Text

Proposed Tech Specs,Incorporating Five of Six Responses to NRC 870925 Comments
	ML20236H576
Person / Time
Site:	Crane
Issue date:	10/26/1987
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20236H565	List: ML20236H562; ML20236H576; ML20236H822;
References
	NUDOCS 8711040211
	Download: ML20236H576 (131)
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THREE MILE ISLAND NUCLEAR EATION UNIT 2

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(r g QV 1 INDEX l c n -- L '> -DEFINITIONS 1 ,o SECTION PAGE i A 'y,,4 I 1.0 DEFINITIONS ,) 4 .T t a 1.1 DEFINED TERMS.................................................... 1-1 1.2 RECOVERY OPERATIONS PLAN......................................... 1-1 i d \\ 4; / 1.3 M00E............................................................. 1-1 l. 1.4 ACTI0N........................................................... 1-1 1.5 OPERABLE - OPERABILITY........................................... 1-1 1.6 REPORTABLE EVENT................................................. 1-1 1.7 CONTAINMENT INTEGRITY............................................ 1-2 1.8 CHANNEL CALIBRATION.............................................. 1-2 1.9 CHANNEL CHECK.................................................... 1-2 1.10 CHANNEL FUNCTIONAL TEST.......................................... 1-3 1.11 STAGGERED TEST BASIS............................................. 1-3 1.12 FREQUENCY N0TATION............................................... 1-3 N 1.13 FIRE SUPPRESSION HATER SYSTEM.................................... 1-3 i s t >t .u,sC 1.14 REVIEW SIGNIFICANCE.............................................. 1-3 ,l 1.15 CORE ALTERATION.................................................. 1-4 j 1.16 LOSS TO AMBIENT.................................................. 1-4 / l.17 ACCIDENT GENERATED HATER......................................... 1-4 ')

t l.18 LICENSED OPERATOR (0L)...........................................

1-4 1.19 SENIOR LICENSED OPERATOR (50L)................................... 1-4 l 1.20 FUEL HANDLING SENIOR LICENSED OPERATOR (S0L-FH).................. 1-4 ii 3 1.21 CONTAINMENT IS0LATION............................................ 1-5 t a r ! Q Y) FACILITY MODE (TABLE 1.1)............................................. 1-6 / FREQUENCY NOTATION (TABLE 1.2).......... 1-7 s I THREE R:LE ISLAND - UNIT 2 I l 022tP l DC i Jb-i_ L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

INDEX j i ADMINISTRATIVE CONTROLS j 1 SECTION PAGE J 2.0~ SAFETY LIMITS................................................... 2-1 1 i i 1 THREE MILE ISLAND - UNIT 2 II 0127P

v. INDEX. I ' LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l SECTION PAGE-i ' 3.0 ~ APPLICABILITY................................................... 3.0-1 3.1 WATER INJECTION COOLING AND REACTIVITY' CONTROL SYSTEMS '3.1.1 BORATION CONTR0L.......................................... 3.1-1 BORATED COOLING WATER INJECTION............................ 3.1-1 BORCN CONCENTRATION - REACTOR COOLANT SYSTEM............... -3.1-2 BORON CONCENTRATION - FUEL TRANSFER CANAL.................. 3.1-3 BORON CONCENTRATION - SPENT FUEL POOL "A".................. 3.1-4 3.3 INSTRUMENTATION 3.3.1 NEUTRON MONITORING INSTRUMENTATION......................... 3.3-1 INTERMEDIATE AND SOURCE RANGE NEUTRON FLUX MONITORS........ 3.3-1 3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION. 3.3-2 3.3.3 MONITORING INSTRUMENTATION................................. 3.3-3 1 RADIATION MONITORING INSTRUMENTATION....................... 3.3-3 METEOROLOGICAL INSTRUMENTATION............................. 3.3-4~ ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION............ 3.3-5 CHLORINE DETECTION SYSTEMS................................. 3.3-6 FIRE DETECTION INSTRUMENTATION............................. 3.3-7 3.4 REACTOR COOLANT SYSTEM J -3.4.1 REACTOR COOLANT L00PS...................................... 3.4-1 ] J 3.4.2 REACTOR VESSEL WATER LEVEL' MONITORING...................... 3.4-2 3.4.9 PRESSURE / TEMPERATURE LIMITS................................ 3.4-3 REACTOR COOLANT SYSTEM..................................... 3.4-3 1 3.5 COMMUNICATIONS I 3.5.1 CONTROL R00M............................................... 3.5-1 i THREE MILE ISLAND - UNIT 2 III l l 0127P

