Text

Amend 30 to License DPR-73,modifying App a Tech Specs Sections & Revises Tech Specs Aligning Licensing Requirements to Appropriate Current,As Well as Future,Plant Conditions Through Current Cleanup Operations
	ML20155B310
Person / Time
Site:	Three Mile Island
Issue date:	05/25/1988
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20155B292	List: ML20155B288; ML20155B310; ML20155B315;
References
	NUDOCS 8806130142
	Download: ML20155B310 (91)
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GPU NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. DPR-73

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by GPU Nuclear Corporation, (the licensee) dated April 23, 1987, as supplemented by letters dated October 26, 1987, November 9, 1987, and December 4, 1987, complies -

with the standards and requirements of the Atomic Energy Act of 1954,

! as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and reg'lations of the Comission; C. There is reasonable asst.:ance (i) that the activities authorized i

by this amendment can be conducted without endangering the health

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common j defense and security or to the health and safety of the public; and 1

E. The issuance of this amendment is in accordance with 10 CFR Part l 51 of the Comission's regulations and all applicable recuirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. OPR-73 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 30, are hereby incoroorated in the license.

GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications and all Commission Orders issued subsequent to March 28, 1979.

3. This license amendment is effective as of its date of issuan's.

FOR THE NUCLEAR REGULATORY COMMISSION J -

bAb$ ~

J n F. Stolz, Director P oject Directorate I-

' Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

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a ATTACHMENT TO LICENSE AMENDMENT NO. 30 FACILITY OPERATING LICENSE NO. OPR-73 9

DOCKET NO. 50-320 Replace the following sections /pages of the Appendix A Technical Specifications with the attached sections /pages. The revised sections /pages are identified by amendment number and contain vertical lines indicating the area of change, Remove Insert Cover Page Cover Page Index Index Section 1 Section l' Section 2 Section 2 9 Section 3 Section 3 Section 3/4 Section 3/4 Section 6 Section 6 9

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O 8 THREE MILE ISLAND NUCLEAR STATION UNIT 2 Technical Specifications Appendix "A" -

to License No. DPR-73 1

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. INDEX DEFINITIONS SECTION Page 1.0 DEFINITIONS 1.1 DEFINED TERMS..................................................... 1-1

1. 2 REC 0VERY OPERATIONS PLAN.......................................... 1-1

1. 3 M0DE..............................................................

1-1 1.4 ACTI0N............................................................ 1-1 1.5 O P E RAB L E - O P E RAB I L I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 'f.ST........................................... 1-4 1.11 STAGGERED TEST BASIS.............................................. 1-4 1.12 FREQUENCY N0TATION................................................ 1-4 1.13 FIRE SUPPRESSION WATER SYSTEM..................................... 1-4 1.14 REVIEW SIGNIFICANCE............................................... 1-4 1.15 CORE ALTERATION................................................... 1-5 1.16 LOSS TO AMBIENT................................................... 1-5 1.17 ACCIDENT GENERATED WATER.......................................... 1-5 1 1.18 LICENSED OPERATOR (0L)............................................ 1-5 1.19 SENIOR LICENSED OPERATOR (50L).................................... 1-5 1.20 FUEL HANDLING SENIOR LICENSED OPERATOR (50L-FH). . . . . . . . . . . . . . . . . . . 1-5 THREE MILE 'iLAND - UNIT 2 i Amendment 31

INDEX SAFETY LIMITS -

SECTION . PAGE

1. 0 DEFINITIONS - (Continued) 1.21 CONTAINMENT IS0LATION............................................. 1-6 FACILITY MODES (TABLE 1.1).............................................. 1-7 FREQUENCY NOTATION (TABLE 1.2).................................. ....... 1-8 2.0 SAFETY LIMITS...................................................... 2-1 THREE MILE ISLAND - UNIT 2 ii Amendment 30

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. INDEX LIMITING CONDITIONS FOR OPERATION SECTION PAGE 3.0 APPLICABILITY..................................................... 3.0-1 3.1 WATER INJECTION COOLING ~AND REACTIVITY CONTROL SYSTEMS 3.1.1 BORATION CONTROL .

Borated Cooling Water Injection.............................. 3.1-1 Boron Concentration Reactor Coolant System................... 3.1-2 Boron Concentration - Fuel Transfer Cana1.................... 3.1-3 Boron Concentration - Spent Fuel Pool "A".................... 3.1-3 3.3 INSTRUMENTATION 3.3.1 NEUTRON MONITORING INSTRUMENTATION...i....................... 3.3-1 Intermediate and Source Range Neutron Flux Monitors.......... 3.3-1{

3.3.? ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION... 3.3-1 3.3.3 MONITORING INSTRUMENTATION................................... 3.3-1 Radiation Monitoring Instrumentation......................... 3.3-1 Meteorological Instrumentation............................ . 3.3-2 Essential Parameters Monitoring Instrumentation............ 3.3-2 Chlorine Detection Systems................................... 3.3-2 Fire Detection Instrumentation.............................., 3.3-2 3.4 REACTOR COOLANT SYSTEM 3.4.1 REACTOR COOLANT L00PS........................................ 3.4-1 3.4.2 REACTOR VESSEL WATER LEVEL MONITORING........................ 3.4-1 3.4.9 PRESSURE / TEMPERATURE LIMITS.................................. 3.4-1 Reactor Coolant System....................................... 3.4-1 3.5 COMMUNICATIONS 3.5.1 CONTROL R00M................................................. 3.5-1 3.6 CONTAINMENT SYSTEMS 3.6.1 PRIMARY CONTAINMENT.......................................... 3.6-1 1

Containment Integrity........................................ 3.6-1 Containment Isolation........................................ 3.6-4 l THREE MILE ISLAND - UNIT 2 iii Amendment 30

. INDEX LIMITING CONDITIONS FOR OPERATION .

SECTION PAGE Containment Air Locks (Mode 1)............................... 3.6-4 I Internal Pressure............................................ 3.6-4 Air Temperature.............................................. 3.6-4 Containment Air Locks (Modes 2-3)............................ 3.6-5 1 3.6.3 CONTAINMENT PURGE EXHAUST SYSTEM............................. 3.6-5 I

3.7 PLANT SYSTEMS 3.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM........................... 3.7-1 3.7.6 FLOOD PROTECTION............................................. 3.7-1 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.................... 3. 7-2L 3.7.9 SEALED SOURCES............................................... 3.7-3' 3.7.10 FIRE SUPPRESSION SYSTEMS..................................... 3.7-4 Fire Supp'ression Water System................................ 3.7-4 Deluge / Sprinkler Systems..................................... 3.7-5 Halon System................................................. 3.7-6 Fire Hose Stations........................................... 3.7-6 PENETRATION FIRE BARRIERS.................................... 3.7-7 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 A.C. S0VRCES................................................. 3.8-1 3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution............................................ 3.8-4 0.C. Distribution............................................ 3.8-5 3.9 RADI0 ACTIVE MATERIALS STORAGE 3.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING........... 3.9-1 )

3.9.2 SPENT FUEL STORAGE POOL " A" WATER LEVEL. . . . . . . . . . . . . . . . . . . . . . 3.9-1 3.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING........ 3.9-1 l

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INDEX LIMITING CONDITIONS FOR OPERATION SECTION PAGE 3.9.4 FUEL' TRANSFER CANAL (DEEP END) WATER LEVEL................... 3.9-2 3.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP.

SYSTEMS...................................................... 3.9-2 Fuel Handling Building Air Cleanup System.................... 3.9-2 Auxiliary Building Air Cleanup Exhaust System................ 3.9-3 3.9.13 ACCIDENT GENERATED WATER..................................... 3.9-3 h

3.10 CRANE OPERATIONS 3.10.1 CONTAINMENT BUILDING......................................... 3.10-1 3.10.2 FUEL NANDLING BUILDING....................................... 3.10-1 l

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INDEX LIMITING CONDITIONS FOR OPERATION SECTION PAGE 3/4.0 APPLICABILITY................................................... B 3/4 0-1 3/4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL AND BORATED COOLING WATER INJECTION......... B 3/4 1-1 1

3/4.3 INSTRUMENTATION 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION........................... B 3/4 3-1 3/4 3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.. B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................... B 3/4 3-1 Radiation Monitoring Instrumentation......................... B 3/4 3 2 Meteorological Monitoring Instrumentation.................... B 3/4 3-2 Essential Parameters Monitoring Instrumentation.............. B 3/4 3-2 Chlorine Detection Systems................................... B 3/4 3-2 Fire Detection Instrumentation............................... B 3/4 3-3 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT L00PS........................................ B 3/4 4-1 3/4.4.2 REACTOR VESSEL WATER LEVEL M^'IIT0 RING........................ B 3/4 4-1 3/4.4.9 PRESSURE / TEMPERATURE LIMIT................................... B 3/4 4-1 ,

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. INDEX LIMITING CONDITIONS FOR OPERATION .

