Text

Amend 30 to License DPR-73,modifying Tech Spec Sections 1,2, 3,3/4 & 6 to Align License Requirements W/Plant Conditions
	ML20195B688
Person / Time
Site:	Three Mile Island
Issue date:	05/27/1988
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20195B673	List: ML20195B666; ML20195B688; ML20195B699;
References
	NUDOCS 8806210484
	Download: ML20195B688 (91)
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UNITED STATES

NUCLEAR HEGULATORY COMMISSION g W. l WASHING ton. D. C. 20555

% ,, .; ,f GPU NUCLEAR CORPORATION 00CKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, Oh!T NO. 2 AMENDNENT TO FACILITY OPERATING LICENSE Amencrent No. 30 License No. OPR-73

1. The Nuclear Regulatory Comission (the Commission) 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 stardards 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 regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance wit 5 the Comission's regulations; D. The issuance of this amendment will not be iniinical to the comen defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 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 para 9raph 2.c.f2) of Facility Operating License No. OPR-73 is hereby amended to read as follows:

I2) Technical Soecifications The Tec.hnical Specifications contained in Appendix A, as revised through Amendment No. 30, are hereby incorporated 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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/J n F. Stolz, Director

! Project Directorate I-

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

Attachment:

Changes to the Technical Specifications Date of Issuance: MAy 2 7 jggg

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ATTACHMENT TO LfCENSE AMENDMENT NO. 30 ,

FACILITY OPERATING LICENSE NO. OPR-73 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.

s Remove Insert Cover Page Cover Page Index Index Section 1 Section 1 Section'2 Section 2 Section 3- Section 3 Section 3/4 Section 3/4 Section 6 Section 6 .

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

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to License No. OPR-73

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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 M00E.............................................................. 1-1 1.4 ACTI0N............................................................ 1-1 1.5 OPERABLE - OPERABILITY............................................ 1-1

1. 6 REPORTABLE EVENT................................................. 1-1 1.7 CONTAINMENT INTEGRITY............................................. 1-2 1.8 CHANNEL CALIBRATION............................................... 1-2

1. 9 CHANNEL CHECK..................................................... 1-2 1.10 CHANNEL FUNCTIONAL TEST........................................... 1-4 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 LCSS TO AMBIENT................................................... 1-5 1.17 ACCIDENT GENERATED WATER.......................................... 1-5 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 ISLAND - UNIT 2 i Amendment 3'

51 , s-2NDEX 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

. 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 INSTT.UMENTATION 3.3.1 . NEUTRON MONITORING INSTRUMENTATION........................... 3.3-1 Intermediate and Source Range Neutron Flux Monitors.......... 3. 3-T 3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION... 3.3-1 3.3.3 MONITORING INSTRUMENTATION................................... 3.3-1 r 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 9 Reactor Coolant System....................................... 3.4-1

3. 5 COMMUNICATIONS 3.5.1 CONTROL R00M................................................. 3.5-1 3.6 CONTAINMENT SYSTEMS l

3.6.1 PRIMARY CONTAINMENT.......................................... 3.6-1 i Containment Integrity........................................ 3.6-1 Containment Isolation........................................ 3.6-4 l THREE MILE ISLAND - UNIT 2 iii Amencment 30 i

O' 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 l

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.................... 3.7-2_

3.7.9 SEALED SOURCES............................................... 3.7-3' 3.7.10 FIRE SUPPRESSION SYSTEMS..................................... 3.7-4 Fire Suppression 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. SOURCES................................................. 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 THREE MILE ISLAND - UNIT 2 iv Amendment 30 1

n INDEX LIMITING CONDITIONS FOR OPERATION SECTION +

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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 HANDLING BUILDING....................................... 3.10-1 THREE MILE ISLANO - UNIT 2 v Amendment 30

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 BORATION 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 SYSTE*'

3/4.4.1 REACTOR COOLANT L00PS........................................ B 3/4 4-1 3/4.>.2 REACTOR VESSEL WATER LEVEL MONITORING........................ B 3/4 4-1 3/4.4.9 PRESSURE / TEMPERATURE LIMIT................................... B 3/4 4-1 THREE MILE ISLAND - UNIT 2 vi Amendment 30

y INDEX LIMITING CONDITIONS FOR OPERATION SECTION PAGE 3/4.5 COMMUNICATIONS.................................................. B 3/4 S-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 Containment Airlocks (Mode 1)................................ B 3/a 6-1 Inte rnal P re s su re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 E-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 l

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 PENET RATION FIRE BARRI ER. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 ENO) WATER LEVEL MONITORING. . . . . . . . . B 3/4 9-1 3/4.9.4 FUEL TRANSFER C ANAL (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 i

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INDEX DESIGN FEATURES SECTION

_PA_G_E 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 THREE MILE ISLAND - UNIT 2 viii Amendment 30 s

m INDEM ADMINISTRATIVE CONTROLS SECTION PAGE 6.0 ADMINISTRATIVE CONTR0LS........................................... 6-1 6.1 RESPONSIBILITY.................................................... 6-1 6.2 ORGANIZATION

6. 2.1 GPUNC Organization.............................................. 6-1 6.2.2 TMI-2 Organization.............................................. 6-1 6.3 UNIT STAFF QUALIFICATIONS......................................... 6-3 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 AUDITS......................................................... 6-7 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............................................. 6-8 6.5.4.6 Authority.................................................. 6-9 !

6.5.4.7 Qualifications................................ ............ 6-9 i 6.5.4.8 Records.................................................... 6-9 ;

6.6 REPORTABLE EVENTS ACTI0N......................................... 6-10 6.8 PROCEDURES........................................ .............. 6-10

. 1 THREE MILE ISLAND - UNIT 2 ix Amencment 30 l

INDEX ADMINISTRATIVE CONTROLS -

'SECTION PAGE ,

6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES.................... 6-11 i 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 i

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1 SECTION 1.0 DEFINITIONS gemo t

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t 1.0 DEFINITIONS l

DEFINED TERMS 1.1 The OEFINED 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 Cotunission prior to implementation.

MODE 1.3 The FACILITY MODE shall correspond to the plant conditicr.s specified in Table 1.1. Prior to the transition to the following Facility Mode, a report sha*,1 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 e technical provisions of 10 CFR 50 and the appendices thereto, to TMI-2 in ;

Facility Mode 2 and thereafter, and demonstrates that necessary 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, compnnent or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources,

. cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also capable of perferming their related support function (s).

