Text

Modified App R Tech Specs Re Alternative Shutdown Instrumentation
	ML20244B179
Person / Time
Site:	Fermi
Issue date:	05/31/1989
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20244B167	List: ML20244B179; NRC-89-0111, Forwards Modified App R Tech Specs Re Alternate Shutdown Sys,Per Discussions W/Nrc.Mod Involves Action & Surveillance Requirements for Power Supply Designated for Alternative Shutdown;
References
	NUDOCS 8906130009
	Download: ML20244B179 (12)
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NCDIFIED APPENDIX R M CAL SPECIFICATIONS i

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I 8906130009 890531 PDR ADOCK 05000341 P- PDC

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l 3/4.3.11 ATM70IX R ALTERI%TIVE SIKT1DORN INSTRUMENTATION LIMITI?G 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 tne ntmber of OPERABLE alternative shutdown monitoring instrumentation channels less than required, take the ACTION required by Table 3.3.11-1. The provisions of Specification 3.0.4 are not applicable.

SUWEILLAtCE luotumENTS:

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

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TABLE 3.3.11-1

.e APPEf0IX R ALTERNATIVE SHU'IDNN INSTRUMENTATION MINIM M CHANNELS INSTRMENT CPERABIE ACTION l1.' C'M 11 Unit- 1-Volts 1 131

2. C7U 11 Unit 1-Frequency. 1 131

3. C7G 11 Unit .1-Watts 1 131

- 4. CTG 11 Unit 1-Vars 1 131

5. Condensate Storage Tank Level 1 132 6.. Standby Feedwater Flow 1 132.

7. - Reactor Water Level 1 133 J8. Reactor Pressure- 1 133

'9. Torus Water Temperature 1 133

10. Torus Water Level 1 133

11. Primary Containment Temperature 1 133 ACTION EmmBENTS ACTION 131 - Declare C7G 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 status within 7 days or be in at least HOT SHU7DOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHU7DOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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l' TABLE 4.3.11.1-1 APPE!OIX R ALTERfRTIVE SHU7DOWN INSTRLMENIATION SUH/EILLANCE REQUIREMDCS CHANNEL CHANNEL INSTEMENT CHECK CALIBRATION

' l. ~ C'IG 11 Unit 1-Volts 'M R.

- 2. , CTG 11 Unit 1-Frequency :

M R

13. ' CTG 11 Unit 1-Watts M R

4. C2G 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

10. Torus Water Level M 'R

11. Primary Containment Temperature. M R-

7-3/4.7.11' APPENDIX R ALTERNATIVE SHUTDNN AUXILTARY SYSTmS LIMITING CONDITION FOR OPERATION:

3.7.11 The Apperrlix R Alternative Shutdown auxiliary systems shall be OPERABLE as' described below:

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

b. An OPERABLE C7G 11 Unit 1 and power train capable of'

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supplying power to the Peaker Buc.

c. 'No OPERABLE Drywell Cooling Units (Units 1 and 2) consisting of a fan and cooling coil capable of being supplied with cooling water from the EBCW system.

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

APPLICABILITY: OPERATIONAL C010ITIONS 1, 2, and 3 ACTION:

a.- For the SBN system:

1. With one SBN pump inoperable, within 7 days and at -

least once per 31 days thereafter, perform Surveillance Requirement 4.7.ll.l.b, using the OPERABLE SBFW pump. 'Ihe OPERABLE SBFW pump need not be tested more frequently than once per 31 days. Otherwise, be in at least HOT SHUTDO4N within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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2. With the SBFW system otherwise inoperable, restore l the system to OPERABLE status within 7 days or be in at least HCTf SHUIDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUIDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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b. With an inoperable C7G 11 Unit 1:

1. Verify within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the 120 KV bus is available by performing Surveillance Requirement 4.8.1.1.1, and

2. Within 7 days, restore the C7G 11 Unit 1 to OPERABLE status or provide an alternative source of power to the Alternative Shutdown bus.

Otherwise, be in at least HCTP SHU7DONN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SIUIDONN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. For the Drywell Cooling System:

1. With one drywell cooling unit inoperable, within 7 '

l days and at least once per 31 days thereaf ter, perform Surveillance' Requirement 4.7.11.3 using the OPEFABLE Drywell Cooling Unit. The OPERABLE Drywell Cooling Unic need not be tested more frequently than once per 31 days. Otherwise, be in at least HOT SHUIDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHU7DONN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . I

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 SHUTDONN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SIKUDONN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. With one or more required alternative shutdown system control circuits inoperable, restore the inoperable circuits to OPERABLE status within 7 days or be in at least HOT SHU7DONN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in CGD SHU7DONN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . !

e. The provisions of Specification 3.0.4 are not applicable.

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4.7.11.1 The SBEW system shall be demonstrated OPERABLE:

a. At least once every 31 days by:

1. Verifying by venting at the high point vents that the system piping from the pump discharge to the system isolation valves is 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 corrtet 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.

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4.7.11.2 C7U 11 Unit 1 shall be demonstrated OPERABLE by starting ard supplying load of at least 10 F4f 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 IMGIS by operating the unit for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months with the f an 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.