SECTION PAGE 3/4.5 COMMUNICATIONS.................................................. B 3/4 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 Isolation........................................ B 3/4 6-1 Contai nment Ai rl ocks (Mode 1). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 Internal Pressure............................................ B 3/4 6-1 Air Temperature.............................................. B 3/4 6-1 Containment Airlocks (Modes 2 and 3). . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 3/4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM............................. B 3/4 6-1

' 1 3/4.7 PLANT SYSTEMS................................................... B 3/4 7-1 3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM........................... B 3/4 7-1 3/4.7.6 FLOOD PROTECTION............................................. B 3/4 7-1 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.................... B 3/4 7-2 3/4.7.9 SEALED SOURCE INTEGRITY...................................... B 3/4 7-2 3/4.7.10 FIRE SUPPRESSION SYSTEMS..................................... B 3/4 7-2 3/4.7.11 PENETRATION FIRE BARRIER..................................... B 3/4 7-3 3/4.8 ELECTRICAL POWER SYSTEMS........................................ B 3/4 8-1 3/4.9 RADI0 ACTIVE WASTE STORAGE 3/4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING............ B 3/4 9-1 3/4.9.2 SPENT FUEL STORAGE POOL " A" WATER LEVEL. . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING......... B 3/4 9-1 3/4.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL.................... B 3/4 9-1 3/4.9.12 FUEL HANDLING BUILDING BUILDING AIR CLEANUP SYSTEMS.......... B 3/4 9-1 Auxiliary Building Air Cleanup System........................ B 3/4 9-1 THREE MILE ISLAND - UNIT 2 vii Amendment 30

. INDEX DESIGN FEATURES -

SECTiON. PAGE 3/4.9.13 ACCIDENT GENERATED WATER..................................... B 3/4 9-1 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 5.0 DESIGN FEATURES................................................... 5-1 5.1 SITE 5.1.1 Exclusion Area.................................................. 5-1 5.1. 2 Low Population Zone............................................. 5-1 5.1.3 Si te Boundary for Gaseous Ef fluents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 -_

5.1. 4 Site Boundary for Liquid Effluents.............................. 5-1 5.2 CONTAINMENT 5.2.1 Configuration.............................................. .... 5-2 5.2.2 Design Pressure and Temperature................................. 5-2 5.4 REACTOR COOLANT SYSTEM 5.4.1 Design Pressure and Temperature.....'...........................

. 5-4 5.4.2 Volume.......................................................... 5-4 5.5 . METEOROLOGICAL TOWER LOCATION..................................... 5-5 1

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. c-INDEX ADMINISTRATIVE CONTROLS ,

SECTION- PAGE 6.0 ADMINISTRATIVE CONTROLS..... ..................................... 6-1 6.1 RESPONSIBILITi.... ............................. ................. '6-1 6.2 ORGANIZATION 6.2.1 GPUNC Organization.............................................. 6-1 6.2.2 THI-2 Organization.............................................. 6-1 6.3 UNIT STAFF QUALIFICATIONS......................................... 6 6.4 TRAINING.......................................................... 6-3 6.5 REVIEW AND AUDIT .--

6.5.1 TECHNICAL REVIEW AND CONTR0L................................... 6-3

6.5.1.10 Records..................................................... ~6-5 6.5.1.11 Qualifications.............................................. 6-5 6.5.2 INDEPENDENT SAFETY REVIEW...................................... 6-5 6.5.2.1 Function................................................... 6-5 6.5.2.5 Responsibilities........................................... 6-6 6.5.2.7 Records.................................................... 6-7 6.5.3 AU0ITS......................................................... 6-7 I 6.5.3.2 Records.................................................... 6-8 l 6.5.4 SAFETY REVIEW GROUP (SRG)...................................... 6-8 6.5.4.1 Function................................................... 6-8 6.5.4.2 Organization............................................... 6-8 6.5.4.3 Responsibility................................l............ 6 6.5.4.6 Authority.................................................. 6-9' ,

6.5.4.7 Qualitications............................................. 6-9 6.5.4.8 l Records.................................................... 6-9 i 6.6 REPORTABLE EVENT 3 ACTI0N......................................... 6-10 ~l 6.8 PROCEDURES....................................................... 6-10 i

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INDEX ADMINISTRATIVE CONTROLS -

SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES.................... 6-11 6.9.1.4 ANNUAL REP 0RTS................................................ 6-11 l 6.9.2 SPECIAL REP 0RTS............................................... 6-12 6.10 RECORD RETENTION................................................ 6-12 6.11 RADIATION PROTECTION PR0 GRAM.................................... 6-14 6.12 HIGH RADIATION AREA............................................ 6-14 1

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9 SECTION 1.0 DEFINITIONS 9

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. , l 1.0 DEFINITIONS DEFINED TERMS 1.1 The OEFINEO TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

RECOVERY OPERATIONS PLAN 1.2 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. Prior to the transition to the following Facility Mode, a report shall be submitted to the NRC no later than 60 days prior to transition which provides the basis for the transition. At least 90 days prior to facility -

Mode 2, a report shall be submitted which evaluates the applicability of the ,

technical provisions of 10 CFR 50 and the appendices thereto, to TMI-2 in Facility Mode 2 and thereafter, and demonstrates that nacessary design features required for protection of the public health and safety exist.

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

OPERABLE - OPERABILITY 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 tne assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also capable of performing their related support function (s).

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

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1.0 DEFINITIONS CONTAINMENT INTEGRITY

1. 7 CONTAINMENT INTEGRITY shall exist when;

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

1. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions on each side of the penetra-tion. Isolation valves inside the Reactor Building shall be capable of remote operation from a control station outside the Reactor Building, or;

2. Closed by double barrier isolation outside the Reactor Building when the inside barrier is inaccessible due to ALARA considerations or the penetration has been modified as part of the cleanup effort (i.e.,

Mode 1), or;

3. Open per an approved procedure but are capable of being closed pursuant to either Specification 1.7.a.1 or 1.7.a.2. Controls shall __

be implemented to minimize the time the penetration is allowed open and to specify the conditions for which the penetration is open.

Penetrations will be expeditiously closed upon completion of the condition specified in the approved procedures.

b. The Equipment Hatch is closed and sealed,

c. Each airlock is GPERABLE pursuant to Specification 3.6.1.3.

d. The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.

e. ' Water level in Spent Fuel Pool "A"/ Fuel Transfer Canal is maintained pursuant to Specification 3.9.2/3.9.4 when the Fuel Transfer tubes are open.

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, overlappir.g or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK

1. 9 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where THREE MILE ISLAND - UNIT 2 1-2 Amendment 30

S-1.0 DEFINITIONS l possible, comparison of the channel indication and/or status with other indica-*

tions 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. Bistable 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 WATER SYSTEM 1.13 A FIRE SUPPRESSION WATER 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 manipulation 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 preclude completion of movement of a component to a safe conservative position.

LOSS-T0 AMBIENT 1.16 LOSS-T0-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, is:

(a) Water that existed in the THI-2 Auxiliary, Fuel Handling, and Contain -

ment 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 pCi/ml or less before processing; (b) Water that has a total activity of greater than one pCi/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 pCi/ml of tritium before processing.

1.18 LICENSED OPERATOR (0L) - 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 (SOL) - any individual who possesses an NRC Senior Operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, "Operators Licenses."

1.20 FUEL HANDLING SENIOR REACTOR OPERATOR (SOL-FH) - an individual licensed by the Nuclear Regulatory Commission to supervise fuel handling and core alteration operations.

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. 1.'O DEFINITIONS 1.21 CONTAINMENT ISOLATION shall-exist when:

a. Each penetration is:

1.' Closed by an accessible manual valve, a welded or bolted blind flange, or a deactivated automatic valve secured in the closed posi-tion to provide isolation of each penetration, or;

2. Open per an approved procedure but can be closed pursuant to Specification 1.21.a.1. Controls shall be implemented to minimize the time the penetration is allowed open and to specify the condi-tions for which the penetration is open. Penetrations shall be expeditiously closed upon completion of the conditions specified in the approved procedures.

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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. TABLE 1.1 FACILITY MODES MODE PLANT CONDITION 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 and Reactor Coolant System are defueled to the extent reasonably achievable,

b. The possibility of criticality in the Reactor Builoing 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 TMI-2 site.

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, TABLE 1.2 FREQUENCY NOTATION P

NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days. l A At least once per 12 months. j l

R At least once per 18 months. __

l Not applicable.

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SECTION 2.0 SAFETY LIMITS AND -

LIMITING SAFETY SYSTEM SETTINGS i

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i *2.0 ' SAFETY LIMITS

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

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O a SECTION 3.0 LIMITING CONDITIONS FOR OPERATION THREE MILE ISLAND - UNIT 2 Amendment 30

,3 LIMITING CONDITIONS FOR OPERATION 3.0 APPLICABILITY LIMITING CONDITIONS FOR OPERATION 3.0.1 'imiting Conditions for Operation and ACTION requirements shall be applicable during the FACILITY MODE or other conditions specified for each 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 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 apprtpriate actions to rectify the problem to the extent possible under the circumstances, and submit --

a report to the Commission pursuant to the requirements of Section 50.73 of 10 CFR Part 50.

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THREE MILE ISLAND - UNIT 2 3.0-1 Amendment 30

t!MXT!NG CONDlT10NS FOR OPERATION 3.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 3.1.1 BORATION CONTROL BORATED COOLING. WATER INJECTION 3.1.1.1 The following systems, capable of injecting borated cooling water 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 i System. I

c. The BWST shall contain at least 390,000 galluns of borated water at a l minimum temperature of 50 degrees Fahrenheit and a boron concentration of between 4350 and 6000 ppm.

APPLICABILITY: MODE 1 --

ACTION:

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

b. With both flowpaths from the BWST 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 .