r:- L L INDEX L L l' . LIMITING CONDITIONS FOR OPERATION SECTION PAGE 3.6 CONTAINMENT SYSTEMS 3.6.1 PRIMARY CONTAINMENT........................................ 3.6-1 CONTAINMENT INTEGRITY...................................... 3.6-1 CONTAINMENT IS0LATION...................................... 3.6-4 CONTAINMENT AIR LOCKS (MODE 1)............................. 3.6-5 INTERNAL PRESSURE.......................................... 3.6-6 AIR TEMPERATURE............................................ 3.6-7 CONTAINMENTEAIR LOCKS (M00ES 2 AND 3)...................... 3.6-8 3.6.3 CONTAINMENT PURGE EXHAUST SYSTEM........................... 3.6-9 3.7 PLANT SYSTEMS 3.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM......................... 3.7-1 3.7.6 FLOOD PROTECTION........................................... 3.7-2 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.................. 3.7 3.7.9 SEALED S0URCES............................................. 3.7-5 3.7.10 FIRE SUPPRESSION SYSTEMS................................... 3.7-6 FIRE SUPPRESSION WATER SYSTEM.............................. 3.7-6 DELUGE / SPRINKLER SYSTEMS................................... 3.7-7 HALON SYSTEM............................................... 3.7-8 FIRE HOSE STATIONS......................................... 3.7-9 PENETRATION FIRE BARRIERS.................................. 3.7-10 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 A.C. S0URCES............................................... 3.8-1 3.8.2 DNSITE POWER DISTRIBUTION SYSTEMS.......................... 3.8-4 A.C. DISTRIBUTION.......................................... 3.8-4 0.C. DISTRIBUTION.......................................... 3.8-5 THREE MILE ISLAND - UNIT 2 IV 0127P

[' INDEX LIMITING CONDITIONS FOR OPERATION I SECTION PAGE 3.9 RADIOACTIVE MATERIALS STORAGE j. 3,9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING......... -3.9-1 3.9.2 SPENT FUEL STORAGE POOL "A" WATER LEVEL.................... 3.9-2 i l 3.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITTRING...... 3.9-3 3.9.4 ~ FUEL TRANSFER CANAL (DEEP END) WATER LEVEL................. 3.9-4 l 3.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING.................. 3.9-5 l AIR CLEANUP SYSTEMS i FUEL HANDLING BUILDING AIR CLEANUP SYSTEM.................. 3.9-5 AUXILIARY BUILDING AIR CLEANUP EXHAUST SYSTEM.............. 3.9-5 3.9.13 ACCIDENT GENERATED WATER................................... 3.9-6 3.10 CRANE OPERATIONS 3.10.1 CONTAINMENT BUILDING....................................... 3.10-1 3.10.2 FUEL HANDLING BUILDING..................................... 3.10-2 l l THREE MILE ISLAND - UNIT 2 V 0127P

r' INDEX BASES SECTION PAGE p 3/4.0 APPLICABILITY.............................................. B 3/4.0-1 i .3/4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL. SYSTEMS..... B 3/4.1-1 3/4.1.1 BORATIO4 CONTROL AND BORATED COOLING WATER INJECTION... B 3/4.1-1 ') 3/4.3 INSTRUMENTATION 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION..................... B 3/4.3-1 .3/4.3.2 DELETED......-........................................... B 3/4.3-1 l 3/4.3.3 MONITORING INSTRUMENTATION.............................. G 3/4.3-1 RADIATION MONITORING INSTRUMENTATION............ -....... B 3/4.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION.............. B 3/4.3-1 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION........ B 3/4.3-1 i CHLORINE DETECTION SYSTEMS.............................. B 3/4.3-1 FIRE DETECTION INSTRUMENTATION......................... B 3/4.3-2 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 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 PRESSURE / TEMPERATURE LIMITS............................ B 3/4.4-1 3/4.5 COMMUNICATIONS............................................. 83/4.5-1 3/4.6 CONTAINMENT SYSTEMS ) 3/4.6.1 PRIMARY CONTAINMENT.................................... B 3/4.6-1 CONTAINMENT INTEGRITY.................................. B 3/4.6-1 CONTAINMENT IS0LATION.................................. B 3/4.6-1 CONTAINMENT AIRLOCKS (MODE 1).......................... B 3/4.6-1 INTERNAL PRESSURE...................................... B 3/4.6-1 AIR TEMPERATURE..................... B 3/4.6-1 CONTAINMENT AIRLOCKS (MODES 2 AND 3).................... B 3/4.6-2 3/4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM....................... B 3/4.6-2 1 THREE MILE ISLAND - UNIT 2 VI 0127P

