAL_ REPORTS (Continued)

(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) results of the last isotopic analysis for radioluine performed prior to exceeding the limit, results of analy5is while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit (each result should include date and time of sampling and the radiciodine concentrations);

(3) clean ep system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) graph of the 1 131 and one other radiotodine isotope concentrations in microcuries per gram as a function of time i

for the duration of the specific activity above the steady-state level; and i

(5) the time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

MONTHLY OPERATING REPORTS 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be. submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 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 prov.ded 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 ! to 10 CfR Part 50.

$Dilg[NyAL RAD 10ACTlyE EFFLUENT RELEASE REPQHI 0.9.1.8 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 l

cffluents 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 1 to 10 CFR Part 50.

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i MMINISTRATIVECONTROLS 6.10 RECORD RETENT10 - (sontinued) 6.10.3 The following i$ cords 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.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

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

e.

Records of transient or operational cycles for those unit components identified in Table 5.7.1 1.

f.

Records of reactor tests and experiments, g.

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

h.

Records of inservice inspections performed pursuant to these Technical Specifications.

i.

Records of quality assurance activities required by the Operational Quality Assurance Manual.

j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the OSRO and the NSPG.

1.

Records of the service lives of all hydraAlic and mechanical snubbers required by Specification 3.7.5 'ncluding the date at which the service life commences and assor,iated installation and maintenance records, m.

Records of analyses required by the radiological environmental monitoring program that woul_d permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effective at specified times and QA records showing that these procedures were followed.

n.

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

FERMI - UNIT 2 6 22 Amendment No. JJ, Me,

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area, b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.

c.

A heahn physics qualified individual (i.e., qualified in radiation protection procedures with a radiation dose rate monitorir.g device who is respon)sible for providing positive control over the activities within the area and shall perform seriodic radiation surveillance at the frequency specified by the iealth Physicist in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrems shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the= administrative control of the Nuclear Shift Supervisor on duty and/ or the health physic supervision.

Doors shall remain locked except during periods of access by personnel under an ap) roved RWP which shall specify the dose rate levels in the immediate wor ( area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose in excess of 1000 mrems* that are located within large areas, such as the containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device, in lieu of the stay time specification of the RWP, continuous surveillance, direct or remote (such as use of closed circuit TV cameras) may be made by personnel qualified in r,adiation protection procedures to provide positive exposure control over the activities within the area.

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

6.13.2 Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n.

This documentation shall contain:

• Measurement made at 18 inches from source of radioactivity.

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ADMINISTRATIVf CONTROLS 6.13 PROCESS CONTROL PROGRAM (ECP) (Continued) 1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)

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

b.

Shall become effective after review and acceptance by the OSR0 and the approval of the Plant fianager.

6.14 0FFSITE DOSE-(ALCULATION MANUAL (0DCM) 6.14.1 The ODCH shall be approved by the Commission prior to implementation.

6.14.2 Changes to the ODCH:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n.

This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s) and 2)

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 ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the OSR0 and the approval of the Plant Manager.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCH as part of or concurrent with the Semiannual 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 area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

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