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

d. With the BWST water volume or boron concentration or minimum temperature out-of-specification, suspend all operations involving CORE ALTERATIONS and/or the Reactor Coolant System and restore the BWST to specification

'within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

J THREE MILE ISLAND - UNIT 2 3.1-1 Amendment 30

LIMlTING CONDITXONS FOR OPERATXON ;

BORON CONCENTRATION - REACTOR COOLANT SYSTEM 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: M00' 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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THREE MILE ISLAND - UNIT 2 3.1-2 Amendment 30

.LIMATXNG CONDXT10NS FOR OPERAT10N BORON CONCENTRATION - FUEL TRANSFER' CANAL ;

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.

APPLICABILITY: MODE 1 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.

BORON CONCENTRATION - SPENT FUEL POOL "A" 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: ~[

If the above conditicn 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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l TH.1 ! M:'.E ISLAND - UNIT 2 3.1-3 Amendment 30 a

.~ ..

. LXMfTING CON 0!T10NS FOR OPERAT10N 3.3 INSTRUMENTATION

3. 3.1' NEUTRON MONITORING INSTRUMENTATION INTERMEDIATE AND SOURCE P.ANGE NEUTRON FLUX MONITORS ,

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.

AP P LICABi.'Li 1Y: 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 REC 0VERY OPERATIONS PLAN, restore inoperable channel to 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 -

hours by a mass balance calculation and at least once per 7 days by a chem-ical analysis and restore at least one source range neutron monitoring channel to operable status within 7 days. '

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

r 3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION OELETED 3.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION i I

3 3.3.1 The radiation monitors listed in Table 4.3-3 of the RECOVERY OPERATIONS a FLAN shall be OPERABLE-

APPLICABILITY: MODES 1, 2 and 3 as Required in Table 4.3-3 of the RECOVERY

OPERATIONS PLAN.

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As Required in Table 4.3-3 of the RECOVERY OPERATIONS PLAN 1

1 THREE MILE ISLAND - UNIT 2 3.3-1 Amendment 30 l l

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UMITINGC}NDITIONSFOROPERATXON METEOROLOGICAL INSTRUMENTATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 4.3-5 of the REC 0VERY 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.

ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION 3.3.3.5 The Essential Parameters Monitoring Instrumentation shall be OPERABLE in accordance with the requirements of Table 4.3-7 of the REC 0VERY OPERATIONS PLAN.

APPLICABILITY: MODE 1 ,

ACTION:

- instrumentation not in accordance with the requirements of Table 4.3-7 the REC 0VERY 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 .

CHLORINE DETECTION SYSTEMS 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 ppn, shall be OPERABLE:

a. 'One at the air intake tunnel, and l

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

APPLICABILITY: MODE 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 1 recirculation mode of operation; restore the incperable detection system to l OPERABLE status within 30 days. l l

FIRE DETECTION INSTRUMENTATION I 3.3.3.8 As a minimum, the fire detection instrumentation for ear.k fira detection

ene shown in Table 4.3-11 of the RECOVERY OPERATIONS PLAN shall La CeERABLE.

THREE MILE ISLAND - UNIT 2 3.3-2 Amendment 30

0 4 LINITVNG CON 0!TXONS FOR OPERATXON APPLICABILIT(: 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 ir.stru-ment with the same coverage is OPERABLE, or;

1. Within I hour, establish a 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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I THREE MILE ISLAND - UNIT 2 3.3-3 Amendment 30 J

tXMITING CONDITIONS FOR OPERATION 3.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS 3.4.1 Deleted .

REACTOR VESSEL WATER LEVEL MONITORING 3.4.2 As a minimum two independent reactor vessel level monitoring instruments shall be OPERABLE.

APPLICABILITY: MODE 1 ACTION

a. With only one reactor vessel 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 instru-ment to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ;

3.4.9 PRESSURE / TEMPERATURE LIMITS l

l REACTOR COOLANT SYSTEM '

3.4.9.1 The Reactor Coolant System shall be maintained between a T of less than 200*F and greater than 50*F. avg 3.4.9.2 The Reactor Coolant System shall remain open to the reactor building ;

atmosphere unless repressuriz: tion is approved.in a safety evaluation submitted to the NRC. This safety evaluation shall specify the maximum 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 to within limits and submit a report pursuant to Specification 3.0.3.

THREE MILE ISLAND - UNIT 2 3.4-1 Amendment 30 i ._

V. . .

, - IMITING CONDITIONS FOR OPERATION ~

3.5 COMMUNICATIONS ,

3.5.1 Control Roem Direct communication shall be maintained between the Control Room or the Com-mand Center and personnel in the Reactor Building. As stated in Table 6.2-1 the additional SOL or SOL, limited to fuel handling, notwithstanding location, will have direct communications with personnel in the' Reactor Building performing CORE ALTERATIONS.

APPLICA3ILITY: MODE 1 during CORE ALTERATIONS ACTION:

When direct communication between the Control; Room or the Command Center and personnel in the Reactor Building as stated in the above specification cannot be maintained, suspend all operations involving CORE ALTERATIONS and restore communications to OPERABLE status.

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THREE MILE ISLAND - UNIT 2 3.5-1 Amendment 30

LI'MITlNG CONDTTIONS FOR OPERATION 3.6 CONTAINMENT SYSTEMS 3.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY 3.6.1.1.a Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODE 1 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. --

3.6.1.1.b Modifications to Containment Penetrations may be made provided a single isolation barrier is maintained.

APPLICABILITY: MODE 1 ACTION:

With no isolation barriers provided, the following activities in containment tre prohibited:

a. Core Alterations.

b. Heavy load lifts in the Reactor Building *

c. Activities which could result in a fire in the Reactor Building (e.g. ,

welding, burning). '

l "This does not preclude completion of those activities necessary to place the plant in a safe configuration. l THREE MILE ISLAND - UNIT 2 3.6-1 Amendment 30 l

., 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* Unit Cooling Water R-584*

R-587* R-580*

3-583* Reactor Building Spray BS R-586* Inlet Line R-589* Decay Heat Coolant Supply DH R-590*

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

R-537* Nitrogen and Fill to Core CF Flooding Tank R-539* Leakage Cooling DC R-542* Pressurizer Auxiliary Spray OH R-544* Nitrogen and Fill to Core CF Flooding Tank R-55'7* Nuclear Services Closed Cooling NS Water to Reactor Coolant Pump Oil and Motor Coolers R-559* Intermediate Closed Cooling Water IC to Roller Nut Drive Cooling Coils R-563* Intermediate Closed Cooling System IC R-566* Service Air SA R-570* High Pressure Injection MU R-572*

R-545A# Building Pressure BS R-554C#

R-571C#

THREE MILE ISLAND - UNIT 2 3.6-2 Amendment 30

~

TABLE 3.6-2 (Cont'd)

Penetration Function System R-562C# Building Spray System BS j Pressure System R-593# Sump Penetration Sleeve- OH R-594# and Drain Line ;

l R-616# Auxiliary Feedwater Lines EF R-623#

1 R-617# Feedwater Lines FW ;

R-618# l R-619# Steam Line MS R-620# j R-621#

R-622#

R-524** Fuel Transfer Canal Fill SF _

R-525** Isolation Valve Test for Decay DH '

i Heat LIne )

R-535** Demineralized Service Water DW 1 R-548** Fire Service FS R-569"* Secondary Flush and Drain SV CODES: BS--Reactor Building Spray CF--Core Flooding l DC--Decay Heat Closed Cooling Water DH--Decay Heat Removal EF--Emergency Feedwater l FW--Feedwater l IC--Intermediate Closed Cooling Jater l MU--Makeup and Purification i RR--Reactor Building Emergency Cooling - River Water l SA--Station Service Air l MS--Main Stream i NS--Nuclear Services Closed Cooling Water SF--Spent Fuel Cooling DW--Demineralizer Service Water FS--Fire Service SV--Steam Generator and Secondary Side Vents and Orains Penetrations which utilizs a check valve inside containment as a containment I isolation valve.

Penetrations which have single valve isolation.

Penetraticns which have manual isolation valves inside the Reactor Building that are not capable of remote operations from a control station outside of Reactor Building.

THREE MILE If> LAND - UNIT 2 3.6-3 Amendment 30

i 1

. LIMITING CONDITIONS FOR OPERATION i CONTAINMENT ISOLATION 3.6.1.2 Primary CONTAINHENT ISOLATION shall be maintained.

APPLICAB'ILITY:' MODES 2 and 3 ACTION:

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

CONTAINMENT AIR LOCKS (MODE 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 the criteria of Recovery Operations Plan Section 4.6.1.3.1.

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 .

INTERNAL PRESSURE 3.6.1.4 Primary containment pressure shall be maintained from 0 psig to not less than 12.2 psia. -

APPLICABILITY: MODES 1, 2, 3 ACTION:

With the containment internal pressure outside the above limits, restore the internal pressure to within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

AIR TEMPERATURE

3. 6.1. 5 Primary containment average air temperature shall be maintained between 50 F and 130 F.

APPLICABILITY: MODE 1 ACTION:

With the containment average air temperature outside the above limit;, 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 3.6-4 Amendment 30

, kIMITINGCONDITIONSFOROPERATI'ON CONTAINMENT AIR LOCKS (MODES 2 and 3) .

