ML20059N957

Amend 59 to License NPF-43,adding Section 3/4.3.11 to Tech Specs W/Limiting Condition for Operation & Surveillance Requirements for Alternative Shutdown Sys

ML20059N957
Person / Time
Site:	Fermi  (NPF-43-A-059, NPF-43-A-59)
Issue date:	10/04/1990
From:	Pierson R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059N959	List: ML20059N957 ML20059N961
References
NUDOCS 9010240186
Download: ML20059N957 (23)

Text

,

1

j. hf :

f/f]>R EI0' 7

'o[

UNITED STATES y

t NUCLEAR REGULATORY COMMISSION q

E" t L.

,g WASHINGTON, D. C. 20665

'(

r

,o

$l DETROIT EDISON COMPANY DOCKET NO. 50-341

}

FERMI-2 AMENDMENT TO' FACILITY OPERATING LICENSE 8

Amendment No. 59 y

License No. NPF-43:

j i

1.

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

A.

The application for ' amendment by the Detroit Edison Company (the 1

licensee) dated December 22, 1988, as supplemented May 31, 1989, _

q complies with the-standards and requirements of.the_ Atomic Energy

_y Act of_1954,Jas-amended (the Act), and the Commission's rules'and iJ regulations set forth in 10 CFR Chapter I; 1

.t B.

The facility willaoperate in conformity with the application, th'e j

l provisions;of the-Act, and the rules and regulations'of-the I

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 (11) that such_ activities will be. conducted-in compliance with'the Commission's regulations; H

s P

D.'

The issuance of'this amendmentEwill-not be inimical to the common

~

defense andisecurity or to the health _and-safety.of-the public;'and~

l 1

E.

The issuance of this amendment.is in accordance with 10 CFR Part 51'of; d

the Commission'sqregulations;andsall applicable requirements have'been satisfied; 2.

Accordingly, the license is amended by changes to:the Technical ~Specifica-D I'

tions'as-indicated in the attachment to this license amendment;and para-i a

L graph 2.C.(2) of; Facility Operating 1 License No.1 NPF-43 is - hereby. amended ;

.to read as-follows:

qi Technica'l= Specifications-and: Environmental Protection Plan-o 1The Technical, Specifications _ contained-in Appendix A,Las revised' through Amendment No. 59, and the Environmental. Protection Plan :

contained inJAppendix 8. are -hereby incorporated in the license.

l Deco shallLoperate the facility in accordance with the' Technical-

)

=

Specifications.and.the Environmental Protection Plan.

i 9010240186 901004 1

ADOCK0500g1 1

PDR P

4

~

s, v,-.--+

f 4

- i i

n j

p

] -

i.

,)

E

l

-t

'.3.

This license amendment is effective'as of its date of issuance, T

FOR THE NUCLEAR Rf GULATORY COMISSION

- i Mc.,h I'

Robhrtr.Pierson, Director Project Directorate.III-1 1

-Division of Reactor Projects

.III,

?!

..Y IV, V & Special Projects mcq Office of Nuclear Reactor Regulation

.i Attachmenti.

Changes to the Technical Specifications r

Date.-of Issuance:.0ctober 4, 1990.

6

'1 i

~

j s

'l l

I

.+

- i

'i 4

_ fj 4

t 7

1 1i I

+

h

_1_

Ei l- k

e

• c !. >

.c 4

y

'y j

ATTACHMENT ' TO,LJ, CENSE, AMENDMENT _ N0;,5g j

TO

- FACILITY 0PERATING LICENSE N0'. NPF-43 q,

o DOCKET NO. 50,-3,41-

, 9:

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

.the attached pages; The revised pages are identified by Arendmen 1

contain aLvertical line indicating the area. of change.. The corre,t number and sponding j

is over. leaf pages:are also provided to n.aintain document completeness.