REPORTABLE EVENT

1. 6 A REPORTA8LE EVENT shall be any of those conditions specified in Specifications 50.73 of 10 CFR Part 50.

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

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. 1.0 DEFfNXT10NS 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'~

ce 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 OPERABLE pursuant to Specification 3.6.1.3.

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

e. ' Water level in Spent Fuel Pool "A"/ Fuel [ransfer Canal is maintair.ed 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, overlapping 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 l

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>s Y '1.0 DEFINITIONS 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 OEFINITIONS CHANNEL FUNCTIONAL TEST l'.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 corraspond 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 hycrant curb valves, and the first valve upstream of the wa.er r flow alarm device on each

-sprinkler, hose standpipe or spray system risu .

REVIEW SIGNIFICANT 1.14 REVIEW SIGNIFICANT items shall consist of items that are Important to Safety, or proposed changes to Technical Specifications, License, Special Orcers or Agreements, Recovery Operations Plan, Organization Plan, or involve an Unreviewed Safety Question or a Significant Environmental Imnact. Also, those. system operating procedures and associated emergency; donormal, alarm response procedures which require NRC approval. In addition, those activities not-covered by an NRC approved system description, SER or TER and wnich exceed PEIS values.

THREE MILE ISLAND - UNIT 2 1-4 Amendment 30

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-TO-AMBIENT is a passive cooling mode by which decay heat, generated by the reactor core, is removed and transferred to the surrounding environment by air and passive components (i.e., Reactor Vessel) inside the Reacter 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 Ci/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 aod becomes contaminated by use in cleanup; (c) Water that contains greater than 0.025 pCi/ml of tritium before processing.

1.18 LICENSED OPERATOR (OL) - any individual who possesses an NRC operator's Ticense 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 segulatory Commission to supervise fuel handling and core alteration operations.

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1.0 DEFINITIONS

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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. .

THREE MILE ISLAND - UNIT 2 1-6 Amendment 30 i

? TABLE 1.1 FACILITY MODES MODE PLANT CONDITION ,

1 The reactor shall be ;beritical with an average reactor coolant terre /ature of less than 200 F.

2 Mode 2 shall exis! < hen the following conditions are met:

a. The Reacto lessel and Reactor Coolant System are defue's J to the extent reasonably achievable.

b. The pos! Jility of criticality in the Reactor Buildir. is precluded,

c. There tre. no canisters containing core material in tri Peactor Building.

-3 Mode 3 .1411 exist when the conditions for Mode 2 ,

are m' end no canisters containing core material are <.'ored on the THI-2 site.

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1 TABLE 1.2 !

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

O 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.

A At least once per 12 months.

R At least once per 18 months. __

N.A. , Not applicable.

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THREE MILE ISLAND - UNIT 2 1-8 Amendment 30

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SECTION 2.0 SAFETY LIMITS AND _

LIMITING SAFETY SYSTEM SETTINGS 9

o 2.0 ' SAFETY LIMITS o.

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

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9 fu SECTION 3.0 LIMITING CONDITIONS FOR OPERATION THREE MILE ISLAND - UNIT 2 Amendment 30 t

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_3 LfMITfNG CONDXT!ONS FOR OPERATION O

3.0 APPLICABILITY LIMITING CONDITIONS FOR OPERATION 3.0.1 Limiting 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 appropriate actions to rectify the problem to the extent possible under the circumstances, and submit --

a report to the Commission pursuant to the requirements of Section 50.73 of .

10 CFR Part 50.

THREE MILE ISLAND - UNIT 2 3.0-1 Amendment 30 t

LIMITING CONDITIONS FOR OPERATION 3.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 3.1.1 BORATION CONTROL

.B0 RATED 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 Berated Water Storage Tank and common drop line.

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

c. The BWST shall contain at least 390,000 gallons 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 _.

l ACTION:

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

b. With both flowpaths from the 8WST 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 dedir

Reactor Building Sump Recirculation System inoperable, restore operabio ..atus within 7 days,

d. With the BWST water volume or boron concantration or minimum temperature out-of-specification, sMpend all operatitans involving CORE ALTERATIONS and/or the Reactor Coolant S3 stem and restore the BWST to specification within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

l THREE MILE ISLAND - UNIT 2 3.1-1 Amendmer.t 30

LXMfTXNG CON 08TIONS FOR OPERATTON O.

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: MODE 1

. ACTION:

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

L i

THREE MILE ISLAND - UNIT 2 3.1-2 Amendment 30 l

L_

LIMITING CON 0XTXONS FOR OPERATION

-0 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 condition is not satisfied (boron concentration between 4350 and 6000 ppm), take action necessary to restore the boron concentration to within acceptable limits. -

4 THREE MILE ISLAND - UNIT 2 3.1-3 Amendment 30 y .,,y .

,,-,-a, ,y . ~ , , - - -,,, , . - , n nw w-w--m - - -- --- --- - - - r my- -- n v +-

i

. LXMfTANG CONDXTXONS FOR OPERATION i

3.3 INSTRUMENTATION 3.3.1 NEUTRON MONITORING INSTRUMENTATION INTERMEDIATE AND SOURCE RANGE 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 RECOVERY OPERATIONS PLAN shall be OPERABLE.

APPLICABILITY: MODE 1 ACTION:

a. With the number of source range neutron monitoring channels CPERABLE one lets than required by the Minimum Channels OPERABLE requirement of Table 4.3-1 of the RECOVERY 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by a mass balance calculation and at least once per 7 days by a chem-ical analysis and restore at least one source range neutron monitoring channel to operable status within 7 days. j

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

3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION DELETED l 3.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION

3. 3. 3.1 The radiation monitors listed in Table 4.3-3 of the RECOVERY OPERATIONS PLAN shall be OPERABLE APPLICABILITY: MODES 1, 2 and 3 as Required in Table 4.3-3 of the RECOVERY OPERATIONS PLAN.

l l ACTION:

As Required in Table 4.3-3 of the RECOVERY OPERATIONS PLAN THREE MILE ISLAND - UNIT 2 3.3-1 Amendment 30

E LIMITING CONDITIONS FOR OPERATION M_ETEOR0 LOGICAL INSTRUMENTATION

3. 3. 3. 4 The meteorological monitoring instrumentation channels shown in Table 1 4.3-5 of the REC 0VEkY OPERATIONS PLAN shall be OPERABLE. ]

APPLICABILITY: MODES 1 and 2 ACTION:

l 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:

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

CHLORINE DETECTION SYSTEMS 3.3.3.7 Two chlorine detection systems, with their alarm / trip setpoints adjusted to actuate at a chlcrine concentration of less than or equal to 5 ppm, shall be OPERABLE:

z. 'One at the air intake tunnel, and

b. One at the Control Rocm air supply duct.

