Text

Proposed Tech Specs,Revised to Be Consistent W/Current Plant Conditions & Operations & to Provide Transition Through Remainder of Cleanup of Facility
	ML20210C901
Person / Time
Site:	Three Mile Island
Issue date:	04/23/1987
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20210C858	List: ML20210C856; ML20210C865; ML20210C901;
References
	NUDOCS 8705060357
	Download: ML20210C901 (88)
	v • d • e

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l THREE MILE ISLAND NUCLEAR STATION UNIT 2 Technical Specifications Appendix A to License No. DPR-73

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6 INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 DEFINED TERMS.................................................... 1-1 1.2 REC 0VERY OP E RATIONS P LAN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.3 M00E............................................................. 1-1 1.4 ACTI0N........................................................... 1-1 1.5 OPERABLE - OPERABILITY........................................... 1-1 1.6 REPORTABLE EVENT................................................. 1-1 1.7 CONTAINMENT INTEGRITY............................................ 1-2 1.8 CHANNEL CALIBRATION.............................................. 1-2 1.9 CHANNEL CHECK.................................................... 1-2 1.10 CHANNEL FUNCTIONAL TEST.......................................... 1-3 1.11 STAGGERED TEST BASIS............................................. 1-3 1.12 FREQUENCY N0TATION............................................... 1-3 1.13 FIRE SUPPRESSION WATER SYSTEM.................................... 1-3 1.14 REVIEW SIGNIFICANCE.............................................. 1-3 1.15 CORE ALTERATION.................................................. 1-4 1.16 LOSS TO AMBIENT.................................................. 1-4 1.17 ACCIDENT GENERATED WATER......................................... 1-4 1.18 LICENSED OPERATOR (0L)........................................... 1-4 1.19 SENIOR LICENSED OPERATOR (50L)................................... 1-4 1.20 FUEL HANDLING SENIOR LICENSED OPERATOR (50L-FH).................. 1-4 1.21 CONTAINMENT IS0LATION............................................ 1-4 FACILITY MODE (TABLE I.1)............................................. 1-5 FREQUENCY NOTATION (TABLE 1.2)........................................ 1-6 THREE MILE ISLAND - UNIT 2 I ,

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ADMINISTRATIVE CONTROLE SECTION PAGE 2.0 SAFETY LIMITS................................................... 2-1 ;

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,5m INDEX- .

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE !

3.0 A P P L I CA B I L I T( . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.0-1 3.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 3.1.1 BORATION 00NTROL.......................................... 3.1-1 BORATED COOLING HATER INJECTION............................ 3.1 . BORON CONCENTRATION REACTOR COOLANT SYSTEM............... 3.1-2 BORON CONCENTRATION - FUEL TRANSFER CANAL.................. 3.1-3 BORON CONCENTRATION - SPENT FUEL POOL "A".................. 3.1-4 3.3 INSTRUMENTATION 3.3.1 NEUTRON HONITORING INSTRUMENTATION......................... 3.3-1 INTERMEDIATE AND SOURCE RANGE NEUTRON FLUX MONITORS........ 3.3-1 3.3.2 ENGINEERdDSAFETYFEATUREACTUATIONSYSTEMINSTRUMENTATION. 3.3-2 3.3.3 MONITORING INSTRUMENTATION................................. 3.3-3 :

RADIATION MONITORING INSTRUMENTATION....................... 3.3-3 METEOROLOGICAL INSTRUMENTATION.............'............... . 3.3-4 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION............ 3.3-5 CHLORINE DETECTION SYSTEMS................................. 3.3-6 FIRE DETECTION INSTRUMENTATION............................. 3.3-7 s 3.4 REACTOR COOLANT SYSTEM 3.4.1 REACTOR COOLANT L00PS...................................... 3.4-1 3.4.1 REACTOR VESSEL HATER LEVEL M0NITORING...................... 3.4-2 3.4.9 PRESSURE / TEMPERATURE LIMITS................................ 3.4-3 REACTOR COOLANT SYSTEM..................................... 3.4-3 3.S COMMUNICATIONS 3.5.1 CONTROL R00H............................................... 3.5-1 THREE MILE ISLAND - UNIT 2 III

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INDEX LIMITING CONDITIONS ~FOR OPERATION SECTION PAGE

3.6 CONTAINMENT SYSTEMS 3.6.1 PRIMARY CONTAINMENT........................................ 3.6-1 CONTAINMENT INTEGRITY...................................... 3.6-1 CONTAINMENT IS0LATION...................................... 3.6-4 CONTAINMENT AIR LOCKS ( MODE 1 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-S INTERNAL PRESSURE.......................................... 3.6-6

-AIR TEMPERATURE............................................ 3.6-7 CONTAINMENT AIR LOCKS (MODES 2 AND 3)...................... 3.6-8 3.6.3 - CONTAINMENT PURGE EXHAUST SYSTEM........................... -3.6-9 a

3.7 PLANT SYSTEMS 3.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM......................... 3.7-1 3.7.6 FLOOD PROTECTION........................................... 3.7-2 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.................. 3.7-4 3.7.9 SEALED S00RCES............................................. 3.7-5 3.7.10 FIRE SUPPRESSION SYSTEMS................................... 3.7-6

. FIRE SUPPRESSION WATER SYSTEM.............................. 3.7-6 DELUGE / SPRINKLER SYSTEMS................................... 3.7-7 HALON SYSTEM............................................... 3.7-8 FIRE HOSE STATIONS......................................... 3.7-9 PENETRATION FIRE BARRIERS.................................. 3.7-10

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3.8 ELECTRICAL POMER SYSTEMS 3.8.1 A.C. SOURCES............................................... 3.8-1 3.8.2 ONSITE POMER DISTRIBUTION SYSTEMS.......................... 3.8-4 A.C. DISTRIBUTION.......................................... 3.8-4 D.C. DISTRIBUTION.......................................... 3.8-S

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INDEX LIMITING ODNDITIONS FOR OPERATION SECTION PAGE 3.9 RADIOACTIVE MATERIALS STORAGE 3.9.1- SPENT FUEL STORAGE POOL."A" NATER LEVEL MONITORING......... '3.9-1 3.9.2 SPENT FUEL STORAGE POOL "A" WATER LEVEL.................... 3.9 ,

3.9.3 FUEL TRANSFER CANAL (DEEP ~END) NATER LEVEL MONITORING...... 3.9-3 3.9.4 FUEL TRANSFER CANAL (DEEP END) HATER LEVEL................. 3.9-4 3.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING.................. 3.9-5 AIR CLEANUP SYSTEMS' FUEL HANDLING BUILDING AIR CLEANUP SYSTEM.................. 3.9-5 AUXILIARY BUILDING AIR CLEANUP EXHAUST SYSTEM.............. 3.9-5 3.9.13 ACCIDENT GENERATED WATER................................... 3.9-6 3.10 CRANE OPERATIONS 3.10.1 CONTAINMENT BUILDING....................................... 3.10-1 3.10.2 FUEL HANDLING BUILDING..................................... 3.10-2 I

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INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY.............................................. B 3/4.0-1 3/4.1 HATER INJECTION'C00 LING AND REACTIVITY CONTROL SYSTEMS..... B 3/4.1-1 3/4.1.1 B0 RATION-CONTROL AND BORATED COOLING HATER INJECTION... B 3/4.1-1 3/4.3 INSTRUMENTATION 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION..................... B 3/4.3-1 3/4.3.2 DELETED................................................ B 3/4.3-1 3/4.3.3 MONITORING. INSTRUMENTATION............................. B 3/4.3-1 RADIATION MONITORING INSTRUMENTATION................... B 3/4.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION.............. B 3/4.3-1 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION........ B 3/4.3-1 CHLORINE DETECTION SYSTEMS............................. B 3/4.3-1 FIRE DETECTION INSTRUMENTATION......................... B 3/4.3-2 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 R EACTOR COO LA N T L00P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.4-1 3/4.4.2 REACTOR VESSEL HATER LEVEL MONITORING.................. B 3/4.4-1 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................ B 3/4.4-1 3/4.5 COMMUNICATIONS............................................. B3/4.5-1 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...................... ............. B 3/4.6-1 CONTAINMENT INTEGRITY.................................. B 3/4.6-1 .