R REMOVE INSERT 1

^

Ev v-viii viii xiii.

xiii xiv xiv xv xv a

xvi xvi i

-xxiv xxiv 3/4 3-89*-

3/4 3-89*

'l 3/4 3-90 3/4 3-91 i

3/4 3-92

' 3/4 7-3 3/4 7-3 i

3/4 7-4 3/4 7-4 3/4.7-41

-3/4-7-42 3/4 7-43

• B 3/4 3-5

• ? ?/A-3-5 j

B-3/4 3-61 B 3/4 3 ;

g B 3/4-7 B 3/4 7 J B 3/4 7-Sa-i

,a -

9

, \\ ;,

Mfv'eFlear page provided tc rcaintain'-dtcupent completeness. ilo charges

. contained;in these pages.

I/-i 14-

• ~

.l.-

i

+

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS-d

.1 L-SECTION PAGE!

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM 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-INSTRUMENTATION.....................................

3/4 3-23 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION

]

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

3/4 3-32>

i

'l 3/423.5

= REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION i

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 1}

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

3/4 3-51 1

Meteorological Monitoring Instrumentation...........

3/4 3-54

' I Remote Shutdown System Instrumentation and Controls.

3/4 3-57 l

j Accident Monitoring Instrumentation.................

3/4 3-60 J i i

Source Range Monitors...............................

3/4 3-64

,a Traversing In-Core Probe System.....................

3/4 3-65 Chlorine Detectio_n System..........................

3/4 3-66 l

Fire Detection Instrumentation......................

3/4 3-67 a

1 Loose-Part Detection System.......................... 3/4 3-70 Radioactive Liquid Effluent MonitoringL l

' Instrumentation......................................

3/4 3-71 h

Radioactive Gaseous Effluent Monitoring i

Instrumentation......................................c3/4 3 -l 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM..................

3/4.3-85 ll

~ /4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION 3

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. 53, 59

LIMITING _ CONDITIONS FOP. OPFRATION_AND SURVEILLANCE REQUIREMENTS SECTION PAGE CONTAINMENT SYSTEMS (Contini;od) 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen Recombinei Systems............................................

3/4 6-57 Drywell and Suppression Chamber Oxygen Concentration.

3/4 6-58 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System...........

3/4 7-1 Emergency Equipment Cooling Water System.............

3/4 7-3 Emergency Equipment Service Water System.............

3/4 7-4 Diesel Generator Cooling Water System................

3/4 7-5 Ultimate Heat Sink...................................

3/4 7-6 3/4.7.2 CONTROL ROOM EMERGENCY FI LTRATION SYS1EM.............

3/4 7-8 3/4.7.3 SHORE BARRIER PROTECTION.............................

3/4 7-11 c

3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM................

3/4 7-14 3/4.7.5 S N U BS E R S.............................................

3 /4 7 - 16 3/4.7.6 SEALED SOURCE CONTAMINATION..........................

3/4 7-22 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System........................

3/4 7-24 l

Spay and/or Sprinkler Systems......................... 3/4 7-27 C0 Systems..........................................

3/4 7-29 Ha$on Sy s tem s........................................

3/4 7-30 Fire Hose Staticns...................................

3/4 7-31 I

Yard Fi re Hydrants and Hydrant Hose House............

3/4 7-36 S/4.7.8 FI RE R AT ED ASSEMBLI ES................................

3/4 7-38 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND MOISTURE SEPARATOR REHEATER.............................................

3/4 7-40 3/4.7.10 RESERVED i

3/4.7.11 APPENDIX R ALTERNATIVE SHUTDOWN AUXILIARY SYSTEMS.,..

3/4 7-41 I

I FERMI - UNIT 2 viii Amendment No. 39,59

l BASES SECTION PAGE INSTRUMENTATION (Continued)

MONITORING INSTRUMENTATION (Continued)

Meteorological Monitoring Instrumentation.......

B 3/4 3-4 Remote Shutdown System Instrumentation and Controls........................................

B 3/4 3-4 Accident Moni tori ng Instrumentatio.1.............

B 3/4 3-4 Source Range Monitors...........................

B 3/4 3-4 Traversi ng In-Core Probe System.................

B 3/4 3-4 Chlorine Detection System.......................