APPLICABILI1<: M0CE 1 ACTION:

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

FIRE DETECTION INSTRUMENTATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 4.3-11 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.

THREE MILE ISLAND - UNIT 2 3.3-2 Amendment 30 i

e LIMITING CONDITIONS FOR'0PERATION-APPLICABILITY: MODES 1, 2 and 3 ACTION:

With the number of OPERABLE fire detection instruments less than required by Table 4.3-11 of the RECOVERY OPERATIONS PLAN,' insure that an alternate instru-ment with the same coverage is OPERABLE, or;

1. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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.

THREE MILE ISLAND - UNIT 2 3.3-3 Amendment 30

'LIMlTXNG CONDITIONS FOR OPERAT80N 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 REACTOR COOLANT SYSTEM 3.4.9.1 The Reactor Coolant System shall be maintained between a T avg of less than 200 F and greater than 50*F.

3.4.9.2 The Reactor Coolant System shall remain open to the reactor building atmosphere unless repressurization is approved.in a safety evaluation submitted to the NRC. This safety evaluation shall specify the maximum pressure limits and overpressure protection that is required.

APPLICABILITY: MODE 1 ,

ACTION:

With the Reactor Coolant System temperature exceeding the temperature limits, ir. mediately 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

- LIMITING CONDITIONS FOR OPERATION 3.5 COMMUNICATIONS 3.5.1 Control Room 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.

APPLICABILITY:. 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.

3.5-1 Amendment 30 THREE MILE ISLAND - UNIT 2

1 LIMITING CONDITIONS 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 maintcined.

APPLICABILITY: MODE 1 ACTION:

With no isolation barriers provided, the following activities in containment are 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 l

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

THREE MILE ISLAND - UNIT 2 3.6-1 Amendment 30 l

i

9 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*

R-583* Reactor Building Spray 85 R-586* Inlet Line R-589* Decay Heat Coolant Supply OH R-590*

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 Not 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 Pressure System R-593# Sump Penetration Sleeve OH R-594# and Orain Line R-616# Auxiliary Feedwater Lines EF R-623#

R-617# Feedwater Lines FW R-618#

R-619# Steam Line MS R-620#

R-621#

R-622#

R-524** Fuel Transfer Canal Fill SF __

R-525** Isolation Valve Test for Decay DH Heat LIne R-535** Demineralized Service Water OW R-548** Fire Service FS R-569** Secondary Flush and Drain SV CODES: BS--Reactor Building Spray CF--Core Flooding DC--Decay Heat Closed Cooling Water OH--Decay Heat Removal EF--Emergency Feedwater FW--Feedwater IC--Intermediate Closed Cooling Water MU--Makeup and Purification RR--Reactor Building Emergency Cooling - River Water SA--Station Service Air MS--Main Stream NS--Nuclear Services Closed Cooling Water SF--Spent Fuel Cooling DW--Demineralizer Service Water FS--Fire Service SV--Steam Generator and Secondary Side Vents and Drains Penetrations which utilize a check valve inside containment as a containment isolation valve.

Penetrations which have single valve isolation.

- Penetrations 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 ISLAND - UNIT 2 3.6-3 Amendment 30 i

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

APPLICABILITY: ' 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 .

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

THREE MILE ISLAND - UNIT 2 3.6-4 Amendment 30 1

4

. - LIMITING CONDITIONS FOR OPERATI'ON CONTAINMENT AIR LOCKS (MODES 2 and 3) 3 . 6 . 1 15 Each Containment Air Lock shall be' 0PERABLE with at least one door closed unless otherwise specified per the criteria of Recovery Operations Plan Sect *on 4.6.1.6.1.

APPLICABILITY: MODES 2 and 3' ACTION:

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

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

APPLICABILITY: M0CES 1, 2, and 3 ACTION:

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

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

i

r m

d . 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 Mean Sea Level USGS datum, at the river water intake structure of Three Mile Island Nuclear Station, Unit 1.

APPLICABILITY: MODES 1, 2, 3 ACTION:

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

1. Initiate patrol and inspection of the dikes surrounding the site for signs of deterioration such as undermining or excessive seepage. ~~

2. Inform the Site Operations Director (500) and as directed by the 500:

(a) Prepare all flood panels and door seals for installation, (b) Check all building floor drains and puaps 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 te inhibit ficatation, (f) Arrange for alternate supolics 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 Level 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

.4

, LIMITING CONDITIONS FOR OPERATION 3'. 7. 7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM l 3.7.7.1 The Control Room Ventilation and Emergency Air Cleanup System shall be OPERABLE

with:

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

b. Two Control Room Bypass Fans, l l

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.

1 APPLICABILITY: MODE 1 ACTION:

a. With one Co'ntrol Room Supply Fan or its associated cooling coil inoperable, l restore the inoperable fan and/or cooling coil to CPERABLE status within 7-days,

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

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

d. With one isolation damper in the nutside air intake duct inoperabic, rettore 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 .

l I

l

Standby onsite AC power (emerger.cy diesel generators' is not recuired for operability.

THREE MILE ISLAND - UNIT 2 3.7-2 Amendment 30

4 LIMITING CONDITIONS FOR OPERATION 3.7.9 SEALED SOURCES SEALED SOURCE ~ INTEGRITY 3.7.9.1. Each sealed source containing radioactive material either in ;xcess 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 withdrawn from use and:

1. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations. __

b. The provisions of Specification 3.0.3 are not applicable.