CONTAINMENT IS0LATION.................................. B 3/4.6-1 CONTAINMENT AIRLOCKS (MODE 1).......................... 8 3/4.6-1 INTERNAL PRESSURE...................................... B 3/4.6-1 l AIR TEMPERATURE........................................ B 3/4.6-1 .i CONTAINMENT AIRLOCKS (MODES 2 AND 3)................... B 3/4.6-2 3/4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM....................... B 3/4.6-2 l I

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-INDEX l RASES 4

SECTION :PAGE 3/4.7' PLANT SYSTEMS

. B 3/4.7-1 3/4'.7.4 NUCLEAR SERVICE-RIVER WATER; SYSTEM..................... -

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3/4.7.6 FLOOD PROTECTION....................................... B 3/4.7-1 j 3/4.7.7 CONTROL ROOM ~ EMERGENCY AIR CLEANUP SYSTEM.............. B 3/4.7-1 3/4.7.9 SEALED SOURCE INTEGRITY................................ B-3/4.7-1 B 3/4.7-1 i

3/4.7.10-.. FIRE SUPPRESSION SYSTEMS...............................-

3/4.7.11 - PENETRATION FIRE BARRIERS.............................. - B 3/4.7-2 B 3/4.8-1; 3/4.8 ELECTRICAL POWER SYSTEMS...................................

3/4.9. RADI0 ACTIVE WASTE STORAGE l~

. 3/4.9.1 SPENT FUEL STORAGE 1 POOL "A" WATER LEVEL MONITORING..... B 3/4.9-1 B 3/4.9-1 3/4.9.2 SPENT FUEL' STORAGE POOL "A" WATER LEVEL................

3/4.9.3 FUEL TRANSFER CANAL.(DEEP END) WATER LEVEL............. ; B 3/4.9-1 1 MONITORING' 3/4.9.4 FUEL TRANSFER CANAL (DEEP END) HATER LEVEL............. B 3/4.9-1 1

i 3/4.9.12 FUEL HANDLING BUILDING AIR-CLEANUP SYSTEM.............. B 3/4.9-1 AUXILIARY BUILDING AIR CLEANUP SYSTEM.................. B 3/4.9-1.

3/4.9.13 ACCIDENT GENERATED WATER............................... B 3/4.9-1 3/4.10 CRANE OPERATIONS....................................... . .. B 3/4.10-1 3/4.10.1 CRANE OPERATIONS - CONTAINMENT BUILDING................ . B_3/4.10-1 3/4.10.2 CRANE OPERATIONS - FUEL HANDLING BUILDING.............. . B 3/4.10-1; f

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INDEX l 1

DESIGN FEATURES SECTION PAGE 5.1 SITE 5.1.1 EXCLUSION AREA............................................. 1 5.1.2 LOW POPU LAT ION Z0N E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.3 SITE BOUNDARY FOR GASE0US EFFLUENTS. . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.4 SITE BOUNDARY FOR LIQUID EFFLUENTS. . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2 CONTAINMENT 5.2.1 CONFIGURATION.............................................. 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE............................ 5-1 5.4 REACTOR COOLANT SYSTEM 5.4.1 DELETED.................................................... 5-4 5.4.2 V0LUME..................................................... 5-4 5.5 METEOROLOGICAL TOWER L0 CATION.................................... 5-4 THREE MILE ISLAND - UNIT 2 VIII 0127P

INDEX ADMINISTRATIVE CONTROLS' SECTION PAGE-6.1 RESPONSIBILITY................................................... 6-1 6.2 ORGANIZATION 6.2.1 GPUNC ORGANIZATION......................................... 6-1 6.2.2 THI-2 ORGANIZATION......................................... 6-1 6.3 UNI T STAF F QUALI FICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-3 6.4 TRAINING......................................................... 6-3 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTR0L............................... 6-5 6.5.1.10 REC 0RDS.................................................... 6-5 6.5.1.11 QUALIFICATIONS............................................. 6-5 6.5.2 ~ INDEPENDENT SAFETY REVIEH.................................. 6-5 6.5.2.1 FUNCTION................................................... 6-5 6.5.2.5 RESP 0NSIBILITIES........................................... 6-6 6.5.2.7 REC 0RDS.................................................... 6-7 6.5.3 AUDITS..................................................... 6-7 6.5.3.2 REC 0RDS.................................................... 6-7 6.5.4 SAFETY REVIEH GROUP (SRG).................................. 6-8 6.5.4.1 FUNCTION................................................... 6-8 6.5.4.2 ORGANIZATION............................................... 6-8 6.5.4.3 RESPONSIBILITY............................................. 6-9 6.5.4.6 AUTHORITY.................................................. 6-9 6.5.4.7 QUALIFICATIONS............................................. 6-9 6.5.4.8 REC 0RDS.................................................... 6-10 6.6 REPORTABLE EVENTS ACTI0N......................................... 6-10 6.8 PROCEDURES....................................................... 6-10 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES................. 6-11 6.9.1.4 ANNUAL REP 0RTS............................................. 6-12 6.9.2 SPECIAL REP 0RTS............................................ 6-14 6.10 RECORD RETENTION................................................ 6-14 6.11 RADIATION PROTECTION PR0 GRAM.................................... 6-16 6.12 HIGH RADIATION AREA............................................. 6-16 THREE MILE ISLAND ' UNIT 2 IX 0127P

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- 1:0 DEFINITIONS

!. DEFINED ~ TERMS 1.1- The. DEFINED TERMS of this section appear in capitalized type r nd a are?

applicable-throughout.these Technical Specifications.

RECOVERY OPERATIONS PLAN

' l.2 The RECOVERY OPERATIONS PLAN shall define the ' surveillance requirements

. to be performed to ensure equipment operability as required-by the Limiting Conditions for Operation. This plan, and changes thereto, shall be approved

. by the-Commission prior to implementation.

MODE 1.3 The FACILITY MODE shall correspond to the plant conditions specified in Table 1.1.

ACTION 1.4 ACTION shall be those additional requirements specified as corollary statements to each :pecification and shall be part'of the. specifications.

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< OPERABLE - OPERABILITY i 1.5 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary

' attendant instrumentation, controls, normal and emergency electrical- power -

sources, cooling or seal water, lubrication or other. auxiliary equipment, that

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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).

REPORTABLE EVENT 1.6 A REPORTABLE EVENT shall be any of those conditions specified in.Section 50.73 of 10 CFR Part 50.

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11.0 DEFINITIONS- jl CONTAINMENT INTEGRITY l

1.7 ~ CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closed during accident conditions, except' those' listed in Table 3.6.2,-are.either:

1. Capable of being closed by' valves.on each' side of the penetration

.or by_ double valve ~1 solation outside of.the reactor building per procedures approved pursuant to Specification 6.8.2. or;

12. Closed by manual valves,-blind flanges, or deactivated automatic valves secured in their closed positions to provide double isolation of each penetration.

it. The Equipment Hatch is closed and. sealed.

-c. 'Each airlock is OPERABLE pursuant to Specification 3.6.1.3.

d. The sealing mechanism _a'ssociated with each penetration (e.g., welds, bellows or 0-rings):1s OPERABLE.

CHANNEL CALIBRATION

1.8 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of-the~

! channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. - The' CHANNEL

CALIBRATION shall encompass the entire channel including the~ sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL. TEST. CHANNEL ,

CALIBRATION may be performed by any series of sequential, overlapping or. total channel steps such that the entire channel is calibrated.

