Text

Notice of Issuance of Amend to License DPR-73,incorporating Recovery Mode Proposed Tech Specs Established by 800211 NRR Order
	ML20137R463
Person / Time
Site:	Three Mile Island
Issue date:	01/27/1986
From:	Travers W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20137Q397	List: ML20137Q394; ML20137R463;
References
	NUDOCS 8602130192
	Download: ML20137R463 (159)
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Enclosure 1 UNITED STATES NUCLEAR REGULATORY COMMISSION GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION, UNIT 2 DOCKET N0. 50-320 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LI-CENSE I.

GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (collectively, the licensee) are the holders of Facility Operating License No. DPR-73, which had authorized operation of the Three Mile Island Nuclear Station, Unit 2 (TMI-2)-

at power levels up to 2772 megawatts thennal. The facility, which is located in Londonderry Township, Dauphin County, Pennsylvania, is a pressurized water reactor previously used for the commercial generation of electricity.

II.

By Order for Modification of License, dated July 20, 1979, the licensee's authority to operate the facility was suspended and the licensee's authority was limited to maintenance of the facility in the present shutdown cooling mode (44 FR 45271). By further Order of the Director, Office of Nuclear keactor Regulation, dated February 11, 1980, a new set of formal license requirements was imposed to reflect the post-accident condition of the facility and to assure the continued maintenance of the current safe, stable, long-term cooling condition of the facility (45 FR 11292).

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The new requirements imposed on the licensee by the February 11, 1980 Order of the Director of Nuclear Reactor Regulation were issued as the Recovery Mode Proposed Technical Specifications (PTS), and have been revised, in part, in subsequent Amendments of Order.

In response to the notice of opportunity to request a hearing provided by the Order of the Director, Office of Nuclear Reactor Regulation, dated February 11, 1980, several petitions for leave to intervene were filed and a prehearing conference was conducted on July 7, 1980. Subsequent to that time, discussions with the recognized parties have led to mutual agreement in the areas of concern, resulting in the resolution of all outstanding issues and the withdrawal of all petitions.

On November 8, 1985, the Atomic Safety and Licensing Board issued an Order entitled " Granting Joint Motion to Approve Stipulation, Dismissing ECNP and Dismissing Proceeding." This order approved the joint stipulation entered into ~by the Environmental Coalition on Nuclear Power (ECNP) the last remaining intervenor, the NRC Staff and the Licensee for the purpose of resolving all remaining' proposed contentions and consequently terminated the proceeding.

III.

In light of the termination of this proceeding, the NRC staff is now formally amending the License (Facility Operating License No. DPR-73) to include those Proposed Technical Specifications issued by the Order of the Director, Nuclear Reactor Regulation ~, dated February 11, 1980, as amended from time to time by Amendments of Order. Each of these revisions to the PTS was

issued with a supporting staff safety evaluation as were the corresponding Amendments of Order. Appropriate environmental reviews of each action were performed as well. The staff has concluded in these safety evaluations that the PTS, as amended, impose appropriate limitations on the licensee to assure the continued maintenance of the facility in a safe shutdown condition.

IV.

Accordingly, pursuaat to the Atomic Energy Act of 1954, as amended, Facility Operating Licens! No. DPR-73 is hereby amended to incorporate the Recovery Mode Proposed Te:hnical Specifications as Appendix A to said license.

The supporting documents approving the previous revisions to the Proposed Technical Specifications are available for inspection at the Comission's Public Document Room, 1717 H Street, NW, Washington,~DC 20555, and at the Commission's Local Public Document Room at the State Library of Pennsylvania, Government Publications Section, Education Building, Commonwealth and Walnut Streets, Harrisburg, Pennsylvania 17126. This license amendment is effective as of the date of its issuance.

Dated at Middletown, Pennsylvania this 27th day of January,1986 FOR THE NUCLEAR REGULATORY COMMISSION A) W William D. Travers Director TMI-2 Cleanup Project Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

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.. UNITED STATES NUCLEAR REGULATORY COMMISSION

,s.... WASHINGTON. D.C. 20655 January 27, 1986 Docket No. 50-320 Docketing and Sonnce Section ,

othee of the Secretary of the Commission

SUBJECT:

Three Mile Island Nuclear Station, Unit 2 -

i - Operating License No. DPR-73; Docket No. 50-320 Notice of Issuance of Amendment to Facility Operating License Two signed originals of the Federal Register Notice identified below are enclosed for your transmittal to the Office of the Federal Register for pubhcation. Additional conformed copies ( )of the Notice are enclosed for your use.

O Notice of Receipt of Application for Construction Permit (s) and Operating Uconse(s).

O Notice of Receipt of Partial Application for Construction Permit (s) and Facility Ucense(s): Time for Submission of Views on Antitrust Matters.

O Notice of Availability of Applicant's Environmental Report.

O Notice of Proposed issuance of Amendment to Facility Operating License

. O Notice of Receipt of Application for Facility License (s); Notice of Availability of Applicant's Environmental Report; and Nobce of Consideration of issuance of Facility License (s) and Notice of Opportunity for Hearing. .

O Notice of Availability of NRC Draft / Final Environmental Statement.

O Notice of Limited Work Authonzation.

O Noece of Availability of Safety Evaluation Report.

O Notice of issuance of Construchon Permit (s).

D(Notice of issuance of Facility Operating License (s) or Amendment (s).

O Other.

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l billia!m D. Travers, Director

TMI-2 Cleanup Project Directorate

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Enclosure:

As Stated r ,.

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THREE MILE ISLAND NUCLEAR STATION UNIT 2 Technical Specifications Appendix "A" to License No. DPR-73 0

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INDEX DEFINITIONS SECTION f.ifli

1. 0 DEFINITIONS 1.1 DEFINED TERMS...................................................., 1-1 1.2 RECOVERY OPE RATIONS P LAN. . . . . . . . . . . . . . . . . . . . . . 1-1 ........

1.3 RECOVERY M0DE..................................................... 1-1 1.4 ACTION.....................................................,,,.,,, 1-1 1.5 OPE RAB L E - 0PE RAB I LI TY. . . . . . . . . . . . . . . . . . . . . . . .1-1 ........

1.6 REPORTABLE OCCURRENCE............................................. 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........................................... 1-2 1.11 STAGGERED TEST 8 ASIS................... .......................... 1-2 1.12 FREQUENCY N0TATION................................................ 1-2 1.13 FI RE SUPPRESSION WATER SYSTEM. . . . . . . . . . . . . . . . . . . .1-2 .........

1.14 REVIEW SIGNIFICANCE............................................... 1-3 l 1.15 CORE ALTERATION................................................... 1-4 1.is LOSS TO AMsIENT................................................... 1-4 1.17 ACCIDENT GENERATED

! WATER.......................................... 1-4 l

l FREQUENCY NOTATION (TA8LE 1.2)......................................... 1-5 I

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_I N ._E X SAFETY LIMITS SECTION f.3EE 2.1 SAFETY LIMITS Reactor Coolant System Pressure........................................ 2-1 BASES 2.1 SAFETY LIMITS Reactor Coolant System Pressure........................................ 8 2-1 e

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INDEX

. LIMITING CONDITIONS FOR OPERATION i

i 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 In Boron Concentration.....jection.............................. 3.1-1

..................................... 3.1-1 3.1. 3 CONTROL ASSEMBLIES Mechanisms.................................................... 3.1-2

_3_. 3 INSTRUMENTATION 3.3.1 NEUTRON MONITORING INSTRUMENTATION Intermediate and Source Range Neutron Flux Monitors. . . . . . . . . . . 3.3-1 3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM

.. INSTRUMENTATION............................................ 3.3-1 3.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.

Seismic Instrumentation...................................... 3.3-3 Meteorological Instrumentation...............

............... 3.3-3 Essential Parameters Monitoring Instrumenta ............... -3.3-3 3.3-6 Post-accident Chlorine Detection S Instrumentation............... .. tion..............

.............. 3.3-6 Fire Detection......ystems.................... .............. 3.3-6 i

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......................................... 3.3-7 L 3.4 REACTOR C00LANT' SYSTEM 3.4.1 REACTOR COOLANT L00PS........................................ 3.4-1 3.4.2 REACTOR VESSEL WATER LEVEL MONITORING........................ 3.4-1 I

3.4.9 PRESSURE / TEMPERATURE LIMITS -

Re a c to r Coo l a n t Sys t em . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-1 3.5 COMMUNICATIONS

.~) 3.5.1 CONT RO L R00M . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3.5-1 .............

l THREE MILE ISLAND - UNIT 2 III January 7.19s5

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_INDEX I o

LIMITING CONDITIONS FOR OPERATION

_SECTION PAGE 3.6 CONTAINMENT SYSTEMS 3.6.1 PRIMARY CONTAINMENT Containmentjntegrity........................ ............... 3.6-1 Containment Air Locks........................ 3.6-1 Internal Pressure..................... ...............

Air Temperature....................... ...................... 3.6-1

...................... 3.6-2 3.6.3 CONTAINMENT PURGE EXHAUST SYSTEM 3.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers..................................... ..... 3.6-2 Hydrogen Purge Cleanup System.......................... ..... 3.6-2 3.7 PLANT SYSTEMS 3.7.1 FEEDWATER SYSTEM............................................. 3.7-1

) 3.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM............... 3.7-1 3.7.3 CLOSED CYCLE COOLING WATER SYSTEM Nuclear Services Closed Cycle Cooling System................. 3.7-1 Decay Heat Closed Cooling Water System. . . . . . . . . . . . . . . . . . . . 3.7-2 Mini Decay Heat Removal System............................ ..

.. 3.7-2 3.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM........................... 3.7-2 3.7.6 FLOOD PROTECTION............................................. 3.7-3 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.................... 3.7-4 3.7.9 SEALED SOURCES............................................... 3.7-5 3.7.10 FIRE SUPPRESSION SYSTEMS Fi re S upp re s s i o n Wa te r Sys t em. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7-6 Deluge / Sprinkler Systems....................

Halon System................................ ................ .

3.7-8 Fire Hose Stations........................... ............... 3.7-9

............... 3.7-9 3.7.11 PENETRATION FIRE BARRIERS.................................... 3.7-11 THREE MILE ISLAND - UNIT 2 IV January 7.1985

l INDEX LIMITING CONDITIONS FOR OPERATION SECTION PAGE 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 D.C. Distribution............................................ 3.8-4 3.9 RADIOACTIVE WASTE STORAGE 3.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING. . . . . . . . . . . . . . 3.9-1 3.9.2 SPENT FUE L STORAGE P0OL "A" WATER LEVEL. . . . . . . . . . . . . . . . . . . . . . . . . 3.9-1 3.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING........... 3.9-2 3.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL...................... 3.9-2

. 3.9.12.1 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP

_- SY5TEMS...................................................... 3.9-1 3.9.13 ACCIDENT GENERATED WATER..................................... 3.9-2 3.9.14 REACTOR BUILDING SUMP WATER.................................. 3.9-2 3.10 CRANE OPERATIONS 3.10.1 CONTAINMENT BUILDING.......................................... 3.10-1 3.10.2 FUEL HANDLING BUILDING........................................ 3.10-1 SURVEILLANCE REQUIREMENTS 4.0 APPLICABILITY..................................................... 4.0-1 THREE MILE ISLAND - UNIT 2 V May 31, 1985

INDEX BASES 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 3/4.1.3 CONTROL ASSEMBLIES...................................... B 3/4 1-1 3/4.3 INSTRUMENTATION 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION...................... B 3/4 3 J 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION....................................... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.............................. B 3/4 3-1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT L00PS................................... B 3/4 4-1 3/4.4.2 REACTOR VESSEL WATER LEVEL MONITORING................... B 3/4 4-1 3/4.4.9

't PRESSURE / TEMPERATURE LIMIT.....*......................... B~3/4 4-1 3/4.5 COMMUNICATIONS............................................. B 3/4 5-1 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..................................... B 3/4 6-1 3/4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM........................ B 3/4 6-1 3/4.6.4 COMBUSTIBLE GAS CONTR0L................................. B 3/4 6-1 3/4.7 PLANT SYSTEMS 3/4.7.1 FEE 0 WATER SYSTEM........................................ B 3/4 7-1 3/4.7.2 ' SECONDARY SERVICES CLOSED COOLING WATER SYSTEM.......... B 3/4 7-1 3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM....................... B 3/4 7-1 3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM...................... B 3/4 7-1 s

THREE MILE ISLAND - UNIT 2 'VI May 31,1985

INDEX BASES SECTION PAGE 3/4.7.6 FLOOD PROTECTION......................................... B 3/4 7-2 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM................ B 3/4 7-2 3/4.7.9 SEALED SOURCE CONTAMINATION.............................. B 3/4 7-2 3/4.7.10 FIRE SUPPRESSION SYSTEMS................................. B 3/4 7-2 3/4.7.11 PENETRATION FIRE BARRIER................................. B 3/4 7-3 3/4.8 ELECTRICAL POWER SYSTEMS.................................... B 3/4 8-1 3/4.9 RADI0 ACTIVE WASTE STORAGE 3/4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING. . . . . . . . B 3/4 9-1

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3/4.9.2 SPENT FUEL STORAGE POOL "A" WATER LEVEL................... B 3/4 9-1 3/4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING..... B 3/4 9-1 3/4.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL................ B 3/4 9-1 3/4.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS........................................ B 3/4 9-1 3/4.9.13 ACCIDENT GENERATED WATER.................................. B 3/4 9-1 3/4.10 DEFUELING OPERATIONS........................................ 8 3/4 1 -1 l

THREE MILE ISLAND - UNIT 2 VII May 31, 1985 ew a - - n - -

i INDEX DES]GN FEATURES SECTION PAGE 5.1 SITE '

5.1.1 Exclusion 5.1.2 Low Population Area.................................................. 5-1 5.1. 3. Site Soundary for Zone..........................................

Gaseous Ef fluents. . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.4 Site Boundary for Liquid . 5-1 Effluents............................ . 5-1 5.2 CONTAINMENT 5.2.1 Configuration.......................................

5.2.2 Des ign Press ure and Tempe ra ture. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1

........... 5-1 5.4 REACTOR COOLANT SYSTEM 5.4.1 Design Pressure and Tem 5.4.2 Vo 1 ume . . . . . . . . . . . . . . . . . p e r a t u r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-4

......................................... 5-4 5.5 METEOROLOGICAL TOWER LOCATI0N..................................... 5-4 4

THREE MILE-ISLAND - UNIT 2 VIII January 7.19sh

INDEX ADMINISTRATIVE CONTROLS SECT 20N

_PAGE 6.1 RESPONSIBILITY.................................................... 6-1 6.2 ORGANIZATION 6.2.1 G PUNC Organization............

6.2.2 TMI-2 Organization............. ................................ 6-1

................................ 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 CONTROL 6.5.1.10 Records.....................

6.5.1.11 Qualifications.............. ................................ 6-5

................................ 6-5 6.5.2 INDEPENDENT SAFETY REVIEW '

6.5.2.1 Function.....................

6.5.2.5 Responsibilities............................................ 6-5 6.5.2.7 R e c o r d s . . . . . . . . . . . . . . . . . . . .............................. 6-6 6-7 6.5.3 AUDITS.......................................................... 6-7 6.5.3.2 Audit Records............................................... 6-7 6.5.4 SAFETY REVIEW GROUP 6.5.4.1 Function.................. .................................

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 6.5.4.8 Record.........................

............................ 6-9

............................ 6-10 6.6 REPORTA8LE OCCURRENCE ACTION....................................... 6-9 6.8 PROCEDURES....................................................'..... 6-10

_6. 9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURR

6.9.2 SPECIAL REP 0RTS.......................ENCES....................... 6-11

........................... 6-14 THREE MILE ISLAND - UNIT 2 IX January 7.1985

INDEX ADNINISTRATIVE CONTROLS i

SECTION PAGE 6.10 RECORD RETENTION.................................................. 6-14 6.11 RADIATION PROTECTION PR0 GRAM...................................... 6-16 6.12 HIGH RADIATION AREA............................................... 6-16 1

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- THREE MILE ISLAND - UNIT 2 X January 7.1985

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SECTION 1.0 DEFINITIONS

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1.0 DEFINITIONS DEFINED TERMS .

1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

RECOVERY OPERATIONS PLAN 1.2 The REC 0VERY OPERATIONS PLAN shall define the surveillance requirements

.to be performed to ensure equipment operability as required by the Limiting '

Conditions for Operation. This plan, and changes thereto, shall be approved by the Commission prior to implementation.

RECOVERY MODE 1.3 The RECOVERY MODE shall correspond to a condition in which the reactor is suberitical with an average reactor coolant temperature of less than 200*F.

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 s

1.5 A system, subsystem, train, component or device shall be OPERABLE or have

OPERABILITY when it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or ather auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also capable of performing their related support function (s).

REPORTABLE EVENT .