B 3/4 3-5 Fire Detection Instrumentation................... B 3/4 3-5 Loose-Part Detection System.....................

B 3/4 3-5 Radioactive Liquid Effluent Monitoring l

Instrumentation.........................

B 3/4 3-5 Radioactive Gaseous Effluent Monitoring Instrumentation.................................

B 3/4 3-6 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.............

B 3/4 3-6 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEMS ACTUATION I N ST R UME NT AT I ON.................................

B 3/4 3-6 3/4.3.10 RESERVED I

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

B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM............................

B 3/4 4-1 l

3/4.4.2 SAFETY / RELIEF VALVES............................-

B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE t

Leakage Detection Systems.......................

B 3/4 4-2 Operati onal Le a kage.............................

B 3/4 4-2 3/4.4.4 CHEMISTRY.......................................

B 3/4 4-2 3/4.4.5-SPECIFIC ACTIVITY...............................

B 3/4 4-3 i

3/4.4.6 PRESSURE / TEMPERATURE LIMITS.....................

B 3/4,4 {

i 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES................

B 3/4 4-5 i

3/4.4.8 STRUCTURAL INTEGRITY............................

B 3/4 4-5.

i 3/4.4.9 RESIDUAL HEAT REM 0 VAL...........................

.B 3/4 4-5 FERMI - UNIT 2 xiii Amendment No. 49, 53, 59

l' e

BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.10 CORE THERMAL HYDRAULIC STABILITY................

B 3/4 4-8 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1/2 ECCS - OPERATING and SHUTD0WN.................... B 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER.............................. B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Contai nment Integri ty.................... B 3/4 6-1 Primary Contai nment Leakage...................... B 3/4 6-1 Prima ry Contai nment Ai r Locks.................... B 3/4 6-la MSI\\ Leakags_ Control System...................... B 3/4 6-2 Primary Containment Structural Integrity......... B 3/4 6-2 Drywell and Suppression Chamber Internal Pressure....................................... B 3/4 6-2 Drywell Average Air Temperature.................. B 3/4 6-2 Drywell and Suppression Chamber Purge System..... B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS......................... B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES............. B 3/4 6-6

. 3/4.6.4 VACUUM RELIEF.................................... B 3/4 6-6 3/4.6.5 SECONDARY CONTAINMENT............................

B 3/4 6-6 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL........... B 3/4 6-7 FERMI - UNIT 2 xiv Amendment No. 49, 59

BASES i

SECTION PAGE I

3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS...........................

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM........

B 3/4 7-1 3/4.7.3 SHORE BARRIER PROTECTION........................

B 3/4 7-1 I

3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM...........

B 3/4 7-la 3/4.7.$

SNUBBERS.......................................

B 3/4 7-2 j

3/4.7.6 SEALED SOURCE CONTAMINATION.....................

B 3/4 7-4 3/4.7.7 FIRE SUPPRESSION SYSTEMS........................

B 3/4 7-4 3/4.7.8 FIRE RATED ASSEMBLIES...........................

B 3/4 7-4 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND MOISTURE SEPARATOR REHEATER..............................

B 3/4 7-5 3/4.7.10 RESERVED 3/4.7.11 APPENDIX'R ALTERNATIVE SHUTDOWN AUXILIARY I

SYSTEMS.........................................

B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS-3/4.8.1, 3/4.8.2, and

-3/4.8.3 A.C. SOURCES, D.C. SOUR 0ES, and ONSITE POWER DISTRIBUTION SYSTEMS...............

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.........

B 3/4 8-3 i

3/4.9 REFUELING OPERATION 3 3/4.9.1 REACTOR MODE SWITCH.............................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION.................................

B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION............................

B 3/4 9-1 3/4.9.4 DECAY TIME......................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS..................................

B 3/4 9 3/4.9.6 REFUELING PLATF0RM..............................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE'P00L............

B 3/4 9-2 3/4.9.8 and 3/4~9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L.......

B 3/4 9-2 L

3/4.9.10 CONTROL ROD REM 0 VAL.............................