THREE MILE ISLAND - UNIT 2 3.7-3 Amendment 30 ,

o: LIMITING CON 0XTIONS FOR OPERATION 3.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM 3.7.10.1 The FIRE SUPPRESSION WATER SYSTEM snall be OPERABLE with;

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

1. Unit 1 Circulating Water Flume Diesel Fire Pump

2. Unit 1. River Water Intake Diesel Fire Pump

3. Unit 2 River Water Intake Diesel Fire Pump

4. Unit 1 River Water Intake Motor Fire Pump

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

1. Altitude Tank --

2. Unit 1 Circulating Water Fiume

3. Unit 1 River Water Intake Structure

4. Unit 2 River Water Intake Structure

c. An OPERABLE flow path capable of taking suction from a water supply and transferring the water through distributio piping with OPERABLE section-alizing control or isolation valves to the .are hydrant curb vsives 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.

APPLICABILI!Y: MODES 1, 2 and 3 ACTION:

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

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

THREE MILE ISLAND - UNIT 2 3.7-4 Amendment 30

, _ LIMITING' CONDITIONS FOR OPERATION

~

OELUGE/SPRINXLER SYSTEMS 3.7.10.2 The Deluge and/or Sprinkler Systems located in the following areas shall be:0PERABLE:

a. Deletid.

b. Deleted.

c. Air Intake Tunnel (Deluge - 2 of 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 WOG-F .*

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.

""This f acility'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 CONDITIONS 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 ona or more of the above required Halon systems inoperable, establish a reving (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 ares (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

THREE MILE ISLAND - UNIT 2 3.7-6 Amendment 30

3 1 LIMITING CONDIT0NS FOR OPERATION PENETRATION FIRE BARRIERS

3. 7.~ 11 All Penetration Fire Barriers protecting Safety Related areas shall be functional.

APPLICABILITY: 'HODES 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 wi' thin 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 du 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

c ~

e. LIMITANG CONDITf0NS FOR OPERATRON

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 q.- 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 4.8.2.2.2.a.4 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Restore the full --

complement of offsite A.C. electrical power sources to OPERABLE status .

within 7 days,

b. With both offsite circuits of the above required A.C. electrical power sources inoperable, 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 precluci completion of those activities necessary to place the plant in a safe configuration.

THREE MILE ISLAND - UNIT 2 3.8-1 Amendment 30

TABLE 3.8-1 TESTING FREQUENCY MATRIX DELETED THREE MILE ISLAND - UNIT 2 3.8-2 Amencment 30

O

. TABLE 3.0-2 RESTORATION TIME MATRIX DELETED m

4 I

THREE MILE ISLAND - UNIT 2 3.8-3 Amencment 30

'O LIMITING CONDITIONS FOR OPERATION 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 witnin 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 REC 0VERY OPERATIONS PLAN shall be OPERABLE and energized.

APPLICA3ILIR: 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.

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

THREE MILE ISLAND - UNIT 2 3.8-4 Amencment 30

o.

g

_- LfMfTfNG CONDATONS FOR OPERATION D.C. DISTRIBUTION

.3.8.2.2.1 The following 0.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 0.C. bus 2-100, 250/125-volt 0.C.

battery bank A and a full capacity charger.

TRAIN "B" consisting of 250/125-volt 0.C. bus 2-200, 250/125-volt 0.C.

battery bank B, and a full capacity charger.

APPLICABILITY: MODE 1 ACTION:

a. With one 250/125-volt 0.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 0.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 . -

THREE MILE ISLAND - UNIT 2 3.8-5 Amendment 30

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E' LIMKTING CONDXTXONS 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 OPERA 8LE.

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

o 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 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 Racovery 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

LIMITING CONDITIONS FOR OPERATION r

-b. With no Fuel Transfer Canal (deep end) water level instruments OPERABLE, terminate all activities involving any Canister containing core T.atarial in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assemoly and all coerations involving changes in the Fuel Transfer Canal (deeo 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 maintainec at the level specified in Section 4.9.4 of tne Recovery Operations Plan.

APoLICABILITY: 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 ccre 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 BUILOING 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.

l APPLICABILITY: HODES 1, 2 and 3 ACTION:

With the Fuel Handling Building Air Cleanup Exhaust System inoperable, restore the system to OPERAB.2 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

! of which could exceed 50% of the Appendix B Technical Specification i instantaneous release rate for gaseous ef fluents, until the system is restored to OPERABLE status.

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

LIMITING CCNDITIONS FOR OPERATICN g.

3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shall be OPERABLE with one of the four system air cleanup exhaust fans CPERABLE.

APDLICABILITY: MODES 1, 2, 3 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 .whic.n could exceed 50% of the Appendix B Technical Specification instantan,tous 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 -

shall be subject to approval by the NRC prior to implementation.

APPLICABILITY: MODES 1, 2 and 3 ACTION:

None except as provided in Specification 3.0.3.

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

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1 LIMITING CONDITIONS FOR OPERATION 3.10 CRANE OPERATIONS CONTAINMENT BUILDING 3.10.1 Loads in excess of 2400 lbs. shall be prohibited from travel over the followicg areas unless a docketed Safety Evaluation for the activity is

.a proved oy the NRC:

a. reactor vessel

b. incore instrument seal table and guide tubes (includes travel y 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 analysis __

APPLICABILITY: MODE 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 recort to the Commission pursuant to Specification 6.9'.2 within the next 30 cays.

FUEL HANCLING BUILDING 3.10.2 Loads in excess of 2400 lbs. shall be probibited from travel over the folicwing areas unless a docketed Safety Evaluation for the activity is approved by the NRC:

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

b. any Canister that contains core material, regardless of its location

c. areas not previously analyzed in a docketed, NRC approved load droo analysis THREE MILE ISLAND - UNIT 2 3.10-1 Amencment 30

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, LIMITING CONDITICNS FOR OPERAT!ON APDLICABILITY: MODES 1 and 2 ACTION:

With the requirements of the above specification not satisfiec, place the crane load in a safe condition and correct the circumstances wnich causea or allowec tne Limiting Condition for Operations to be exceeded prior to continuing :rane operations limitea by Specification 3.10.2. Prepare and submit a special report to the Commission pursuant to Specification 6.9.2 within the next 30 cays.

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f THREE MILE ISLAND - UNIT 2 3.10-2 Amenament 30

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' i BASES FOR LIMITING CONDITIONS FOR OPERATION I

SURVEILLANCE REQUIREMENTS 1

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NOTE The sumfnary statements contained in this section provide the bases foi the Specifications of Section 3.0 and 4.0 and are not consicered a part ,

of these Technical Specifications as provided in 10 CFR 50.36 i

.. 3/4.0 APDLICABILITY v

BASES The scecifications of this section provide the general recuirements applicable to eat' of the Limiting Conditions for Operation anc 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 proviced to celineate 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 o? cannot be complied with. The intent of tnis specification is to require that inoperable equipment be restored to an OPERABLE status in a prompt manner, that the unit be maintained in stable

~~

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 during the FACILITY MODE or other conditions for which the Limiting Concitions 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 survei?Tance 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 regate 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 restrict.ive to ensure that the reliability associated with the surveillance activity is net degraded beyond that obtained from the nominal specified interval.

