ML20058G313

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Corrected Amends 59 & 61 to License NPF-43,correcting Text Errors
ML20058G313
Person / Time
Site: Fermi 
(NPF-43-A-059, NPF-43-A-061, NPF-43-A-59, NPF-43-A-61)
Issue date: 11/01/1990
From:
NRC
To:
Shared Package
ML20058G318 List:
References
NUDOCS 9011130059
Download: ML20058G313 (10)
v • d • e


Text

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I!Elu hMIT!NGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS num rm 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ I/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.................

3/4 3-9 3/4.3.3 E8 4 ENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.....................................

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

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

3/4 3-36

--t 3/4.3.6 CONTROL R00 8 LOCK INSTRUMENTATION...................

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

3/4 3-47 Seismic Monitoring Instrumentation..................

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

3/4 3-54 c

Remote Shutdown System Instrumentation and Controls.

3/4 3-57 Accident Monitor.ng Instrumentation.................

3/4 3-60 Source Range Monitors...............................

3/4 3-64 Traversing In- : ore Probe System.....................

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

3/4 3-66 Fire Detection Instrumentation......................

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

3/4 3-70 Radioactive Liquid Effluent Monitoring Instrumentation.....................................

3/4 3-71 Radioactive Gaseous Effluent Monitoring Instrumentation.....................................

3/4 3-76 o

3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM..................

3/4 3-85 3/4.3.9 FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUATION I N ST RUMENT AT ION......................................

3/4 3-86 3/4.3.10 RESERVED 3/4.3.11 APPENDIX R ALTERNATIVE SHUT 00WN INSTRUMENTATION......

3/4 3-90 i

FERMI - UNIT 2 v

Amendment No. U, 59 1

00111300S* 901101 PDR ADOCK 05000341 P

FDC

4-mu i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION pag CONTAINMENT SYSTEMS (Continued) 3/4.6.6 PRIMARY CONTAINNENT ATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen Recombiner f

Systees............................................

3/4 6-57 j

Drywell and Suppression Chamber Oxygen Concentration.

3/4 6-58 3/4.7 PLANT SYSTEM $

i I

3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water Systes...........

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

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

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

3/4 7-5 U l t i ma te He a t S i n k...................................

3/4 7-6 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM.............

3/4 7-8 3/4.7.3 SHORE BARdIER PROTECT!0N.............................

3/4 7-11 i

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

3/4 7-14 3/4.7.5 SNUB B E R S.............................................

3 /4 7-16 l,

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 Spay and/or Spri nkler Sys tees......................... 3/4 7-27 l

CO, Systems..........................................

3/4 7-29 hat on Sy s tems........................................

3/4 7-30 l,

Fire Hose Stations...................................

3/4 7-31 Yard Fire Hydrants and Hydrant Hose House............

3/4 7-36 3/4.7.8 F I RE RAT ED AS SEMB LI E S................................

3/4 7-38 l-3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND M0ISTURE SEPARATOR R EH E AT E R.............................................

3 /4 7-4 0 3/4.7.10 RESEkVED 3/4.7.11 APPENDIX R ALTERNATIVE SHLITDOWN AUXILIARY SYSTEMS....

3/4 7-41 1

FERMI - UNIT 2 viit Amendment No. If,59

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1 Jggg BASES INSTRUMENTATION (Continued)

MONITORING INSTRUMENTATION (Continued)

Meteorological Monitoring Instrumentation....... 8 3/4 3-4 i

Remote Shutdown System Instrumentation and Controls........................................

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 Chlorine Detection Systes.......................

B 3/4 3 5 Fire Detection Instrumentation................... B 3/4 3-5 l

Loose-Part Detection System.....................

B 3/4 3-5 1

Radioactive Liquid Effluent Monitoring Instrumentation.....,...........................

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

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 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 C0OLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM............................

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

B 3/4 4-la i

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.......................

B 3/4 4-2 Operational Leskage.............................

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

B 3/4 4-4 3/4.4.7 MAIN STEAM LINE !$0LATION VALVES................