B 3/4 9-2 l

l FERMI - UNIT 2 xv Amendment No. 39, II, 59

BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...

B 3/4 9-2 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY...................

B 3/4 10-1 3/4.10.2 I SEQUENCE CONTROL SYSTEM.....................

B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS..................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS.............................

B 3/4 10-1 t

3/4.10.5 DELETED........................................

B 3/4 10-1 3/4.10.6 TRAINING STARTUPS...............................

B 3/4 10-1 v

FERMI - UNIT 2 xvi Amendment' No. 46, 59

j I

LIST OF TABLES (Continued)

TABLE PAGE 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION..................

3/4 3-68 3.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING 4

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

3/4 3-72 l

4.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-74 3.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION................................

3/4 3-77 4.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT 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 TRIP 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 3.3.11-1 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 5

3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE P RE SSURE MONITORS..............................

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

3/4 4-15 4.4.5 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 RADIATIO.1 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 SYSTEM 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 FIRE HOSE STATIONS..............................

3/4 7-32 3.7.7.6 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT.......

3/4-7 !

. HOSE HOUSE l-4.8.1.1.2-1

-DIESEL GENERATOR TEST SCHEDULE.................

3/4 8-8 FERMI - UNIT 2 xxiv Amendment No. 49, 59 L

l'

-e e

e

?-

J J

A-A

--o-s

.4 f

1 g '

.)

5*

-I I

E=

a s

gg "w

- t g$$

S G

EEE Rg 1

6

m 86 i

w e

~=

k E

s mz E

O c

5 l

=

a

• =t d

s I"E v!

sw E

.c y

a, E

I

w IB s

m 5

1 i

b 9

-l f,,

t a

E E

3 g

z.

g 82 e p" i

E

=

I c

g m

i FERMI - UNIT 2 3/4 3-89'

n I

1 l

INSTRUMENTATION 3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.11 The alternative shutdown system instrumentation channels shown in Table 3.3.11-1 shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3 ACTION:

With~the number of OPERABLE alternative shutdown monitoring instrumentatian channels less than required, take the ACTION

-i required by Table 3.3.11-1.

The provisions of Specification 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS 4.3.11.1 Each alternative shutdown instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.11.1-1.

i FERMI - UNIT 2 3/4 3-90 Amendment No. 59

TABLE 3.3.11-1 APPENDIX R ALTERNATIVE SHUTOOWN INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.

CTu 11 Unit 1-Volts 1

131 2.

CTG 11 Unit 1-Frequency 1

131 3.

CTG 11 Unit 1-Watts 1

131 4.

CTG 11 Unit 1-Vars 1

131 t

5.

Condensate Storage Tank Level 1

132 6.

Standby Feedwater Flow 1

132 7.

Reactor Water Level 1

133 8.

Reactor Pressure 1

133 9.

Torus Water Temperature 1

133 10.

Torus Water Level 1

133 11.

Primary Containment Temperature 1

133 ACTION STATEMENTS 1

ACTION 131 - Declare CTG 11 Unit 1 inoperable and take the ACTION required by Specification 3.7.11.

ACTION 132 - Declare the SBFW system inoperable and take the ACTION required by Specification 3.7.11.

ACTION 133 - Restore the inoperable channel to OPERABLE st6tus within 7 days or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C i

FERMI - UNIT _2 3/4 3-91 Amendment No. 59

\\

F TABLE 4.3.11.1-1 g

APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL U

INSTRUMENT CHECK CALIBRA110N 1.

CTG 11 Unit 1-Volts M

R 2.

CTG 11 Unit 1-Frequency M

R 3.

CTG 11 Unit 1-Watts M

R l

4.

CTG 11 Unit 1-Vars M

R 5.-

Condensate Storage Tank Level M

R 6.

Standby Feedwater Flow M

R 7.

Reactor Water Level M

R 8.

Reactor Pressure M

R 9.

Torus Water Temperature M

R j

10.

Torus Water Level M

R 11.