THREE MILE ISLAND - L' NIT 2 B 3/4 0-1 Am'nd 'Dt 30

-APDL!CABILIIY BASES 4.0.3 The provisions of this specification set forth the criteria for ceter-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, wren suen items are found or known to be inoperable althougn still meeting the Surveillance Requirements.

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

3.4.1 WATER INJECTICN CCOLING AND REACT!vITY CONTROL Svs7EuS s BASES 3/4.1.1 BORATION CCNTROL AND BORATED CCOLING WATER INJECT:CN The limitation on minimum boron concentration ensures that the core will remaia sutcritical under all crecible conditions *nich may exist curing the long-term

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cooling mode. The maximum boron concentration is provided to ensure that pre-cipitation of boron will not occur in the RCS and thereby cause possicle flow restrictions. The specification recuiring tne OPERABILITY of systems cacaole of injecting borated cooling water into the RCS within the recuired Doron con-entration limits, The CPERABILITY of equipment for a Reactor Building Sumo Recirculation System is required to provide a recirculation patn from ine Reactor Building Sump in the event of an unisolatable leak in the Reactor Vessel. The required volume of borated water in the BWST provides sufficient water to provide a continuous supply of water to the vessel during tne interim period before the recirculation flowpath from the Reactor Building Suma can ce placed in service. Minimum boron concentration limits have been provicec for the Reactor Coolant System. Refueling Canal (deep end) anc 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 Shioment Safety Evaluation Report and the Cefueling 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 tnese pools will not result in a criticality potential.

B 3/4 1-1 Amencment 30 THREE MILE ISLANO - L' NIT 2 I

g 3/4.'3 INSTRUMENTATION

.5 BASES ~

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

3/4.3.2 ENGINEEREO 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.

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

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

.. . INSTRUMENTATION

. BASE 5 s

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERASILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation coses to the public as a result of routine or accicental release of radioactive materials to the atmosphere. This capability is required to evaluate tne need for initiating protective measures to protect the health and safety of tne 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 habitability 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.

THREE MILE ISLAND - UNIT 2 g 3/4 3.; Amencment 30 7

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- INSTRLMENTATION

. EASES-3/4.3.3.8 AND 3/4.3.3.9 FIRE OETECTION INSTRUMENTATION OPERABILITY of'the Fire Detection Instrumentation ensures that adecuate warning capability is available for the prompt detection of fires. This capability is recuired in order to detect and locate fires in their early stages. Promet cetection of fires will reduce the potential for damage to Safety Related eouipment 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 reovired to provide detection capability ur the inoperable instrumentation is returned to service.

1 THREE MILE ISLAND - UNIT 2 5 3/4 3-3 Amencment 30 t

p, . . . . . . . . .

3/4:4- REACTOR CCOLANT SYSTEM C

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 irdication 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 u1 explained increases in Reactor Coolant System inventory which could result in a boron dilution event.

Two independent monitors are required to provide reduncancy and to minimi:e f the necessity to disec.;tinue processing because of inst rument failures.

I i 3/4.4.9 PRESSURE / TEMPERATURE LIMIT The Reactor Coolant System minimum temperature is maintained to prevent precipitation of the boron used to maintain suberiticality. The maximum reac-

! 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-l ing source such as criticality.

, Reactor coolant chemistry surveillance requirements are included in the l RECOVERY OPERATIONS PLAN. These requirements provide assurance that locali:ed corrosion or pitting in crevice areas, which could tend to promote stress corrosien cracking in heat affected zones of welds in stainless steel piping or components, will not occur.

l THREE MILE ISLAND - UMIT 2 3 3/4 4-1 Amencment 3C i

c'- . '!ASE5 V

3/4.5 COMMUNICAT!0NS

' The requirements for ccmmunications caca:ility ensure that eersonnel in tne Reactor Building can be prom:tly informed of significant enanges in facility status or-core reactivity concitiens during CORE ALTERATIONS, t

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

3/4.5 CONTA%NMENT SYSTEMS

. BASES

-3/4.6.1 PRIMARY CONTAINMENT 3/A.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 uncontrollec manner.

3/4.6.1.2 CCNTAINMENT ISOLATION .

Containment Isolation is maintained to ensure the containment is procerly maintained as a contamination barrier for the residual contamination wnich j remains inside the containment.

3/4.6.1.3 CONTAINMENT AIR LOCKS (M00E 1) l The containment air locks must be maintained OPERABLE to provide the appro-priate containment sealing capability. These air locks will be useo during -

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 Operations Plan Section 4.6.1.3.1.b shall be prohibited to minimize the potential for an uncontrolled release to the environment.

3/4.6.1.4 INTERNAL PRESSURE The negative pressure limit provides assurance that the Containment 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 censideration. During periods when both doors in either or both per-sonnel air locks are open, the containment purge system will be operating to 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.

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

THREE MILE ISLANO - UNIT 2 B 3/4 6-1 Amencment 30 i

,e 14.6'CONTAINMENTSYSTEMS U

BASES

. 3 /,4. 6 ; 1. 6 CONTAINMENT AIRLCCKS (M00ES'2 AND 3) l Thp Containment. Air Locks must be maintained OPERABLE to provide assurance that the containment Is properly maintained as a contamination barrier for the residual contamination which remains inside the containment. These air locks ;

will be used d; ring entries into the Containment to ensure tnat radioactive materials are not being released to the environs. One door must be closed at all times; newever, to permit the passage of long ite.as into the Reactor Building, both doors may be opened simultaneously in accordance with site- t approved procedures, s

3/4.5.3 CONTAINMENT PURGE EXHAUST SYSTEM The (PERABILITY requirements for the Containment Purge Exhaust System ensure that during Containment purge operations all radioactive particulate material will le filtered through the HEPA filters prior to release to tne atmosphere.