B 3/4 4-5 3/4.4.8 STRUCTURAL 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. #9, 53, 59

y 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 $HUTD0WN.................... B 3/4 b-1 3/4.5.3

$UPPRE SSION CMAMBER.............................. B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Contai nment Integrity.................... B 3/4 6-1 Primary Containment Leakage...................... B 3/4 6-1 Primary Contai nment Ai r Locks.................... B 3/4 6-la MSIV Leakage Control System...................... B 3/4 6 2 Primary Containment Structural Integrity........

8 3/4 6 2 Drywell and Suppression Chamber Internal P re s s u re....................................... B 3 /4 6-2 Drywell Average Ai r Temperature.................. B 3/4 6-2 Orywell and Suppression Chamber Purge System..... B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS........................

8 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES............. B 3/4 6-6 3/4.6.4 VACUUM RELIEF...................................

8 3/4 6-6 3/4.6.5 SECONDARY CONTAINMENT............................ B 3/4 6-6 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL..........

8 3/4 6-7 FERMI - UNIT 2 xiv Amendment No. gg, 59

Jan

./

BASES

.x M

f.EE 3/4.7 PLANT SYSTEMS

'3/4.7.1 SERVICE WATER SYSTEMS...........................

B 3/4 7-1 3/4.7.2 CONTROL R00M EMERGENCY FILTRATION SYSTEM........

C V4 7-1 3/4.7.3 SHORE BARRIER PR0TECTION........................

B 3/4 7-1 3/4.7.4 REACTOR CORi ISOLATION COOLING SYSTEM...........

B 3/4 7-la 3/4.7.5

$NUBBERS........................................

B 3/4 7-2 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 ASSE2 LIES...........................

B 3/4 7-4 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND MDISTORE l

l SEPARATOR REHEATER..............................

B 3/4 *-5 3/4.7.10 RESERVED 3/4.7.11 APPENDIX R ALTERNATIVE SHUT 00WN AUXILIARY j

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

B 3/4 7-5

{

L 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1,'3/4.8.2.1and.

l 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and DNSITE POWER I

DISTRIBUTION SYSTEMS............................

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

B 3/4 8-3 3/4.9 REFUELING OPERATIONS-t 3/4.9.1 REACTOR MODE SWITCH.............................. B 3/4 9-1 3/4.9.2 I NSTRtMENTAT ! 0N.....................'............ -B 3/4.9-1

'3/4.P.a CONTR0L'R00 P0SITION............................

B'3/4 9-1 n

j

3/4.9 s 'OECAY **ME.......................................

B 3/4 9-1 E'

3/4.9.S' C0WRJN I CATI ONS...................... s........... B 3/4 9-1

, 3/A.9.6-REFUE LING PLATF0RM..............................

B 3/4 9-2' x

.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 WAT ER LEVEL - SPENT FUEL STORAGE P00L.......

B 3/4 9 2 3/4.-9.10 CONTROL R00 REM 0 VAL.............................

B 3/4 9-2 FERMI;- UNIT 2 xv Amendment No. If, SI. 59'-

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I! Ell BASES 11.9119!!

PAGE r

i 3/4.9 REFUELINGOPERAI,10NS(Continued) 3/4.9.11 RE.SIDl; AEAT REMOVAL AND COOLANT CIRCULATION...

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIE RY CONTAINMENT INTEGRITY...................

8 3/4 10-1 3/4.10.2 R00 SEQUENCE CONTROL 5YSTEM.....................

8 3/4 10-1 3/4.10.3 SHUTDOWN MRGIN DEMONSTRATIONS..................

8 3/4 10-1 3/4.10.4 RECIRCULATION L00PS.............................

8 3/4 10-1 3/4.10.5' DELETED........................................

8 3/4 10-1 3/4.10.6 TRAINING STARTUPS...............................

8 3/4 10-1 I

i Amendment No. d6, 59 FERMI - UNIT 2 xvi

g LIST OF TABLES (Continued)

,Tjpg PAGE 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION.................. 3/4 3-68 3.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION................................

3/4 3-72 4.3.7.13-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-74

. 3.3.7.12-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION................................

3/4 3-77 4.3.7.12-1 RADI0 ACTIVE GASEQUS EFFLUENT MONITORING L

INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-81 3.3.9-1

~ FEEDWATER/ MAIN TUR81NE TRIP SYSTEM ACTUATION l

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 l

3,4~3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS.............................