Primary Containment Temperature M

R t

FERMI - UNIT 2 3/4 3-92 Amendment No. 59

l e

PLANT SYSTEMS EMERGENCY EQUIPMENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 Two independent emergency equipment cooling water (EECW) system subsystems shall be OPERABLE with eath subsystem comprised of:

a.

One OPERABLE EECW pump, and b.

An OPERABLE flow path capable of removing heat from the associated safety-related equipment.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

With an emergency equipment cooling water system aubsystem inoperable, restore the inoperable subsystem to_0PERABLE status 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 HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and declare the associated safety-related equipment inoperable and take the ACTION required by Specifications 3.4.9.1, 3.4.9.2, 3.5.1, 3.5.2,.3.6.2.2, 3.6.2.3, 3.7.11, 3.9.11.1, and 3.9.11.2, as applicable l

SURVEILLANCJ RE9EIREMENTS 4.7.1.2 The emergency equipment cooling water system shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power-a.

operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in its correct

position, b.

At least once per 18 months during shutdown, by verifying that'each automatic valve servicing nonsafety-related equipment actuates to its isolation position and the associated EECW pump automatically starts on an automatic actuation test signal.

i-FERMI - UNIT 2 3/4 7-3 Amendment No. 59

PLANT SYSTEMS l

EMERGENCY EQUIPMENT COOLING WATER SYSTEM

' LIMITING CONDITION FOR OPERATION 3.7.1.3 Two independent emergency equipment service water (EESW) system subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE emergency equipment service water pump, and b.

An OPERABLE flow path capable of taking suction from the associated ultimate heat sink and transferring the water through the associated EECW heat exchanger.

I APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTIOj:

With an e crgency equipment service water system subsystem inoperable, restore the inoperable subsystem to OPERABLE status 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 HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following i

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and declare the associated safety-related equipment inoperable and j

take the ACTION required by Specifications 3.4.9.1, 3.4.9.2, 3.5.1, 3.5.2, 3.6.2.2, 3.6.2.3, 3.7.11, 3.9.11.1, and 3.9.11.2, as applicable 1

g SURVEILLANCE REQUIREMENTS

4. 7.1. 3 ' The emergency equipment service water system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position, b.

At least once per IP months during shutdown,'by verifying'the EESW pump automatically starts upon receipt of an actuation test signal.

i i

I j

. FERMI - UNIT 2 3/4 7-4 Amendment No.59 l

i t

I

PLANT SYSTEMS 3/4.7.11 APPENDIX R ALTERNATIVE SHUTDOWN AUXILIARY SYSTEMS f

LIMITING CONDITION FOR OPERATION v

3.7.11 The Appendix R Alternative Shutdown auFilitry systems shall be OPERABLE as described below:

a.

A Standby Feedwater (SBFW) System consisting of two OPERABLE SBFW pumps and an OPERABLE flow path from the condensate storage tank to the reactor vessel.

b.

An OPERABLE CTG 11 Unit 1 and power train capable of supplying power to the Peaker Bus.

c.

Two OPERABLE Drywell Cooling Units (Units I and 2) consisting i

of a fan and cooling coil capable of being supplied with cooling water from the EECW system.

i d.

The OPERABLE Appendix R Alternative Shutdown control circuits listed in UFSAR Table 9A.6.9-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3 ACTION:

a.

For the SBFW system:

.i 1.

With one SBFW pump inoperable, within 7 days and at least once per 31 days thereafter, perform Surveillance Requirement 4.7.11.1.b, using the OPERABLE SBFW pump.

The OPERABLE SBFW pump need not be tested more frequently than once per 31 days.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 2.

With the SBFW system otherwise inoperable, res', ore the system to OPERABLE _ status within 7. days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN' within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

With an inoperable CTG 11 Unit 1:

1.

Verify within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,1the 120 KV bus is available by L

-performing Surveillance Requirement 4.8.1.1.1, and l

2.

Within 7 days, restore the CTG 11 Unit 1 to OPERABLE status or provide an alternative source of power to the l

Alternative Shutdown bus.

l Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

FERMI;- UNIT 2 3/4 7-41 Amendment No.59

~

L I

PLANT SYSTEMS 3/4.7.11 APPENDIX R ALTERNATIVE SHUTDOWN AUXILIARY SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (continued) c.