3.6.1.6 Each Containment Air Lock shall be OPERABLE with at least one door closed unless otherwise specified per the' criteria of Recovery Operations Plan

^Section 4.6.1.6.1.

APPLICABILITY: MODES 2 and 3 ACTION:

With no containment Air Lock dcor 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 .

3.6.3 CONTAINMENT PURGE EXHAUST SYSTEM 3.6.3.1 One train of the Containment Purge Exhaust System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 ACTION: -

With no Containment Purge Exhaust train OPERABLE, secure the Containment Purge System and restore one train to OPERABLE status prior to resuming purge operations.

4 THREE MILE ISLAND - UNIT 2 3.6-5 Amendment 30

a

. LIMITING CONDITIONS FOR OPERATION 3.7 PLANT SYSTEMS 3.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM Deleted.

3.7.6 FLOOD PROTECTION 3.7.6.1 Flood protection shall be provided when the water level of the Susquehanna River exceeds 301 feet Meen Sea Level USGS datum, at the river water intake structure of Three Mile Island Nuclear Station, Unit 1.

APPLICABILITY: H0 DES 1, 2, 3 l-ACTION:

a. With the water level at the Unit l' Intake Structure approaching 301 feet Mean Sea Levei USGS d:tum:

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 (500) and as directed by the 500:

(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, (f) Arrange for alternate supplies of diesel fuel oil and ensure fuel storage tanks are filled, and (g) Check that all containers are sealed and secure in the Southeast Storage Facility,

b. With the water level at the Unit 1 Intake Structure exceeding 301 feet and approaching 302 feet Mean Sea levei USGS datum:

1. 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 Director Operations.

THREE MILE ISLAND - UNIT 2 3.7-1 Amendment 30

,LIMITXNG CONDATIONS FOR OPERATION 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM 3.7.7.1 The Control Room Ventilation and Emergency Air Cleanup System shall be-OPERABLE

with:

a. Two Control Room supply Fans and associated cooling coils, I 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 1 l

ACTION:

a. With one Control Room Supply Fan or its associated cooling coil inoperable, -

i restore the inoperable fan and/or cooling coil to OPERABLE status within 7- 1 days. .

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

c. With the filter train inoperable, restore the filter train to OPERABLE l 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 isolation 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 .

Standby onsite AC power (emergency diesel generators) is not required for operability.

THREE MILE ISLAND - UNIT 2 3.7-2 Amendment 30

'LXMITXNG CON 0ZT10NS FOR OPERATION 3.7.9 SEALED SOURCES ~

SEALED SOURCE INTEGRITY 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 > 0.005 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 witharawn 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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l THREE MILE ISLAND - UNIT 2 3.7-3 Amendment 30

LIMITING CONDIT10NS FOR OPERATION 3.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM 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) stoarate water supplies of the following four (4) shall be avail-able 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 tak'ing suction from a water supply and '

transferring the water through distributio* oiping with OPERABLE section-alizing control or isolation valves to the .<ard 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 Specifi-cation 3.7.10.2 and 3.7.10.4.

APPLICABILITY: H0 DES 1, 2 and 3 ACTION:

a. With 3 pumps or 3 water supplies inoperable, restcre 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 .

THREE MILE ISLANO - UNIT 2 3.7-4 Amendment 30 ,

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LIMITING CONDITXONS FOR OPERATXON OELUGE/ SPRINKLER SYSTEMS 3.7.10.2 The Deluge and/or Sprinkler Systems located in the following areas

-shall be OPERABLE:

a. Deleted,

b. Deleted.

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

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

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

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

g. Deleted.

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

i. Waste gas disposal filter WDG-F-1* .

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 suppres-sion 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.

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^^^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 operational only when charcoal filters are installed.

THREE MILE ISLAND - UNIT 2 3.7-5 Amendment 30

. LIMITING CONDlTIONS FOR OPERATION-HALON SYSTEM 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 equip-ment 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.

FIRE HOSE STATIONS -

3.7.10.4 The fire hose stations listed in Table 4.7-1 of 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 .

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

THREE MILE ISLAND - UNIT 2 3.7-6 Amendment 30

LIMfTING CONDXTONS FOR OPERATf0N PENETRATION FIRE BARRIERS 3.7.11 All Penetration Fire Barriers protecting Safety Related areas shall be functional.

APPLICABILITY: ' MODES 1, 2, 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 consid-erations, 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. ~{

THREE MILE ISLAND - UNIT 2 3.7-7 Amendment 30

. LIMIT 1NG CONDTTIONS FOR OPERAT10N 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 A.C. SOURCES

3. 8.1.1 As a minimum, the following A.C. electrical power sources shall'be OPERABLE: -

a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system.

b. Deleted APPLICABILITY: MODE 1 ACTION:

a. With one offsite circuit of the above required A.C. electrical power sources inoperable, verify the OPERABILITY of the remaining offsite circuit and demonstrate the OPERABILITY of the D.C. bus trains by per-forming Surveillance Requirements in the Recovery Operations Plan Sec- -

tions 4.8.2.2.1 and 4.0.2.2.2.a.4 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Restore the full -- '

complement af 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, suspend CORE ALTERATIONS and cease movement of heavy loads in the reactor building.* 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 within 7 days.

This does not preclude completion of those activities necessary to place the plant in a safe configuration.

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l THREE MILE ISLAND - UNIT 2 3.8-1 Amendment 30

, TABLE 3.8-1 TESTING FREQUENCY MATRIX OELETED v

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THREE MILE ISLAND - UNIT 2 3.8-2 Amendment 30

TABLE 3.8-2 l I

RESTORATION TIME MATRIX ;

DELETED THREE MILE ISLAND - UNIT 2 3.8-3 Amendment 30

LIMITING CONDlTIONS FOR OPERAT10N 3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 3.8.2.1 A.C. DISTRIBUTION 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 accordance with site approved procedures) between redundant busses.

APPLICABILITY: MODE 1 ACTION:

With less than the above complement 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 AC electrical busses listed in Section 4.8.2.1.2 of the-RECOVERY OPERATIONS PLAN shall be OPERABLE and energized.

. APPLICABILITY: MODE 1 __

ACTION:

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

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b. With any of the above A.C. busses de-enerized,' 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 THREE MILE ISLAND - UNIT 2 3.8-4 Amendment 30

.LfMXTING CONDXTONS FOR OPERATf0N D.C. DISTRIBUTION 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 2-100, 250/125-volt D.C.

battery bank A and a full capacity charger.

TRAIN "B" consisting of 250/125-volt D.C. bus 2-20C, 250/125-volt D.C.

battery bank B, and a full capacity charger.

APPLICABILITY: MODE 1 ACTION:

a. With one 250/125-volt 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 THREE MILE ISLAND - UNIT 2 3.8-5 Amendment 30

LIMITING CONDITIONS FOR OPERATION 3.9 RADIOACTIVE WASTE STORAGE SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING 3.9.1 Two independent Spent Fuel Storage Pool "A" water level monitoring instruments shall be OPERABLE.

APPLICABILITY: Modes 1 and 2, whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".

ACTION:

a. With only one Spent Fuel Storage Pool "A" water level monitoring instru-ment OPERABLE, immediately verify that the water level is within limits, re-verify the level at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and restore a second instrument to OPERABLE status within 7 days.

b. With no Spent Fuel Storage Pool "A" water level monitoring instruments OPERABLE, terminate all activities involving any Canister containing core material in or over Spent Fuel Storage Pool "A" and all operations 4

involving changes in Spent Fuel Storage Pool "A" water inventory and -"

restore at least one instrument to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SPENT FUEL STORAGE POOL "A" WATER LEVEL 3.9.2 The water level in Spent Fuel Storage Pool "A" shall be maintained as specified in Section 4.9.2 of the Recovery Operations Plan.

APPLICABILITY: Modes 1 and 2, whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".

ACTION:

With Spent Fuel Storage Pool "A" water level not within the specified band, l terminate all activities involving any Canister containing core material in or over Spent Fuel Storage Pool "A" and restore the water level to within specifi-cation within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING 3.9.3 Two independent Fuel Transfer Canal (deep end) water level monitoring instruments shall be OPERABLE.

APPLICABILITY: MODE 1 ACTION:

a. With only one Fuel Transfer Canal (deep end) water level monitoring instrument OPERABLE, immediately verify that the water level is within limits, re-verify the level at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and restore a second instrument to OPERABLE status within 7 days.

THREE MILE ISLAND - UNIT 2 3.9-1 Amendment 30

LXMITING CONDXTXONS FOR OPERATXON

b. With no Fuel Transfer Canal (deep end) water level instruments OPERABLE, terminate all activities involving any Canister containing ' core material in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assembly and all operations involving changes in the Fuel Transfer Canal (deep end) water inventory and restore one inoperable instrument to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

FUEL TRANSFER CANAL (DEEP END) WATER LEVEL 3.9.4 The water level in the Fuel Transfer Canal (deep end) shall be maintained at the level specified in Section 4.9.4 of the Recovery Operations Plan.

APPLICABILITY: MODE 1 ACTION:

a. With the Fuel Transfer Canal (deep end) water level not within the speci-fied band, terminate all activities involving any Canister containing core material in or over the Fuel Transfer Canal (deep end) and/or all activ-ities involving the plenum assembly and restore the water level to within specification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS

, 3.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be OPERABLE with one of the four system air cleanup exhaust fans OPERABLE.