CHANNEL CHEcr, 1.9 A CHANNEL CHECK shall be the qualitative assessment of channel behavior-during operation by observation. This determination'shall include,'where 4

possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels.

measuring.the same parameter.

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1.0 DEFINITIONS CHANNEL FUNCTIONAL TEST

-1.10 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as -

close to the primary sensor as practicable-to verify OPERABILITY

' including alarm and/or trip functions.

b. B1 stable channels - the injection of a simulated signal into the channel-sensor to verify OPERABILITY including alarm and/or trip functions.

STAGGERED TEST BASIS 1.11 A STAGGERED TEST BASIS shall consist of:

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

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

FREQUENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined in Table 1.2.

FIRE SUPPRESSION HATER SYSTEM 1.13 A FIRE SUPPRESSION HATER SYSTEM shall consist of: a water source; gravity tank or pumps; and distribution piping and associated sectionalizing control or isolation valves. Such valves shall include yard hydrant curb valves, and the first valve upstream of the water flow alarm device on each sprinkler, hose standpipe or spray system riser.

REVIEW SIGNIFICANT 1.14 REVIEW SIGNIFICANT items shall consist of items that are Important to Safety, or proposed changes to Technical Specifications, License, Special Orders or Agreements, Recovery Operations Plan, Organization Plan, or involve an Unreviewed Safety Question or a Significant Environmental Impact. Also,

, those system operating procedures and associated emergency, abnormal, alarm response procedures which require NRC approval. In addition, those activities not covered by an NRC approved system description, SER or TER and which exceed PEIS values.

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1.0 DEFINITIONS CORE ALTERATION-1.15 CORE ALTERATION shall be the movement or nanipulation of any reactor component (including fuel) within the reactor pressure. vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not

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preclude completion of movement of.a component to a safe conservative position.

LOSS-TO-AMBIENT 1.16 LOSS-TO-AMBIENT is a passive cooling mode by which decay' heat, generated-by the reactor core, is removed and transferred to the surrounding environment by air and passive components (i.e., Reactor Vessel) inside the Reactor Building.

ACCIDENT GENERATED WATER 1.17 ACCIDENT GENERATED WATER, as defined in the settlement of the City of Lancaster litigation, 1s:

a. Water the existed in the THI-2 Auxiliary, Fuel Handling, and Containment Buildings including the primary system as of October 16, 1979, with the exception of water which as a result of decontamination operations becomes commingled with non-accident generated water such that the commingled water has a tritium content of 0.025 uC1/ml or less before processing;

b. Water that has a total activity of greater than one uC1/ml prior to processing except where such water is originally non-accident water and becomes contaminated by use in cleanup;

, c. Water that contains greater than 0.025 uCi/mi of tritium before processing.

1.18 LICENSED OPEPATOR (OL) - any individual who possesses an NRC Operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operators Licenses."

1.19 SENIOR LICENSED OPERATOR (SOM - any individual who possesses an NRC Senior Operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operators Licenses."

l.20 FUEL HANDLING SENIOR LICENSED OPERATOR (SOL-FH) - an individual licensed by the Nuclear Regulatory Commission to supervise fuel handling and core alterations operations.

1.21 CONTAINMENT ISOLATION shall exist when:

a. Each penetration is closed by a manual valve, a welded or bolted blind or a deactivated automatic valve secured in the closed position flange,ide to prov isolation of each penetration.

b. The Equipment Hatch is closed and sealed,

c. Each Containment Airlock is OPERABLE pursuant to Specification 3.6.1.6.

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i TABLE:1.1-l FACILITY-MODES-PLANT CONDITZON MODE 1- The-reactor,shall'_be subcritical'with an' average- !

reactor coolant temperature of less than 200*F.

-2 Mode 2 shall exist when the following conditions are<

met:

a. The Reactor Vessel is defueled to the exten't reasonably achievable,

b. The possibility of criticality in the Reactor Building is precluded.

c. There are no-canisters containing core material in.

the Reactor Building.

3 Mode 3 shall exist when the conditions for Mode 2 are:

met and no canisters containing core material'are stored on the THI-2 site.

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TABLE 1.2 ,

FREQUENCY NOTATION NOTATION FREQUENCY:

S_. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , i

D At least once'per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

N At least once per 7 days.

M At,least'onc'e per 31 days.

Q At-_least once per.92 days.

-SA At least once per 184 days.

A At'least once per 12 months.

R At least once per 18 months.

N.A. Not applicable.

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i SECTION 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 0127P

2.0 SAFETY LIMITS

.There are no safety limits which apply to THI-2.

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i SECTION 3.0 LIMITING CONDITIONS FOR OPERATION 0127P

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3.0 APPLICABILITY. l, LIMITING CONDITIONS FOR OPERATION f -

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3.0.1 Limiting Conditions for Operation and ACTION requirements shall be !

applicable during the FACILITY'M00E or other conditions specified for each ~l 1 specification.

3.0.2 Adherence to the requirements of the ' Limiting Condition for Operation !

and/or associated ACTION within the specified time interval shall constitute i compliance with the specification. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 In the event a Limiting Condition for Operation and/or associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the-specification, initiate appropriate actions to rectify.

the problem to the extent possible under the circumstances and submit a report to the Commission pursuant to the requirements of 50.73 of 10 CFR Part 50.

THREE MILE ISLAND - UNIT 2, 3.0-1 0127P

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3.1 HATER INJECTION COOLING AND REACTIVITY' CONTROL' SYSTEMS' 1 -;

3.1.1 'BORATION-CONTROL' l

BORATED COOLING NATER INJECTION LIMITING CONDITIONS FOR OPERATION 1

3.1.1.1 The.following systems, capable of injecting borated cooling water- i into the Reactor. Coolant System, shall be OPERABLE with:

a. Two operable flowpaths downstream from the Borated Water Storage Tank and common drop line.

b. Dedicated on-site equipment for a Reactor Building. Sump-Recirculation System.

c. .The BHST shall contain at least~390,000 gallons of borated water except U .as changed per procedures approved pursucnt to Specification 6.8.2 at_a' minimum temperature of 50-degrees Fahrenhelt and a boron concentration of between 4350 and 6000 ppm.

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APPLICABILITYi MODE 1 ACTION

! a. With one flowpath from the BHST inoperable, restore to OPERABLE status or j establish an alternate flowpath within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

! b. With both flowpaths from the BHST inoperable,' suspend all operations involving CORE ALTERATIONS and/or the Reactor Coolant System and restore the inoperable flowpaths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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c. With the dedicated Reactor Building Sump Recirculation System inoperable, restore to OPERASLE status within 7 days.

d. With-the BHST water volume, boron concentration or minimum temperature l out-of-specification, suspend all operations involving CORE ALTERATIONS-and/or the Reactor Coolant System and restore the BHST to specification within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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BORON CONCENTRATION - REACTOR COOLANT SYSTEM LIMITING CONDITIONS FOR OPERATION 3.1.1.2 The boron concentration of the coolant-in all filled portions.of the Reactor Coolant System shall be maintained between 4350 and 6000 ppm and at a

. temperature above 50*F.

APPLICABILITY: ' MODE 1 ACTION If either of the above conditions are not satisfied (Boron Concentration between 4350 and 6000 ppm and temperature above 50*F) immediately suspend all activities involving CORE ALTERATION and/or the Reactor Coolant System and take. action in accordance with Specification 3.0.3 to restore the concentration to within acceptable limits.

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BORON CONCENTRATION - FUEL TRANSFER CANAL LIMITING CONDITIONS FOR OPERATION 3.1.1.3 The boron concentration of the water in all filled portions of the

. Fuel Transfer Canal (deep end) shall be maintained between 4350 and 6000 ppm. l

- APPLICABILITY: MODE l'

~ ACTION-If the.above condition is not satisfied (boron concentration between 4350 and 6000 ppm), take action necessary to restore the boron concentration to within acceptable limits.