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BASES B 3/4.3.11 APPENDIX R ALTERNATIVE SIRTIDG4N 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. 'Ihus, the system capability is consistent with General Design Criterion 3 and Appendix R to 10CFR50.

B 3/4.7.11 APPENDIX R ALTERPRTIVE SIRTIDOWN AUXILIARY SYSTDiS 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.

C'IG 11 Unit I has a diesel engine starter and thus can be started independently from offsite power. C'IU 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 Drywell Cooling Units are necessary for Appendix R Alternative shutdown. Therefore unlimited operation with one of the two components inoperable is justified provided increased surveillance is performed on the components which remain OPERABLE. ;

The SBFW pump performs a function for Appendix R Alternative Shutdown analogous to RCIC for Remote Shutdown. As such the SBFW Surveillance i Requirements are patterned after BCIC Surveillance Requirements, j including the flow test capacity requirement. The specified flow value includes an allowance for normal instrument tolerance above the minimum flow requiroS for adequate core cooling.

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 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 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 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 Monitors................................ 3/4 3-64 Traversing In-Core 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

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

3/4 3-85 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION....................................... 3/4 3-86

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3/4 3. II AffENOfK fl. A LT Eltud T I U E .fr{llTOcWU SW.sTit is IH G WTA TI C hl e____-___________

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen Recombiner 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 FILTRATION SYSTEM. . . . . . . . . . . . . 3/4 7-8 3/4.7.3 SHORE BARRIER PROTECTION............................. 3/4 7-11 i

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3/4.7.4 REACTOR CORE - ISOLATION COOLING SYSTEM. . . . . . . . . . . . . . . . 3/4 7-14 3/4.7.5 SNUBBERS.............................................. 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 Spray and/or Sprinkler Systems. . . . . . . . . . . . . . . . . . . . . . . 3/4 7-27 CO Systems..........................................

3/4 7-29 2

Hal on Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-30 F i re Ho s e Stati ons. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-31 Yard Fire Hydrants and Hydrant Hose Houses........... 3/4 7-36 3/4 7-38

'3/4.7.8 FIRE RATED ASSEMBLIES................................

3/4 7-40

-b 3/4.7.9 MAIN TURBINE BYPASS SYSTEM...........................

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3l4 7, II A PP E WO ik R . M TERWA TWE SH U YOO4/M A UKIL.YAlt *r S Y STEk4S :

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INDEX

.i BASES PAGE SECTION .

INSTRUMENTATION (Continued)

. MONITORING INSTRUMENTATION (Continued)

Meteorological ~ Nonitoring Instrumentation....... B 3/4 3-4 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 System....................... B 3/4 3-5 Fire Detection Instrumentation.................. B 3/4 3-5 Loose-Part Detection System..................... B 3/4 3-5 l

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

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

B 3/4 3-6 a

TURBINE OVERSPEED PROTECTION SYSTEM............. B 3/4 3-6 3/4.3.8 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEMS ACTUATION INSTRUMENTATION................................. B 3/4 3-6 3/4 3,ro gesegu J /'/. 7,// #//N'* 't Al-TE cN4'u a 3/4.4 REACTOR COOLANT SYSTE 9 tivT17 cevy 7pyrteu rne ctA Tico 3/4.4.1 RECIRCULATION SYSTEM............................ B 3/4 41 B 3/4 41 3/4.4.2 SAFETY / RELIEF VALVES............................

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems....................... B 3/4 4-2 B 3/4 4-2 Operational Leakage.............................

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

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

B 3/4 4-4 3/4.4.6 PRESSURE / TEMPERATURE LIMITS.....................

B 3/4 4-5 3/4.4.7 MAI'J STEAM LINE ISOLATION VALVES. . . . . . . . . . . . . . . .

B 3/4 4-5

' 3/4.4.8 STRUCTURALINTEGRITY........T...................

< B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REM 0 VAL...........................

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BASES PAGE SECTION .

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 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . . . . . B 3/4 7-1 3/4.7.5 SNUBBERS........................................

B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION..................... B 3/4 7-4 FIRE SUPPRESSION SYSTEMS........................

B 3/4 7-4 3/4.7.7 8 3/4 7-4 3/4.7.8 FIRE RATED ASSEMBLIES...........................

MAIN TURBINE BYPASS SYSTEM......................

B 3/4 7-5 3/4.7.9 s/4 710 stGsaRven

/f 7r 81P E @ t v /t OTPAM#'E 3/4.8 ELECTRICAL POWER SYSTE k 3/'/ SHuTDowA) AUxit/ARY S Y %

3 /4.8.1, 3/4.8.2, and 3/4.8.3. A.C. SOURCES, D.C. SOURCES, and ONSITE POWER B 3/4 8-1 DISTRIBUTION SYSTEMS............................

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

3/4.9 REFUELING OPERATIONS B 3/4 9-1 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 C019tVN ICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4 9-2 3/4.9.6 REFUELING PLATF0RM..............................

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

3/4.9.8 and 3/4.9.9 WATEP LEVEL - REACTOR VESSEL B 3/4 9-2 and WATER LEVEL - SPENT FUEL STORAGE P00L.......

B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL.............................

(' B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...

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ML20244B179

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