APPLICABILITY: MODES 1, 2 and 3 ACTION:

With the Fuel Handling Building Air Cleanup Exhaust System inoperable, restore the system to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or, suspend all operations involving movement of liquid and solid radioactive wastes in the Fuel Handling Building (other than sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN), the release '

o of which could exceed 50% of the Appendix B Technical Specification instantaneous release rate for gaseous effluents, until the system is ret.tored to OPERABLE status, l

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THREE MILE ISLAND - UNIT 2 3.9-2 Amendment 30

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' LIM! TING COND!TRONS FOR OPERATION 3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shall be OPERABLE with one of the four system air cleanup exhaust fans OPERABLE. .

APPLICABILITY: MODES 1, 2, 3 i ACTION:

With the Auxiliary Building Air Cleanup Exhaust System inoperable, restore the system to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or, suspend all operations involving movement of liquid and solid radioactive wastes in the Auxiliary Building (other than sampling evolutions required by the Technical -

Specifications or RECOVERY OPERATIONS PLAN), the release of which could exceed 50% of the Appendix B Technical Specification instantaneous release rate for gaseous effluents, until the system is restored to OPERABLE status. ,

ACCIDENT GENERATED WATER 3.9.13 Discharge of ACCIDENT GENERATED WATER shall be prohibited until approved by the NRC. Procedures pertaining to the disposal of ACCIDENT GENERATED WATER -- j shall be subject to approval by the NRC prior to implementation.

l APPLICABILITY: MODES 1, 2 and 3 l l ACTION:

, None except as provided in Specification 3.0.3.

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THREE MILE ISLAND - UNIT 2 3.9-3 Amendment 30 i

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. LIMITING CONDITIONS FOR OPERATION 3.10 CRANE OPERATIONS CONTAINHENT BUILDING 3.10.1 Loads in excess of 2400 lbs. shall be prohibited from travel over the following areas unless a docketed Safety Evaluation for the activity is approved by the NRC:

a. reactor vessel

b. incore instrument seal table and guide tubes (includes travel by polar crane block)

c. deep end of the Fuel Transfer Canal

d. any Canister that contains core material regardless of its location

e. areas not previously analyzed in a docketed, NRC approved load drop ,

j analysis __

APPLICABILITY: H0DE 1 ACTION:

With the requirements of the above specification not satisfied, place the crane load in a safe condition and correct the circumstances which caused or allowed the Limiting Condition for Operations to be exceeded prior to continuing crane ,

operations limited by Specification 3.10.1. Prepare and submit a special report to the Commission pursuant to Specification 6.9.2 within the next 30 days.

FUEL HANDLING BUILDING .

1 3.10.2 Loads in excess of 2400 lbs. shall be probibited from travel over the followir g areas unless a docketed Safety Evaluation for the activity is approved by the NRC-l

a. any area of the spent fuel storage pool which contains one or more l Canisters which contain core material l l

b. any Canister that e n'.ains core material, regardless of its location i i c. areas not previously analyzed in a docketed, NRC approved load drop i analysis i

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THREE MILE ISLANO - UNIT 2 3.10-1 Amendment 30 4

llMITING CONDITIONS FOR OPERATION ,

l APPLICABILITY: MODES 1 and 2 .

ACTION:

.With the requirements of the above specification not satisfied, place the crane load in a safe condition and correct the circumstances which caused or allowed the Limiting Condition for Operations to be exceeded prior to continuing crane operations limited by Specification 3.10.2. Prepare and submit a special report '

to the Commission pursuant to Specification 6.9.2 within the next 30 days, l

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THREE MILE ISLAND - UNIT 2 3.10-2 Amendment 30 i

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1 LIMITING CONDITIONS FOR OPERATION l SURVEILLANCE REQUIREMENTS l l

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NOTE .

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The summary statements contained in this section provide the bases for the Specifications of -

Section 3.0 and 4.0 and are not considered a part of these Technical Specifications as provided in 10 CFR 50.3G e

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'3/4.0 APPLYCABTLYTY BASES _

The specifications of this section provide the general requirements applicable to each of the limiting Conditions for Operation and Surveillance Requirements within Section 3/4.

3.0.1 This specification defines the applicability of each specification in terms of the FACILITY MODE or other specified conditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements or when the provisions of the stated ACTION statement are not or cannot be complied with. The intent of this specification is to require that inoperable equipment be restored to an i OPERABLE status in a prompt manner, that the unit be maintained in stable

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conditions, and that the Commission be promptly notified of such conditions. -

4.0.1 This specification provides that surveillance activities necessary to ,

insure the Limiting Conditions for Operation are met and will be performed I during the FACILITY MODE or other conditions for which the Limiting Conditions i for Operation are applicable.

4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allow'able tolerance value and permits the performance of more frequent surveillance activities.

The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not deoraded beyond that obtained from the nominal specified interval.

THREE MILE ISLAND - UNIT 2 B 3/4 0-1 Amendment 30

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'APPLICABfLfTY

. 1 BASES 4.0.3 Tha provisions of this specification set forth the criteria for deter-mination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operations. Under this criteria, equipment, systems or compo-nents are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or compo-nents OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

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J.4.1 MATER INJECTION C00LlNG AND REACTIV1TY CONTROL SYSTEMS BASES I

l 3/4.1.1 BORATION CONTROL AND BORATE 0 COOLING WATER INJECTION l l

The limitation on minimum boron concentration ensures that the core will remain

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subcritical under all credible conditions which may exist during the long-term cooling mode. The maximum boron concentration is provided to ensure that pre-cipitation of boron will not occur in the RCS and thereby cause possible flow i restrictions. The specification requiring the OPERABILITY of systems capable j of injecting borated cooling water into the RCS within the required boron con-cntration limits. The OPERABILITY of equipment for a Reactor Building Sur -

Recirculation System is required to provide a. recirculation path from the '

Reactor Building Sump in the event of an unisolatable leak in the Reactor l Vessel. The required volume of borated water in the BWST provides sufficient l water to provide a continuous supply of water to the vessel during the interim period before tne recirculation flowpath from the Reactor Building Sump can be l placed in service. Minimum boron concentration limits have been'provided for l the Reactor Coolant System. Refueling Canal (deep end) and Spent Fuel Storage '

Pool "A" to provide assurance that any event involving these volumes of water will not result in a margin of safety less than that analyzed for the Reactor ~~

Vessel. In addition, the Canister Handling and Preparation for Shipment :

Safety Evaluation Report and the Defueling Safety Evaluation Report take -

credit for the boron concentration requirements in the refueling canal (deep end) and the spent fuel storage pool "A" to assure that accidental rupturing of a canister in these pools will not resuit in a criticality potential.

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i BASES 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION The neutron monitoring in' trumentation, which was included in the normal Reactor Protection Systerr Instrumentation, provides information regarding the shutdown status of the c are and it will be used to monitor changes in neutron generation.

3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Deleted 3/4.3.3 MONITORING INSTRUMENTATION -

3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that the radiation levels are measured in the areas served by the respective monitors.

d THREE MILE ISLAND - UNIT 2 B 3/4 3-1 Amendment 30

INSTRUMENTATION

. BASES 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that' sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive

. materials to the atmosphere. This capability is required to evaluate the need-for initiating protective measures to protect the health and safety of the public.

3/4.3.3.5 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION The OPERABILITY of the Essential Parameters Monitoring Instrumentation ensures that sufficient information is available on selected plant parameters to '

monitor and assess these variables. Reactor Coolant System temperature indica-tion is provided outside the Control Room in the event that Control Room habitaD'ility is lost. _

3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection systems ensures that an accidental chlorine release will be detected promptly and the Control Room Emergency 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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THREE MILE ISLAND - UNIT 2 8 3/4 3-i Amendment 30

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' INSTRUMENTATION 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. 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 Safety Related 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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THREE MILE ISLAND - UNIT 2 8 3/4 3-3 Amendment 30

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'3/4.4 REACTOR COOLANT SYSTCM BASES 3/4.4.1 REACTOR COOLANT LOOPS Deleted.

3/4.4.2 REACTOR VESSEL LEVEL MONITORING The Reactor Vessel Water Level Monitor ensures that indication is available to monitor for changes in reactor vessel water level. This. capability will provide l 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 LIMIT _

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The Reactor Coolant System minimum temperature is maintained to prevent precipitation of the boron used to maintain subcriticality. Themaximumreac-[

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

Reactor coolant chemistry surveillance requirements are included in the RECOVERY OPERATIONS PLAN. These requirements provide assurance that localized corrosion or pitting in crevice areas, which could tend to pre: note stress .

corrosion cracking in heat affected zones of welds in stainless steel piping c components, will not occur.

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i THREE MILE ISLAND - UNIT 2 B 3/4 4-1 Amendment 30 l

s 4 SASES-

-3/4.5 COMMUNICATIONS .

The requirements for communications capability ensure that personnel in' the Reactor Building can be promptly informed of signi'icant changes in facility l

status or core reactivity conditions during CORE ALTERATIONS.

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THREE MILE ISLAND - UNIT 2 8 3/4 5-1 Amendment 30

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, '3f 4. 6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY is maintained to ensure that radioactive materials l in the Containment Building are not released to the environment in an uncontrolled manner.