l~ ^i (. INDEX pASES u j 'SECTION PAGE j 1 3/4.7 PLANT SYSTEMS j 3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM..................... B 3/4.7-1. 3/4.7.6 FLOOD PROTECTION....................................... B 3/4.7-1 L l 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP' SYSTEM............. B 3/4.7-1 3/4.7.9 . SEALED SOURCE INTEGRITY................................ B 3/4.7-1 3/4.7.10 FIRE SUPPRESSION SYSTEMS............................... B 3/4.7-1 1 3/4.7.11 PENETRATION FIRE BARRIERS........... B 3/4.7-2 3/4.8 ELECTRICAL' POWER SYSTEMS................................... B 3/4.8-1

3/4._9 RADIOACTIVE WASTE STORAGE 3/4.9.1 SPENT FUEL STORAGE POOL " A" WATER LEVEL MONITORING.....

B 3/4.9-1 3/4.9.2 SPENT FUEL STORAGE POOL "A" WATER LEVEL................ B 3/4.9-1 3/4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL............. B 3/4.9-1 MONITORING 1 3/4.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL............. B 3/4.9-1 3/4.9.12 FUEL HANDLING BUILDING AIR CLEANUP SYSTEM.............. B 3/4.9-1 AUXILIARY BUILOING AIR CLEANUP SYSTEM.................. B 3/4.9-1 3/4.9.13 ACCIDENT GENERATED WATER............................... B 3/4.9-1 3/4.10 CRANE OPERATIONS.......................................,.. B 3/4.10-1 3/4.10.1 CRANE OPERATIONS - CONTAINMENT BUILDING................ B 3/4.10-1 3/4.10.2 CRANE OPERATIONS - FUEL HANDLING BUILDING.............. B 3/4.10-1 l h ] THREE MILE ISLAND - UNIT 2 VII 1 0127P

? I f INDEX t i I-DESIGN FEATURES t l SECTION PAGE 5.1 SITE-t 5.1.1 EXCLUSION AREA.................................... 5-1 5.1.2 LOW POPULATION Z0NE........................................ 5-1 5.1.3 SITE BOUNDARY FOR GASEGUS EFFLUENTS...............,........ 5-1 l 8 5.1.4 SITE BOUNDARY FOR LIQUID EFFLUENTS......................... 5-1 5.2 CONTAINMENT 5.2.1 CONFIGURATION.............................................. 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE............................ 5-1 f 5.4 REACTOR COOLANT SYSTEM t 5.4.1 0ELETED........'........................................... 5-4 5.4.2 V0LUME..................................................... 5-4 5.5 METEOROLOGICAL TOWER LOCATION.................................... 5-4 S l ) .I l I i I ,I 1 l l I THREE MILE ISLAND - UNIT 2 VIII 0127P l l

) INDEX _A_D_MINISTRATIVE CONTROLS 'SECTION PAGE I 6.1 RESPONSIBILITY............ 4............................... 4.... 6-1 6.2 ORGANIZATION 6.2.1 'GPUNC ORGANIZATION......................................... 6-1 6.2.2 TMI-2 ORGANIZATION......................................... 6-1 i s 1 4 6.3 UNIT STAFF-QUALIFICATIONS........................................ 6-3 6.4 T R A IN IN G.......................................................... 6-3 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTR0L............................... 6-5 6.5.1.10 REC 0RDS.................................................... 6-5 6.5.1.11 QUALIFICATIONS............................................. 5-5 6.5.2 INDEPENDENT SAFETY REVIEW.................................. 6-3 6.5.2.1 FUNCTION................................................... 6-5 6.5.2.5 RESP 0NSIBILITIES........................................... 6-6 ] 6.5.2.7 R eC 0Ro S.................................................... 6-7 6.5,3 AUDITS..................................................... 6-7 6.5.3.2 RECORDS............ 4. 6-7 6.5.4 SAFE T / REVIEW GR OUP ( SRG ).................................. 6-8 6.5.4.1 FUNCTION.................................................... 6-8 6.5.4.2 ORGANIZATION.................................... 6-8 6.5.4.3 RESPONSIBILITY............................................ 6-9 6.5.4.6 AUTHOR1TY.................................................. 6-9 6.5.4.7 QUALIFICATIONS............................................. 6-9 6.5.4.8 REC 0RDS.................................................... 6-10 ,6. 6 REPORTABLE EVENTS ACTI0N.......................................... 6-10 l 6.8 PROCEDURES........................................................ 6-10 6.9 REPORTING REQUIREMENTS 1 I 6.9.1 ROUTINE REPORTS TsND REPORTABLE OCCURRENCES................ 6-11 6.9.1.4 ANNUAL REP 0RTS............................................. 6-12 6.9.2 SPECIAL REP 0RTS............................................. 6-14 -6.10 RECORD RETENTION................................................. 6-14 6.11 RADIATION PROTECTION PR0 GRAM.................................... 6-16 1 6.12 HIGH RADIATION AREA............................................. 6-16 i l l THREE MILE ISLAND - UNIT 2 IX t l l 0127P E