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4 THREE MILE lSLAND - UNIT 2 B 3/4 6-2 Amencment 30 t

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3/4.7 PLANT SYSTius BASES l-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 tne event of flood conditions. The. limit of elevation of 302 ft. Mean Sea Level USGS datum is the elevation at which f acility flood control measures are required to be taken. l I

THREE MILE ISLAND - UNIT 2 B 3/4 7-1 AmencTent 30 t

PLANT SYSigu3 9

BASES 3/4.7.7 CONTROL ROCM EMERGENCY AIR CLEANUP SYSTEM The OPERASILITY of the control room emergency air cleanup system ensures tnat (1) the ambient air temperature does not ' exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled oy tnis system and (21 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 oe required to place THI-2 in a stable configeration with core alterations suspended. In this case, operability requirements to ensure THI-2 Controi Room haoitaoility may be temporarily suscended. The OPERABit!Tv of tnis systen in conjunction with control room design provisions is baseo co limiting the radiation exposure to personnel occupying the control room to 5 rem er 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 The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility wnere 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 greater than 3575 gpm.

In the event that portions of the Fire Suppression Systems are inoperable, alternate backup fire fighting equipment is reouired to be mace available in the affected areas until the affected equipment can be restored to service.

In the event that the Fire Suppression Water System becomes inoperable, immediate corrective measures must be taken since this system provices the major fire suopression capability of the plant.

1 THREE H!'.E ISLAND - UNIT 2 33,'47-2 Amencment 30 f

I

.p PLANT SYSTEMS BASES

' V4. 7.11 PENETRATION FIRE BARRIERS

%he functional integrity of the Fire Barrier Penetration Seals ensuras that fires will be confined or adequately retarced from spreading to adjacent portions of the facility. This design feature minimizes the possioility 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 tne facility fire protection program and are suoject to periccic_ inspections.

During periods of time when the seals are not functional, a roving fire waten }

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. ;

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

c. n- BASES-

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3/4.'8 ELECTRICAL DOWER SYSTEMS

'The OPERABILITY of the A.C..and 0.C. Power sources and associated distribution I

-systems' ensures that s'uf'icient poner will be available wnen required. l' I-i

.I , 3 i-4 L .;

B 3/4 8-1 Amendment 3^

THREE MILE ISLAND - UNIT 2 4

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w c, 3/4.9 RADICACTIVE WASTE STORAGE BASES 3/4.9.1 SPENT FUEL STORAGE D00L "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 END) WATER LEVEL MONITORING Fuel Transfer Canal Water Level Monitoring instrumentation has been orovided to assure the capability to monitor water level.in the deep end of the Fuel Transfer Canal. __.

3/4.9.4 FUEL TRANSFER CANAL (OEEP END) WATER LEVEL:

The water level in the Fuel Transfer Canal (deep end) has been established to limit the dose rate, due to the storage of the plenum assembly and Canisters, to acceptable levels.

3/4.9.12 CUEL HANDLING BUILOING/ AUXILIARY BUILDING AIR CLEANUP SYSTEMS The requirement for the Fuel Handling Building / Auxiliary Builcing 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 OPERA 8LE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , the Technical Specifications recuire 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 8 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)

! days and liquid radioactive waste with an activity greater than 0.5 curies of particulates with half-lives greater than eight (8) days. 3 3/4.9.13 ACCIDENT GENERATED WATER These specifications are provided to ensure compliance with the Commission's Statement of May 25, 1979, and tne Commission's Statement of Policy and Notice of Intent to Prepare a Programmatic Environmental Impact Statement of Novemoer 21, 1979, which prohibit these actions pending evaluation of the environmental impacts of such actions. The PEIS issued in March, 1981, ceferred a decision on the ultimate disposal of processed water. Furtner Commission action is necessary prior to release of ACCIDENT GENERATED WATER.

3 3/4 9-1 Amencment 30 THREE MILE !$ LAND - UNIT 2 t

3/4.9 'RA0:05CrivE WASTE' STORAGE BASES However, the Commission has recogni:ed that there may be emergency situations, not at tnis time forseen, which coula require rapid action. In these situations, the Commission nas indicated its intention to consult with the Council on Environmental Quality to tne 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, anc Contain-ment Buildings including the primary system as of October 16, 1979, .itn 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 cefore processing; (b) Water that has a total activity of greater than one pCi/mi prior to processing except wnere such water is originally non-accident water _

and becomes contaminated by use in cleanup; (c) Water that contains greater than 0.025 pCi/mi of tritium before processing.

3/4.9.14 Oeleted.

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

P 3/4.10 CEFUELING OPERATIONS 9

. 9ASES 3/4.10.1 CRANE OPERATIONS - CONTAINMENT BUILDING A load crop into the Reactor Vessel may cause reconfigurations of the core debris anc/or structural damage which Could hinder recovery efforts. A load crop on the Incore Instrument Seal Table and/or guide tuees may result in an unisolaole leak ' rom the Reactor Vessel. The restriction on movement of loacs in excess of the nominal weight of a fuel or control rod assemoly and associate:

hanaling. tool over these areas is to mitigate the potential consequer.ces stated above in the event this load is cropped.

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 neavy loads in the. fuel handling building is to prevent the drop of a neavy load in the fuel nandling building in areas where the rupture of a fuel canister could ,

I occur. __

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8 3/4 10-1 Amencment 30 l THREE MILE ISLAND - UNIT 2 l

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I SECTION 6.0 ACHINISTRATIVE CONTROL 5 t

3 6.0 ACMINSTRATIVE CONTROLS

p 6.1 RESPONSIBILITY 6.1.1 The Of fice of the Director-THI-2 consists of the Director-TMI-2 and tne Deputy Director-TMI-2 and shall be responsible for overall unit operation anc snali celegate in writing the succession to this responsibility during both of their aosences.

6.2 ORGANIZATION GPUNC ORGANIZATION 6.2.1 The GPU Nuclear Corporation (GPUNC) Organization for unit management and technical support shall be as shown on Figure 1-1 of the Organization Plan. The Organization Plan and changes thereto shall be approved by the NRC prior to implementation.