3/4.6.1.2 CONTAINMENT ISOLATION Containment Isolation is maintained to ensure the containment is properly maintained as a contamination barrier for the res. al contamination which remains inside the containment.

3/4.6.1.3 CONTAINMENT AIR LOCKS (MODE 1)

The containment air locks mu'st be maintained OPERABLE to provide the appro-priate containment sealing capability. These air locks will te used dm ing --

entries into the containment to ensure that radioactive materials are not being released to the environs. The preferred method for ensuring that radio-active materials are not released during these entries is to maintain at 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 site approved procedures. During periods when both doors are open, the activities listed in Recovery Operatiens Plan Section 4.6.1.3.1.b shall be prohibited to minimize the potential for an uncontrolled release to the envi ron.n ent.

3/4.6.1.4 INTERNAL PRESSURE The negative pressure limit provides assurance that the Contain. Tent will not exceed its design negative pressure differential. The positive pressure limit :

provides assurance that leakage from the Containment will be limited for off- '

site dose consideration. During periods when both doors in either or both per- i sonnel air locks are open, the containment purge system will be operating to i maintain Containment pressure within the limits of the Technical Specifica- '

tions with the restrictions of 4.6.1.3.1.b and 4.6.1.6.1.b also applying.

l 3/4.6.1.5 AIR TEMPERATURE I The average air temperature of the Containment atmospnere is currently being maintained between 50 F and 130*F, This condition will maximize the service life of the instrumentation and equipment installed in the Containment and ensure that Reactor Coolant System temperature does not drop below 50 F vio LOSS-TO-AMBIENT cooling. This temperature will ansure that boron will remain in solution. .

THREE MILE ISLAND - UNIT 2 B 3/4 6-1 Amendment 30

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'3'/4.6__ CONTAINMENT SYSTEMS d

,. BASES _,

3/4.6.'l.6-CONTAINMENTAIRLOCKS(MODES 2AND_3}

'The Containment. Air Locks must be mairitained OPERABLE to provide assurance that the containment is properly maintained as a contamination barrier for the

'rasidual cor,tamination 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, j 3/4.6.3, CONTAINMENT PURGE EXHAUST SYSTEM i

The OPERABILITY requirements for the Containment Purge Exhaust System ensure !

that during Containment purge operations all radioactive particulate material l will be filtered through the HEPA filters prior to release to the atmosphere. !

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THREE MILE ISLAND - UNIT 2 B 3/4 6-2 Amendment 30

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_, 3*/4. 7 PLANT SYSTEMS BASES 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 requirdd to be taken. l l

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THREE MILE ISLAND - UNIT 2 8 3/4 7-1 Amendment 30

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'PEANT SYSTEMS BASES 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 tempe ature 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. Under certain conditions (i.e.,

loss of offsite power combined with a severe accident at Unit 1), it would be required to place TMI-2 in a stable configuration with core alterations suspended. In this case, operability requirements to ensure THI-2 Control Rnom habitability may be temporarily suspended. The OPERABILITY of this system 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 require-ments 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 10 CFR 70.39(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 l

The OPERABILITY of the Fire Suppression Systems ensures that adequate fire I 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 Suppression Systems is adequate to minimize potential damage to Safety Related equipment and is a major element in the Facility Fire Protection Program. Any two of the four main fire pumps provide combined capacity l greater than 3575 gpm.

l 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. l In the 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.

THREE MILE ISLAND - UNIT 2 B 3/4 7-2 Amendment 30

PbANT SYSTEMS BASES 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 Seals 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 l is required to be maintained in the vicinity of the affected seal until 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.

i THREE MILE ISLAND - UNIT 2 B 3/4-7-3 Amendment 30

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SASES 3/4.8 ELECTRICAL POWER SYSTEMS The OPERABILITY of the A.C.' and 0.C. power sources and associated distribution systems ensures that sufficient power will be available when required.

THREE MILE ISLAND - UNIT 2 8 3/4 8-1 Amendment 30

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3/4.9 RADI0 ACTIVE WASTE STORAGE BASES 3/4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING Spent Fuel Storage Pool Water "A" 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 POOL "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 (OEEP ENO) WATER 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 dosa rate, due to the storage of the plenum assembly and Canisters, to acceptable levels.

3/4.9.12 FUEL HANDLING BUILOING/ AUXILIARY BUILDING AIR CLEANUP SYSTEMS The requirement for the Fuel Handling Building / Auxiliary Building Air Cleanup System to be operating or OPERABLE ensures that radioactive material released '

to these buildings will be filtered through the HEPA filters prior to release to the atmosphere. In the event the system are not restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , the Technical Specifications require the suspension of any liquid or solid radioactive waste handling, the release of which could exceed 50% of the instantaneous release rate limits for gaseous effluents specified in Section 2.1.2 of the Appendix B Technical Specifications. These restrictions correspond to solid radioactive waste with a total activity of greater than 1 curie of particulates with half-lives greater than eight (8) I days and liquid radioactive waste with an activity greater than 0.5 curies of l particulates with half-lives greater ,than eight (8) days. l 3/4.9.13 ACCIDENT GENERATED WATER These specifications are provided to ensure compliance with the Commission's l 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 thase 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 prior to release of ACCIDENT GENERATED WATER.

THREE MILE ISLAND - UNIT 2 8 3/4 9-1 Amendment 30

. 3/4.9 RADI0ACT!VE WASTE STORAGE BASES However, the Commission has recognized that there may be emergency situations, not at this time forseen, 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.

ACCIDENT GENERATED WATER, as defined in the settlement of the City of Lancaster litigation, is:

(a) Water that existed in the TMI-2 Auxiliary, Fuel Handling, and Contain .

ment Buildings including the primary system as of October 16, 1979, with exception of water wich 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 pCi/ml or less before processing; (b) Water that has a total activity of greater than one pCi/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 pCi/ml of tritium before processing.

3/4.9.14 Deleted.

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. 3/4.10 DEFUELlNG OPERATf0NS BASES i

I 3/4.10.1 CRANE OPERATIONS - CONTAINMENT BUILDING

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A 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 ' rom the Reactor Vessel. The restriction on movement of loads in excess of the nominal weight of a fuel or control rod assembly and associated handling tool o'.6r 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 in the rupture of a canister containing core material. The restriction on movement of heavy loads in the fuel handling 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. __

THREE MILE ISLAND - UNIT 2 B 3/4 10-1 Amencment 30

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9 SECTION 6.0 ADMINISTRATIVE CONTROLS l

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'6:0 ADMfNSTRATfVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The.0ffice of the Director-THI-2 consists of the Director-TMI-2 and the Deputy Director-THI-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 shif t shall be composed of at least -

the minimun shift crew composition shown in Table 6.2-1.

b. During Mode 1, at least one licensed Operator shall be in the i control room when fuel is in the reactor.

c. During Mode 1, an individual qualified in radiation protection procedures shall be on site 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 I the unit arid any personnel required for other essential functions during a fire emergency.

e. An individual qualified in radiation protection procedures shall be l on site whenever Radioactive Waste Management activities are in l progress. '

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THREE MILE ISLAND - UNIT 2 6-1 Amendment No. 30

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AOMINTSTRATfVE CONTROLS Table 6.2-1 .

MINIMUM SHIFT' CREW COMPOSITION #

LICENSE MODE 1 CATEGORY 50L .

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OL 1 Non-Licensed 2

Shift crew composition may be less than the minimum require-ments #or 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 to accomm'odate unaxpected absence of on duty shift crew members provided immediate action is taken to. restore the -~

shif t crew compos ition to within the minimum requirements' -

of Table 6.2-1.

During CORE ALTER 4TIONS an additional SOL or an SOL limited to fuel handling wil' be stationed on the operating floor, in the command center, or in the control room to directly control the particular CORE ALTERATION activity being performed.

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I THREE MILE ISLAND - UNIT 2 6-2 Amendment No. 30 I l

'ADMINTSTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum quali-fications of ANSI-N 18.1 of 1971 for comparable positions unless otherwise noted in the Technical Specifications.

6.3.2 The Manager, Radiological Controls THI-2 shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975. Each Radiological Controls Technician in responsible positions / Foreman shall meet or exceed the qualifica-tions of ANSI 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved THI-2 Radiation Controls training program. Individaals who do not meet ANSI 18.1-1971 Section 4.5.2 are not considered technicians for pur-poses of determining qualifications but are permitted to perform work for which qualification has been demonstrated. All Radiological Controls Technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall ~~

be maintained under the direction of the Plant Training Manager and shall meet -

or exceed the requirements and recommendations of Regulatory Guide 1.8 cf 1977 and 10 CFR 55.59 except that Radiological Controls training may be under the l direction of Vice President-Radiological and Environmental Controls.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Training Manager and shall meet or exceed the require-ments of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 Technical Review and Control The Office of TMI-2 Division Director and Support Division Vice-Presidents ,

within GPU Nuclear Coporation as indicated in Organization Plan Figure 1.1, '

shall be responsible for ensuring the preparation, review, and approval of documents required by the activities within their functional area of respon-sibility for TMI-2. Implementing approvals shall be performed at the cogni-zant section manager / director level or above. Independent safety review and audit shall be conducted in accordance with this Technical Specification.