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SECTION 1.0 DEFINITIONS

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1 l J.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINE 0 TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications. R_ECOVERY OPERATIONS P.LAN j 1.2 The RECOVERY OPERATIONS PLAN shall define the surveillance requirements to be performed to ensure equipment operability as required by the Limiting 3 Conditions for Operation. This plan, and changes thereto, shall be approved by the Commission prior to implementation. I MODE J 1.3 Tha FACILITY MODE shall correspond to the plant conditions specified in Table 1.1. Prior to the transition to the following Facility Mode, a report J shall be submitted to the NRC no later than 30 days prior to transition which i provides the basis for the transition. ACTION j 1.4 ACTION shall be those additional requirements specified " cerollary statements to each specification and shal? be part of the spech 'Uons. OPERABLE - OPERABILITY 1.5 A system, subsystem, train, component or device shall be OPERABLE or have OPERA 8ILITY when it is capable of performing its specified function (s). Implicit in this definttion shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that j are re:1uired for the system, subs.ystem, 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 S0. j l I l s THREE MILE ISLAND - UNIT 2 1-1 0229P

i 1.0 DEFINITIONS CONTAINMENT INTEGRITY j 1.7 CONTAINMENT INTEGRITY shall exist when: c ( a. All penetrations required to be closed during accident conditions, except { those listed in Table 3.6-2, are either: j 1. Closed by manual valves, blind flanges, or reactivated automatic valves secured in their closed positions on each side of the penetration. Isolation valves inside the Reactor Building shall be capable of remote operation from a control station outside the Reactor Building, or; j 4 2. Closed by double barrier isolation outside the Reactor Building ) when the inside barrier is inaccessible dJe to ALARA considerations j or the penetration has been modified as part of the cleanup effort j (i.e., Mode 1), or; j 3. Open per an approved procedure but are capable of being closed pursuant to either Specification 1.7 a.1 or 1.7.a.2. Controis shall be implemented to minimize the time the penetration is allowed open and to specify the conditions for which the penetration is open. Penetrations will be expeditiously closed upon completion of the condition specified in the approved 3 procedures, j b. The Equipment Hatch is closed and sealed. ) i c. Each airlock is OPERABLE pursuant to Specification 3.6.1.3. d. The sealing mechanism associated with each penetration (e.g., welds, i bellows or 0-rings) is'0PERABLE. e. Water level in Spent Fuel Pool "A"/ Fuel Transfer Canal is maintained j pursuant to Specification 3.9.2./3.9.4 when the Fuel Transfer tubes are ) open. { { CHANNEL CALIBRATION 1.8 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to ) known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any. series of sequential, overlapping or total I 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 indications and/or status derived from independent instrument channels measuring the same parameter. THREE MILE ISLAND - UNIT 2 1-2