TMI-2 ORGANIZATION 6.2.2 The unit organization shall be shown on Figure 1-2 of the Organization Plan and: __

a. During Mode 1, each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

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

c. During Mode 1, an individual qualified in radiation protection procedures shall be 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 shif t crew during MODE 1 necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

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

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

,, 1 ADMINISTRATIVE CONTROLS Table 6.2-1 MINIMUM SHIFT CREW CCMPOSITION#

LICENSE MODE 1 CATEGORY 50L 1" OL 1 Non-Licensed 2

Shift crew composition may be less than the minimum require-ments for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

During CORE ALTERATIONS an additional SOL or an SOL limited to fuel handling will be stationed on the operating floor, in the command center, or in the control room to directly control the

, particular CORE ALTERATION activity being performed.

l l-THREE MILE ISLAND - UN!T 2 6-2 Amendment No. 30 l'

ADMINISTRATIVE CONTROLS

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6.3 UNIT-STAFF OVALIFICATIONS l

6,3.1 Each member of the unit staff shall meet or exceed the minimum cuali-l fications of ANSI-N 18.1 of 1971 for ccmparable positions unless otherwise I noted in the Technical Specifications.

6.3.2 The Manager, Radiological Controls TMI-2 shall meet or exceed the cuali-i fications of Regulatory Guide 1.8, September 1975. Each Radiological Controls I Tecnnician in responsible positions / Foreman shall meet or exceed the cualifica-tions of ANSI 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified tnrougn an NRC approved THI-2 Radiation Controls training program. Individuals who ce 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 nnich 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 of 1977 and 10 CFR 55.59 except that Radiological Controls training may be under the l direction of Vice President-Rad 41ogical and Environmental Controls.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant T mining 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 Direc. tor 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 THI-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 Tecnnical Specification.

Divisiens other than the TMI-2 Division will perform the Independent Safety Review of their own procedures affecting TMI-2 in acco'rdance 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 reoresent an Unreviewed Safety Question (USQ) or Tech Spec change, including Recovery Operations Plan Change (requires in line SRG review and NRC approval).

THREE MILE ISLAND - UNIT 2 6-3 Amencment Nc. 30 t

- ACP:NISTRATIVE CONTROLS 9

ACTIVITIES 4 6.5.1.1 Each procedure required by Technical Scecification 6.8 and other 8

procedures including tnose for test and experiments and cnanges tnereto shall ce precared 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 organi:ation as the individual who prepared the procedure or change.

6.5.1.2 Deleted.

6.5.1.3 Proposed modifications to . nit structures, systems and components shall be designed by an individual / organization knowledgeable in the areas affected by the proposed modification. Each sucn modification shall be tecn-nically reviewed by an individual / group other than the individual / group whicn designed the modification but may be from the same group as the individual wno designed 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 'mplementing 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 wnich 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 acditional cross-disciolinary 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 imoacts the operational status of unit systems or equipment, it must be concurred with by the THI-2 Division. Unreviewed Safety Question, Technical Scecification change (including Recovery Operations Plan cnange), or Significant Environmental Impact requires line TMI-2 Division and SRG review prior to implementation.

THREE MILE ISLAND - UNIT 2 6-4 Amencment No. D I

s y- ADMINISTRATIVE 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.

QUALICICATION5 6.5.1.11 Responsibile Technical Reviewers shall meet or exceed the qualifica-tions of ANSI /ANS-3.1 - 1978 Section 4.4 for Reactor Engineering, Irstrumenta-tion and Control, Chemistry and Radiochemistry, Radiation Protection and Quality Assurance Reviewers or have seven (7) years of appropriate excerience in the area of their specialty. All other RTRs shall meet Section 4.5, 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 THI-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 THI-2 in accordance with approved procedures except when tney impact the operational status of unit systems or equipment (requires THI-2 Division concurrence), a significant environmental impact (requires in line SRG and Environmental Licensing review), or reoresent 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 naving direct responsibility for the performance of the activities under review, bJt who may be from tre same functionally cognizant organization as the individual / group performing the original work. For those TMI-2 Division documents determined to be Review Significant, the Independent Safety Review snail be performed by or under the cognizance of SRG.

6.5.2.3 GPU Nuclear Corporation shall collectively have or have access to the exoerience and competence required to indecencently review subjects in tne following areas:

a. Nuclear Unit operations D. Nuclear engineering THREE MILE ISLAND - UNIT 2 6-5 Amencment N:. 30

C ~ACMINI$TRATIVE CONTROLS lE

c. Chemistry and radiochemistry

'e d. Metallurgy

e. Instrumentation and control l

f. Radiological safety j

g. Mechanical engineering ;

h. Electrical engineering

i. Administrative controis and quality assurance practices

j. Emergency plans and related organization, procedures and equipnent

k. Other appropriate fields such as radioactive waste oceration associatec with the unique characteristics of THI-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. Wri..en safety evaluations of changes in the facility as described in the Safety Analysis Report, Technical Evaluation Reports, or docketed System Oescriptions, changes in procedures as described '~

i .s the Safety Analysis Report, Technical Evaluation Reports, or docketed System Descriptions, and tests or experiments not described in t,'e Safety Analysis Report, Technical Evaluation Reports, or docket 9d System Descriptions, which are completed without prior NRC

, approva: under the provisions of 10 CFR 50.59(a)(1). This review of items det?rmined not to be Review Significant when performed by SRG is a suppl oental review to verify that such changes, tests or experiments Jid not involve a change in the Technical Specifications or an Unrevieu d Safety Question.

b. Proposed changes in procedures, proposed changes to the facility, or proposed tests er experiments, any of which involves a change in tne 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. Sucn reviews are performed after the fact. Review of events covered under tnis subsection shall include results of any investigations made and tne 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 recommencations as appropriate.

e. Investigation of all reportable events including the preparation anc forwarcing of reports covering evaluation and recommendations to l

prevent recurrence, shall be reviewed by THI-2 SRG.

1 THREE MI'.E ISLAND - UNIT 2 6-6 Amendment No. 30 i

o ACMINISTRATIVE CONTROLS w

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 tne Direc.or TMI-2 snall be performed by TMI-2 SRG.

g. Written 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 ;peration of structures, systems, or components, tnat 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.

6.5.2.6 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 Tecnnical 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 imolementing procedures. The audit frecuency shall De at least once per 12 months.

f. The Security P'an and implementing procedures. The audit frequency snall be at least once per 12 months.

THREE MILE ISLAND - UNIT 2 6-7 Amencment No. 30

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ADMIN: STRAT:VE CONTROLS

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g. The Radiation Protection Plan and implementing procedures. Tne acci.