For the Drywell Cooling System:

t 1.

With one drywell cooling unit inoperable, within 7 days and at least once per 31 days thereaf ter, perform Surveillance Requirement 4.7.11.3 using the OPERABLE Drywell Cooling Unit.

The OPERABLE Drywell Cooling Unit need not be tested more frequently than once per 31 days.-

Otherwise, be in at least HOT SHUTDOWN within the next 12 I

hours and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

With both drywell cooling units inoperable, restore at least one drywell cooling unit to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the_next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

With one or more required alternative shutdown system control circuits inoperable, restore the inoperable circuits to OPERABLE i

status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

e.

The provisions of Specification 3.0.t are not applicable, l

i l

FERMI - UNIT 2 3/4 7-42 Amendment No.59 2

a PLANT SYSTEMS

'9 SURVEILLANCE REQUIREMENTS 4.7.11.1 The SBFW system shall be demonstrated OPERABLE:

a.

At least once every 31 days by:

1.

Verifying by ven?ing at the high point vents that the system piping froe the pump discharge to the system isolation valves it filled with water, and 2.

Verifying that each valve (manual, power-operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once every 92 days on a STAGGERED TEST BASIS by verifying that each SBFW pump develops a flow of > 600 gpm in a test flow path with a system head corresponding to the reactor vessel operating pressure including injection line losses.

4.7.11.2 CTG 11 Unit I shall be demonstrated OPERABLE by starting and supplying load of at least 10 MW to the Peaker Bus at least once every 31 days.

4.7.11.3 Drywell Cooling Units 1 and 2 shall be. verified OPERABLE at least once every 92 days on a STAGGERED TEST BASIS by operating the unit for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with the fan in "HIGH" speed.

4.7.11.4 Each required alternative shutdown system control circuit shall be demonstrated OPERABLE by verifying its capability-to perform its intended function (s) at least once per 18 months.

I l-l=

FERMI -' UNIT.2 3/4 7-43 Amendment No. 59

l INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) l 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 protective 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 I

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 FIRE DETECTION INSTRUMENTATION OPERABILITY of the detection instrumentation ensures that both adequate warning capability is available for prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will discharge extinguishing agent in a timely manner.

Prompt detection and suppression of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

F_ ire detectors that are used to actuate fire suppression systems represent a more critically important component of plant's fire protection program than detectors that are installed solely for early fire warning and notification.

Consequently, the minimum number of OPERABLE fire detectors must be greater.

The loss of detection capability for fire suppression systems, actuated fire detectors, represents a significant degradation of protection for any area.

As a result, the establishment of a fire watch patrol must be initiated at an earlier stage than would be warranted for the loss of detectors that provide:

only early fire warning.

The establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

3/4.3.7.10 LOOSE-PART DETECTION SYSTEM 4

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..

3/4.3.7.11 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology the procedures in the ODCM to ensure that the FERMI - UNIT 2 B 3/4 3-5 t

i INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.11 RADIOACTIVE LIQUID EFFLUENT M0NITORING INSTRUMENTAT10$ (Continuec) 1 alarm / trip will occur prior to exceeding the liraits of 10 CFR Part 20. The OPERABILITY ar' a s of this instrumentation is consistent with the requirements of General Des W + iteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.7.12, RADI0 ACTIVE GASEOUS EFFLUENT MON _lTORING INSTRUMENTATION c

The radioactive gaseous effluent monitoring instrurentation is provided to monitor and control, as applicable, the releases of-radicactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordarce with the methcdology ar.d parameters in the ODCP utilizing the system design flow rates as specified in the ODCM. This conservative method is used because the Fermi 2 design does not include flow rate measurement devices. This will ensure the elarm/ trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrutnentation also includes provisions for tenitoring and contro111r.g the concentrations cf potentially explosive gas mixtures in the main condenser offgas treatment system. The OFERABILITY and use of this instrumentation is consistert with the requirements of General Design Criteria 60, 63, ar.d 64 of Apper, dix A to 10 CFR Part 50.