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

l 1-1 November 22, 1985 THREE MILE ISLAND UNIT 2

1.0 DEFINITIONS l I

CONTAINMENT INTEGRITY ;

1.7 CONTAINMENT INTEGRITY shall exist when:

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

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

. by double valve isolation outside of the reactor building per proce-dures approved pursuant to Specification 6.8.2. Isolation valves inside the reactor building shall be capable of remote operation from a control station outside of the reactor building, or;

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

b. The Equipment Hatch is closed and sealed.

c. Each airlock is OPERABLE pursuant to Specification 3.6.1.3.

.s.

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

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

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

~ CALIBRATION shall encompass the entire shannel 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 tdtal 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 possible, comparison of the channel indication and/or status with other indica-tions and/or status derived from independent instrument channels measuring the same parameter.

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1. 0 DEFINITIONS

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CHANNEL FUNCTIONAL TEST * !

1.10 A CHANNEL FUNCTIONAL TEST shall be:

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a. Analog channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY 1%cluding alarm and/or trip functions.

b. Sistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip 3

functions. '

f 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 perfomance of surveillance 4

, requirements shall correspond to the intervals defined in Table 1.2.

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

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

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

i November 22, 1985

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

4 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 TMI-2 Auxiliary, Fuel Handling, and Contain-ment Buildings including the primary system as of October 16,1979, with the exception of water which as a result of decontamination

, operations becomes commingled with non-accident generated water such *

}. , that the commingled water has a tritium content of 0.025 pCi/ml or .

lea before processing;

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sb) Water that has a total activity of greater than one pCi/ml prior to processing except where such water is originally non-accident water and becomes contaminated by use in cleanup; (c) Water that contains greater than 0.025 pCi/ml of tritium before processing. -

1.18 LICENSE 0 OPERATOR (OL) - any individual who possesses an NRC operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operators Licenses."

t

. 1.19 SENIOR LICENSED OPERATOR (SOL) - any individual who posseses an NRC Senior Operator's license pursuant to Title 10, Code of Federal Regulations, Part 55,

" Operators Licenses."

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

THREE MILE ISLAND - UNIT 2 1-4 May 31,1985

TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

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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.

A At least once per 18 months.

N.A. Nat applicable.

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i SECTION 2.0 SAFETY LIMITS AND f.

LIMITING SAFETY SYSTEM SETTINGS

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N NOTE s

The summary statements contained in this section provide the bases for the speci-fications of Section 2.0 and are not '

considered a part of these Technical Specifications as provided in 10 CFR 50.36.

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2.1 SAFETY LIMITS BASES 2.1.3 REACTOR COOLANT SYSTEM PRESSURE The reactor coolant system is currently open to the reactor building atmosphere.

Should reactor coolant system repressurization become necessary during the course of the recovery, a maximum pressure rating will be specified by an NRC approved safety evaluation.

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THREE MILE ISLAND - UNIT 2 B 2-1 January 7.1985

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f SECTIONS 3.0 AND 4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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g 3 LIMITING CONDITIONS FOR OPERATION 3.0 APPLICABILITY .

LIMITING CONDITIONS FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the RECOVERY 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 take all other actions necessary to maintain the unit in a stable condition; and submit a report to the Commission pursuant to the requirements of Section 50.73 of 10 CFR Part 50.

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l THREE MILE ISLAND - UNIT 2 3.0-1 November 22, 1985

( LIMITING CONDITIONS FOR OPERATION -

4 3.1 WATER INJECTION C0OLING AND REACTIVITY CONTROL SYSTEMS .

3.1.1 BORATION CONTROL BORATED COOLING WATER INJECTION 3.1.1.1 The following systems, capable of injecting borated cooling water into the Reactor Coolant System, shall be'0PERA8LE with:

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

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

c. The BWST shall contain at least 390,000 gallons of borated water except as changed per procedures approved pursuant to Specification 6.8.2 at a minimum temperature of 50 degrees Farenheit and a boron concentration of between 4350 and 6000 ppe.

APPLICABILITY: REC 0VERY MODE

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ACTION:

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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 .

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

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

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

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I THREE MILE ISLAND - UNIT 2 3.1-1 September 23. 1985

LIMITING CONDITIONS FOR OPERATION I l BORON CONCENTRATION l 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 1 temperature above 50*F.

APPLICABILITY: REC 0VERY MODE 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 1 activities involving CORE ALTERATION or the Reactor Coolant System and take action in accordance with procedures approved pursuant to Specification 6.8.2 to restore the concentration to within acceptable limits.

3.1.1.3 The boron concentration of the water in all filled portions of the Fuel Transfer Canal (deep end) and the Spent Fuel Storage Pool "A" shall be maintained between 4350 and 6000 ppm.

APPLICABILITY: RECOVERY MODE ACTION

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k,jf 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.

3.1. 3 CONTROL ASSEMBLIES MECHANISMS 3.1.3.1 deleted.

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THREE MILE ISLAND - UNIT 2 3.1-2 May 31, 1985 f

LIMITING CONDITIONS FOR OPERATION 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 shall be OPERA 8tE. !

APPLICABILITY: RECOVERY MODE ACTION:

a. With the number of source range neutron monitoring channels OPERA 8LE one less than required by the Minimum Channels OPERA 8LE requirement of Table 4.3-1, restore inoperable channel to OPERA 8LE status within 30 l days. If the inoperable channel cannot be restored to OPERA 8LE status .

within 30 days, prepare ' and submit a Special Report to the Consiission pursuant to Specification 6.9.2 within the next 30 days outlining the cause of the malfunction and the plans for monitoring the conditinn,of the core,

b. With no source range neutron monitoring channels OPERA 8LE, suspend all

, ( 'j T activities involving CORE ALTERATION, verify compliance with the boron concentration requirements of Specification 3.1.1.2 at least once per 24 Q hours by a mass balance calculation and at least once per 7 days by a chemical analysis and restore at least one source range neutron monitoring channel to operable status within 7 days. If not restored to operable status within 7 days, promptly, but not later than 30 days from loss of operability, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2, outlining the cause of the malfunction (s),

the plans for monitoring the condition of the core and the plans for resumption of activities involving CORE ALTERATIONS. ~

c. With no intermediate range neutron monitoring channels OPERABLE, restore

at least one intermediate range channel to OPERA 8LE status within 7 days. If not restored to OPERABLE status within 7 days, promptly, but not later than 30 days from loss of OPERABILITY, prepare and submit a special report to the Commission pursuant to Specification 6.9.2, outlining the cause of the malfunction (s) and the plans for monitoring the condition of the core.

! 3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3.3.2.1 The. Engineered Safety Feature Actuation System (ESFAS) instrumentation channels shoyn in Table 4.3-2 shall be OPERABLE with their Trip Se~tpoints set in accordance with the values shown in the Trip Setpoint column of Table 4.3-2.

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THREE MILE ISLAND - UNIT 2 3.3-1 January 7,1905 l

'i Table 3.3-1 NEUTRON MONITORING INSTRUMENTATION TRANSFERRED TO TABLE 4.3-1 0F TNE RECOVERY OPERATIONS PLAN TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATION TRANSFERRED TO TABLE 4.3-2 0F THE RECOVERY OPERATIONS PLAN TABLE 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION TRIP SETPOINTS TRANSFERRED TO TABLE 4.3-2 0F THE RECOVERY OPERATIONS PLAN

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THREE MILE ISLAND - UNIT 2 3.3-2 January 7. 1985 l

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.. . l LIMITING CONDITIONS FOR OPERATION 1 APPLICABILITY: RECOVERY MODE.

ACTION:

a.

.With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 4.3-2 declare the channel inoperable and apply the applicable ACTION 1

requirement of Table 4.3-2 until the channel is restored to OPERA 8LE status with the Setpoint Value. trip setpoint adjusted consistent with the Trip b.

.With an ESFAS instrumentation channel inoperable, take the action shown in Table 4.3-2.

l 3.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 3.3.3.1 PLAN shallThe radiation be OPERABLE monitors listed in Table 4.3-3 of the RECOVERY OPERATIO l APPLICA8ILITY: As Required in Table 4.3-3 of the RECOVERY OPERATIONS PLAN.

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As Required in Table 4.3-3 of the RECOVERY OPERATIONS PLAN. I SEISMIC INSTRUMENTATION ,

3.3.3.3 Deleted METEOROLOGICAL INSTRUMENTATION

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3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 4.3-5 of the RECOVERY OPERATIONS PLAN shall be OPERA 8LE. l APPLICA8ILITY: RECOVERY MODE ACTION:

With any of the above required meteorological monitoring channels inoperable, restore the inoperable channel (s) to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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l THREE MILE ISLAND - UNIT 2 3.3-3 January 7. 19u5

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. TA8LE 3.3-7 i

SEISMIC MONITORING INSTRUMENTATION i

DELETED

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Three Mile Island - Unit 2 3.3-4 January 7.1985l

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l TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION Transferred to Tabie 4.3-5 of the Recovery Operations Plan.

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Three Mile Island - Unit 2 3.3-5 January 7, 1985

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LIMITING CONDITIONS FOR OPERATION ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION 3.3.3.5 The Essential Parametars Monitoring Instrumentation shall be OPERABLI in accordance with the requiren.9nts of Table 4.3-7 of the RECOVERY OPERATIONS PLAN. )

APPLICABILITY: RECOVERY MODE.

ACTION:

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- a. With the exception of the Reactor Vessel Water Level Monitoring instru-mentation, the Spent Fuel Storage Pool "A" Water Level mon.toring instru-mentaticr;, and the Fuel T-ansfer Canal (Deep End) Water Level monitoring instrumentation, for instrumentation not in accordance wi.a the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN, restore the inoperable instrument (s) to the requ kements of Table 4.3-7 of the REC 0VERY OPERATIONS PLAN within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. The operability requirements for the Reactor Vessel Water Level monitoring instrumentation shall be as specified in specification 3.4.2.

c. The operability requirements for the Spent Fuel Storage Pool "A" Water

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Level Monitoring instrumen'Ttion shall be as specified in speciff-( , cation 3.9.1. .

d. The operability requirements for the Fuel Transfer Canal (Deep End) Water

- Level monitoring instrumentation shall be as specified in specifi-cation 3.9.3. ,

PO$T-ACCIDENT INSTRUMENTATION 3.3.3.6 Deleted. .

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

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a. One at the air intake tunnel, and

b. One at the Control Room air supply duct.

APPLICABILITY: DEC0VERY MODE.

ACTION: 1, 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 OPERA 8LE status within 30 days.

THREE MILE ISLANO - UNIT 2 3.3-6 November 52. 1985

LIMITING CONDITIONS FOR OPERATION FIRE DETECTION 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 l OPERABLE.

APPLICABILITY: RECOVERY MODE .

ACTION:

With the number of OPERABLE fire detection instruments less than required by.

Table 4.3-11 of the RECOVERY OPERATIONS PLAN, insure that an alternate instrument with the same coverage is OPERABLE, or;

1. Within I hour, establish a fire watch patrol to inspect the zone with the inoperable instrument (s) at least once per hour, and

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

days.

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3.3-7 November 22. 1985 THREE MILE ISLAND - UNIT 2

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TABLE 3.3-9 REMOTE SHUTDOWN MONTORING INSTRUMENTATION Contents of this Table moved to Table 4.3-7 of the Recovery Operation Plan

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THREE MILE ISLAND - UNIT 2 3.3-8 January 7.1985

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TABLE 3.3 10 POST-ACCIDENT MONITORING INSTRUMENTATION Deleted 1

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THREE MILE ISLAND - UNIT 2 3.3-9 January 7, Ir85

4 TABLE 3.3-11 FIRE DETECTION INSTRUMENTS Transferred to Table 4.3-11 of the Recovery Operations Plan

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9 THREE MILE ISLAND - UNIT 2 3,3-10 January 7. 1985

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. LIMITING CONDITIONS FOR OPERATION ,

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3.4 REACTOR COOLANT SYSTEM -i

~ REACTOR COOLANT LOOPS j

3.4.1 The Reactor Coolant System shall be operated in accordance with procedures approved pursuant to Specification 6.8.2 APPLICABILITY: RECOVERY MODE.

ACTION: -

l None except as provided in Specification 3.0.3.

REACTOR VESSEL WATER LEVEL MONITORING e

3.4.2 As a minimum two independent reactor vessel level monitoring instruments shall be OPERABLE.

, APPLICABILITY: RECOVERY MODE WITH THE RV HEAD REMOVED ACTION

a. With only one reactor vessel level monitoring instrument OPERABLE, terminate all activities involving changes in the reactor coolant system water volume, restore the system 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 level monitoring instrument OPERABLE, terminate all activities involving changes in the reactor coolant system water volume.

Restore the system to OPERA 8LE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . I SAFETY VALVES

! 3.4.3 Deleted.

, 3.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM 3.4.9.1 The Reactor Coolant System shall be maintained between a T,yg 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 repressuri2ation is approved in a safety evaluation submitted to the NRC. This safety evaluation and associated procedures approved pursuant to Specification 6.8.2 shall specify the maximum pressure limits and over-pressure protection that is required.

t November 22, 1985 THREE MILE ISLAND - UNIT 2 3.4-1

,-+-...-.-,.---.----3my,y,,,.y-p_my,- .,,-,y..,.,-w. . , , , ,.,,y, , , _ . ,,,,m,_ , , _ . , ,m _ _ . . , , _ + - . - _ - , _ _ _ _ - . , _ _ . - -

LIMITING CONDITIONS FOR OPERATION I.

APPLICABILITY: RECOVERY MODE ACTION:

With the Reactor Coolant System temperature exceeding the temperature limits, immediately adjust the Reactor Coolant System temperature to within limits and g submit a report pursuant to Specification 3.0.3.

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THREE MILE ISLAND - UNIT 2 3.4-2 January 7, 1985 i

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LIMITING CONDITIONS FOR OPERATION 3.5 COM4UNICATIONS 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 50L or 50L limited to fuel handling, notwithst ; ding location, will have direct communications with personnel. in the Reactor Butiding [

performing CORE ALTERATIONS. l APPLICABILITY: 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 l be maintained, suspend all operations involving CORE ALTERATIONS and restore communications to OPERA 8LE status.

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THREE MILE ISLAND - UNIT 2 3.5-1 November 22, 1985 I

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LIMITING CONDITIONS FOR OPERATICN

3. 6 CONTAINMENT SYSTEMS 3.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY

3. 6.1.1 Primary CONTAINMENT .i; EGRITY shall be maintained unless it is not required per procedures approved pursuant to Specification 6.8.2.

APPLICABILITY: RECOVERY MODE.

ACTION:

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

s.

4 At least one deactivated automatic valve secured in the isolation position, or

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

CONTAINMENT AIR LOCKS A ,

3.6.1.3 Each containment air lock shall be OPERA 8LE with:

a. Both doors closed except when the air lock is being used for transit entry and exit through the containment, then at least one air lock door shall be closed unless otherwise specified per procedures approved pursuant to Specification 6.8.2.

b. Deleted -

APPLICABILITY: RECOVERY MODE.

ACTION

i 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. ~

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l THREE MILE ISLAND - UNIT 2 3.6-1 January 7,1985 1.

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LIMITING CONDITIONS FOR OPERATION .

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APPLICA8ILITY: REC 0VERY MODE.

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: RECOVERY MODE. .

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 .

3.6.3 CONTAINMENT PURGE EXHAUST SYSTEM 3.6.3.1 One train of the Containment Purge Exhaust System shall be OPERA 8LE.

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APPLICABILITY: During Purge Operations

, ACTION:

i With no Containment Purge Exhaust train OPERA 8LE, secure the Containment Purge System and restore one train to OPERABLE status within 7 days.

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I 3.6.4 COM8USTI8LE GAS CONTROL 3.6.4.1 Deleted HYOR0 GEN PURGE CLEANUP SYSTEM 3.6.4.3 Deleted

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i November 22, 1985 THREE MILE ISLAND - UNIT 2 3.6-2

! Figure 3.6-1 Minimum Allowable Centainment Pressure as a Function of 8WST Temperature and Containment Average Air Temperature DELETED

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I THREE MILE ISLAND - UNIT 2 3.6-3 _ January 7,1985

Enclosure 2

b. TABLE 3.6-2 ,,,

PENETRATIONS WITHOUT DOUBLE ISOLATION

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Function Syste_m Penetration Reactor Coolant Pump MU R-573*

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 BS i

R-586* Inlet Line

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Deca / Heat Coolant Supply DH.

R-589*

R-590*

High Pressure Injection MU 2 R-591*

R-Et2*

[r. ]> } .

Nitrogen and Fill to Core CF R-537' Flooding Tank Leakage Cooling DC R-539* ..