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- BORON CONCENTRATION - SPENT FUEL POOL "A" LIMITING CONDITIONS FOR OPERATION 3.1.1.4 The boron concentration of the water in all filled. portions of Spent Fuel Pool "A" shall be maintained between 4350 and 6000 ppm.

APPLICABILITY: MODES 1 and 2

~ ACTION:

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If the above condition is not satisfied (boron concentration between 4350 and 6000 ppm), take action necessary to restore the boron concentration to within acceptable limits.

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3.3 INSTRUMENTATION-F 3.3.1 NEUTRON MONITORING INSTRUMENTATION

INTERMEDIATE AND SOURCE RANGE NEUTRON FLUX MONITORS LIMITING CONDITIONS FOR OPERATION t 3.3.1.1 As~a minimum, the intermediate and source range neutron monitoring instrumentation' channels of Table 4.3-1 of. the REC 0VERY OPERATIONS PLAN shall be OPERABLE.

l' APPLICABILITY: MODE 1 ACTION:

a. With the number of source range neutron monitoring channels OPERABLE one

less than required by the Minimum Channels OPERABLE requirement of Table

4.3-1 of the RECOVERY OPERATIONS PLAN, restore the inoperable channel to 4 OPERABLE status within 30 days.

b. With no source range neutron monitoring channels OPERABLE, suspend all

~

activities involving CORE-ALTERATION, verify compliance with the boron -

concentration requirements of Specification 3.1.1.2 at.least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by a mass balance calculation and at least once per 7. days by a.

chemical analysis and restore at least one source range neutron-l monitoring channel to OPERABLE status within 7 days.

3

c. With no intermediate range neutron monitoring channels 0PERABLE,' restore at least one intermediate range channel to OPERABLE status within 7 days. l e

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i 1 THREE MILE ISLAND - UNIT 2' 3.3-1 0127P

- . ~ , - - - . . -. - -- - - . . , . . . --

=3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Deleted i

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THREE MILE ISLAND - UNIT 2 3.3-2

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0127P P

3.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITIONS FOR OPERATION 4

. 3.3.3.1. The radiation monitors listed in Table 4.3-3 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3 as required in Table 4.3-3 of the RECOVERY OPERATIONS PLAN.

ACTION:

As required in Table 4.3-3 of the RECOVERY OPERATIONS PLAN .

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3 THREE MILE ISLAND - UNIT 2 3.3-3 j- 0127P

METEOROLOGICAL INSTRUMENTATION )

LIMITING CDNDITIONS~FOR OPERATION 3.3.3.4

.~

The meteorological monitoring instrumentation channels shown in Table 4.3-5 of the RECOVERY OPERATIONS PLAN shall be OPERABLE..

APPLICABILITY: MODES 1 AND 2 ACTION:

With any of the above required meteorological monitoring channels inoperable, restore the inoperable channel (s) to OPERABLE status within 7 days. l h

THREE MILE ISLAND - UNIT 2 3.3-4 0127P

ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION LIMITING CONDITIONS-FOR OPERATION 3.3.3.5 The Essential Parameters Monitoring Instrumentation shall be OPERABLE in accordance with the requirements of Table 4.3-7 of the RECOVERY OPERATIONS ,

?

P LAN.

APPLICABILITY: MODE 1 ACTION:

For instrumentation not in accordance with the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN, restore the inoperable instrument (s) to the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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' CHLORINE DETECTION SYSTEMS W

- LIMITING CONDITIONS FOR OPERATION 3.3.3.7 Two Chlorine Detection Systems, with their alarm / trip setpoints adjusted to actuate at a. chlorine concentration of less than or equal to 5

. ppm, shall be OPERABLE:

a. One at the air intake tunnel, and

b. One at'the Control Room air supply duct.

APPLICABILITY: H0DE 1 ACTION:

With one or more Chlorine Detection Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation; restore the inoperable detection system to CPERABLE status within 30 days.

THREE MILE ISLAND - UNIT 2 3.3-6 0127P i

FIRE DETECTION INSTRUMENTATION

' LIMITING CONDITIONS FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in: Table 4.3-11 of the-RECOVERY OPERATIONS PLAN shall be

' OPERABLE.

APPLICABILITY: MODES 1, 2 and 3

- ACTION:

With..the number of OPERABLE fire detection instruments less'than required by Table 4.3-11 of the RECOVERY OPERATIONS PLAN,-insure that an alternate instrument with the same coverage is OPERABLE,lar; 1.- Within I hour,: establish al fire watch patrol to inspect.the zone with the inoperable. instrument (s) at least once per hour, and

2. Restore the inoperable instrument (s) to OPERABLE status within 14 days.

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THREE MILE ISLAND - UNIT 2- 3.3-7 0127P I

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l 3.4 REACTOR COOLANT SYSTEM-

-' REACTOR COOLANT LOOPS ,

LIMITING CONDITIONS FOR OPERATION

' 3.4.1 Deleted. 55 A

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THREE MILE ISLAND - UNIT 2 3.4-1 0127P !

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l REACTOR VESSEL WATER LEVEL MONITORING LIMITING CONDITIONS FOR OPERATION 3.4.2 As a minimum two independent Reactor Vessel water level monitoring instruments shall be OPERABLE.

i APPLICABILITY: MODE 1 !

ACTION ,

a. -

With only one Reactor Vessel water level monitoring instrument OPERABLE, terminate all activities involving changes in the Reactor Coolant System water volume and restore the inoperable instrument to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. With no Reactor Vessel water level monitoring instrument OPERABLE, terminate all activities involving changes in~the Reactor Coolant System water volume and restore at least one Reactor Vessel water level instrument to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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THREE MILE ISLAND - UNIT 2 3.4-2 0127P ,

3.4.9 PRESSURE / TEMPERA 1URE' LIMITS.

REACTOR COOLANT-SYSTEM LIMITING CONDITIONS FOR OPERATION 3.4.9.1 The Reactor Coolant System shall be maintained between a Tavg Of less than 200*F and greater than 50*F.

3.4.9.2 The Reactor Coolant System shall remain open to the reactor building atmosphere unless repressurization is approved in a safety evaluation submitted to the NRC. This safety evaluation shall specify the maximum l 55 -

pressure limits and overpressure protection that is required.

APPLICABILITY: MODE 1 ACTION:

With the Reactor Coolant System temperature exceeding the temperature limits, immediately adjust the Reactor Coolant System temperature ix) within limits and -

submit a report pursuant to Specification 3.0.3.

THREE MILE ISLAND - UNIT 2 3.4-3 0127P

3.5 COMMUNICATIONS l

! CONTROL: ROOM' ,

LIMITING CONDITIONS FOR OPERATION 3.5.1' Direct communication shall be maintained between-the Control Room or .

the Command Center and personnel in the Reactor Building. As stated in Table 6.2-1,'the additional 50L or SOL limited to fuel handling, notwithstanding location,~.will have direct communications'.with personnel in the Reactor:

Building performing CORE ALTERATIONS.

APPLICABILITY: -MODE-1 during CORE ALTERATIONS:

ACTION:

When direct communication between the Control Rooai or the' Command' Center and personnel in the Reactor. Building as stated.in the above' specification cannoti

.be maintained, suspend all operations involving CORE' ALTERATIONS and.-restore communications to OPERABLE status.

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0127P-

=-. . : . - -. _ - - . .. - .... _- -- . . . . .. .. ,

3.6 CONTAINMENT SYSTEMS -

3.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY

, LIMITING CONDITIONS FOR OPERATION l

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained unless it is not ,

required per-procedures approved pursuant to Specification 6.8.2. i APPLICABILITY: MODE l-ACTION:

With CONTAINMENT INTEGRITY required and one containment isolation valve per containment penetration open or inoperable, maintain the affected penetration (s) closed with either:

a. At least one deactivated automatic valve secured in the isolation

' position, or

b. At least one closed manual valve, or a blind flange.