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

3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND L

ANALYSI S PROGRAM..............................

3/4 4-18 4.4.6.1.3-1

- REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITH0RAWAL SCHEDULE............................

3/4 4-22 4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED IN LOC KED HIGH RADI ATION AREAS.........

3/4 6-35 E

3.6.3-1 PRIMARY 00KTAIMMENT 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 8ARRIER................

3/4 7-12

. 3.7.7.5-1

. FIRE H0SE STATIONS..............................

3/4 7-32

- 3.7.7.6-1 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT.......

3/4 7-37 H0SE MOUSE

)

4. 8.1.1. 2-1 DIESEL GENERATOR TEST SCHEDULE.................

3/4 8-8 FERMI - UNIT 2' xxiv Amendment No. Ay, 59

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___________________.,_____i

INSTRUMENTATION BASES' MONITORING INSTRUMENTATION (Continued) 3/4.3.7.8 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine 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 system required by this specification is consistent with the recommendatix.s of Regulatory Guide 1.95

" Protection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release", Revision 1, January,1977.

M4.3.7.9 FIRE DETECTION INSTRUMENTATION OPERABILITY of the detection instrumentation ensures that both acquate warning capability is available for prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will dischar3e 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.

Fire 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.

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

The loss of detection capability for fire suppression systems, actuated by I

fire detectors, represents a significant degradation of protection for any area, l

As a result, the establishment of a fire watch patrol must be initiated at an i

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 l

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 RADI0 ACTIVE LIOVID EFFLVENT 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 and parameters in the ODCH to ensure that the FERMI - UNIT 2 B 3/4 3-5

e TABLE'3.6.3 1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES TABLE NOTATIONS (Continued)

(k) Will automatically close when a) RCIC Turbine Steam Stop Valve E51-F045 closes or b) RCIC Turbine Governor Trip and Throttle Valve E51-F059 J

closes.

(1) Will. automatically close as a result of the conditions listad in Note (i) above, as well as when RCIC flow is. greater than 130 gpm.

(m) These-valves are actuated by remote manual key-locked switches and will cut the TIP cable and seal off the TIP guide tube when actuated.

These valves are squib-fired.

L (n) Hay be closed remotely as a secondary actuation mode to reverse flow.

(o) Valves. realign automatically en a reactor scram signal.

g f

(p) Thermal relief valves.

(q) Locked closed.

j (r) Not subject to Type C leakage tests.

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FERMI - UNIT 2' 3/4 6-47

a CONT'dNMENT SYSTEMS 3/4.6.4 VACUUM RELIEF S PPRESSION CHAMBER - DRYWELL VACVVM BREAKERS LIMITING CONDITION FOR OPERATION 3.6.4.1 All suppression chamber - drywell vacuum breakers shall be closed and at least 10 vacuum breakers shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With one of the above required vacuum breakers inoperable for opening but kno.:n to be closed, restore the inoperable vacuum breaker 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 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 one or more suppression chamber - drywell vacuum breakers open, close the open vacuum breaker (s) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least H0T SHVTDOWN 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 />.

c.

With one of the position indicators of any suppression chamber -

drywell vacuum breakers inoperable, verify that all other vacumn breakers are closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and:

1.

Verify the vacuum breaker (s) with the inoperable position indicator to be closed by demonstrating the other indicator to be OPERABLE within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per 14 days thereafter, or 2.

Verify the vacuum breaker (s) with the inoperable position indicator to be closed by conducting a test which demonstrates that the drywell-to-suppression chamber AP is maintained at-greater than or equal to 0.5 psi for one hour without makeup within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 14 days thereafter.

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 SHVIDOWN 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 of the closed position indicators of one or more suppression chamber - drywell vacuum breaker (s) indicating open and the redundant closed position indicator indicating closed after a suppression chamber - drywell vacuum breaker opening as a result of a steam release, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, cycle the. applicable valve (s) to determine which of the redundant indicators is OPERABLE.

FERMI - UNIT 2 3/4 6-48 Amendment No. M,61

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