R-542*

Pressurizer Auxiliary Spray DH Nitrogen and Fill to Core CF R-544* -

Flooding Tank

' Nuclear Services Closed Cooling NS R-557* Water to Reactor Coolant Pump l 011 and Motor Coolers Intermediate Closed Cooling IC R-559*

Water to Roller Nut Drive Cooling coils Intermediate Closed Cooling IC R-563*

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- - System f SA R-566*- Service Air High Pressure Injection MU

! R-570*

R-572*

3.6-4 August 12. 1985 THREE MILE ISLAND - UNIT 2 teft!! ss; d

-, ,w ,,-,,w,,y,,-w,, ,--__,,,,,--..w,,,--,,,,,.-ww..,e--, m--.-y-e-%..,,, - , , . . . .. - . - - .--e. . ,.,,,.,y. e -v..,....y-- ---,

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1 i l Penetration Function System R-545A# Building Pressure BS R-554C#

R-571C#

R-562C# SL11 ding Spray System BS Pressure System R-593# Sump Pe.7etration Sleeve DH R-594# and Drain Line R-616# Auxiliary Feedwater Lines EF

,-623#

R R-617# Feedwater Lines FW R-618#

R-619# Steam Lines MS

- R-620#

R-621#

R-622#

A .

. Codes: BS-- Reactor Building Spray ,

CF-- Core Flooding -

DC-- Decay Heat Closed Cooling Water DH-- Decay Heat Removal EF-- Emergency Feedwater FW-- Feedwater -

IC-- Intermediate Closed Cooling Water i . MU-- Makeup and Purification l RR-- Reactor Building Emergency Cooling - River Water SA-- Station Service Air MS-- Main Steam NS-- Nuclear Services Closed Cooling Water

Penetrations which utilize a check valve inside containment as a containment isolation valve 4 # Penetrations which have single valve isolation THREE MILE ISLAND - UNIT 2 3.6-5 August 12, 1985 ;

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LIMITING CONDITIONS FOR OPERATION ..

l 3.7 PLANT SYSTEMS .

3.7.1 FEEDWATER SYSTEM Deleted by Amendment of Order Dated April 1, 1982. ,

3.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM Deleted by Ameruhent of Order Dated Aprh1 1,1982.

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3.7.3 CLOSED CYCLE COOLING WATER SYSTEM

. NUCLEAR SERVICES CLOSED CYCLE C0OLING SYSTEM i

3.7.3.1 Deleted.

I DECAY HEAT CLOSED COOLING WATER SYSTEM

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3.7.3.2 Deleted.

i MINI DECAY MEAT REMOVAL SYSTEM (MDHRS)

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) 3.7.3.3 Deleted. .

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THREE MILE ISLAND - UNIT 2 3.7-1 September 23, 1985 I

LIMITING CONDITIONS FOR OPERATION 3.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM 3.7.4.1 Two independent Nuclear Service River Water loops shall be OPERABLE.

APPLICABILITY: RECOVERY MODE.

ACTION: _

With or.e Nuclear Service River Water loop inoperable, restore the inoperable loop to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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n THREE MILE ISLANO - UNIT 2 3.7-2 September 23, 1985 0

, LIMITING CONDITIONS FOR OPERATION t^

3.7.6 FLOOD PROTECTION 3.7.6.1 Flood protection shall be provided for all Safety Related systems, components and structures when the water level of the Susquehanna River I exceeds 301 feet Mean Sea Level USGS datum, at the river water intake structure of Three Mile Island Nuclear Station, Unit 1.

APPLICABILITY: At all times.

ACTION:

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

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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 l SOD:

a) Prepare all flood panels and door seals for installation, b) Check all building floor drains and pumps to ensure proper *

']4 operation, c) Commence daily soundings of the Intake Screen House Floor, d) Check all water tight doors to ensure proper operation, e) Fill all outdoor storage tanks to inhibit floatation, and f) Arrange for alternate supplies of diesel fuel oil and ensure fuel storage tanks are filled.

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

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

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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. 'In" orm the Director Site Operations. I THREE MILE ISLAND - UNIT 2 3.7-3 January 7,1985 L -

, LIMITING CONDITIONS FOR OPERATION 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM 3.7.7.1 The Control Room Ventilation and Emergency Air Cleanup System shall I be OPERABLE with:

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

b. Two Control Room Bypass Fans, '

c. One charcoal adsorber and HEPA filter train, and

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

e. The control Room air inlet radiation monitor OPERA 8LE. I APPLICABILITY: REC 0VERY MDDE ACTION:

a. With one Control Room Supply Fan or its associated cooling coil l inoperable, restore the inoperable fan and/or cooling coil to OPERA 8LE status within 7 days.

I b. With one Control Room Bypass Fan inoperable restare the' inoperable I-I

) fan to OPERA 8LE status within 7 days.

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c. With the filter train inoperable, restore the filter train to i

OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . -

d. With one isolation damper in the outside air intake duct inoperable, restore the inoperable damper to OPERA 8LE 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 g 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 .

t THREE MILE ISLAND - UNIT 2 3.7-4 January 7,1905

LIMITING CONDITIONS FOR OPERATION i

3.7.9 SEALED SOURCES SEALED SOURCE INTEGRITY 3.7.9.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material (except as noted in 4.7.9.2) shall be free of

> 0.005 microcuries of removable contamination.

APPLICA8ILITY: RECOVERY MODE ACTION: ,

4 a.

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

1. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 are not applicable.

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THREE MILE ISLAND - UNIT 2 3.7-5 January 7.1985 t _ _ _ _ - _ _ . - _ _ _ -

i LIMITING CONDITIONS FOR OPERATION 3.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM 3.7.10.1 The FIRE SUPPRESSION WATER SYSTEM shall be OPERA 8LE with;

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

1. Unit 1 Circulating Water Flume Diesel Fire Pump

2. Unit 1 River Water Intake Diesel Fire Pump

3. Unit 2 River Water Intake Diesel Fire Pump

4. Unit 1 River Water Intake Motor Fire Pump

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

1. Altitude Tank l b -

2. Unit 1 Circulating Water Flume .

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3. Unit 1 River Water Intake Structure

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4. Unit 2 River Water Intake Structure

c. An OPERABLE flow path capable of t.aking suction from a water supply and transferring the water through distribution piping with OPERA 8LE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the water flow alarm device on -

each sprinkler, hose standpipe, or spray system riser required to t

be OPERA 8LE per Specification 3.7.10.2 and 3.7.10.4.

APPLICA8ILITY: RECOVERY MODE ACTION:

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

November 22, 1985 i THREE MILE ISLAND - UNIT 2 3.7-6

LIMITING CONDIT!0M3 FOR OPERATION FIRESUPPRFSSIONWATEk5YSTEM(Continued)

ACTION (Continued)

b. With the Fire Suppression Water System otherwise inoperable:

1. Establish a backup Fire Suppression Water Syvi.ee within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. Deleted. l 1

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1 THREE MILE ISLAND - UNIT 2 3.7-7 November 22. 1985

l . .

LIMITING CON 0!TIONS FOR OPERATION DELUGE / SPRINKLER SYSTEMS 3.7.10.2 !

shall be OPERA 8LE:

The Deluge and/or Sprinkler Systems located in the following areas

a. !

Ofesel Generator Fuel 011 Tanks

b. Diesel Generator Building Air Intake

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/8#

f. Control Room Bypass Filter AH-F-5

g. Diesel Generator Rooms

h. Fuel Handling Building Exhaust Filter AH-F-14A/Bf

1. Waste gas disposal filter WDG-F-1

j. Auxiliary Building exhaust filters AH-F-10A/8#

k. Southeast Storage Facility ***

APPLICABILITY: RECOVERY MODE.

( ACTION:

- With one or more of the above required deluge and/or sprinkler systems inoperable, establish a roving (at least once perhour) fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; restore the system to OPERA 8LE status within 14 days.

l

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

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

THREE MILE ISLAND - UNIT 2 3.7-8 November 22, 1985

( LIMITING CONDITIONS FOR OPERATION HALON SYSTEM

3.7.10.3 The following Halon systems shall be OPERA 8LE 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 Rcom - Control Building 305' elevation.

. +

b. Air Intake Tunnel (4 Zones)

APPLICA8ILITY: REC 0VERY MODE ACTION:

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

l 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:

APPLICA8ILITY: RECOVERY MODE ACTION:

With one or more of the fire hose stations shown in Table 4.7-1 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERA 8LE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

i*

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

THREE MILE ISLAND - UNIT 2 3.7-9 November 22, 1985

TA8LE 3.7-4 FIRE HOSE STATIONS i

Transferred to Table 4.7-1 of the Recovery Operations Plan i .

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i THREE MILE ISLAND - UNIT 2 3.7-10 January 7. 1985 I

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LIMITING CONDITIONS FOR OPERATION

(

i PENETRATION FIRE 8ARRIERS 3.7.11 All Penetration Fire Barriers protecting Safety Related areas shall be functional.

APPLICABILITY: RECOVERY MODE ACTION:

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

1. Establish a roving (at least once per hour) fire watch on at least one side of the affected penetration within I hour, except areas inaccessible due to occupational exposure considerations and

2. For those areas inacesssible due to occupational exposure considerations, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the cause of the malfunction and the means for ensuring an adequate firewatch is maintained in the affected area and for restoring the fire barrier (s) to a functional status.

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THREE MILE ISLAND - UNIT 2 3.7-11 January 7, 1985

, LIMITING CONDITIONS FOR OPERATION t

3. 8 ELECTRICAL POWER SYSTEMS 3.8.1 A.C. SOURCES

3. 8.1.1 As a minimum, Me following A.C. electrical power sources shall be

OPERA 8LE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class IE distribu' tion system. i b.

Two separate and independent class IE diesel generators each with:

1.

A separate day fuel tank containing a minimum volume of 500 gallons of fuel.

2.

A separate fuel storage system containing a minimum volume of 19,000 gallons of fuel.

3. A separate fuel transfer pump. ;

APPLICA81LITY: REC 0VERY MODE.

ACTION:

I a.

With either an offsite circuit or diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERA 8ILITY of the remaining A. C. sources by performing Surveillance Requirements 4.8.1.1.1 and 4.8.1.1.2.a.4 in accordance with the applicable row in the Testing Frequency Matrix of Table 3.8-1; reitore the full complement of the above required A.C. electrical power sources to OPERA 8LE status within 7 days. I b.

With one offsite circuit and one diesel generator or two offsite circuits or two diesel generators of the above required A. C. electrical power -

sources inoperable, demonstrate the OPERABILITY of the remaining A.C.

i sources by performing Surveillance Requirements 4.8.1.1.1 and 4.8.1.1.2.a.4 in accordance with the applicable two rows in the Testing Frequency Matrix of Table 3.8-1; restore at least one of the inoperable sources to OPERABLE status in accordance with the Restoration Time Matrix of Table 3.8-2.

Restore the full complement of the above required A.C. electrical power sources to OPERABLE status within 7 days from the time of initial loss. I I

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THREE MILE ISLAND - UNIT 2 3.8-1 January 7,1985

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

TA8LE 3.8-1 TESTING FREQUENCY MATRIX Component Testing Frequencies i

sg a U b 2 1 2 I C N 0 a a' ** **

0 1 M

, P P E O a * ** **

R N 2

A E 8 N b * *

A L T E

kg * *

Key: I a Offsite power circuit No. 1

' i a Offsite power circuit No.-2

b Class IE diesel generator (Red) ,

b Class IE diesel generator (Green)

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

- Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months c lass the diesel generator has been demonstrated OPERABLE per Sui veillance Requirement 4.8.1.1.2 within the previous 7 days, then demonstration of diesel generator operability is not required. _.

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I THREE MILE ISLAND - UNIT 2 3.8-2 January 7, 1985

TABLE 3.8-2

.I RESTORATION TIME MATRIX Restore One Restore Other Component Component (Hours) (days)

Combination as 24 of Two 7 Inoperable Components ab 12 7 bb 12 7 Note: a and b above correspond to components described in Specification 3.8.1.1, items a and b respectively.

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THREE MILE ISLAND - UNIT 2 3.8-3 .1anuary 7, 1985

. o LIMITING CONDITIONS FOR OPERATION d

3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS !

A. C. DISTRIBUTION l

3.8.2.1 The following A.C. elect' ical busses listed in Section 4.8.2.1 of the RECOVERY OPERATIONS PLAN shall be OPERA 8LE and energized with tie breakers open (unless closed in accordance with procedures approved pursuant to Specifica-tion 6.8.2) between redundant busses.

APPLICABILITY: RECOVE'Y R MODE.

ACTION:

w With less than the above complement of A.C. busses OPERA 8LE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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l THREE MILE ISLAND - UNIT 2 3.8-4 January 7, 1985 i

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LIMITING CONDITIONS FOR OPERATION D.C. DISTRIBUTION i

3.8.2.3 The following D.C. bus trains shall be energized and OPERABLE with l tie breakers between bus trains open (unless closed in accordance with approved procedures): !

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

battery bank A and a full capacity charger.

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

battery bank.8, and a full capacity charger.

APPLICABILITY: RECOVERY MODE.

ACTION:

a.

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

b.

With one 250/125 volt D.C. battery and/or its charger inoperable, restore the inoperable battery and/or charger to OPERA 8LE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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e THREE MILE ISLAND - UNIT 2 3.8-5

i LIMITING CONDITIONS FOR OPERATION -

3.9 RADI0 ACTIVE WASTE STORAGE SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITCRI E 3.9.1 Two independent Spent Fuel Storage Pool "A" water level monitoring instruments shall be OPERABLE.

APPLICABILITY: Whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".

ACTION:

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

b. With no Spent Fuel Storage Pool "A" water level monitoring instruments OPERABLE, terminate all activities involving any Canister cons "..iag 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 OPERA 8LE status witt.fn 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 per NRC approved procedures. ,

t' APPLICABILITY: Whenever any Canister containing core material is in the Spent Fuel Storage Pool "A".

ACTION: -

With Spent Fuel Storage Pool "A" water level not in accordance with approved procedures, terminate all activities involving any Canister containing core material in or ever Spent Fuel Storage Pool "A" 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 TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING 3.9.3 Two independent Fuel Transfer Canal (deep end) water level monitoring instruments shall be OPERA 8LE.

APPLICA8ILITY: Whenaver any Canister containing core material and/or the plenum assembly is in the Fuel Transfer Canal (deep end).

ACTION:

a. With only one Fuel Transfer Canal (deep and) water level monitoring instrument OPERA 8LE,.famediately 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 November 22, 1985

LIMITING CONDITIONS FOR OPERATION

(

b. With no Fuel Transfer Canal (deep end) water level instruments OPERABLE, terminate all activities involving any Canister containing core material in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assembly and a.11 operations involving changes in the .iel Transfer Canal (deep end) water inventory and restore one inoperable instrument to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

FUEL TRANSFER CANAL (DEEP END) WATER LEVEL 3.9.4 The water level in the Fuel Transfer Canal (deep end) shall be maintained at the level snecified per NRC approved procedures.

APPLICABILITY: Whenever any Canister containing core material and/or the plenum assembly is in the Fuel Trnasfer Canal (deep end).

ACTION:

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

FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS I .

3.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be OPERABLE with exhaust ventilation flow through the HEPA filters during system operation. The Fuel Handling Building Air Cleanup Exhaust System is OPERABLE when two of the four system air cleanup exhaust fans are OPERABLE.

APPLICABILITY: RECOVERY MODE ACTION: ,

a. With the Fuel Handling Building Air Cleanup Exhaust System inoperable due to flow requirements, return the flow to within acceptable limits within four (4) hours or;

' ~

b. With the Fuel Handling Building Air Cleanup Exhaust System inoperable (other than as allowed in paragraph 3.9.12.1 a above), suspend all opera-tions involving movement of liquid and gaseous radioactive wastes in the Fuel Handling Building (other than sampling evolutions required by the.

Technical Specifications or RECOVERY OPERATIONS PLAN) until the system is restored to OPERABLE status.

b THREE MILE ISLAND - UNIT 2 3.9-2 May 31, 1985

LIMITING CONDITIONS FOR OPERATION l

3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shal1 be OPERABLE with exhaust ventilation flow through the HEPA filters during system operation.

The Auxiliary Building Air Cleanup Exhaust System is OPERABLE when two of the four system air cleanup exhaust fans are OPERABLE.

APPLICABILITY: REC 0VERY MODE ACTION:

a. With the / iliary Building Air Cleanup Exhaust System inoperable due to flow requirements, return the flow to within acceptable limits within four (4) hours or;

b. With the Auxiliary Building Air Cleanup Exhaust System inoperable (other than as allowed in paragraph 3.9.12.2 a above), suspend all operations involving movement of liquid and gaseous radioactive wastes in the Auxiliary Building (other than sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN) 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. ACCIDENT GENERATED WATER shall be discharged in accordance with procedures approved pursuant to Specification 6.8.2. ,

APPLICABILITY: RECOVERY MODE i

ACTION: -

None except as provided in Specification 3.0.3.

REACTOR BUILDING SUMP WATER _

3.9.14 Deleted.

.THREE MILE ISLAND UNIT 2 3. 9- 3 May 31, 1985

. . I LIMITING CONDITIONS FOR OPERATION I

3.10 CRANE OPERATIONS i

CONTAINMENT BUILDING

{

3.10.1 Loads in excess of 2400 lbs. shall be prohibited from travel over the following areas unless a docketed Safety Evaluation for the activity is approved by the NRC:

a. reactor vessel

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

c. deep end of the Euel 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: RECOVERY MODE ACTION:

{~ With the requirements of the above specification not satisfied, place the crane

load in a safe condition and correct the circumstances which caused or allowed the Limiting Condition for Operations to be exceeded prior to continuing crane operations limited by Specification 3.10.1. Prepare and submit a special report to the Commission pursuant to Specificat.fon 6.9.2 within the next 30 days.