THREE MILE ISLAND - UNIT 2 3.6-1 0127P

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. TABLE 3.6-2 PENETRATIONS WITHOUT DOUBLE ISOLATION Penetration Function System

-R-573* Reactor. Coolant Pump: MU -

R-574* Seal-Water Supply R-575*

R-576*

~R-577* . Reactor Building Air RR R-579*..

Un1t Cooling. Water R-584*

R-587* R-580*

R-583* Reactor Building Spray BS R-586* Inlet Line R-589*- Decay' Heat Coolant Supply: -DH R-590*

R-591* High Pressure Injection' MU R-592* ,

R-537' Nitrogen and Fill to Core- CF-Flooding Tank

, R-539* Leakage Cool 1ng .DC R-542* Pressurizer Auxiliary Spray DH R-544* Nitrogen and Fill to Core CF' Flooding Tank R-557* Nuclear Services Closed Cooling NS 4 Water to Reactor Coolant Pump 011 and Motor Coolers I

R-559* Intermediate Closed. Cooling IC Hater to Roller Nut Drive Cooling Colls 1

.i R-563* Intermediate Closed Cooling IC j System R-566* Service Air SA-R-570* High Pressure Injection MU R-572*

!1 j-1 THREE MILE ISLAND - UNIT 2 3.6-2 0127P o

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TABLE 3.6-2:'(Cent'd) x f .

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, Penetration- Function- ' System 1R-545A#- Building Pressure ' BS R-554C#'

R-571C#1 lR-562C# Bul'iding' Spray _ System .BS Pressure; System tR-593#' Sump Penetration Sleeve :DH' R-594# and: Drain Line t-R-616# Auxiliary Feedwater Lines- EF

?R-623#

'- FM

-R-617# .Feedwater-Lines. -

.R-618# ,

R-619#. . Steam Line - MS -

R-620#

R-621#

R-622#

CODES: BS--Reactor Building Spray CF--Core Flooding DC--Decay Heat Closed Cooling Water

DH--Decay Heat Removal

[ EF--Emergency Feedwater l FN--Feedwater IC--Intermediate Closed Cooling Water

~

[ MU--Makeup and Purification .

RR--Reactor Building Emergency Cooling - River Water SA--Station Service Air MS--Main Stream NS--Nuclear Services Closed Cooling Hater i

Penetrations which utilize a check valve inside containment as a containment isolation valve.

Penetrations which have single valve isolation.

1 THREE MILE ISLAND - UNIT 2 3.6-3

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. CONTAINMENT ISOLATION LIMITING CONDITIONS FOR~ OPERATION 3.6.1.2 Primary CONTAINMENT ISOLATION shall be maintained unless not required

-per approved procedures.

APPLICABILITY: MODES 2 and 3' ACTION:

With CONTAINMENT ISOLATION not in accordance with requirements, restore CONTAINMENT ISOLATION within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , d

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CONTAINMENT AIR LOCKS (MODE 1) l LIMITING CONDITIONS FOR OPERATION 1

3.6.1.3 Each Containment Air Lock shall be OPERABLE with both doors closed "

except when the Air Lock is being used for transit entry and exit through the Containment, then at least one Air Lock door shall be closed unless otherwise specified per procedures approved pursuant to Specification 6.8.2.

APPLICABILITY: MODE 1 ACTION:

With an Air Lock inoperable, maintain at least one door closed and restore the Air Lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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l THREE MILE ISLAND - UNIT 2 3.6-5 0127P

INTERNAL PRESSURE

' LIMITING CONDITIONS FOR OPERATION 3.6.1.4 Primary Containment pressure shall be maintained from 0 psig to not-

less than 12.2 psia. -

APPLICABILITY: Modes 1, 2, and 3 ACTION:

Hith the Containment internal pressure outside.the above limits, restore the internal pressure to within the limits within one (1) hour.

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AIR TEMPERATURE LIMITING CONDITIONS FOR OPERATION 3.6.1.5 Primary Containment average air. temperature shall be maintained

~ between 50*F and 130*F.

APPLICABILITY: MODE 1 ACTION:

I With the Containment average air temperature outside the above limits, restore the average air temperature to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

THREE MILE ISLAND - UNIT 2 3.6-7 0127P

CONTAINMENT AIR LOCKS (MODES 2 AND'3) .

LIMITING CONDITIONS FOR OPERATION 3.6.1.6 Each Containment Air Lock shall be OPERABLE with at least one door

' closed unless otherwise specified per approved procedures.

APPLICABILITY: MODES 2 and 3 ACTION:

With no containment Air Lock door OPERABLE, restore at least one door-to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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1 THREE MILE ISLAND - UNIT 2 3.6-8 0127P

~ 3.6.3 CONTAINMENT PURGE EXHAUST SYSTEM LIMITING CONDITIONS FOR OPERATION 3.6.3.1 One train of the Containment Purge Exhaust System will be OPERABLE.

APPLICABILITY: Modes 1, 2, and 3 ACTION: \s With no Containment Purge Exhaust train OPERABLE, secure the Containment Purge System and restore one (1) train to OPERABLE status prior to resuming purge operations.

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/3.7 PLANT SYSTEMS- 4 l

'3.7.4 4 NUCLEAR SERVICE-RIVER WATER SYSTEM

-Deleted 51 --

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c.- .

3.7.6' FLOOD PROTECTION LIMITING CONDITIONS FOR OPERATION 3.7.6.1 . Flood protedtion shall be provided for all Safety Relate'd systems,-

components and structures when the water level of the Susquehanna River exceeds 301 feet Mean Sea Level USGS datum, at the river water intake structure of Three Mlle Island Nuclear. Station, Unit 1.

APPLICABILITY: MODES 1, 2 and 3 ACTION:

a. With 'the water level at the Unit 1 ' Intake Structure approaching 301~ feet Mean Sea Level USGS' datum:

1. Initiate patrol- and inspection of the dikes surrounding the site -

for signs of deterioration such as undermining or excessive seepage.

2. Inform the Site Operations Director.(SOD) and as-directed by the S0D:

a. Prepare all flood panels and door seals for installation,

b. Check all building floor drains and-pumps to ensure proper operation,

c. Commence daily soundings of the Intake Screen House Floor,

d. Check all water tight doors to ensure proper operation,

e. Fill all outdoor storage tanks to inhibit floatation, and

f. Arrange for alternate supplies of diesel fuel oil and ensure fuel storage tanks are filled.

g. Check that all containers are sealed and secure in the Southeast Storage Facility.

THREE MILE ISLAND - UNIT 2 3.7-2 0127P

3 .' 7 '. 6 FL000 PROTECTION (continued')

ACTION: '(continued)

b. With the water level at the Unit 1 Intake Structure exceeding 301 feetr

'and approaching 302 feet Mean Sea Level USGS datum:

11 . Ensure all door seals and flood panels are installed and all water

' tight doors are closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 2.- Inform the Site Operations Director.

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3.7.7 ' CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM LIMITING CONDITIONS'FOR OPERATION 3.7.7.1 The Control Room Ventilation and Emergency Air Cleanup System shall I

be OPERABLE with:

a. Two Control Room supply fans and associated cooling coils,

b. Two Control Room bypass fans,

c. One charcoal adsorber and HEPA filter train, and

d. Two isolation dampers in the outside air intake duct.

e. The Control Room air inlet radiation monitor OPERABLE.