' frequency shall be at least once per 12 menths.

h. The Fire Protection Program and implementing crocedures. 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 cualified offsite licensee personnel or an outside fire protection firm.

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

k. Any other 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 TMI-2, the Office of the Director THI-2, or the Of fice of the President - 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 90 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 Grouo (SRG)

FUNCTION 6.5.4.1 The SRG shall be a full-time group of engineers, independent of the site Operations of Engineering staff, and located onsite within the TMI-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 TMI-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 TM1-2.

RE5?CNSIBILITY 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 consiceration of nuclear or radiological safety.

THREE MILE ISLAND - UNIT 2 6-8 Amendment No. 3:

i

5 ADMINISTRATIVE 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) assessment of unit operations and performance and unit safety programs from a nuclear safety perspective.

(3) any other matter 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 THI-2 ceem appropria a for consideration.

6.5.4.5 For those reviews requiring expertise outside that possessed by SRG.

iG 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 appropriate.

Authority 6.5.4.6 The-SRG shall have access to the unit and unit records as necessary to perform its evaluations and assessments. Based on its reviews, the SRG ~~

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

The Manager, SRG is advisory to the Of# ice of the Director TMI-2. However, he has the authority and responsibility to bring to the attention of the Office of the President any issues he believes are not being addressed with adequate consiceration of nuclear or radiological safety.

OUALIFICATIONS 6.5.1.7 The SRG engineers shall have either; (1) a Bachelor's Degree in Engineering or the Physical Sciences and five (5) years of professional level experience in the nuclear power field including technical supporting functions, or, (2) 9 years of appropriate experience. Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.

The Manager, SRG, shall meet or exceed the requirements of section 4.7 of ANSI /ANS 3.1-1978.

R_ECORDS 5.5.4.3 Although day to day results of evaluations by the SRG are communicated l directly to the responsible department by the SRG, special reports are preparec l only for items deemed appropriate by SRG as concurred with by one Manager, SRG's

! immediate supervisor. These special reports of evaluations and assessments oy l SRG shall be prepared, approved, and then transmitted to the Office of the Director, TMI-2 and the management position resporsible for the area reviewec l

througn the Manager, SRG's immediate supervisor. These reports shall ce I maintained for tne life of the operating license.

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THREE MILE ISLAND - UNIT 2 6-9 AmJndment No. 3; l

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g. ACHINISTRATIVE CONTRCLS-6.6- REPORTABLE EVENTS ACTION 6.6.1 The following actions sndll be taken for REPORTABLE EVENTS:

a. The Commission 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 supervisor and the Office of the Director THI-2.

c. Deleted.

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 applicable procedures recommended in Appendix "A" of Regulatory --

Guide 1.33, Revision 2, February 1978.

b. Recovery Operations Plan implementation.

c. Surveillance and test activities of safety related equipment and radioactive waste management equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Radiation Protection Plan implementation.

g. Limiting the amount of overtime worked 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 any procedure prepared pursuant to 6.8.1, shall be prepared, reviewed and approved in accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.

6.8.2.2 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, anc THREE MILE ISLAND - UNIT 2 6-10 Amencment No. 3-

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

ACM:N:STRAT!VE CONTROLS e

b. (1) For those procedures which affect the operational status of uni ,

systems or equipment, the change is approved by two members of the unit management staff, at least one of whom hoics a Senior Reactor Ocerator's License. If one of tne two acove signatures is not by a supervisory person within the Department having cognizance of the procedure being changed, the signature of that supervisory perscn within the department will also be required, or (2) For those procedures which do not affect the operational status of unit systems or ecuipment, the enange is approved by two memoers of the responsible organi:ation. If one of the two above signatures is not by a section manager / director within the Cepartment having cognizance of the procedure being changed, the signature of that section manager / director within the department will also be rec. ec, and

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

d. Those changes 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 following approval by the management level specified for implementation by Section 6.5.1.9.

6.9 REPORTING REQUIREMENTS RCUTINE 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 otherwise noted.

ANNUAL REPORTS 1 6.9.1.4 Annual reports covering the activities of the unit as described celev 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 tabulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and joo func-tions,2 e.g., reactor operations and surveillance, inservice inspec-tion, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. The dose assignment to various cuty functions may be estimates based on pocket cosimeter, TLD, or film l

1A singie suomittal may ce made for a multiple unit station. The submittal snould combine those sections that are common to all units at the station.

2Tnis taculation supplements the requirements of 5 20.407 of 10 CFR Part 20.

THREE MILE !SLAND - UNIT 2 6-11 Amendment NO. 3C I

ADMINISTR'TIVE CONTROLS e

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 frem external sources shall be assigned 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) l at the Harrisburg International Airport for the previous twelve-month period.

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

l RADIATION SAFETY PROGRAM REPORT 6.9.1.6 Deleted.

REPORTABLE OCCURRENCES 6.9.1.7 Deleted.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 Deleted.

l THIRTY DAY WRITTEN REPORTS 6.9.1.9 Deleted.

REPORTING REOUIREMENTS FOR INCIDENT WHICH OCCURRED ON MARCH 28, 1979 6.9.1.10 Section Deleted. All reporting requirements completed.

SPECIAL REPORTS 6.9.2 Special eports shall be submitted to the NRC Region I Administrator witnin the ttne period specified for each report.

6.10 DECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

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

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

record.

THREE MILE ISLAND - UNIT 2 6-12 Amencment No. 30 i

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y ACMINISTRATIVE CONTROLS

' RECORD RETENTION (Continued)

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

6.10.2 The following records-shall be retained as long as the Licensee has an NRC license to operate or possess the Three Mile Island facility.

a. Records and logs of unit operation covering time interval at each power 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 Specifications -

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 facility design modifications made to systems and equipment described in the Safety Analysis Report, TER, 50, or Safety Evaluation previously submitted to 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 comocnents designed for a limited number of transients or cycles.

1. Records of reactor tests and experiments.

tr . Records of training and qualification for current members of the unit staff.

n. Records of in-service inspections performed pursuant to tnese Technical Specifications,

o. Records of Quality Assurance activities required by the Operating Quality Assurance Plan.

6-13 Amencmen; NO. 33 THREE MILE ISLAND - UNIT 2

ADMINISTRATIVE' CONTROLS e

p. Records af 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 Ccmmittee (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 recuirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation es.posure.

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.

THREE MILE 15LANO - UNIT 2 6-13 Amendment No. 30 i

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