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

a. any area of the spent fuel storage 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 drop analysis

. I THREE MILE ISLAND - UNIT 2 3.10-1 May 31,1985

LIMITING CONDITIONS FOR OPERATION APPLICABILITY: RECOVERY MODE ACTION:

With the requirements of the above specification not satisfied, place the crane load in a safe condition and correct the circumstances which caused or allowed the Limiting condition for Operations to be exceeded prior to continuing crane operations limited by Specification 3.10.2. Prepare and submit a special report to the Commission pursuant to Specification 6.9.2 within the next 30 days.

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THREE MILE ISLAND - UNIT 2 3.10-2 May 31, 1985

5 9 4

8ASES FOR LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS e

9

_ NOTE The summary statements contained in this section provide the bases for the Specifications of Section 3.0 and 4.0 and are not considered a part of these Technical Specifications as provided in 10 CFR 50.36.

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w ,- ,- - , ,,w,,-- - ---

- , , , , - - - - + - , - ----4

3/4.0 APPLICABILITY BASES The specifications of this section provide the general requirements applicable within Section 3/4.to each of the Limiting Conditions for Operation and Surveillance

3. 0.1 This specification defines the applicability of each specification in terms of the RECOVERY MODE or other specified conditions and is provided to delineate specifically when each specification is applicable.

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

4 3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements or when the provisions of the stated ACTION statement are not or cannot be complied with.

The intent of this specification is to require that inoperable equipment be restored to an 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 insure the Limiting Conditions for Operation are met and will during the RECOVERY for Operation are applicable. MODE or other conditions for which the Limiting conditions 4.0.2 The provisions of this specificati n9 provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval.

flexibility because of scheduling and performance considerations.These "at least" associated with a surveillance frequency does not negate thisThe phrase allowable tolerance value and permits the performance of more frequent surveillance activities.

l The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated from the nominal with the surveillance specified interval. activity is not degraded beyond that obtained 1

h THREE MILE ISLAND - UNIT 2 8 3/4 0-1

.ve -w--. - - - _ _ , - , . _ _ - _ . . - . , - , . . _ , - _ - . . _ , _ . , , , _ , _ _ , , , ,

r , - - ..- . . , , . - . ___._y___ ..-,-,s, .--,-_-.__,--. ,,.-, , _ _ _ _ ,w--.-,-,,, - . - _ -

APPLICABILITY BASES 4.0.3 The provisions of this specification set forth the criteria for deter-mination Conditionsof for compliance with the OPERABILITY requirements of the Limiting 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.0PERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

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THREE MILE ISLAND - UNIT 2 8 3/4 0-2 y-+w -w- - - , -y__ -, - _ . . , . - + . - - - ,- ~

3.4.1 WATER INJECTION C0OLING AND REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 80RATTSN CONTROL AND BORATED COOLING WATER INJECTION The limitation on minimum boron concentration ensures that the core will remain I suberitical under all credible conditions which may exist during the long-term I cooling mode. The maximum boron concentration is provided to ensure that pre- l cipitation of boron will not occur in the RCS and thereby cause possible flow ,

restrictions. The specification requires the OPERABILITY of systems capable l of injecting borated cooling water *into the RCS within the required boron con-centration limits. The required volume of borated water in the BWST provides ,

sufficient water to keep the core covered in the event of an un'solatable leak '

from the reactor vessel. The specified water volume is sufficient to provide a continuous supply of water to the vessel during the interim period before the recirculation flowpath from the Reactor Building Sump can be placed in service. Minimum boron concentration limits have been provided for the Refuel-ing Canal (deep and) and Spent Fuel Storage Pool "A" to provide assurance that any event involving these volumes of water will not result in a margin of safety less than that analyzed for the reactor vessel.

3/4.1.3 CONTROL ASSEMBLIE_5 All full-length control rods were fully inserted as a result of the reactor trip on March 28, 1979. This Specification has been deleted since the reactor vessel head has been removed.

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B 3/4 1-1 September 23.198!

THREE MILE ISLAND - UNIT 2 ,

3/4.3 INSTRUMENTATION 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 generation.

status of the core and it will be used to monitor changes in neutron 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATI Except for automatic starting of the diesel generators on loss of offsite power, all automatic features of the ESFAS instrumentation have been defeated.

This action prevents inadvertent actuation of the ESF systems. The diesel generators will start automatically on loss of offsite power.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the level trip setpoint alarm or automatic action is initiated when the radiation is exceeded.

3/4.3.3.3 SEISMIC INSTRUMENTATION Deleted.

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THREE MILE ISLAND - UNIT 2 8 3/4 3-1 January 7.1985

INSTRUMENTATION BASES 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERA 8ILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to-the public as a result of routine or accidental release of radioactive materials to the atmosphere.

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

This instrumentation is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

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. Neutron monitoring and Reactor Coolant System temperature indication are provided outside the Control Room in the event that Control Room habitability is lost.

Design Criterion 19 of 10 CFR 50, Appendix A. This is consistent with General 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION Deleted.

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.

The Chlorine Detection Systems required by this specification are consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant 1975. Control Room Operators Against an Accidental Chlorine Release," February THREE MILE ISLAND - UNIT 2 8 3/4 3-2 January 7, 1985

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

INSTRUMENTATION BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the Fire Detection Instrumentation ensures that adequate warning L capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to Safety Related equipment and is an integral element in the overall facility fire protection program.

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

, 4 January 7.1985 l

THREE MILE ISLAND - UNIT 2 8 3/4 3-3 _

1 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS Alternative methods are available for removal of reactor decay heat. These methods include use of the Decay Heat Removal System, the Mini Decay Heat Removal System, and the " Loss to Ambient" cooling mode. Either of these cooling methods provides adequate cooling of the reactor and each method is available for decay heat removal. '

for use of these cooling methods. Procedures have been prepared and approved 3/4.4.2 REACTOR VESSEL WATER LEVEL MONITORING The Reactor monitor Vessel for changes Watervessel in reactor Levelwater Monitor level.ensures that indication is available This device will provide warning.of a leak from the Reactor Coolant System or unexplained increases in Reactor Coolant System inventory which could result in a boron dilution event.

Two independant monitors are required to provide redundancy and to minimize the necessity to discontinue processing because of instrument failures. ,

3/4.4.3 SAFETY VALVES Deleted.

l 3/4.4.9 PRESSURE / TEMPERATURE LIMIT .

The Reactor Coolant System pressure and temperature will be controlled in accordance with approved procedures to prevent a nonductile failure of the Reactor Coolant System while at the same time preventing precipitation of tha boron used to maintain subcriticality.

During the RECOVERY MODE, the Reactor Coolant System boundary will be modified periodically to meet recovery objectives. Whenever the Reactor Coolant System is not vented (open to the atmosphere), overpressure protection will be pro-vided to ensure that the allowable RCS pressure is not exceeded.

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

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THREE MILE ISLAND - UNIT 2 8 3/4 4-1 January 7,1905 l

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, o BASES 3/4.5 COMUNICATIONS The requirements for communications capability ensure that personnel in the Reactor Building can be promptly informed of significant changes in facility status or core reactivity conditions during CORE ALTERATIONS.

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l THREE MILE ISLAND - UNIT 2 8 3/4 5-1 January 7.1985

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY i

Primary CONTAINMENT INTEGRITY is maintained as required per procedure to ensure !

that radioactive materials in the Containment Building are not released to the environment in an encontro11ed manner.

3/4.6.1.3 CONTAINMENT AIR LOCKS The containment air locks must be maintained OPERA 8LE to provide CONTAINMENT INTEGRITY. These air locks will be used during entries into the contain- ;

ment to ensure that radioactive materials are not being released to the environs.

The preferred method for ensuring that radioactive materials are not releaseo 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 l doors suant may be open simultaneously to Specification 6.8.2. in accordance with procedures approved pur- i 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 consideration. During periods when ,both doors in either or both personnel air locks are open, the containment purge system will be operating to maintain Containment pressure within the limits of the Technical Specification.

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 maxit.ize the service life of the instrumentation and equipment installed in the Containment and ensure that Reactor Coolant System temperature does not drop below 50'F via LOSS-TO-AMBIENT. This temperature will ensure that boron will remain in solution. Continued OPERABILITY of these items is required to. continue j monitoring and mitigating the March 28, 1979 incident.

3/4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM j

The OPERABILITY requirements for the Containment Purge Exhaust System ensure that during Containment purge operations all radioactive particulate material i

, will be filtered through the HEPA filters prior to re'asse to the atmosphere.

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i THREE MILE ISLAND - UNIT 2 8 3/4 6-1 January 7.1905

,-m _ - _ . -

,-m,-- ,,e,_,--_____ , , - . - , , _ - _ _ , _ - _ _ - _ . _ . - , , . - - - , , - - . - - - _ _ ,_

B 8 CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTI8LE GAS CONTROL The gas partitioner is provided to analyze the hydrogen concentration in the containment atmosphere so that actions can be initiated to reduce the hydrogen concentration if it approaches its flammable limit. If excessive hydrogen concentrations are detected, appropriate act'icns will be initiated to' reduce the hydrogen concentration to a safe level.

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THREE MILE ISLAND - UNIT 2 8 3/4 6-2 January /. 1W83

- - - - .-.w--e goe>,-,+,.,. eve,e----%-, , .,,.-,-y ---,,-w- - , .-- -, - . , - - - - -

o- 4 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 FEEDWATER SYSTEM Deleted by Amendment of Order Dated April 1, 1982.

3/A.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM Deleted.' -

3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM 3/4.7.3.1 NUCLEAR SERVICES CLOSED CYCLE COOLING SYSTEM

~~ .

Deleted.

3/4.7.3.2 DECAY HEAT CLOSED COOLING WATER SYSTEM t

Deleted.

4 3/4.7.3.3 MINI DECAY HEAT REMOVAL SYSTEM (MOHRS)

Deleted.

3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM The Nuclear Service River Water System uses' river water to cool the diesel generators. Therefore, it must be OPERABLE also. This system rejects its heat to the river as the Ultimate Heat Sink.

3/4.7.6 FLOOD PROTECTIDN The limitation on flood protection ensures that facility protective actions

' will be taken in the event of flood conditions. The limit of elevation of 302 ft. Mean Sea Level USGS datum is the elevation at which facility flood control measures-are required to be taken to proviA protection to Safety l-Related equipment.

i~

4 THREE MILE. ISLAND - UNIT 2 8 3/4 7-1 September 23, 1985 i -

1

-m-., ,- ,..w. ,-- - -.,r, .,,,..,,_.-.a--.,_, - . - -, , . _ . .,.-n.--,, ,. . - . -. . . , . - - , , . , .-...,.n-- , _ , --.. -- - . - . .

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERA 8ILITY of the control room emergency air cleanup system ensures that

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERASILITY of this system in conjunction with control room' design provisions is based on limiting the radiation exposure to' personnel occupying the control room to 5 i ren or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",10 CFR 50.

3/4.7.9 SEALED SOURCE CONTAMINATION The limitation on removable contamination for sources requiring leak testing, including alpha @ Un rs, is based on 10CFR70.39(c) limits for plutonium.

Thh limitatWa trill ensure that leakage from byproduct, source, and Special Nuclear Material sources will not exceed allowable intake values.

- ]/4,7,J0 FIRESUPPRESSIONSYSg5 Tr.e OPERABILITY of the Fire $~upp ession Systems ensures that adequate fire suppression capability is availph!c to confine and extinguish fires occurring in any portion of the facility where Safety Related equipment is located.

The Fire Suppression Syste: Gr,7,14ts of the water system, spray and/or 4prinH erg, Halon and fire hose stations. The collective capability of the Fire Suppressicr, kynee 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 required to be made 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, i

immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a Special Report to the Commission provides for timely evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued operation of the nuclear plant.

l 8 3/4 7-2 2

THREE MILE ISLAND - UNIT 2 January 7.1935

r- ,

PLANT SYSTEMS BASES 3/4.7.11 PENETRATI_0N FIRE BARRIERS The functional integrity of the Fire Barrier Penetration Seals ensures that fires will be confined or adequately retarded from spreading to adjccent portions of the faciljty. This design feature minimizes the possibility of a single fire rapidlycinvolving several areas of the facility prior to detection and extinguishment.

The Fire Barrier Penetration Seals are a positive element periodic inspections. in the facility fire protection ~ program and are subject to During periods of time when the seals are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected seal until the seal is restored to furictional status.

e i

r THREE MILE ISLAND - UNIT 2 8 3/4 7-3 v- f --3 + -m, ,,e e---.-,e,-- sw.._,,,,---,,a , - - - --+---..w.,,ww- . - - w,,i. ,w.,.y, , w, --%,y7 . - - - -,- r-- ,-

BASES 3/4.8 ELECTRICAL POWER SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the Safety Related equipment required to maintain the unit in stable conditions during recovery from the March 28, 1979 accident.

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i THREE MILE ISLAND - UNIT 2 8 3/4 8-1

e 3/4.9 RADIOACTIVE WASTE STORAGE BASES 3/4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MCNITORING

^

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 Poul "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 (DEEP END) WATER LEVEL MONITORING Fuel Transfer Canal Water Level Monitoring instrumentation has been provided to assure the capability to monitor water level in the deep end of the Fuel Transfer Canal.

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

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

3/4.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS The requirements for the Fuel Handling / Auxiliary Building Air Cleanup Systems to be operating or OPERABLE ensure that all radioactive material released from the liquid radioactive wastes being stored in the new radwaste storage tanks which have been installed in the spent fuel storage pool or elsewhere in the Auxiliary Building will be filtered through the HEPA filters prior to release to the atmosphere.

3/4.9.13 ACCIDENT GENERATED WATER

, These specifications are provided to ensure compliance with the Commission's Statement of May 25, 1979, and the Commission's Statement of Policy and Notice t of Intent to Prepare a Programmatic Environmental Impact Statement of l November 21, 1979, which prohibit these actions pending evaluation of the {

environmental impacts of such actions. The PEIS issued in March, 1981, l deferred a decision on the ultimate disposal of processed water. Further '

Commission action is necessary prior to release of ACCIDENT GENERATED WATER.

However, the Commission has recognized that there may be emergency situations, not at this time forseen, which could require rapid action. In these situations, the Commission has indicated its intention to consult with the

. Council on Environmental Quality to the extent practicable.

I THREE MILE ISLAND - UNIT 2 B 3/4.9-1 May 31, 1985

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3/4.9 RADI0 ACTIVE WASTE STORAGE BASES ACCIDENTGENERATEDWATER,asdefinedinthesettlementoftheCityofLancaster litigatio, is:

(a) Water that existed in the TMI-2 Auxiliary, Fuel Handling, and Contain-ment Buildings including the primary system as of October 16, 1979, wi,th exception of water wich as a result of decontamination operations.

becomes commingled with non-accident generated water such that the

, commingled water has a tritium content of 0.025 pCi/ml or less before-processing; (b) Water that has a total activity of greater than one pCi/ml prior to processing except where such water is originally non-accident water and becomes contaminated by use in cleanup; (c) Water that contains greater than 0.025 pCi/ml of tritium before processing.

3/4.9.14 Deleted.

THREE MILE ISLAND - UNIT 2 8 3/4 9-2 May 31,1985 )

a,

.3/4.10 DEFUELING OPERATIONS ,

1 i

BASES 3/4.10 CRANE TRAVEL - CONTAINMENT SUILDING .

9 A load drop into the Reactor Vessel may cause reconfigurations of the core debris and/or strectural damage which could hinder recovery efforts. A load drop on the Incore Instrument-Seal Table and/or guide tubes may result in an

.unisolable leak from the Reactor Vessel. The restriction on movement of loads in excess of the nominal weight of a fuel or control rod assembly and associated handling tool over these areas is to mitigate the potential consequences stated above in the event this load is dropped. '-

4 i

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THREE MILE ISLAND - UNIT 2 8 3/4 10-1 July 17, 1984

g D e

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c 5

RECOVERY OPERATIONS PLAN TMI-2 9

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INDEX SURVEILLANCE REQUIREMENTS

'SECTION P,,g 4.1 ' WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 4.1.1 80 RATION CONTRdt 4.1.1.1 Borated Cooling Water In 4.1.1.2 Boron Concentration.....jection.............................. 4.1-1

..................................... 4.1-3 4.1.3 CONTROL ASSEMBLIES 4.1.3.1 Rod Positions................................................ 4.1-3 4.3 INSTRUMENTATION 4.3.1 NEUTRON MONITORING INSTRUMENTATION............................. 4.3-1 4.3.2

! ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTA 4.3-1 4.3.3 MONITORING INSTRUMENTATION 4.3.3.1 Radiation Monitoring Instrumentation.....

4.3-1 4.3.3.3.1 4.3.3.4 Meteorological Seismic Instrumentation....... .......... ...................