APPLICABILITY: MODE I ACTION:

a. With one Control Room supply fan or its associated cooling coil inoperable, restore the inoperable fan and/or cooling coil to OPERABLE Status within 7 days.

b. With one Control Room bypass fan inoperable restore the inoperable fan to OPERABLE status within 7 days.

c. With the filter train inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. With one isolation damper in the outside air intake duct inoperable, restore the inoperable damper to OPERABLE status or close the duct within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one isol.ation damper secured in the closed position.

e. With the Control Room Air Inlet Radiation Monitor inoperable, restore it to OPERABLE status or place the Control Room Emergency Air Cleanup System in the recirculation mode of operation within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

THREE MILE ISLAND - UNIT 2 3.7-4 0127P

- 3.7.9 SEALED SOURCES

-SEALED SOURCE INTEGRITY' I LIMITING CONDITIONS FOR OPERATION

- 3.7.9.1 Each sealed source containing radioactive material-either in excess

- of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material (except as noted in 4.7.9.2) shall be free of 1 0.005 .i microcuries of removable contamination.

APPLICABILITY: MODES 1, 2 and 3 ACTION:

a. Each' sealed source with removable contamination in excess of the above limit shall be immediately withdrawn ~from use and:

1. Either' decontaminated and repaired, or

2. Disposed of-in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 are not applicable.

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3.7.10 FIRE-SUPPRESSION SYSTEMS-FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITIONS FOR OPERATION 3.7.10.1 The FIRE SUPPRESSION WATER. SYSTEM shall be OPERABLE with;

a. At least 2 of the following 4 high pressure pumps shall be OPERABLE with-their discharge aligned to the fire suppression header:

1. Unit 1 Circulating Water Flume Diesel Fire Pump

2. Unit 1' River Water Intake Diesel Fire Pump

3. Unit 2 River Water Intake Diesel Fire Pump

4. Unit 1 River Water Intake Motor. Fire Pump

b. Two (2) separate water supplies of the following four (4) shall be-available with at least 90,000 gallons each:

1. Altitude Tank

2. Unit 1 Circulating Water Flume

3. Unit 1 River Water Intake Structure

4. Unit 2 River Water Intake Structure

c. An OPERABLE flow path capable of taking suction from a water supply and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe, or spray system riser required to be OPERABLE per Specification 3.7.10.2 and 3.7.10.4.

APPLICABILITY: MODES 1, 2 and 3 ACTION:

a. With 3 pumps or 3 water supplies inoperable, restore the inoperable equipment to OPERABLE status within 7 days.

b. With the Fire Suppression Water System otherwise inoperable establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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THREE MILE ISLAND - UNIT 2 3.7-6 0127P l

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-DELUGE / SPRINKLER SYSTEMS LIMITING CONDITIONS FOR OPERATION 3.7.10.2 The Deluge and/or Sprinkler Systems located in the following areas shall be OPERABLE:

a. DELETED 51

b. DELETED

c. Air Intake Tunnel (Deluge - 2 of the 3 zones)

d. Hydrogen Purge Exhaust Filter AH-F-34#* g.

e. Reactor Building Purge Exhaust Filters AH-F-31A/B#* l

f. Control Room Bypass Filter AH-F-5* l

g. DELETED 51

h. Fuel Handling Building Exhaust Filter AH-F-14A/B#*- l l

1. Haste gas disposal filter WDG-F-l*

l

j. Auxiliary Building exhaust filters AH-F-10A/B#*

k. Southeast Storage Facility ***

APPLICABILITY: MODES 1, 2 and 3 ACTION:

With one or more of the above required deluge and/or sprinkler systems inoperable, establish a roving (at least once per hour) fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; restore the system to OPERABLE status within 14 days.

- - This facility's Action Statement shall require a roving fire watch once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months instead of once per hour.

Supply line may be isolated by a single manually operated valve.

System is required to be operable only when charcoal filters are installed,.

4F THREE MILE ISLAND - UNIT 2 3.7-7 0127P

HALON SYSTEM LIMITING CONDITIONS FOR OPERATION 3.7.10.3 The following Halon systems shall be OPERABLE with the storage tanks having at least 95% of full charge weight and 90% of full charge pressure (corrected to 70*F).

a. Cable Room and Transformer Room - Control Building 305' elevation

b. Air Intake Tunnel (4 Zones)

APPLICABILITY: MODE 1 ACTION:

With one or more of the above required Halon systems inoperable, establish a roving (at least once per hour) fire watch

with backup fire suppression equipment for the unprotected area (a) within I hour; restore the system to OPERABLE status within 14 days.

Except in the air intake tunnel where a fire watch is not required.

THREE MILE ISLAND - UNIT 2 3.7-8 0127P

FIRE HOSE STATIONS'

' LIMITING CONDITIONS FOR OPERATION 13.7.10.4 The fire hose stations listed in Table 4.7-1 in the RECOVERY OPERATIONS PLAN shall be OPERABLE.

APPLICABILITY: . MODES 1, 2 and 3 ACTION:

With one or more of the fire hose stations shown in Table 4.7-1 in the RECOVERY OPERATIONS PLAN inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

THREE MILE ISLAND - UNIT 2 3.7-9 0127P

PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 3.7.11 All Penetration Fire Barriers protecting Safety Related areas shall be functional.

APPLICABILITY: MODES 1, 2 and 3 ACTION:

With one or more of the above-required Penetration Fire Barriers non-functional:

1. Establish a roving (at least once per hour) fire watch on at least one side of the affected penetration within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , except' areas inaccessible due to occupational exposure considerations and

2. For those areas inaccessible due to occupational exposure considerations, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the cause of the

malfunction and the means for ensuring an adequate firewatch is maintained in the affected area and for restoring the fire barrier (s) to a functional status.

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THREE MILE ISLAND - UNIT 2 3.7-10

! 0127P l

= a 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 A.C. SOURCES LIMITING CONDITIONS FOR OPERATION 3.8.1.1 As.a minimum, tne following A.C. electrical power sources shall be

.0PERABLE:

a. Two physically independent circuits'between the offsite transmission network and the onsite. Class IE. distribution system.

b. Deleted APPLICABILITY: MODE 1 ACTION:

a. With one offsite circuit of.the required A.C. electrical power sources inoperable, verify the operability of the remaining off-site circuit and demonstrate the OPERABILITY of the D.C. bus trains by performing the Surveillance Requirements in.the RECOVERY OPERATIONS PLAN Sections- 51 4.8.2.2.1 and 4.8.2.2.2.a.4 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Restore the full compliment of offsite A.C. electrical power sources to OPERABLE status within 7 days.

b. With both offsite circuits of the above required A.C. electrical power sources inoperable, restore one circuit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and restore the second A.C. circuit to operable status _wlthiri 7 days. l THREE MILE ISLAND - UNIT 2 3.8-1 0127P

.3 TABLE 3.8-1 TESTING FREQUENCY MATRIX 51

- Deleted THREE MILE ISLAND - UNIT 2 3.8-2 0127P

TABLE 3.8-2 RESTORATION TIME MATRIX Deleted 51 THREE MILE ISLAND - UNIT 2 3.8-3 0127P

3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS

.3.8.2.1 A.C.' DISTRIBUTION LIMITING CONDITIONS FOR OPERATION 3.8.2.1.1 The A.C. electrical busses listed in Section 4.8.2.1.1 of the RECOVERY OPERATIONS PLAN shall be OPERABLE and energized with. tie breakers open (unless closed in accodance with site-approved procedures) between l55 redundant busses.

APPLICABILITY: MODE 1 ACTION:

With less.than the above' compliment of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.8.2.1.2 The A.C.-electrical busses listed in Section 4.8.2.1.2 of the RECOVERY OPERATIONS PLAN shall be OPERABLE and energized.

APPLICABILITY: MODE I ACTION:

a. With any of the above A.C. busses incapable of being supplied by their respective inverter, restore that capability to the affected bus within 7 days.

b. With any of the above A.C. busses de-energized, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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1 THREE MILE ISLAND - UNIT 2 3.8-4 I 0127P e

3.8.2.2 0.C. DISTRIBUTION LIMITING CONDITIONS FOR OPERATION 3.8.2.2.1 The following D.C. bus trains shall be energized and OPERABLE with tie breakers between bus trains open (unless closed in accordance with approved procedures): ;

TRAIN "A" consisting of 250/125-volt D.C. bus 2-IDC, 250/125-volt D.C.