Divisions other than the TMI-2 Division will perform the Independent Safety ,

Review of their own procedures affecting THI-2 in accordance with approved I procedures except when they impact the operational status of unit systems or equipment (requires TMI-2 Division concurrence), a significant environmental i impact (requires in line SRG and Environmental Licensing review), or represent ;

an Unreviewed Safety Question (USQ) or Tech Spec change, including Recovery l Operations Plan Change (requires in line SRG review and NRC approval).

4 THREE MILE ISLAND - UNIT 2 6-3 Amendment No. 30 l

ADMINTSTRATIVE CONTROLS ACTIVITIES 6.5.1.1 Each procedure required by Technical Specification 6.8 and other procedures including those for test and experiments and changes thereto shall be prepared by a designated individual (s)/ group knowledgeable in the area affected by the procedure. Each such procedure, and changes thereto, shall be given a technical review by an individuals (s)/ group other than the preparer, but who may be from the same organization as the individual who prepared the procedure or change.

6. 5.1. 2 Deleted.

6.5.1.3 Proposed modifications to unit structures, systems and components shall be designed by an individual / organization knowledgeable in the areas affected by the proposed modification. Each such modification shall be tech-nically reviewed by an individual / group other than the individual / group which designed the modification but may be from the same group as the individual who designet' the modification.

6.5.1.4 Proposed tests and experiments shall be reviewed by a knowledgeable individual (s)/ group other than the preparer but who may be from the same --

division as the individual who prepared the tests and experiments.

6. 5.1. 5 The Security Plan and implementing procedures shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group which prepared them.

6.5.1.6 The Emergency Plan and implementing procedures shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group which prepared them.

6. 5.1. 7 The Recovery Operations Plan and implementing procedures and changes thereto shall be reviewed by a knowledgeable individual / group other than the individual / group which prepared them.

6.5.1.8 Individuals responsible for reviews performed in accordance with 6.5.1.1 through 6.5.1.7 shall include a determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate personnel.

6.5.1.9 Support Division procedures will be reviewed and approved in accordance with their Division level procedures. If the procedure / change impacts the operational status of unit systems or equipment, it must be concurred with by the TMI-2 Division. Unreviewed Safety Question, Technical Specification change (including Recovery Operations Plan change), or Significant Environmental Impact requires line TMI-2 Division and SRG review prior to implementation.

THREE MILE ISLAND - UNIT 2 6-4 Amendment No. 30

ADNINISTRATIVE CONTROLS RECORDS 6.5.1.10 Written records of activities performed under specifications 6.5.1.1 through 6.5.1.8 shall be maintained in accordance with 6.10.

QUALIFICATIONS 6.5.1.11 Responsibile Technic 61 Reviewers shall meet or exceed the qualifica-tions of ANSI /ANS-3.1 - 1978 Section 4.4 for Reactor Engineering, Instrumenta-tion and Control, Chemistry and Radiochemistry, Radiation Protection and Quality Assurance Reviewers or have seven (7) years of appropriate experience in the area of their specialty. All other RTRs shall meet Section 4.6, i.e.,

shall either, (1) have a Bachelor's Degree in Engineering or the physical sciences and three years of professional-level experience in the area being reviewed or, (2) have seven years of appropriate experience in the field of their specialty. An individual performing reviews may possess competence in more than one specialty area. Credit toward experience will be given for advanced degrees on a one-for-one basis up to a maximum of two years.

6.5.2 INDEPENDENT SAFETY REVIEW __

FUNCTION 6.5.2.1 The Office of TMI-2 Division Director and Support Division Vice Presidents within GPU Nuclear Corporation as indicated in Organization Plan Figure 1.1 shall be. responsible for ensuring the Independent Safety Review of the subjects described in 6.5.2.5 within his assigned area of safety review responsibility.

Divisions other than the 'TMI-2 Division will perform the Independent Safety Review of their own procedures affecting TMI-2 in accordance with approved procedures except when they impact the operational status of unit systems or equipment (requires TMI-2 Division concurrence), a significant environmental impact (requires in line SRG and Environmental Licensing review), or represent and Unreviewed Safety Question (USQ) or Tech. Spec. change,' including Recovery Operations Plan Change (requires in line SRG review and NRC approval).

When the Preparer determines a procedure is not Review Significant, the signature of the RTR indicates concurrence with this determination.

6.5.2.2 Independent safety review shall be completed by an individual / group not having direct responsibility for the performance of the activities under review, but who may be from the same functionally cognizant organization as the individual / group performing the original work. For those THI-2 Division documents determined to be Review Significant, the Independent Safety Review shall be performed by or under the cognizance of SRG, 6.5.2.3 GPU Nuclear Corporation shall collectively have or have access to the experience and competence required to independently review subjects in the following areas:

a. Nuclear Unit operations l

b. Nuclear engineering j THREE MILE ISLAND - UNIT 2 6-5 Amendment No. 30 l l

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' ADMINISTRATIVE CONTROLS

c. Chemistry and radiochemistry

d. Metallurgy .

e. Instrumentation and control

f. Radiologi'al safety

g. Mecha,nicci engineering

h. Electrical engineering

i. Administrative controls and quality assurance practices

j. Emergency plans and related organization, procedures and equipment

k. Other appropriate fields such as radioactive waste operation associated with the unique characteristics of TMI-2.

6.5.2.4 Consultants may be utilized to provided expert advice.

RESPONSIBILITIES 6.5.2.5 The following subjects shall be independently reviewed:

a. Written safety evaluations of changes in the facility as described in the Safety Analysis Report, Technical Evaluation Reports, or docketed System Descriptions, changes in procedures as described _

in the Safety Analysis Report, Technical Evaluation Repurts, or docketed System Descriptions, and tests or experiments not described in the Safety Analysis Report, Technical Evaluation Reports, or docketed System Descriptions, which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1). This review of ,

items determined not to be Review Significant when performed by SRG '

is a supplemental review to verify that such changes, tests or experiments did not involve a change in the Technical Specifications j or an Unreviewed Safety Question. l l

b. Proposed changes in procedures, proposed changes to the facility, i or proposed tests or experiments, any of which involves a change in the Technical Specifications or an Unreviewed Safety Question )

shall be reviewed by SRG prior to implementation. Changes to Review '

Significant procedures which revision is not deemed to be Review Significant shall not be required to be reviewed by SRG prior to implementation.

c. Proposed changes to Technical Specifications or license amendments shall be reviewed by SRG prior to submittal to the NRC for approval.

d. Violations, deviations, and reportable events which require either one or four hour immediate notification to the NRC. Such reviews are performed after the fact. Review of events covered under this subsection shall include results of any investigations made and the recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event. SRG shall review all one or four hour immediate notifications and make recommendations as appropriate.

e. Investigaticn of all reportable events including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, shall be reviewed by TMI-2 SRG.

THREE MILE ISLAND - UNIT 2 6-6 Amendment No. 30

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ADMINISTRATIVE CONTROLS c '

f. Special reviews, investigations or analyses and reports thereon as requested by the Office of the Director TMI-2 or other manager reporting directly to the Office of the Director TMI-2 shall be j performed by THI-2 SRG.

g. Writt'en summaries of audit reports in the area specified in Section 6.5.3.

h. Recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components, that could affect nuclear safety or radioactive waste safety.

. i. Any other matters involving safe operation of the nuclear power plant which the SRG deems appropriate for consideration, or which are referred to the SRG 6.5.2.5 For those subjects which are REVIEW SIGNIFICANT the Independent Safety Review will be performed by an individual (s) meeting the qualifications of Section 6.5.4.7.

RECORDS 6.5.2.7 Reports of reviews encompassed in Section 6.5.2.5 shall be maintained in accordance with 6.10.

6.5.3 Audits 6.5.3.1 Audits of unit activities shall be performed in accordance with the THI-2 Recovery QA Plan. These audits shall encompass:

a. The conformance of unit operations to provisions contained within the Technical Specifications and applicable license conditions. The audit frequency shall be at least once per 12 months.

b. The performance, training and qualifications of the entire unit staff. The audit frequency shall be at least once per 12 months.

c. The verification of the nonconformances and corrective actions pro-gram as related to actions taken to correct deficiencies occurring in unit equipment, structures, systems or methods of operation that affect nuclear safety. The audit frequency shall be at least once per 6 months.

d. The performance of activities required by the Recovery Quality Assurance Plan to meet the criteria of Appendix "B", 10 CFR 50.

The audit frequency shall be at least once per 24 months.

e. The Emergency Plan and implementing procedures. The audit frequency shall be at least once per 12 months. l

f. The Security Plan and implementing procedures. The audit frequency shall be at least once per 12 months.

l THREE MILE ISLAND - UNIT 2 6-7 Amendment No. 30 !

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' ADMINISTRATIVE CONTROLS

g. The Radiation Protaction Plan and implementing procedures. The audit -

frequency shall be at least once per 12 months. ,

b. The Fire Protection Program and implementing procedures. The audit frequency shall be at least once per 24 months.

i. An independent fire protection and loss prevention program inspection and technical audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm,

j. An inspection and technical audit of the fire protection and loss prevention program, by an outside qualified fire consultant at intervals no greater than 3 years.

k. Any otner area of unit operation considered appropriate by the SRG, the Manager, SRG's immediate supervisor, other managers reporting directly to the Office of the Director THI-2, the Office of the Director THI-2, or the Office of the Prasident - GPUNC. any other areas required to be audited by QA will be identified to the appropriate QA Management level. --

RECORDS 6.5.3.2 Audit reports encompassed by sections 6.5.3.1 shall be forwarded for action to the management positions responsible for the areas audited and SRG within 60 days after completion of the audit. SRG will review specified audits performed by QA and make corrective action recommendations as appropriate.