4.3-6 4.3.3.5 Instrumentation...............................

.............. 4.3-8 4.3.3.6 Eisential Parameters Monitoring Instrumentation.............. 4.3-8 4.3.3.7 Post accident Instrumentation................ *.3-8 Chlorine Detection Systems................... ...............

4.3.3.8 Fire Detection................................ .............. 4.3-8

.............. 4.3-12 4.4 REACTOR COOLANT SYSTEM 4.4.1 4.4.2 REACTOR COOLANT L00PS........................................

REACTOR VESSEL WATER LEVEL 4.4-1 MONITORING........................ 4.4-1 i

t 4.4.9 PRESSURE / TEMPERATURE LIMITS

! 4.4.9.1 Reactor Coolant System.......................................

i 4.4-1 i

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i THREE MILE ISLAND - UNIT 2 I January 7.1985

INDEX

_ SURVEILLANCE REQUIREMENTS SECTION f.QE 4.s COMMUNICATIONS................................................... 4.5-1 1

4.6 CONTAINMENT SYSTEMS !

4.6.1 PRIMARY CONTAINMENT 4.6.1.1 Containment Integrity.....................

4.6.1.3 4.6-1

4. 6.1. 4 Containment Air Internal Locks..................... ..................

................ 4.6-1 4.6.1.5 Pressure................... .......................

Air Temperature..................... 4.6-2

. ....................... 4.6-2 4.6.3 CONTAINMENT PURGE EXHAUST i

SYSTEM............................... 4.6-2 4.6.4 COMBUSTIBLE GAS CONTROL 4.6.4.1 Hydrogen Analyzers.................................

4.6.4.3 Hydrogen Purge Cleanup System...................... ........ 4.6-3

. . . . . . . . 4.6-3 4.7 PLANT SYSTEMS.

4.7.1 FEEDWATER SYSTEM............................................... 4.7-1 4.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM................. 4.7-1 4.7.3 CLOSED CYCLE COOLING WATER SYSTEM 4.7.3.1 Nuclear Services Closed Cycle Cooling 4.7.3.2 System.................. 4.7-1 Decay Heat Closed Cooling Water System. . . . . . . . . . . . . .

4.7.3.3 Mini Decay Heat Removal System...................... ......... 4.7-2

. . . . . . . . . 4.7-2 4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM............................... 4.7-3 4.7.6 FLOOD PROTECTION................................................. 4.7-3 4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM. . . . .4.7-4 ............

4.7.9 SEALED S00RCES................................................... 4.7-6 4.7.10 FIRE SUPPRESSION SYSTEMS 4.7.10.1.1 F i re S upp re s s ion Wa te r Sy s tem. . . . . . . . . . . . . . . . . . . . . . . . . .~ . . . . .

4.7.10.2 Deluge / Sprinkler Systems............... .................... 4.7-9 4.7-7 4.7.10.3.1 Halon Systes...........................

i 4.7.10.4 ................... 4.7-9 a

Fire Hose Stations...................... ................... 4.7-10 4.7.11 PENETRATION FIRE i 8ARRIERS....................................... 4.7-10 1 THREE MILE ISLAND - UteIT 2 II January 7.1985 1

- -,n --- ,-- --n--- ,,-, , , - w,- , ,- ,_,- -- .,----,n- - , ,, e----,w- - - . - - - -v-~-

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.o .

f03 SURVEILLANCE REQUIREMENTS SECTION PAGE 4.8 ELECTRICAL POWER SYSTEMS 4.8.1 A.C. SOURCES.................................................. 4.8-1 4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 4.8.1.1 A.C. Distribution........................................... 4.8-2 4.8.2.2.1 0. C. Distribution........................................... 4.8-2 4.9 LIQUID RADIOACTIVE WASTE STORAGE 4.9.1 SFfNT FUEL STORAGE POOL WATER "A" LEVEL MONITORING. . . . . . . . . . . . . 4.9-1 4.9.2 SPENT FUEL STORAGE POOL WATER "A" LEVEL........................ 4.9-1 4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING. .... .. . .. 4.9-1 4.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL..................... 4.9-1 4.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS.. 4.9-1 I

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l THREE MILE ISLAND - UNIT 2 III May 31,1985

, -n ,- --<

v .-a. - ,,,----,r n -

4 Section 4.0 Surveillance Requirements e

a

)

I SURVEILLANCE REQUIREMENTS __ l

I 4.0.1 Surveillance Requirements of the RECOVERY OPERATIONS PLAN shall be applicable during the RECOVERY MODE or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. The Surveillance Requirements shall be ,

l performed to demonstrate compliace with the OPERASILITY requirements of the Limiting Conditions for Operations and in accordance with the RECOVERY OPERA-TIONS PLAN; however, the RECOVERY OPERATIONS PLAN shall not be considered a part of these technical specifications. Changes to the REC 0VERY OPERATIONS PLAN shall be approved by the NRC prior to implementation.

4.0.2 Each Surveillance Requirement of the RECOVERY OPERATIONS PLAN.shall be performed within the specified time interval scith:

I a. A maximum s11owable extension not to exceed 25% of the surveillanc'e interval, and

[

b. A total maximum combined interval time for any 4 consecutive tests l not to exceed 3.25 times the specified surveillance interval.

l 4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a l

Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

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i November 22. 1985 THREE MILE ISLAND - UNIT 2 4.0-1

=~ e--%. co--, --- , . - ,_ ._,e,____ _ _ . , , - . . _ - ,w,,m-w..-... , , ._,, . , , - _ _ ,.,_-,.---s. . _. -,,%_ ,~~,,--,.,-._,_v_,_-.---y--- , , , , , , . -

9 O l

SL*RVEILLANCE REQUIREMENTS 4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 4.1.1 80 RATION CONTROL -

BORATED COOLING WATER INJECTION 4.1.1.1 The systems capable of injecting bora'ted cooling water into the Reactor. Coolant System shall be demonstrated OPERA 8LE:

A.

i At least once per 31 days by verifying that each accessible (per occupational exposure considerations) valve in each flowpath that is not

' locked, seal 1, or otherwise secured in position, is in its correct position. -

, 8. At least onco per 7 days by:

1. Verifying the boron concentration in the BWST is between 4350 and

_ 6000 ppe.

2. Verifying the contained borated water volume in the 8WST is at least 390,000 gallons:

C.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the 8WST . temperature is at least 50 degrees Farenheit when the outside temperature is less than 50 degrees

, Farenheit.

D. At least once per 6 months by verifying the pumps associated with the Reactor Building Sump Recirculatica System produce sufficient head and flow to meet makeup re.quirements.

i 1

l THREE MILE ISLAle - UNIT 2 4.1-1 September 23. 1985 L ,

SURVEILLANCE REQUIREMENTS This page deleted.

l 4

]

.THREE MILE ISLAND - UNIT 2 4.1-2 September 23 1985 Change No. 29

SURVEILLANCE REQUIREMENTS BORON CONCENTRATION 4.1.1.2 The boron concentration of all filled portions of the Reactor ' Coolant .

System and the Refueling Canal shall be determined to be within the specified limits by: ,

^

a. Determining the boron concentration of the coolant in the' filled '

portions to be between 4350 and 6000 ppm by:

1. A mass balance calculation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. A chemical analysis at least once per 7 days. -

b. Verifying the temperature of the coolant in the filled portions of the Reactor Coolant System to be greater than 50'F at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. Deleted 4.1.1.3 The boron concentration of the water filled portions of the Fuel Transfer Canal (deep end) and Spent Fuel Storage Pool "A" shall be determined to be within the specified limits by:

a. Determining the boron concentration of the water in the filled portions of the Fuel Transfer Canal (deep end) and the Spent Fuel Storage Fsol "A" to be between 4350 and 6000 ppm by a chemical analysis at least once per 7 days.

.4.1.3 CONTROL ASSEMBLIES 4.1.3.1 With the Reactor Vessel Head and the, Control Rod Drive Mechanisms removed or disconnected from the reactor vessel there is no surveillance required.

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THREE MILE ISLAND - UNIT 2 4.1-3 Change No. 27 i

SURVEILLANCE REQUIREMENTS 4.3 INSTRUMENTATION 4.3.1 NEUTRON MONITORING INSTRUMENTATION 4.3.1.1 Each intermediate ~and source range neutron monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during RECOVER and at the frequency shown in Table 4.3-1.

4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 4.3.2.1 Each ESFAS instrumentation' channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during RECOVERY MODE and at the frequencies shown in Table 4.3-2.

4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION AND CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-3.

, 4.3.3.2 Deleted.

4.3.3.3 Deleted.

SEISMIC INSTRUMENTATION 4.3.3.3.1 Deleted.

4.3.3.3.2 Deleted.

9 THREE MILE ISLAND - UNIT 2 4.3-1 Change No. 22

r TABLE 4.3-l' E! NEUTRON MONITORING INSTRWENTATION 5

5; CHANNEL MINIMLM CHANNEL CHANNEL FUNCTIONAL TOTAL NO. CHANNELS CHANNELS REA0 OUT FUNCTIONAL UNIT CHECK CALIBRATION TEST OF CHANNELS TO TRIP OPERA 8LE LOCATIONS R III

1. Intermediate Range, Neutron S M 2 ,0 1 Cab'. 217 +

E Flux and Rate Control Room

= 2. Source Range, Neutron Flux 5 R III M 2 0 2 Cab 217(2) ,

and Rate

Control Room NOTE _5

,a (1) - Neutron detectors and all channel components located inside containment may be excluded from y CHANNEL CALIBRATION.

. u (2) - Only one readout required at Cabinet 217.

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}- -

i

% TABLE 4.3-2

m i a ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTIRNENTATION f E

~

4 NININUM.

TOTAL NO.

! h o FLNICTIONAL UNIT OF CHANNELS CHANNELS CHANNELS CHANNEL CHANNEL CHANNEL TO TRIP OPERA 8tE ACTION FUNCTIONAL CHECK CALIBRATION

1. TEST LOSS OF POWER

! E j Z a. 4.16 kw Emergency i m Bus Undervoltage -

} (Loss of Voltage) -

1. Emergency Bus

2-1E and 2-2E 2/ Bus 2/8ss !

s, 2/Ses 1 S R L N

2. Emergency Bus

! J,

2-3E and 2-4E 2/ Bus 1/8vs 2/8us 2 S NA i NA ACTION 1 -

With the number of OPERA 8tE channels one less than the Total Number of 4Channels, hours. place the inoperable channel in the tripped condition within 1

l ACTION 2 -

None except as provided in Specific.tfon 3.0.3.

FUNCTIONAL UNIT ENGINEERED SAFETV FEATURE ACTUATION SYSTEMS INSTRUDENTATION TRIP SETPOINT

1. ALLOWASLE VALUES 4 LOSS OF POWER l .n .

{ K a. 4.16 kJ Emergency Sus I i g Undervoltage (toss of Voltage)

! E

1. Emergency Bus #2-1E and 2-2E 2278 1 69 volts with a 2278 1 114 volts with a U 1.5 i .15 second time delay 1.5 1 0.2 second time delay

l

2. Emergency Bus #2-3E

! and 2-4E 2278 1 69 volts with a 2278 1 114 volts with a I 1.5 i .15 second time delay 1.5 1 0.2 second time delay i

~

1 y ..

= _ TABLE 4.3-3 E .

E RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMFNTS i E "u,

CHANNEL MINIMUM E CHANNEL CHANNEL FUNCTIONAL i 5 FUNCTIONAL UNIT CHECK CALIBRATION TEST CHANNELS OPERABLE

! . APPLICA8ILITY ACTION i

e 1. CONTAINMENT I

I 5

a. Reactor Building Purge Sampler (AMS-3) O SA W 1.

! Note 1 Note 3

b. Reactor Building Equipment Doors (AMS-3) D SA W 1 Note 10 Note 7

. c. Deleted

d. CACE Vent Monitor D SA W 1 Note 1 Note 9

2. FUEL HANDLING BUILDING l

EXHAUST MONITORS j ,,

(HPR-221A or HPR-2218)

a. Gaseous Activity S R M 1 Note 5 Note 6 4

b. Particulate Activity S R M 1 Note 5 Note 6

o v 3. SOS MONITORS l

E. 4 y lit a. Process Monitor (IX04) S R M 1 Note 1 Note 4 f *& b. Area Monitor (IXO3) S SA M 1 Note 1 Note 2 E. 4. Deleted l (See following pages for notes) t i

I TA8LE 4.3-3 (Cont'd)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

, i CHANNEL CHANNEL CHANNEL FUNCTIONAL CHANNELS FUNCTIONAL UNIT CHECK CALIBRATION TEST OPERABLE APPLICABILITY ACTION

5. FUEL TRANSFER CANAL

a. Criticality Monitor S R M Note 11 Note 12 l 1 j 6. FUEL POOL "A" i

a. Criticality Monitor S R M 1 Note 11 Note 12

7. FUEL HANDLING BUILDING

TRUCK BAY i

! a. Criticality Monitor S R M 1 Note 11 Note 12 i

I i

f (See following pages for Notes) l THREE MILE ISLAND - UNIT 2 4.3-4a R0PCR NO. 30 i

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

! i, .

j g TABLE 4.3-3 (Con't) '

=

E ;

x RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

[ NOTES: '

. E ~1) During operation of the monitored system. ,

5 2) If monitor becomes inoperable, repair or replace by equivalent equipment within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . If not completed

! E j e within status.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months terminate operation of the monitored system and restore the inoperable monitor (s) to operable i

e 3) Restore the inoperable monitor (s) to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

l 5 4) If ion exchange effluent monitor is inoperable, sample on 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months frequency for gross beta. If inoperable j

i

[ longer than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months then terminate operation of ion exchange system and restore the inoperable monitor to operable status.

5) With radioactive waste in the fuel handling building.

) .!

6) With the required instrumentation inoperable, suspend all operations involving movement of radioactive wastes

l in the fuel-handling building, restore the inoperable equipment to OPERA 8LE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . ;

- 7) With the AMS-3 inoperable, close at least one of the Reactor Building Equipment Doors and restore the :

, inoperable equipment:to operable status prior to the reopening'of both Equipment Doors.

a

8) Deleted :

j 9) Two filter trains and associated monitors are normally available. -I' one monitor becomes inoperable, dis-j continue operation through the effected filf.er train and transfer o;>erations by the operable filter train. ;

l If both monitors become inoperable, repair or replace by equivalen'. equipment ~ within twelve (12) hours or '

conduct air sampling using alternate methods on a four (4) hour frequency. If repair or replacement is not ;

completed within seven (7) days, terminate operation of the system until at least one monitor is returned to operable status.

{

! 10) With both reactor building equipment hatch airlock ooors open simultaneously.

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TABLE 4.3-3 (Con't)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES: (con't)

11) During either of the following operations:

a. Handling of canisters containing core material.

b. Handling of any heavy load over canisters containing core materials.

. 12) With less than one channel operable, terminate the following operations:

a. Handling of canisters containing core material. *

b. Handling of any heavy load over canisters containing core material.

This shall not prohibit placing a canister in transit in a safe storage location. ,

THREE MILE ISLAND - UNIT 2 4.3-Sa R0PCR NO. 30

TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIRE Deleted l

. I)

THREE MILE ISLAND - UNIT 2 4.3-6 ,

Change No. 22

- - . ,en,-ne.---,- - . . .. - - - - -. - - , -,-.-.v,,,,... ..e,_ , - - - , , -- - - . -~ , - -- , - - - , - , -,,,_,-,,-w-------

.l SURVEILLANCE REQUIREMENTS METEOROLOGICAL INSTRUMENTATION 4.3.3.4 i

be demonstrated OPERA 8LE by the perfomance of t CALIBRATION operations at the frequencies shown in Table 4.3-5. -

_ESSENTIALPARAMETERSMONITORINGINSTRUMENTATkON 4.3.3.5 Each of the Essential Parameters Monitoring Instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CH CALIBRATION operations at the frequencies shown in Table 4.3-7.

POST-ACCIDENT INSTRUMENTATION 4.3.3.6 Deleted i

CHLORINE DETECTION SYSTEMS 4.3.3.7 performance of a CHANNEL CHECK at least once per 12 FUNCTIONAL TEST at least once per 31 days.

following inspections and maintenance shall be performed:At least once per 18 month a.

Check constant head bottle level and refill as necessary,

b. Clean the sensing cells, c.

Check lines asflow necessary, meter operation and clean or replace filters and air d.

Check air pump for proper operation, and e.

i Verify that the detector ;esponds to HCL.

j THREE MILE ISLAND - UNIT 2 4.3-7 4

Change No. 22

-- - + - - - e --,--w -,-.,.,.,-,,n - - - - ~ .,,,--.,,_a_.,_-,-,_-.,--.__,,-.,--,---,------,~,.-,--.nr--

TABLE 4.3-5 METEOROLOC *AL MONITORING INSTRUMENTATION SURVEILLANCE R ..