' battery bank A and a full capacity charger.

t TRAIN "B" consisting of 250/125-volt D.C. bus 2-2DC, 250/125-volt D.C.

battery bank B, and a full capacity charger.

APPLICABILITY: MODE 1 ACTION:

a .- With one 250/125 D.C. bus' inoperable, restore the inoperable bus to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b. With one 250/125-volt D.C. battery and/or its charger inoperable, restore the inoperable battery and/or charger to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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i , ensuiva iinal. an es.slu'enial

' chlorine release will be detected promptly and the Control Room Emergency.

I Ventilation System will automatically isolate the Control Room and initiate-Its operation in the recirculation mode to provide the required protection.

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INSTRUNENTATION BASES !

3/4.3.3.8 and 3/4.3.3.9 FIRE DETECTION INSTRUMENTATION OPERABILITY of the Fire Detection Instrumentation ensures that adequate warning capability'is available for the prompt detection of fires in the monitored areas. This capability is required-in order to detect and locate.

fires in their early stages. Prompt detection of fires will reduce the potential for damage to equipment and is'an integral element in the overall

< facility fire protection program.

In the event that a portion of the Fire Detection Instrumentation.is inoperable, the establishment of frequent fire patrols in_the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service.

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3/4.4 REACTOR'C00LANT SYSTEM

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BASES 3/4.4.1 REACTOR COOLANT LOOPS 55 Deleted.

3/4.4.2 REACTOR VESSEL HATER LEVEL MONITORING The Reactor Vessel Water Level Monitor ensures that indication is available.t.o monitor changes in Reactor Vessel water level. _ This capability will provide warning of a leak from the Reactor Coolant System or unexplained increases in Reactor Coolant System inventory which could result in a boron' dilution event. Two independent monitors are required.to provide redundancy and to minimize the necessity to discontinue processing because of instrument-failures.

3/4.4~.9 PRESSURE / TEMPERATURE LIMITS The Reactor Coolant System minimum temperature is maintained to prevent precipitation of the boron used to maintain subcriticality. The maximum

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reactor coolant temperature is specified to provide a limit for action for any unknown buildup of heat either due to loss of cooling or unanticipated heating source such as criticality.

g Reactor coolant chemistry surveillance requirements are_ included in the RECOVERY OPERATIONS PLAN. These requirements provide assurance that~ localized i corrosion or pitting in crevice areas, which could tend to promote stress-corrosion cracking in heat affected zones of welds in stainless steel piping or components, will not occur.

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l 3/4.5 COMMUNICATIONS The requirements for comunications capability ensure that personnel in the !

Reactor Building can be promptly informed of significant changes in facility status or' core reactivity conditions during CORE ALTERATIONS.

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~3/4.6 ' CONTAINMENT SYSTEMS- . :

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3/4' . 6.1 ' PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY is maintained to ensure that radioactive . ..

materials in the Containment Building are not released to the environment-in aa uncontrolled manner. ,

3/4.6.1.2 CONTAINMENT ISOLATION-Containment. Isolation _is maintained to assure the containment is properly' !

maintained as a contamination barrier for_..the residual contamination which l remains _inside the containment. , j 3/4.6.1.3 ~ CONTAINMENT AIR LOCKS (MODE 1)

The Containment Air Locks must be maintained OPERABLE to provide the appropriate containment sealing capability. These air locks will be used