6.5.4 Safety Review Group (SRG)

FUNCTION 6.5.4.1 The SRG shall be a ful'-time group of engineers, independent of the Site Operations of Engineering staff, and located onsite within the THI-2 division. (See Organization Plan Figure 1.2.)

ORGANIZATION 6.5.4.2 The THI-2 SRG shall consist of the Manager, SRG and a minimum staff of 5 engineers.

The SRG shall report within the THI-2 Division independent of the unit opera-tions and engineering functions, but no lower in the organization than one level below the Office of the Director TMI-2.

RESPONSIBILITY I

6.5.4.3 The Manager, SRG is advisory to the Office of the Director TMI-2.

However, he has the authority and responsibility to bring to the attention of :

the Office of the President GPUNC any issues he believes are not being addressed with adequate consideration of nuclear or radiological safety.

THREE MILE ISLAND - UNIT 2 6-8 Amendment No. 30 1

' AbeINISTRATIVE CONTROLS 6.5.4.4 The review functions of the SRG shall include:

(1) the independent safety review activities stated in Section 6.5.2.5.

(2) aisessnient of unit operations and performance and unit safety programs from a nuclear cafety perspec,tive.

(3) any other i. tter involving safe nuclear operations at the nuclear power plant that the Manager, SRG, the Manager, SRG's immediate supervisor, or other managers reporting directly to the Office of the Director ich-2 deem appropriate for consideration.

6.5.4.5 For those reviews requiring expertise outside that possessed by SRG, SRG is authorized to require reviews by other company groups as deemed appropriate by the Manager, SRG. SRG may also utilize consultant expertise as it deems approp-iate.

Authorij 6.5.4.6 The SRG shail have access to the unit and unit ree.ords us necessary to perform its evaluations a..d assessments. Based on its .-eviews, the SRG -

shall provide recommendations to the management positions responsible for the areas reviewed. Th, SRG shall have authority to require independent reviews by other organizations as necessary to complete its functional respor.sibilities.

The Manager, SRG is advisory to the Office of the Diree'or THI-2. However, he has the authority and respoasibility to bring to the attention of the Office of the President any issues he believes are not being addressed with adequate consideration of nelear or radiological safety.

OUALIFICATION',

6.5.4 7 The SRG engineers shall have either; (1) a Bachelor'< Degree in Engiaaering or tne Physical Sciences and five (5) years of profet sional level experienc? in the nuclear power field including technical suppcrting functions, or, (2) 9 years of aporopriate experience. Credit *oward experience will be giver, for advaace degrees on a one-to-one basis up to a maximum of two years.

The Maneger, SRG, shall meet or exceed the requirements of section 4.7 of ANSI /ANS 3.1-lS78. i i

RECORDS 6.5.4.8 A'though day to ty results of evaluations by the SRG are communicated directly to the respons% der ranc by the SRG, special reports are prepared only for items deemed ap' ri - ay SRG ' 'oncurreo with by the Manager, SRG's l immediate supervisor. Taes- '

al rec ~ , / evaluations and assessments by !

SRG sh&ll be prepared, app'.- C ' o a r. e itted to the Office of the l Director, THI-2 and the mr 1 u3onsible for the area reviewed l through the Manager, SRG, .t- . These reports shall be '

maintained for the life at tn - .e.

-l TEREE MILE ISLAND .l4IT 2 6-9 Amendmert No. 30 l l

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' ADMINISTRATIVE CONTROLS

6. 6 REPORTABLE EVENTS ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Con.iission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the SRG and a report submitted to the Manager, SRG's immediate superviso. and the Office of the Director THI-2.

c. Ocleted.

6.7 SECTION DELETED 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The appli:able procedures recommended in Appendix "A" of Regulatory -

Guide 1.33, Revision 2, February 1978. .

b. Recovery Operations Plan implementation.

c. Surveillance and test ac'tivities of safety-related equipment and radioactive waste management equipment,

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Radiation Prote: tion Plan implementation.

g. Limiting tha amount of overtime workid by plant staff members performing safety related functions in accordance with the NRC policy statement on working hours as transmitted by Generic Letter 82-12.

6.8.2.1 Each procedure and any change to cny procedure prepared pursuant to 6.8.1, shall be preparr.d, reviewed and appro"ed in accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.

6 2.2 Deleted.

6.8.3.1 Temporary changes to procedures of 6.8.1 may be made provided that:

a. The intent of the original procedure control is not altered, and THREE MILE ISLAND - UNIT 2 6-10 Amendment No. 30

' ADMINISTRATIVE CONTROLS

b. (1) For those procedures which affect the operational status of unit systems or equipment, the change is approved by two members of the .

unit m?nagement staff, at least one of whom holds a Senior Reactor Operator's License. If one of the two above signatures is not by a supervisory person within the Depa.*tment having cognizance of the procedure being changed, the signature of that supervisory person within the department will also be raquired, or (2) For those procedures which do not affect the operational status of unit systems or equipment, the change is approved by two members of the responsible organization. If one of the two above signatures is not by a section manager / director within the Department having cognizance of the procedure being changed, the signatuie of that section manager / director within the department will also be required, and

c. The change is documented, Independent Safety Review completed, and the required reviews and approvals are obtained within 14 days, and

d. Those changhs to procedures required by Specification 3.9.13 are -

submitted to the NRC for review within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months follouing approval by the management level specified for implementation by Section 6.5.1.9.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC Region I Administrator unless otl erwise noted.

ANNUAL REPORTS 1 6.9.1.4 Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 1 of each year. .

6. 9.1. 5 Reports required on an annual basis shall include:

a. A tahulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr ,

and their associated man rem emosure according to work and job func- ;

tions,2 e.g., reactor operations and surveillance, inservice inspec- i tion, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. The dose assignment to various duty functions may be es'imates based on pocket dosimeter, TLD, or film L

1A single submittal may be made for a multiple unit station. The su5mittal j should combine those sections that are common to all units at the station. I 21his tabulatior, supplements the requirements of 6 20.407 of 10 CFR Part 20. 1 THREE MILE ISLAND - UNIT 2 6-11 Amendment No. 30

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, ADMINISTR_ATIVE CONTROLS ANNUAL REPORT 1 (Continued) badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assignea to specific major work _ functions.

b. The following information on aircraft movements at the Harrisburg International Airport:

1. The total number of aircraft movements (takeoffs and landings) at the Harrisburg International Airport for the previous twelve-month period.

2. The total number of movements of aircraft larger than 200,000 pounds, based on a current percentage estimate provided by the airport manager or his designee.

RADIATION SAFETY PROGRAM REPORT 6.9.1.6 Deleted. -~

REPORTABLE OCCURRENCES 6.9.1.7 Deleted.

PROMPT HOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 Deleted. ;

THIRTY DAY WRITTEM REPORTS 6.9.1.9 Deleted.

REPORTING REQUIREMENTS FOR INCIDENT WHICH OCCURRED ON HARCH 28, 1979 l 6.9.1.10 Section Deleted. All reporting requirements completed.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC Region I Administrator within the time period specified for each report.

E.10 RECORD RETENTION 6.10.1 The fol ading records shall be retained for at least five years:

a. Records of sealed source and fission detector leak tests aro results,

b. Records of annual physical inventory of all sealed source material of record.

THREE MILE ISLAND - UNIT 2 6-12 Amendment No. 30 m -

ADMINTSTRATfVE CONTROLS RECORD RETENTION (Cor.tinued)

c. Records of changes made to the procedures required by Specifications 6.8.1.d and e.

6.10.2 The following records shal' be retained as long as the Licensee has an NRC license to operate or possess toe Three Mile Island facility,

a. Records and logs of unit. operation covering time interval at each pr . . level,

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety and radioactive waste systems.

c. ALL REPORTABLE EVENTS submitted to the Commission,

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Spec;ficatioas --

6.8.1.a b., c., and f. .

f. Radiation Safety Program Reports and Quarterly Recovery Progress Reports on the March 28, 1979 incident,

g. Records of radioactive shipments.

h. Records and logs of radioactive waste systems operations.

i. Records and drawing changes reflecting fa'cility design modifications made to syttems and equipment described in the Safety Analysis Report, TER, 50, or Safety Evaluation previously submitted tc' NRC.

j. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

k. Records of transient or operational cycles for those unit components designed for a limited number of transients or cycles.

1. Records of reactor tests and experiments.

m. Records of training and qualifica'. ion for current members of the unit staff. ;

n. Records of in-service inspections performed pursuant to these j Technical Specifications. ;

o. Records of Quality Assurance activities reou -ed by the Operating d

Quality Assurance Plan.

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

q. Records of meetings of the Plant Operation Review Committee (PORC) ,

and the General Review Committee (GRC) and reports of evaluations.

prepared by the SRG.

r. Records of the incident which occurred on March 28, 1979.

s. Records of unit radiation and contamination surveys.

t. Records of radiation exposure for all individuals entering radiation

. control areas.

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

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent --

with the requirements of 10 CFR Part 20 and shall be approved, maintained and ,

adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area shall be controlled as specified in the Radiation Protection Plan.

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THREE MILE ISLAND - UNIT 2 6-14 Amendment No. 30

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