MINIMUM CHANNEL INSTRUMENT CHANNEL OPERA 8LE CHECK CALIBRATION

1. WIND SPEED

a. Nominal Elev. 100 ft 1 D SA

2. WIND DIRECTION

. a. Nominal Elev. 100 ft. 1 D SA

3. AIR TEMPERATURE - DELTA T

a. Nominal Elev. 33 ft. 1 D SA

b. Nominal Elev. 150 ft. I D SA THREE MILE ISLAND - UNIT 2 4.3 8 Change No. 22 l

- - _ v . - . _ _. - - . , , - _ - __m- . _ r-- _ _ - - , _ . _ . , , - - , , - . - - . - . , , . . . , . . _ _ - . - - . - - -

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

_ em . w. .e h 8

. ma . M e

TABLE 4.3-6 l REMOTE SHUTDOWN M0NITORING INSTRUMENTATION S DELETED 1

4 s

e 1

e l

l l

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t J

THREE MILE ISLAND - UNIT 2 4,3.g Change No. 22

TA8tE 4.3-7 g ESSENTIAL PARAETERS NDNITORING INSTRUNENTATION SURVEILLANCE REQUIRENENTS

=

m E

NIMINUN m CNANNEL CHANNEL II}

REA00UT OPERA 8LE g INSTRLMENT CHECK CALIBRATION LOCATION (S) CHANNELS

1. Reactor Building Pressure 5 R Control Room. 2 e 2. Reactor Vessel Water Level SN(2) SA Control Room (2) 2(2)

E 3. Incore Thermocouples S R Control Room or

-4 2

Cable Room

4. Reactor Building Water Level NA SA Control Oldg. 1 Area West

5. Oorated Water Storage Tank Level S R Control Room 1

6. Steam Generator Level NA NA NA 1/ Generator l h 7. Spent Fuel Storage Pool SN(2) SA Control Room (2) 2(2)

"A" Water level or Fuel Handling 81dg

8. Fuel Transfer Canal SN(2) SA Control Room (2) 2(2)

(deep end) Water Level or Reactor 81dg (See following page for notes) n m

.5

.E

b L TABLE 4.3-7 (Cont'd)

3Y

A m

ESSENTIAL-PARAMETERS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

l E Notes: .

11 E Nuclear detectors and all channel components located inside containment may be excluded from CHANNEL l 1) Call 8 RATION.

[ 2) One channel may consist of a visual indication such as a level stand pipe.

i = Seven day surveillance applies to visual indication only. Visual indication readout may be in Q the Reactor Su11 ding, or Fuel Handling Building, or by remote television,

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8

[ .

y .~-

= .

I if i

W 1

E S W

m e-

m MN N

e b o W Z W

Wm

J C EL 80 W r to U W

>=

W J M y M C3 e O

(3 c.

e

S *

>=

O e *M ee E

m W

4

==

W s .:

M 2*.

>=

D

SURVEILLANCE REQUIREMENTS l

FIAE DETECTION '

4.3.3.8.1 Each of the required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. l 4.3.3.8.2 The NFPA Code 71 supervised circuits supervision associated with the detector alarms of each of the required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

l 4.3.3.8.3 The nonsupervised circuits between the local panels in Surveillance Requirements 4.3.3.8.2 and the control room shall be demonstrated OPERABLE at least once per 31 days.

4.3.3.8.4 In lieu of Specification 4.3.3.8.2, fire detection instrument for the Southeast Storage Facility shall have circuitry per procedures approved pursuant to Specification 6.8.2.

J r

~

THREE MILE ISLAND - UNIT 2 4.3 12 Change No. 31

TABLE 4.3-11 flRE DETECTION INSTRUMENTS Required Instruments Alternate Operable Instrument Location Heat Instrument Flame Smoke Heat Flame Smoke

1. Auxiliary Building NA NA 2 NA NA 2

2. Control Building 351' Elevation NA NA 1 NA NA 3 331' Elevation (Control Room) NA NA 1 305', 293', 250' Elevations NA NA NA NA 1 1 NA NA 7

3. Control Building Area NA NA 1 NA NA 3

4. Diesel Generator Building A Diesel NA 1 1 NA B Diesel NA 1 NA 1 1 NA NA 1

5. Fuel Handling Building NA NA 3 NA NA 1

6. Reactor Building NA NA 1 NA RC-P-1A/2A NA 1 NA NA 1 NA RC-P-1B/2B NA 2 NA NA 1 NA NA 2

7. River Water Pump House

NA 1 1 NA NA 2

8. Service Building NA NA 3 NA NA 3

9. Deleted

10. Southeast Areas Storage Facility NA NA 2 NA NA 2 l

l THREE MILE ISLAND - UNIT 2 4.3-13 Change No. 22

, _ , _ _ . , . - - = - . . - * - ~ - * ' ' " ~ " " ' ' ~

~

SURVEILLANCE REQUIREMENTS 4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS 4.4.1 in accordance with procedures approved pursuant to Tec .

4.4.2 REACTOR VESSEL, WATER LEVEL MONITORING 4.4.2 The Reactor Vessel Water Level Monitoring Instrumentation shall be demonstrated OPERABLE as required by Table 4.3-7.

SAFETY VALVES

~~ .

4.4.3 Deleted.

4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM 4.4.9.1.1 Deleted.

4.4.9.1.2 Deleted.

4.4.9.1.3 Deleted.

4.4.9.1.4 The pH of the reactor coolant shall be determined to be greater than or equal to 7.5 and less than 8.4 at least once per 7 days.

4.4.9.1.5 The chloride concentration in the reactor coolant shall be deter-mined to be less than or equal to 5 ppm at least once per 7 days.

i THREE MILE ISLAND - UNIT 2 4.4-1 September 23, 1985 Change No. 29 l

SURVEILLANCE REQUIREMENTS 4.5 COMMUNICATIONS 4.5.1 Verify that communications channels are OPERABLE between the Control Room or the Command Center and personnel in the Reactor Building once e,ach day prior to the initiation of any activities involving CORE ALTERATIONS. Also verify that the additional SOL or SOL limited to fuel handling has OPERABLE communication channels once each day prior to the initiation of any activities I involving core alterations.

W THREE MILE ISLAND - UNIT 2 4.5-1 Change No. 22

SURVEILLANCE REQUIREMENTS 4.6 CONTAINMENT SYSTEMS l 4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY

4. 6.1.1 If required per procedures approved pursuant to Specification 6.8.2, primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying per NRC approved procedures that:

1. All penetrations not required to be open per approved procedures are closed by valves, blind flanges, or deactivated automatic valves secured in their positions.

b. By verifying at least once per 31 days that the Containment Equipment Hatch is closed and sealed.

c. By verifying that each Containment Air Lock is OPERABLE per Specification l 3.6.1.3.

CONTAINMENT AIR LOCKS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a. After each opening, except when the air lock is being used for multiple

- entries, then at least once per 72, hours, by verifying less than or equal to 0.01 L seal leakage when the volume between the door seals is stabilized toapresfureof6.5psig. l

b. At least once per three months by performing a mechanical operability check of each airlock, including a visual inspection of the components and lubrication if necessary.

c. Deleted 4.6.1.3.1 When both equipment hatch personnel airlock doors are opened simultaneously, verify the following conditions:

a. The capability exists to expenditiously close at least one airlock door,

b. The airlock doors and containment purge are configured to restrict the outflow of air in accordance with procedures approved pursuant to Tech Spec 6.8.2.

c. The airlock doors are cycled to ensure mechanical operablif ty within seven days prior to opening both doors.

THREE MILE ISLAND - UNIT 2 4.5-1 Change No. 31

.' "IMENis

I _

4.6. .a The primary contalment internal pressure shall be determined to be 1

(-

withih the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , via the 19straentation listed in Table 4.3-7, except during periods when the containment building is open to the agnosphere.

4.6.1.4.b During periods when the containment building is open to the atmoshpere, methods to ensure airflow into the contaiment building shall be implemented in accordance with procedures approved pursuant to Specification 6.8.2 .

l AIR 1D4PERATURE r; .

4.6.1.5 The primary containment average air temerature shall be the aritPmetical average of the temperatures at the following locations and shall be de termined at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

,' Loca:Aon

a. na nominal Elev. 350' (1 temirature indication)

e. RE . nominal Elev. 330' (1 tegerature indication)

c. RB not.inal Elev. 305' (1 temerature indication)

CONTQRENT PLRGE EXHAUST SYSTD4 .

i.

4.6.3 The Containment Purge Exhaust System sha'll be demonstrated DPERABLE:

a. lAt least once per 31 days during operation by verifying that

' Exhaust System in the normal operatin2 mode meets the following .

. conditions:

,1.

Filter Pressure Drop: The d/p across the combined Hr.PA filters shall not exceed 6 inches water gauge while the system is operating.

l

. D. 'At least once per 18 months by verifying that the ventilation system meets the following conditions: -

1. Visually inspect each filter train and associated components in accordance with Section 5 of ANSI N510-1980, as required by a

'- *tegulatory Position C.5.a of Regulatcry Guide 1.52, Revision 2, .

March 1978. Tne inspection r.nould be performed pric to the 00P .:

test of this section. ~

2. Flow Test: Exhaust flow rate shall be within 18,000 cfm to 27,003 cfm operating band for each filter train with one filter train and one exhaust fan operating. Testing shall be in acccrdance l

with ANSI N510-1980, Sectico 8.3.1, paragraphs 3 and 4

'. '3. D*P Test: Each filter train shall bt itsted in accordance with

-I Section 10 of ANSI N310-1950, as rec irer by Regulatory Position C.5.c' of Regelticry G.ide 1.52, Re dsic7 2, F.srch 1978, t -

NOTE:

Installed system flow instrumentation is adequate for the test described ir. Sectior. 4.6.3.b.3 above.

T4.EE MILE !! LAC - U!iiT I 4.i-1 ~

t v u M- N A

SURVEILLANCE REQUIREMENTS

c. Af ter structural maintenance of the HEPA filter or charcoal adsorber housings, or following fire or chemical release in any ventilation zone communicating with the system by verifying that the ventilation system meets the following conditions: -

1. Filter Pressure Drop: Reverify the filter pressure drop surveillance prescribed in Section 4.6.3.a.1 for the affected filter train (s). .

2. DOP Test: Each affected filter train shall be retested in accordance with Section 4.6.3.b.3. .

3. Visual inspection in accordance with ANSI N510-1980 Section 5.

d. After each complete or partial replacement of a HEPA filter bank by verifying that the ventilation system meets the following condition:

1. DOP Test: Each affected filter train shall be retested in accordance with Section 4.6.3.b.3.

4.6.4 COMBUSTIBLE GAS CONTROL HYOROGEN ANALYZERS 4.6.4.1 Deleted.

HYOROGEN PURGE CLEANUP SYSTEM 4.6.4.3 Deleted bC THREE MILE ISLAND - UNIT 2 4.6-3 Change No. 31

o- ,.

l .

SURVEILLANCE REQUIREMENTS 4.7 PLANT SYSTEMS l 4.7.1 FEEDWATER SYSTEM Deleted.

4.7.2 SECONDARY SERVICES CLOSED COOLING WATER $YSTEM

~

L Deleted. '

4.7.3 CLOSED CYCLE COOLING WATER SYSTEM

, NUCLEAR SERVICES CLOSED COOLING SYSTEM 4.7.3.1 Deleted.

4 4

i i

s d

THREE MILE -ISLAND - UNIT 2 4.7-1 . September 23. 1985

. s SURVEILLANCE REQUIREMENTS DECAY HEAT CLOSED WATER SYSTEM 4.7.3.2 Deleted.

MINI DECAY HEAT REMOVAL SYSTEM (M0 HRS) 4.7.3.3 Deleted. ,

1 I

1 .

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THREE MILE ISLAle - UNIT 2 -

4.7-2 . September 23. I M5

SURVEILLANCE REQUIREMENTS 1

4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM i

i 4.7.4.1 Each Nuclear Service River Water Loop shall be demonstrated OPERABLE:

l l

a. At least once per 31 days by:

1. Verifying that each pump starts and operates (unless already oper-ating) for at least 15 minutes and, that during pump operation each pump develops a differential pressure of at least 23.8 psid.

2. Verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed or otherwise secured in position, is in its correct position.

b. At least once per 92 days by cycling each testable valve in the flow path through at least one complete cycle of full travel.

4.7.6 FLOOD PROTECTION 4.7.6.1.1 to be within Thethewater limitlevel by: at the Unit 1 intake structure shall be determined

a. Measurement at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the water level is below elevation 301 feet Mean Sea Level USGS datum.

b. Measurement at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the water level is equal to or above elevation 301 feet Mean Sea Level datum.

4.7.6.1.2 The dike surrounding the island and the dike errosion protection shall be:

a.

Inspected at least once per 61ronths and within 31 days after every flood which exceeds 485,000 cfs at the Harrisburg gage. This inspection shall include:

1. Dike slope and notation of any location where slope is steecer than 2:1.

2. Depressions and notation of their size and location.

3. Stone degradation and notation of any areas whcce splitting, spalling or weathering of stone appears excessive.

4. Vegetation and notation of location, quantity, and type.

5. Operability of inside and outside gates of the Southeast Drainage l

Culvert.

l

, THREE MILE ISLAND - UNIT 2 4.7-3 Change No. 22 l

t

s 1

SURVEILLANCE REQUIREMENTS l

4.7.6.1.3 A Special Report shall be prepared and submitted to the Commission within 30 days if evidence of degradation is noted during an inspection. This 4

. report shall describe the extent and nature of the degradation and the plans l and schedule for restoring the dike and errosion protection to a status equiva-1ent to the original design provisions.

4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM i 4.7.7.1 The Control Room Emergency Air cleanup System shall be demonstrated OPERABLE:

1

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is less than or equal to 200*F.

b. At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbars and verifying that the system operates for at least 15 minutes; and the pressure drop across .

! the combined HEPA filters and charcoal adsorbers banks is less than six (6) inches water gauge while operating.

t

c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

1. Verifying that the cleanup system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory

Positions C.5.a. C.5.c" and C,5.d* of Regulatory Guide 1.52, l Revision 2, March 1978, and the system flow rate is 14,350 cfm i

i 105.

2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with 1 Regulatory Guide 1.52 Revision 2 March 1978, when performing Methyl

, Iodide, 30*C, 95% RH testing per Table 5-1 of ANSI N509-1980 meets an acceptable criteria of H penetration saximum.

j

! 3. Verifying a system flow rate of 14,350 cfm + IDE during system operation when tested in accordance with ANT! N510-1980, Section 8.3.1 Paragraphs 3 and 4.

i i

d. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, when performing Methyl l Iodide, 30*C, 955 RH testing per Table 5-1 of ANSI N509-1980 meets an acceptance criteria of 5% penetration maximum.

l *The prerequisites of Section 10.3 and 12.3 of ANSI-N510-1980 do not apply.

i .

0 1

THREE MILE 15 LAND --UNIT 2 4.7-4 Change No. 31 ,

I I

-~-~. eve, -mme-w,,, ,.-n,. m,n,-,--_-,a . .~. . , , , . - _ ,

SURVEILLANCE REQUIREMENTS CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM (Continued) e.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filter and charcoal adsorber banks is less than 6 inches water gauge while operating the systes at a flow rate of 14,350 cfm + 105.

2.

Verifying that on a control room air inlet radiation test signal or chlorine detection test signal, the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

3.

Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/10 inch wat-e gauge relative to the outside atmosphere during system operation.

f.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to N510-1980*of the DOP when they are tested in place in accordance with ANSI 99.95%

cfm + 10%. Section 10 while operating the system at a flow rate of 14,350 g.

After each complete or partial replacement of a charcoal adsorser bank 99.95% of a halogenated hydrocarbon refrigerant te tested in place in accordance with ANSI N510-1980,*

operating the system at a flow rate, of 14,350 cfm 2101.Section 12, while I

1

The prerequisites of Section 10.3 and 12.3 of AN5!-510-1980 do no apply.

THREE MILE ISLANO - UNIT 2 4.7-5 Change No. 15

SURVEILLANCE REQUIREMENTS 4.7.9 SEALED SOURCES 4.7.9.1 and/or contamination by: Test Requirements - Each sealed source shall be t

a. The licensee, or b.

Other persons specifically authorized by the Commission or an Agreement State.

Thetest per testsample.

method shall have a detection sensitivity of at least 0.005 microcuries 4.7.9.2 Test Frecuencies -

the frequency described below.Each category of sealed sources shall be tested at a.

Source in use (excluding startup sources and fission detectors previously subjected to containing core flux)material:

radioactive - At least once per six senths for all sealed sources 1.

With a half-life greater than 30 days (excluding Hydrogen 3) and

2. In any form other than gas, b.

Stored sources not in use - Each sealed source and fission detector s be the tested previousprior sf7 to use or transfer to another licensee unless tested within Bonths.

Sealed sources and fission detectors transferred without to being aplaced certificate indicating the last test date shall be tested prior into use.

c.

Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected t

to coresource.

to the flux or installed in the core and following repair or saintenance 4.7.9.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of >0.005 microcuries of removable contamination.