3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specificetion is provided to ensure that the turbine overspeed protectior syster instrumentation art the turbine speed control valves are OPERABLE aric will protect the turbine frets excessive overspeed.

Protection fron~ turbine excessive everspeed is not required to protect shfety-related ccrponents, equipment, or structures.

However, it is included in order te improve everall plart reliability.

3]4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUAT10h_ 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 feedwa.ter controller under maximum demand.

,?]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 damaoe systems normally used to shutdown tne_ reactor. Thus,thesystemcapabilityis consistent with General Design Criterion 3 and Appendix R to 10 CFR 50.

I

. FERMI - UNIT 2 B 3/4 3-6 Amendment No. 59

PLANT SYSTEMS BASES 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND MOISTURE SEPARATOR REHEATER The main turbine bypass system is an active bypass system designed to open the bypass valves in the event of a turbine trip to decrease the severity of the pressure transient.

Each valve is sized to pass.a nominal 13 percent reactor steam flow in the full-open position for a controlled total bypass of approximately 26 percent reactor steam flow.

The main turbine bypass system is required to be OPERABLE consistent with the assumptions of the Feedwater Controller Failure analysis.

The primary purpose of the moisture separator reheater is to improve cycle efficiency by using primary system steam to heat the high pressure turbine exhaust before it enters the low pressure turbines.

In doing so, it also t

provides a passive steam bypass flow of about 10 percent that mitigates the early effects of over pressure transients.

The moisture separator reheater is required to be OPERABLE consistent with the assumptions of the Main Turbine Trip with Turbine Bypass Failure analysis and the Feedwater Controller Failure analysis.

The operation with one or both of the main turbine bypasses inoperable or the moisture separator reheater inoperable to perform preventive or. corrective maintenance above 25 percent RATED THERMAL POWER, requires, after one hour, the evaluation of the MCPR in accordance with Specification 3.2.3.

If the MCPR is within the bounds established by Specification 3.2.3, power increases to or operation above 25 percent RATED THERMAL POWER is allowed.

3/4.7.11 APPENDIX R ALTERNATIVE SHUTDOWN AUXILIARY SYSTEMS The systems. identified in this section are those utilized for Appendix R Alternative shutdown but not included in other sections of the Technical Specifications.

The ACTION statements assure that the auxiliary systems.will be OPERABLE or that acceptable alternative means are established to achieve the same objective.

- There are four independent Combustion Turbine-Generator units onsite.. CTG 11 Unit I has a diesel: engine starter and thus can be started independently from offsite power.

CTG 11 Units 2, 3, and 4 have AC-motor starters and rely on a 480-volt AC feed.

The phrase " alternative source of power", as used in Specification 3.7.11, ACTION b.2, is' defined as a source of power that is not reliant on offsite power for starting (if required) or operating (if already running) and capable of supplying the required loads on the 4160-volt busses

' associated with the Alternative Shutdown System.

'One of the two installed Standby Feedwater Pumps and one of the two listed l

Drywell Cooling Units are necessary for' Appendix R Alternative shutdown.

l Therefore unlimited operation with one of the two components inoperable is l'

justified provided increased surveillance is performed on the components which l

. remain OPERABLE.

l FERMI - UNIT 2 B 3/4 7-5

' Amendment No.39, 59 1

+

PLANT SYSTEMS BASES 3/4.7.11 APPENDIX R ALTERNATIVE SHUTDOWN AUXILIARY SYSTEMS (continued)

The SBFW pump performs a function for Appendix R Alternative Shutdown analogous to RCIC for Remote Shutdown, As such the SBFW Surveillance Requirements are patterned after RCIC Surveillance Requirements, including the flow test capacity requirement.

The specified flow value includes an allowance for normal instrument tolerance above the minimum flow required for adequate core cooling.

t i

I' l

l-FERMI - UNIT 2 B 3/4 7-Sa Amendment No. 59