, during entries into the Containment to ensure that radioactive materials are

f. not being released to the environs. The preferred method for ensuring that l- radioactive materials are not released during-these entries is to maintain at 4 least one door closed at all times; however, to permit the passage of long items into the Reactor Building, both doors may be open simultaneously in accordance with procedures approved pursuant to Specification 6.8.2.
1 3/4.6.1.4 INTERNAL PRESSURE The negative pressure limit provides assurance that_.the Containment will not.
E exceed its design negative pressure differential. The positive pressure limit
- provides assurance that leakage from the Containment will be limited for off-site dose calculations. During periods when both doors in either or both
' personnel airlocks are open, the Containment Purge System will be operating to maintain Containment pressure within the limits of the Technical
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Specifications.
3/4.6.1.5 AIR TEMPERATURE l 2 The average air temperature of the Containment atmosphere is currently being
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maintainea oetween au r ano lau t. Inis conoition will maximize tne service !
i life of the instrumentation and equipment installed in the Containment and ensure that Ractor Coolant System temperature does not drop below 50?F through LOSS-iu-AMBIENT Cooling. This temperature will ensure that boron will j remain in solution.
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I CONTAINMENT SYSTEMS BASES
.3/4.6.1.6 CONTAINMENT AIRLOCKS (MODES'2 AND 3)
The Containment-Air Locks must be maintained OPERABLE to provide assurance that the containment is properly maintained as a contamination barrier for the-residual contamination which remains inside the containment. These air locks will be used during entries into the Containment to ensure that radioactive materials are not~being released to the environs. One-door must be closed at all times; however, to permit the passage of long items-into the Reactor Building, both doors may be opened simultaneously in accordance with
' site-approved procedures.
3/4.6.3 CONTAINMENT PURGE FMdAUST SYSTEM i.'e OPERABILITY requ' ements for the Containment Purge Exhaust System. ensure that u'crian Cer.t;;nment purge operations all radioactive particulate material will be filtered through the HEPA filters prior to release to the atmosphere.
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l 3/4.7 PLANT SYSTEMS !
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3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM Deleted.
3/4.7.6' FLOOD PROTECTION The limitation on flood protection ensures that facility protective actions will be taken in the event of flood conditions. The limit of elevation of 302 ft. Mean Sea Level USGS datum is the elevation at which facility flood control measures are required to be taken to provide protection to Safety Related equipment.
3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the Control Room Emergency Air Cleanup System ensures that
1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the Control Room will remain habitable for operations personnel during and following all credible conditions. The OPERABILITY of this-system l In conjunction with Control Room design provisions is based on limiting the radiation exposure to personnel occupying the Control Room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A", 10 CFR 50.
3/4.7.9 SEALED SOURCE INTEGRITY The limitation on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10CFR70.38(c) limits for plutonium.
This limitation will ensure that leakage from byproduct, source, and Special Nuclear Material sources will not exceed allowable intake values.
3/4.7.10 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where Safety Related equipment is located. The Fire Suppression System consists of the water system, spray and/or sprinklers, ;
Halon and fire hose stations. The collective capability of the Fire i Suppression Systems is adequate to minimize potential damage to Safety Related )
equipment and is a major element in tne tac 111ty tire Protection rrogram. any two of the four main fire pumps provide combined capacity greater than 3757 j gpm. l I
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l PLANT SYSTEMS l
BASES' In the event that portions of the Fire Suppression Systems are-inoperable, alternate. backup fire fighting equipment is required to be made available in
the'affected areas until the affected equipment can be restored to service 1
Inlthe event that the Fire Suppression Water System becomes inoperable, immediate corrective measures must be taken since this. system provides the major fire suppression capability of the plant.
3/4.7.11 -PENETRATION FIRE BARRIERS The functional integrity of the Fire Barrier Penetration Seals ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. .This' design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The Fire Barrier Penetration SeLis are a positive element in the facility fire protection program and are subject to periodic inspections. ,
During periods of time when the seals are not functional, a roving fire watch is required to be maintained.in the vicinity of the affected seal untti,the seal is restored to functional status except in areas where the affected seal is inaccessible. For those seals that are' inaccessible, a special report is required to be filed.
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BASES 3/4.8 ELECTRICAL-POWER SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and' associated distribution systems ensures-that sufficient power will be available when required.
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3/4.9 RADIOACTIVE MATERIALS STORAGE BASES 3/4.9.I' SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING Spent Fuel. Storage Pool-"A" Water Level Monitoring instrumentation has been provided to assure the capability to monitor water level in the Spent Fuel Storage Pool "A".
3/4.9.2' SPENT FUEL STORAGE P0OL "A" WATER LEVEL The water level in the Spent Fuel Storage Pool "A" has been established to limit the dose rate, due to the storage of Canisters, to acceptable levels.
3/4.9.3 FUEL TRANSFER CANAL (DEEP END) HATER LEVEL MONITORING Fuel Transfer Canal Water Level Monitoring instrumentation has been provided to assure the capability to monitor water level in the deep end of the Fuel Transfer Canal.
3/4.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL The water level in the Fuel Transfer Canal (deep end) has been established to limit the. dose rate, due to the storage of the plenum assembly and Canisters,_
to acceptable levels.
3/4.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEM The requirement for the Fuel Handling Building / Auxiliary Building Air Cleanup System to be operating or OPERABLE ensures that all radioactive material released from operations involving movement of 11guld and gaseous radioactive wastes in the Auxiliary Building will be filtered through the HEPA filters prior to release to the atmosphere.
3/4.9.13 ACCIDENT GENERATED WATER These specifications are provided to ensure compliance with the Comnission's Statement of May 25, 1979, and the Commission's Statement of Policy and Notice of Intent to Prepare a Programmatic Environmental Impact Statement of November 21, 1979, which prohibit these actions pending evaluation of the environmental impacts of such actions. The PEIS issued in March 1981, deferred a decision on the ultimate disposal of processed water. Further Commission action is necessary orlor to release of ACCIDENT GENERATED HATER.
However, the Commission has recognized that there may be emergency situations, not at this time foreseen, which could require rapid action. In these situations, the Commission has indicated its intention to consult with the ,
Council on Environmental Quality to the extent practicable. '
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BASES-3/4.9 - ' RADIOACTIVE -WASTE STORAGE '
3/4.9.13 ACCIDENT GENERATED WATER ~ Cont'd ACCIDENT GENERATED WATER, as defined in the settlement of the City'of Lancaster litigation, is:
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a. Water that existed in the.TMI-2 Auxillary,1 Fuel Handling, and Containment Buildings including the primary system as of October 16, 1979, with-exception of water which as a. result of decontamination operations becomes commingled with non-accident generated water such.that the
commingled water has a tritium content of 0.025 uC1/ml or less before processing; 4
b. Water that has a total activity of greater than one uC1/ml prior to processing except where such water is originally non-accident water and becomes contaminated by use in cleanup;
c. Water that contains greater than 0.025 uC1/ml'of tritium before processing.
3/4.9.14 Deleted.
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3/4.10 CRANE OPERATIONS l BASEE
. 3/4.10.1 CRANE OPERATIONS - CONTAINMENT BUILDING' ,
A heavy load drop into the Reactor Vessel may cause reconfigurations of the core debris and/or structural damage which could hinder recovery efforts. A-load drop on the Incore Instrument Seal Table and/or-guide-tubes.may result in an unisolable leak-from the Reactor Vessel. The restriction on movement of loads tri excess of the nominal weight of'a fuel or control rod assembly and
. assoc a ei t d handling tool over these areas is to mitigate;the potential-
. consequences stated above in the event this load is dropped.
3/4.10.2 CRANE OPERATIONS - FUEL HANDLING BUILDING A heavy load drop in the -Fuel-Handling Building could result irt the rupture of a: canister containing core materia'l. The restriction on movement of heavy.
loads in the fuel handing building is.to prevent the drop of a heavy load in >
the fuel handling building in areas where the rupture of a fuel canister could occur.
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SECTION 6.0 ADMINISTRATIVE CONTROLS 0127P
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Office of the Director-TMI-2 consists of the Director-TMI-2 and the Deputy Director-TMI-2 and shall be responsible for overall' unit operation and shall delegate in writing-the succession to this responsibility during both of- .
their absences.
6.2 ORGANIZATION GPUNC ORGANIZATION 6.2.1 The GPU Nuclear Corporation (GPUNC) Organization for unit management and technical support shall be as.shown on' Figure 1-1 of the Organization Plan. The Organization Plan and changes thereto shall be approved by the NRC -
prior to implementation.
TMI-2 ORGANIZATION -
6.2.2 The unit organization shall be shown on Figure 1-2 of the Organization Plan and:
a. During Mode 1, each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
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b. During Mode 1, at least one licensed Operator shall be in the control ,
room when fuel is in the reactor.
c. During Mode 1, an individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor.
d. A Site Fire Brigade of at least 5 members shall be maintained onsite'at.-
all times. The Site Fire Brigade shall not include 3 members of the minimum shift crew (during Mode 1) necessary for safe shutdown of the' l unit and any personnel required for other essential functions during a fire emergency.
e. An individual qualified in radiation protection procedures shall be onsite whenever Radioactive Haste Management activities are in progress.
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l TABLE 6.2-1 o
, MINIMUM SHIFT CREW COMPOSITION # l LICENSE RECOVERY MODE CATEGORY SOL 1*
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Non-Licensed 2
Shift-crew composition may be.less than the minimum require-ments for-a_ period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order- j to accommodate unexpected absence of on duty shift crew 1
' members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
During CORE ALTERATIONS an additional SOL or an SOL limited to fuel handling will be stationed on the operating floor, in the command center, or in the Control Room to directly control the l 55 particular-CORE ALTERATION activity being performed.
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3 p. >- .K ADEMISTRATIVE CONTROLS ,
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,r 6.8.2.1 Each procedure and'any change to any procedure prepared pursuant to
.6.8.l', shall-be prepared, revieweo'and approved in accordance with 6.5 and.
willbdreviewedperiodicallyasregtredbyANSI 18.7 -;1976. .
~6.8.2.2 During~Modell, Procedures of 6.8.-l'a'and changes thereto which alter the distribution or processing of a quantity.of radioactive material the release of which could cause the magnitude.of radiological-releasestto exceed 55 10 CFR 50 Appendix;I limits shalifbe subject to approval _-by the NRC prior-.to
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implementation.
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6.8.3.I', Temporary changes (to kocedures of 6.8.1 may be made provided that:
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!' .a. The bhtent ofLthe original procedure control is not altered, and
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g.,il)LForthoseprocedureswhichaffecttheoperationalstatus'ofunit'
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i? . systems or. equipment,-the change is approved by two members of. the unit j management'. staff, at least one of whom holdsja Senior Reactor Operator.'s License. If onk;of the two above stsaatures is not-by a-supervisory person within the' Department having cognizance of the' procedure being- '
changed, the signature of.that supervisory person within the department ,
wdl also be required..or f e
/ 2)1 For those procedures which'do'not affect the operationalistatus of I unit systems or equipment, th'e change 11s approved by two members of'the-
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responsible organization. If one of the;two above signatures 1s not by a section manager / director'within the.Depa'rtment having cognizance.of the-
.procedure'being changed..the signature of that section manager / director within the' department will also be required, and-o
.y f The change is documented, Independent. Safety Review ~ completed, and the required reviews and approvals are obtained within 14 days, and-
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. d. Those changes to procedures described by'6.8.2.2 are submitted to the'NRC for review within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following. approval'by'the management level
specified for implementation by Section 6.5.1.9.
i .Y t j ., 6. 9 REPORTING REQUIREMENTS f .
? ROUTINE REPORTS AND REPORTABLE OCCURRENCES
, 6.9.1 Inadditibwtotheapplicable.reportingrequirementsofTitle10, Code- ~
1 of Federal Regu3ations, the following reports shall be submitted to the NRC' Region'I' Administrator unless otherwise noted.
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ML20210C901

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