THREE MILE ISLAND - UNIT 2 4.7-6 Change No. 22

~

l

I 'l

, l SURVEILLANCE REQUIREMENTS j l

i 4.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM 4.7.10.1.1 The FIRE SUPPRESSION HATER SYSTEM shall be demonstrated OPE

~

a.

At least once per 7 days by verifying that at least 90,000 gallons of water are in the Altitude Tank, equivalent level in Unit I circulating water fiume and/or equivalent level in the river.

b.

At least once per 31 days on a STAGGERED TEST BASIS by starting each pump and operating it for at least 20 minutes on recirculation flow.

i c.

j At least once per 31 days by verifying tht 'each valve (manual, power operated or automatic) in the flow path is in its correct position. l 4

d. At least once per 12 months by:

1.

Running the full flow of one fire pump through all main header loops as a flush, and i

j 2. Cyc1fng each testable valve in the flow path through at least one j complete cycle of full travel. l

e. At least once per 18 months by performing a system functional test which

! includes slaulated automatic actuation of the system (i.e., pumps start at

, set pressure 1 10 psig), and: ,

, 1. Verifying that each pump develops at least 2500 gpa at a total dynamic

head no more than 10% below that indicated on manufactures curves.

2. Cycling each valve in the flow path that is not testable during l plant operation through at least one complete cycle of full travel, and

3. Verifying that each high pressure pump starts (sequentially) to main-tain the fire suppression water system pressure greater than or equal j to 70 psig.

f. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

}

THREE MILE ISLAND - UNIT 2 4.7 7 Change No. 31

_S_URVEILLANCE REQUIREMENTS

_ FIRE SUPPRESSION WATER SYSTEM (Continued) 4.7.10.1.2 Each fire pump diesel engine shall be demonstrated OPERA 8LE:

a.

At least once per 31 days by verifying; 1.

Its and associated fuel storage tank contains at least 250 gallons of fue 2.

The 20 diesel s' tarts from ambient conditions and operates for at least minutes.

t b.

At least once per 92 days by verifying that a sample of diesel fuel from each fuel storage tank, obtained in accordance with ASTM-D270-65 , is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

c.

At least once per 18 months, by:

1.

Subjecting each diesel to an inspection in accordance with procedures prepared the class in ofconjunction service, and with its manufacturer's recommendations for 2.

Verifying each diesel starts from ambient conditions on the auto-start signal and loaded withoperates the fire pump. for greater than or equal to 20 minutes while 4.7.10.1.3 demonstrated OPERABLE:Each fire pump diesel starting battery bank and charger shall a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each battery is above the plates, and 2.

The overall battery voltage is greater than or equal to 24 volts.

b.

At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery, c.

At least once per 18 months by verifying that:

1.

The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and

2. i The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material, i

I P

THREE MILE ISLAND - UNIT 2 4.7-8 Change No. 22 l

SURVEILLANCE REQUIREMENTS DELUGE / SPRINKLER SYSTEMS 4.7.10.2 Each of the required deluge and/or sprinkler systems shall be demonstrated OPERABLE:

a. Atleastonceper12monthsbycyclingeachtestablevalvehntheflow path through at least one complete cycle of full travel. [

b. At least once per 18 months:

1. By performing a system functional test which includes trippir.g

' l detectors and verifying actuation of trip devices on associated deluge valves. Deluge / sprinkler valves shall be inspected internally to verify operability in all instances where header flooding during

, the test is not practical.

2. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel. l

3. By visual inspection of the deluge headers to verify their integrity. l

4. By visual inspection of each nozzle to verify no blockage. g

c. At least one per 3 years by performing an air or gas flow test through i each deluge header and verifying each deluge nozzle is unobstructed.

HALON SYSTEM -

4.7.10.3.1 The Cable Room and Transformer Room Halon system shall be demon-strated OPERABLE at least once per 6 months by verifying each Halon storage tank weight and pressure.

4.7.10.3.2 The Air Intake Tunnel Halon System shall be demonstrated OPERABLE:

a. At least once per 6 months by verifying pressure in each halon storage tank, and

b. At least once per 18 months by verifying storage tank weight.

4 i THREE MILE ISLAND - UNIT 2 4.7-9 Change No. 31 l ,

SURVEILLANCE REQUIREMENTS FIRE HOSE STATIONS 4.7.10.4 Each fire hose station listed in Table 4.7-1 shall be verified OPERABLE: l

a. At least once per 31 days ~by visual inspection of the station to assure all required equipment is.at the station.

b. At least once per 18 months by:

1. Removing the hose for inspection and re-racking, and

- 2. Replacement of all degraded gaskets in couplings.

c. At least once per 3 years by:

1. Partially opening each hose station valve to verify valve OPERASILITY

! and no flow blockage. 1

2. Conducting a hose hydrostatic test at a pressure at least 50 psig i greater than the maximum pressure available at that hose station.

PENETRATION FIRE BARRIERS 4.7.11 The required (accessible per occupational exposure considerations) penetration fire barriers shall be verified to be functional:

a. At least once per 18 months by a visual inspection,

b. Prior to returning a penetration fire barrier to functional status following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

)

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THREE MILE ISLANO - UNIT 2 4.7-10 Change No. 31

.. \

TA8LE 4.7-1 FIRE HOSE STATIONS Auxiliary Building 1.

Fire hose Cooling nearTank, Surge stairway 328' at South end of building near Decay Heat Closed elevation.

2.

3. Fire hose near entrance to Chemical Addition area, 328' elevation.

4. Fire hose near Miscellenceous Waste Holdup Tank room, 305' elevation.

5. Fire hose near Intermediate Closed Coolers 305' elevation.

6. Fire hose near Evaporator Condensate Test Tank Room, 280' elevation.

Fire hose near Reactor Building Emergency Cooling Booster Pumps, 280' elevation.

_ Control Building Area 1.

2. Fire hose near 480 Volt Bus 2-34 282'6" elevation.

Fire hose near entrance to Service Building 282'6" elevation.

Reactor Buildina*

1. Deleted.

2. Deleted.

3.

4.

Fire hose near West stairway, 305' elevation.

5. Fire hose near Southwest stairway, 305' elevation.

6.

Fire hose on East 0 ring, 367' elevation.

Fire hose on West D ring, 367' elevation.

Control Building 1.

Fire hose near doorway on North wall, 305' elevation.

Fuel Hand Building

1. Fire hose on East wall, 347'6" elevation.

" Fire hose stations in the Reactor Building shall be OPERABLE prior to initiating operations which generate combustible materials, and prior to initiatinggrinding, buring, operations etc. which involve the use of.open flames, welding, THREE MILE ISLAND - UNIT 2 4.7-11 Change No. 22

SURVEILLANCE REQUIREMENTS 4.8 ELECTRICAL POWER SYSTEMS 4.8.2 A.C. SOURCES 4.8.1.1.1 Each of the required independent circuits between the offsite trans-mission network and the onsite Class 1E distribution system shall be determined OPERA 8LE at least once per 7 days by verifying correct breaker alignments and indicated power availablity.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERA 8LE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1. Verifying the fuel level in the day fuel tank.

2. Verifying the fuel level in the fuel storage system.

3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4. Verifying the Class IE diesels start from ambient condition and accelerate to at least 900 rpm (ie 60 Hz on the generator) in less than or equal to 10 seconds.

5.

Verifying each Class IE diesel generator is synchronized; loaded to greater than or equal to 3000 kw, and operates for greater than or equal to 60 minutes.

6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b.

At least once per 92 days by verifying that a sample of diesel fuel obtained in accordance with ASTM D270-63, from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

4. 8.1.1. 3 Deleted.

THREE MILE ISLAND - UNIT 2 4.8-1 Change No. 22 l 1

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SURVEILLANCE REQUIREMENTS A.C. SOURCES (Continued) 4.8.1.1.4 Deleted.

4.8.2 DNSITE POWER DISTRIBUTION SYSTEMS A. C. DISTRIBUTION 4.8.2.1 The specified A.C. busses shall be determined OPERA 8LE with tie breakers open between redundant busses at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4160 volt Emergency Bus # 2-1E and 2-3E 4160 volt Emergency Bus # 2-2E and 2-4E 4160 volt Busses # 2-3 and 2-4 480 volt Emergency Bus #2-11E, 2-12E and 2-31E 480 volt Emergency Bus # 2-21E, 2-22E and 2-41E 480 voit Busses # 2-32, 2-35, 2-36, 2-42, 2-45, and 2-46 120 volt A.C. Vital Bus # 2-IV 120 volt A.C. Vital Bus # 2-2V 120 volt A.C. Vital Bus # 2-3V 120 volt A.C. Vital Bus # 2-4V 1

0.C. DISTRIBUTION 4.8.2.2.1 Each D.C. bus train shall be determined OPERA 8LE and energl2ed with tie breakers open at least once per 7 days by verifying correct breaker align-ment and indicated power availability.

4.8.2.3.2 Each 250/125-volt battery bank and charger shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

1.

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks.

2.

The pilot cell specific gravity, corrected to 77'F and full electrolyte level, is greater than or equal to 1.20.

3.

The pilot cell voltage is greater than or equal to 2.13 volts.

4.

The overall battery voltage is greater than or equal to 250/125 volts. -

THREE MILE ISLAND - UNIT 2 4.8-2 Change No. 22

SURVEILLANCE REQUIREMENTS 0.C. DISTRIBUTION (Continued)

b. At least once per 92 days by verifying that:

1. The voltage of each connected cell is greater than or equal to 2.13 volts under float charge and has not decreased more than 0.10 volts from the value observed during the original acceptance test.

2. The specific gravity, correct to 77'F and full electrolyte level, of each connected cell is greater than or equal to 1.20 and has not decreased more than 0.01 from the value observed during the previous test.

3. The electrolyte level of each connected cell is between the minimum and maximum level indication marks.

c. At least once per 18 months by verifying that:

1. The cells, cell plates and battery racks show no visual indication of physical damage or deterioration.

7. The cell-to-cell and terminal connections are clean, tight and coated with anti-corrosion material.

THREE MILE ISLAND - UNIT 2 4.8-3 Change No. 22 !

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t SURVEILLANCE REQUIREMENTS l

' 4.9 LIQUID RADWASTE STORAGE SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING 4.9.1 The Spent Fuel Storage Pool "A" water level monitoring instrumentation shall be demonstrated OPERABLE as required by Table 4.3-7.

4.9.2 Verify that surveillance of Spent Fuel Storage Pool "A" water level is being performed in accordance with NRC approved procedures.

FUEL TRANSFER CANAL WATER LEVEL MONITORING 4.9.3 The Fuel Transfer Canal (deep end) water level monitoring instrumentation shall be demonstrated OPERA 8LE as required by Table 4.3-7.

i 4.9.4 Verify that surveillance of the Fuel Transfer Canal (deep end) water level is being performed in accordance with NRC approved procedures.

FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANVP SYSTEMS 4.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be demonstrated OPERABLE:

A.

At least once per 31 days by verifying that the Air Cleanup Exhaust Systis in the normal operating mode meets the following conditions:

1.

Exhaust Flow Rate: . With two filter trains and two exhaust fans in operation in the Fuel Handling Building flow rate shall be within the 36,000 cfm to 54,000 cfm operating band.

2. . Filter. Pressure Drop: While operating within the flow rate speci-fled in 4.9.12.1. A.1 above, the d/p across the combined HEPA filters and charcoal adsorbers shall not exceed 6 inches water gauge.

3. Fuel Handling Building Pressure: Demonstrate that the system is capable of achieving a negative pressure within the building equal to or greater (more negative) than 1/8 inch water gauge with respect to atmospheric. It may be necessary to close doors and other build-Ing openings to achieve the required value.

With the fuel transfer tubes open and the Fuel Pool not flooded in accordance with NRC approved procedures, the FH8 exhaust flowrate shall be maintained between 26,000 cfm and 54,000 cfm. This condition applies only during system operation (not during system surveillance testing) performed to the criteria

.. of Tech Spec 4.9.12.1. A.

/

THREE MILE ISLANO - UNIT 2 4.9-1 Change No. 27

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SURVEILLANCE REQUIREMENTS B. At least once per 18 months by verifying that the ventilation system meets the following conditions:

1. Visually inspect each filter train and associated components in accordance with Section 5 of ANSI N510-1980, as required by Regulatory Position C.S.a of Regulatory Guide 1.52, Revision 2, March 1978. The inspection should be performed prior to the flow and 00P tests of this section.

2. Flow Test: Exhaust flow rate shall be within 18,000 cfm to 27,000 cfm operating band for each filter train with one filter train and one exhaust fan operating. Testing shall be in accor-dance with ANSI N510-1980,'Section 8.3.1, Paragiaphs 3 and 4.

3. 00P Test: Each filter train shall be tested in accordance with Section 10 of ANSI N510-1980, as required by Regulatory Position C.S.c of Regulatory Guide 1.52, Revision 2, March 1978. Flow through the filter train being tested shall be as prescribed for the flow test in Section 4.9.12.1.b.2 above.

NOTE: Installed system flow instrumentation is adequate for the test described in 4.9.12.1.b.3 above.

)

THREE MILE ISLAND - UNIT 2 4.9-la Change No. 27 1

SURVEILLANCE REQUIREMENTS

4. Fuel Handling Building Pressure: Demonstrate that the system is capable of achieving a negative pressure within the building equal to atmospheric.

to or greater (more negative) than 1/8 inch water gauge with respect It may be necessary to close doors and other build- ,

i ing openings to achieve the required value. A test instrument, such as an inclined mance of this test. nanometer or equivalent, shall be used in the perfor-

c. I Af ter structural maintenance of the HEPA filter or charcoal adsorber I housings, or following fire or chemical release in any ventilation Zone communicating meets the following withconditions:

the system by verifying that the ventilation system ,

i 1

1. Flow Test: Reverify exhaust flow rate for the affected filter train (s) per Section 4.9.12.1.b.2.

2. Filter Pressure Drop: Reverify the filter pressure drop surveil-lance prescribed in Section 4.9.12.1.a.2 for the affected filter train (s)

3. D0P Test:

with SectionEach affected filter train shall be retested in accordance 4.9.12.2.b.3.

d.

After nach complete or partial replacement of a HEPA filter bank by verify-ing that the ventilation system meets the following conditions:

1. DOP Test:

with SectionEach affected filter *train shall be ratested in accordance 4.9.12.1.b.3.

NOTE:

Supply fans may be opeisted as desired except that the number of opere-ting supply fans shall not exceed the number of operating exhaust farb.

4.9.12.2 The Auxiliary Butiding Air Cleanup Exhaust System shall be demon-strated CPERABLE:

a.

At least once per 31 days by verifying that the air cleanup exhaust system in the normal operating mode meets the following conditions:

1.

Exhaust Flow Rate: With two filter trains and two exhaust fans in operation in the Auxiliary building flow rate shall be within the L4,000 cfm to 80,000 cfm operating band.

2.

Filter Pressure Drop: While operating within the flow rate specified in 4.9.12.2.a.1 above, the d/p across the combined HEPA filters and charcoal adsorbers shall not exceed 6 inches water gauge.

THREE MILE ISLAND - UNIT 2 4.9-2 Change No. 15

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SURVEILLANCE REQUIREMENTS J

3. Auxiliary Building Pressure: Demonstrate that the system is capable of achieving negative pressure within the building equal to or greater (more negative) than 1/8 inch water gauge with respect to atmospheric.

It may be necessary to close doors and other building openings to achieve the required value.

b.

At least once per 18 months by verifying that the ventilation system meets the following conditions:

1.

Visually inspect each filter train and associated components in accordance with Section 5 of ANSI N510-1980, as required by Regulatory Position C.5.a of Regulatory Guide 1.52 Revision 2, '

l March 1976. The inspection should be performed prior to the flow and DOP tests of this section.

2. Flow Test: Exhaust flow rate shall be within 27,000 cfm to 40,000 cfm operating band for each filter train with one filter train and l one exhaust fan operating. Testing shall be in accordance with ANSI N510-1990, Section 8.3.1, Paragraphs 3 and 4.

3.

DOP Test: Each filter train shall be tested in accordance with

Section 10 of ANSI N510-1980, as required by Regulatory Position C.5.c of Regulatory Guide 1.52, Revision 2. March 1978. Flow

' through the filter train being tested shall be as prescribed for

, the flew test in Section 4.9.12.2.b.2 above.

NOTE:

Installed system flow instrumentation is adequate for the test described in 4.9.12.2.b.3. above.

4. Auxiliary Building Pressure: Demonstrate that the system is capable of achieving a negative pressure within the building equal to or greater (more negative) than 1/8 inch water gauge with respect to atmospheric.

It may be necessary to close doors and other butiding openings to achieve the required value. A test instrument, such as an inclined manometer or equivalent, shall be used in the performance of this test.

c.

After structural maintenance of the HEPA filter or charcoal adsorber housing, or following fire or chemical release in any ventilation zone I communicating with the system by verifying that the ventilation system meets the following conditions:

1. Flow Test: Reverify exhaust flow rate for the affected filter train (s) per Section 4.9.12.2.b.2.

2. Filter Pressure Drop: Reverify the filter pressure drop surveil-lance prescribed in Section 4.9.12.2.a.2 for the affected filter i

train (s).

THREE MILE ISLANO - UNIT 2 4.9-3 Change No. 15

1

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SURVEILLANCE REQUIREMENTS

)

3. 00P Test: :

Each affected filter train shall be retested in accord-ance with Section 4.9.12.2.b.3.

d.

After each complete or partial replacement of a HEPA filter bank by verifying that the ventilation systaa meets the following conditions:

1. DOP Test:

Each affected filter train shall be retested in accordance with Section 4.9.12.2.b.3.

NOTE:

Supply fans may be operated as desired except that the number of operating exhaust fans.

supply fans shall not exceed the number of operating i

/

THREE MILE ISLAND - UNIT 2 4.9-4 Change No. 15

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b SECTION 5.0 DESIGN FEATURES O

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5.0 DESIGN FEATURES '

4 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area is shown on Figure.5.1-1.

LOW POPULATION ZONE 5.1.2 -The low population zone is shown on Figure 5.1-2.

SITE B0UNDARY FOR GASEOUS EFFLUENTS '

5.1.3 - The site boundary for gaseous effluents shall be as shown in Figure 5.1-3.

SITE B0UNDARY FOR LIQUID EFFLUENTS 5.1. 4 The site boundary for liquid effluents shall be as shown in Figure 5.1-4.

. 5.2 CONTAINNENT i

CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:

a. Nominal.inside diameter = 130 feet.

b. Nominal inside-height = 157 feet.

c. Minimum thickness of concrete walls = 4 feet,

d. Minimum thickness of concrete roof = 3.5 feet.

e. Minimum thickness of concrete floor pad = 13.5 feet.

, f.

Nominal thickness of steel liner = 1/2 inches.

g. Net free volume = 2.1 x 105 cubic feet.

DESIGN PRESSURE AND TEMPERATURE 5.2.2 .The reactor containment building is designed and shall be maintained for a maximum internal pressure of 2 psig and a temperature of 286*F. g THREE MILE ISLAND - UNIT 2 5-1 January 7.1935 ,

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DESIGN FEATURES 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 Deleted VOLUME 5.4.2 12,180 1The 200total water and steam volume of the reactor coolant system is cubic feet at a nominal T,,, of 525'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be' located as shown on Figure 5.5-1.

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SECTION 6.0 ADMINISTRATIVE CONTROLS e

- - v, - , - - - - - - - , ,,, , , , , ,- -, - - - . . . - - , -, -m-, --.-- -

6.0 ADMINSTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 Deputy Director-TMI-2 and shall be responsible for overa shallabsences.

their delegate in writing the succession to this responsibility during both of.

, _6. 2 ORGANIZATION GPUNC ORGANIZATION 6.2.1 and Plan. technical support shall be as shown on Figure 1-1 of t prior to implementation.The Organization Plan and changes thereto shall be appro TM,I-2 ORGANIZATION 6.2.2

. Plan an.The d: unit organization shall be shown on Figure 1-2 of the Organization a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

At least one licensed Operator shall be in the control room when

. fuel is in the reactor.

c.

An individual qualified in radiation protection procedures shall be on site when fuel is in the retctor.

d.

A at Site all times.Fire Brigade of at least 5 members shall be maintained onsite The Site Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

i e.

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

.l :

4 ,

THREE MILE ISLAND - UNIT 2 6-1 November 1,1983

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ADMINISTRATIVE CONTROLS Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

LICENSE RECOVERY MODE CATEGORY SOL la !

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 50L or an 50L limited to fuel handling will be stationed on the operating floor, in the ccamand center, or in the control room as specified in procedures approved pursuant to specification 6.8.2 to directly control the particular CORE ALTERATION activity being performed.

1 THREE MILE ISLAND - UNIT 2 6-2 July 17, 1984 w p,-,- -- w ,_ . ,- - ,,n. - .-...-._.--w ,_, , - ---,-,-

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

6.3.2 The Radiological Controls Director TMI-2 or his deputy shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. Each Radiological Controls Technician in responsible positions / Foreman shall meet or exceed the qualifications of ANSI 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved THI-2 Radiation Controls training program. Individuals who do not meet ANSI 18.1-1971 Section 4.5.2 are not considered technicians for purposes of determining qualifications but are-permitted to perform work for which qualification has been demonstrated. All Radiological Controls Technicians will be qualified through training and examination in each area or specific task related to their radiological con-trols 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 exc'eed the requirements and recommendations of Regulatory Guide 1.8 of 1977 and Appendix "A" of 10 CFR Part 55 except that Radiological Controls training may be under the direction of Vice President-Radiological and Environmental Controls.

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

6.5 REVIEW AND AUDIT 6.5.1- Technical Review and Control The Office of THI-2 Division Director and Support Division Vice-Presidents within GPU Nuclear Coporation as indicated in Organization Plan Figure 1.1, shall be responsible for ensuring the preparation, review, and approval of documents required by the activities within their functional area of respon- ,

sibility for TMI-2. Implementing approvals shall be performed at the cogni-zant section manager / director level or above. Independent safety review and audit shall be conducted in accordance with this Technical Specification.

Divisions other than the TMI-2 Division will perform the Independent Safety Review of their own procedures affecting TMI-2 in accordance with approved procedures except when they impact the operational status of unit systems or

~

equipment (requires TMI-2 Division concurrence), a significant environmental impact (requires in line SRG and Environmental Licensing review), er represent 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

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ADMINISTRATIVE CONTROLS ACTIVITIES 6.5.1.1 Each procedure required by Technical Specification 6.8 and other procedures including those for test and experiments and changes thereto shall be prepared by a designated individual (s)/ group knowledgeable in the area affected by the procedure. Each such procedure, and changes thereto, shall be given a technical review by an individuals (s)/ group other than the preparer, '

but who say be from the same organization as the individual who prepared the procedure or change.

6.5.1.2 Proposed changes to the Technical Specifications shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/' group who prepared the change, and the SRG.

1

' 6.5.1.3 Proposed modifications to unit structures, systems ~and components shall be designed by an individual / organization knowledgeable in the areas affected by the proposed modification. Each such modification shall be technically reviewed by an individual / group other than the individual / group which designed the modification but may be from the same group as the individual who 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 say be from the same division as the individual who prepared the tests and experiments.

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

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

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

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

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

THREE MILE ISLAND - UNIT 2 6-4 November 1, 1983

ADMINISTRATIVE CONTROLS i

RECORDS '

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

QUALIFICATIONS 6.5.1.11 Responsibile Technical Reviewers shall meet or exceed the qualifica-tions of ANSI /ANS-3.1 - 1978 Section 4.4 for Reactor Engineering, Instrumenta-tion and Control, Chemistry and Radiochemistry, Radiation Protection and Quality Assurance Reviewers or have seven (7) years of appropriate experience

' in the area of their specialty. All other RTRs shall meet Section 4.6, i.e. ,

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

6.5.2 INDEPENDENT SAFETY REVIEW FUNCTION 6.5.2.1 The Office of TMI-2 Division Director and Support Division Vice Presidents within GPU Nuclear Corporation as indicated in Organization Plan Figure 1.1 shall be responsible for ensuring the Indep=ndent 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 w*ill perform the Independent Safety

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

When the Preparer determines a procedure is not Review Significant, the

{.

signature of the RTR indicates concurrence with this determination.

i 6.5.2.2 Independent safety review shall be completed by an individual / group i

j not having direct responsibility for the performance of the activities under review, but who may be from the same functionally cognizant organization as the individual / group performing the original work. For those TMI-2 Division documents determined to be Review Significant, the-Independent Safety Review shall be performed by or under the cognizance of SRG.

I THREE MILE ISLAND - UNIT 2 6-5 November 1,1983

\

d

._,____,._._,m__.,._____._,.__,__..,,_....,__m._. . . _ . . . . _ . _ _ . , , . _ _ _ . _ _ . , _ _ . _ , _ . , . . _ , _ _ , _ _ . - _ .

4 ADMINISTRATIVE CONTROLS 6.5.2.3 GPU Nuclear Corporation shall collectively have~ or have 4ccess to the experience and competence required to independently review subjects in the 3 following areas:

a. Nuclear Unit operations

b. Nuclear engineering l

c. Chemistry and radiocntnistry

d. Metallurer,,

e. Instrumentation and control

f. Radiological safety

g. Mechanical engineering

h. Electrical engineering 3,

i.

j. Administrative controls and quality assurance practices k.

Emergency plans and related organization, procedures and equipment Other appropriate fields such as radioactive waste operation associated with the unique characteristics of TMI-2.

6.5.2.4 Consultants may be utilized to provided expert advice.

, RESPONSIBILITIES 6.5.2.5 The following subjects shall be independently reviewed:

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

~ in the Safety Analysis Report Technical Evaluation Reports, or docketed System Descriptions,,and tests or experiments not described 1 in the Safety Analysis Report, Technical Evaluation Reports, or docketed System Descriptions, which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1). This review of items determined not to be Review Significant when performed by SRG is a supplemental review to verify that such changes, tests or experiments did not involve a change in the Technical Specifications or an Unreviewed Safety Question.

b. Proposed changes in procedures, proposed changes to the facility, or proposed tests or experiments, any of which involves a change in the Technical Specifications or an Unreviewed Safety Question shall be reviewed by SRG prior to implementation. Changes to Review Significant procedures which revision is not deemed to be Review Significant shall not be required to be reviewed by SRG prior to implementation.

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

d. Violations, deviations, and reportable events which require either !

one or four hour immediate notification to the NRC. Such reviews i are performed after the fact. Review of events covered under this subsection shall include results of any investigations made and the recommendations THREE MILE ISLAND - UNIT 2 6-6 November 22. 1985

- 0 ADMINISTRATIVE CONTROLS resulting from such investigations to prevent or reduce the proba-bility of recurrence of the event. SRG shall review all one or four hour immediate notifications and make recommendations as appropriate.

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

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

g. Written summaries of audit reports in the area specified in sec-tion 6.5.3.

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

1. 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 TMI-2 Recovery QA Plan. These audits shall encompass:

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

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

c. The verification of the nonconformances and corrective actions pro-gram as related to actions taken to correct deficiencies occurring in unit equipment, structures, systems or methods of operation that affect nuclear safety. The audit frequency shall be at least once per 6 months. l THREE MILE ISLAND - UNIT 2 6-7

P i

4 ADMINISTRATIVE CONTROLS

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

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

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

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

g. The Radiation Protection Plan and implementing procedures. The audit i frequency shall be at least once per 12 months.

h. The Fire Protection Program and implementing procedures. The audit ,

frequency shall be at least once per 24 months.

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

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

k. Any 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 TMI-2, or the Office of the President - GPUNC. any other areas required to be audited by QA will be identified to'the ,

appropriate QA Management level.

RECOR,DS 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 audite'd and SRG within 60 days after completion of the audit. SRG will review specified audits performed by QA and make corrective action recommendations as appropriate.

6.5.4 Safety Review Group (SRG)

FUNCTION 6.5.4.1 The SRG shall be a full-time group of eng's eers, 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 TMI-2 SRG shall consist of the Manager, SRG and a minimum staff of 5 engineers.

. THREE MILE 15LANO - UNIT 2 6-8 November 22. 1985

. ~ . _ . _ _ . . .

1 ADMINISTRATIVE CONTROLS 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 TMI-2.

RESPONSIBILITY h

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

However, he has the authority and responsibility to bring to the attention of the Office of the President GPUNC any issues he believes are not being addressed with adequate consideration of nuclear or radiological safety.

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 TMI-2 deem appropriate for consideration.

6.5.4.5 For those reviews requiring expertise outside that possessed by SRG, SRG is authorized to require reviews by other company groups as deemed appropriate by the Manager, SRG. SRG may also utilize consultant expertise as it deems 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 Office 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 consideration of nuclear or radiological safety.

QUALIFICATIONS 6.5.4.7 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.

5 e

i THREE MILE ISLAND - UNIT 2 6-9 November 1, 1983

^

4 _ -_ _ _ . .. _. .

ADMINISTRATIVE CONTROLS RECORDS ,

6.5.4.8 Although day to day results of evaluations by the SRG are communicated directly to the responsible department by the SRG, special reports are prepared only for items deemed appropriate by SRG as concurred with by the Manager, SRG's 4

immediate supervisor. These special reports of evaluations and assessments by SRG shall be prepared, approved, and then transmitted to the Office of the Director, TMI-2 and the management position responsible for the area reviewed through the Manager, SRG's immediate supervisor. These reports shall be maintained for the life of the operating license.

6.6 REPORTABLE EVENTS ACTION

> 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and/or a report submitted pursuant to the reqJirements 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 TMI-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. Recevery 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.

November 22, 1985 THREE MILE ISLAND - UNIT 2 6-10

,,,,.-,,,.--w-=- $-,,=,- --.,y,- -,, . - , . - ,, ,,-,,,,,-,,,,,,.mm-,- m-y.---. --.. . _ , _ ~ _ , _ _ . ,, , -,-.,ne- .- - ,.-,-,--. . ---, ,

.-..s. . . . . . . . . - . . . . . . . _ . . . . . . .

ADMINISTRATIVE CONTROLS 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 accordar.ce with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.

6.8.2.2 Procedures of 6.8.1.a and changes thereto which:

a. Directly relate to core cooling, or

b. Could cause the magnitude of radiological releases to exceed Itaits established by the NRC, or

c. Could increase the likelihood of failures in systems important to nuclear safety and radioactive waste processing or storage, or,

d. Alter the distribution or processing of significant quantities of stored radioactivity or radioactivity being released through known flow paths.

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

6.8.3.1 Temporary changes to procedures of 6.8.1 may be m;de provided that:

l

a. The intent of the original procedure control is not altered, and

b. (1) For those procedures which affect the operational status of unit systems or equipment, the change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor

~

Operator's License. If one of the two above signatures is not by a supervisory person within the'0epartment having cognizance of the procedure being changed, the signature of that supervisory person within the department will also be required, or (2) For those procedures which do not affect the operational status of unit systems or equipment, the change is approved by two members of the responsible organization. If one of the two above signatures is not by a section manager / director within the Department hav'-

cognizance of the procedure being changed, the signature of tha.

section manager / director within the department will also be required, and

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

d. Those changes to procedures described by 6.8.2.2 are submitted to -

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

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC Region I Administrator unless otherwise noted. l THREE MILE ISLAND - UNIT 2 6-11 November 22, 1985

___....._3 _ _ _ _ _ . . - . . . _. . . . . . -

ADMINISTRATIVE CONTROLS

, ANNUALREPORTd#

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

year.

6.9.1.5 Reports requirsd on an annual basis shall include:

a. A tabulatihn of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 ares /yr and their associated man rem exposure according to work and job functions,I# e.g. , reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In-the aggregate, at least 80% of the total whole body dose received from external sources shall be 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) at i

the Harrisburg International Airport for the previous twelve-month period.

2. The total number of movements of aircraft larger than 200,000 4

pounds, based on a current percentage estimate provided by the airport manager or his designee.

RADIATION SAFETY PROGRAM rep 0RT

6. 9.1. 6 Deleted.

REPORTABLE OCCURRENCES

6. 9.1. 7 Deleted.

I A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

I This tabulation supplements the requirements of K20.407 of.10 CFR Part 20.

THREE MILE ISLAND - UNIT 2 6-12 November 22, 1985

ADMINISTRATIVE CONTROLS PROMPTNOTiFICATIONWITHWRITTENFOLLOWUP

6. 9.1. 8 Deleted.

THIRTY DAY WRITTEN REPORTS 6.9.1.9 Deleted.

I I

THREE MILE ISLAND - UNIT 2 6-13 November 22,1985 1

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS FOR INCIDENT WHICH OCCURRED ON MARCH 28. 1979 6.9.1.10 Section Deleted. All reporting requirements completed.

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

6.10 RECORD RETENTION 1

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.

c. Records of changes made 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.

~

.)

6-14 November 22, 1985 THREE MILE ISLANO - UNIT 2

ADMINISTRATIVE CONTROLS

b. Records and logs of principa'l maintenance activities, inspections, repair and replacement of principal items of equipment telated 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 components

, designed for a limited number cf transients or cycles. ,

1. Records of reactor tests and experiments.

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

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

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

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

q. Records of meetings of the Plant Operation Review Committee (PORC) and the General Review Committee (GRC) and reports of evaluations prepared by the SRG.

i i

THREE MILE ISLAND - UNIT 2 6-15 November 22, 1985 r-w..,.w-. ,. y.9_,. --r_y ,%e,__,, , , . . ______,,_,, ,,,, ,,,._ ,- ._ .,, , ,,,. ._ ,,,, ,g,,,9._,,,,___,,m.m_,,_.,,, _ . , , ., ,_ ,, _.--..y , y.,%--

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4, ADMINISTRATIVE CONTROLS

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

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 Personnel radiation protection shall be consistent with the requirements of 10 CFR Part 20 and the NRC approved Radiation Protection Plan.

[.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.

l l

l

-)

THREE MILE ISLAND - UNIT 2 6-16 Jandary 7.1983

,

ML20137R463

Text

SUBJECT:

Enclosure:

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