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17,0UINITIONS l

h I i 1tEt DNCTIONAL TEST e j 1510 \\ 'HANNEL FUNCTIONAL TEST shall be: f Anu ' thannels - the injection of a simulated signal into the channel'as .l a.. cloa. to the primary' sensor as practicable to verify OPERABILITY including alarm and/or~ trip functions. Blstable channels - the jnjection'of a simulated signal into the. channel { b. . sensor to verify OPERABILITY includin0 alarm'and/or trip functions. J STAGGERED TEST BASIS' i 1.11 A STAGGERED ~ TEST BASIS shall consist of: q A test schedule for n systems', subsystems, trains or designated 4 a. components obtained by dividing.the specified. test interval into n-equal subintervals, y 'tv The testing of one system, subsystem,' train or designated components at~ ] 1 the'beginning of each subinterval. i FREQUENCY NOTATION '1.121The FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined in Table l'.2. FIRE-SUPPRESSION' WATER' SYSTEM ) l 1.13l'A FIRE SUPPRESSION WATER SYSTEM shall consist of: a water source; gravity' tank or pumps; and' distribution piping and associated sectionalizing control or isolation valves. Such valves shall include yard hydrant' curb valves, and the first. valve upstream of the water flow alarm device on each sprinkler, hose standpipe or ~ spray system riser. REVIEW SIGNIFICANT 1.14 REVIEW'SIGNIFICANT' items shal1 consist of items that are Important to ~ Safety,'or proposed changes to Technical Specifications, License, Special Orders or Agreements, Recovery Operations Plan, Organization Plan, or involve q an Unreviewed Safety. Question or a Significant Environmental Impact. Also, those system operating procedures and associated emergency, abnormal, alarm response procedures which require NRC approval. In addition, those activities not covered by an NRC approved system description, SER or TER and'which exceed PEIS values, i l ( THREE MILE ISLAND - UNIT 2 1-3 I 0127P l 1

1 LO DEFINITIONS CORE ALTERATION 1.15 CORE ALTERATION shall be the movement or manipulation of any reactor temponent (including fuel) within the reactor pressure vessel with the vessel i head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not l preclude completion of movement of a component to a safe conservative position. l \\ LOSS-TO-AMBIENT j 1.16 LOSS-TO-AHBIENT is a passive cool.ing 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

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i ACCIDENT GENERATED WATER 1.17 ACCIDENT GENERATED MATER, as defined in the settlement of the City of { Lancaster litigation, is: j 1 a. Hater the existed in the TMI-2 Auxiliary, Fuel Handling, and Containment I Buildings including the primary system as of October 16, 1979, with the exception of water which as a result of decontamination operations becomes commingled with non-accident generated water such that the commingled water has a tritium content of 0.025 uC1/ml oc less before processing; b. Water that has a total activity of greater than one uC1/ml prior to f processing except where such water is originally non-accident water and becomes contaminated by use in cleanup; c. Water that contains greater than 0.025 uC1/ml of tritium before processing. 1.18 LICENSED OPERATOR (OL) - any individual who possesses an NRC Operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operators i Licenses." ] t 1.19 SENIOR LICENSED OPERATOR (SOL) - any individual who possesses an NRC { Senior Operator's license pursuant to Title 10, Code of Federal Regulations, { Part 55, " Operators Licenses." l 1.20 FUEL HANDLING SENIOR LICENSED OPERATOR (SOL-FH) - an individual licensed by the Nuclear Regulatory Commission to supervise fuel handling and core alterations operations. l l l i l l l l l THREE MILE ISLAND - UNIT 2 1-4 (

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.j sl0 ' r1 :00 0EFINITIONS' .g nkn '1,21. CONTAINMENT ISOLATION shallinxistc when: 7-3 1 e-1 W ta 1,Each penetration 1s: m , #m, . s .a' ,,4 ...g 710.;.. lClosediby-an3 accessible ~ manual.vake, a weldedJor bolted blind + 1 i *- Xflange, or:a deactivated automatic valve secured in the closed, fposition to provide tsolation of-each penetration,' or'; t,, 4 -. + ' 2. J.Open per?an.' approved pr,ocedure but'.'can be closed pursuantito t-1 - Specification 1.21.a'.1., Controls shall be ;1mplemented to minimize tho: time the penetration is allowed open;and_to'specify-the . conditions'for which the penetration'is'open.. Penetrations shall- ~' be: expeditiously closed.upon' completion of the conditions specified on the'approvedJprocedures. t + b.- The Equipment Hatch is closed and sealed. c. Each Containment Airlock is OPERABLE pursuant to Specification 3.6'.1.6. , i, b .q 1 h i l .THREE MILE ISLAND - UNIT 2 1-5

p,y'~y;; y, -n p, .y < .~ <., S ,g N 'a. a. . TABLE 1.1. ' H q y;. i > FACILITY MODES 1 l .l .c lL.y // c, MODE-PLANTCONDfTION ') 1 i }j c l', -

l The reactor shall be subcritical with an average L

'r'eactor' coolant temperature of less.-than.200'F. 7 l 4 a :}. 3 2 Mode'2.shall exist when the following conditions are, i li i met: ,,J f-o a. The Reactor Vessel and Reactor Coolant < System are s " 1, [ ' i.- .defueled to the extent' reasonably achievable. d 1 L: * '.b. :Tha: possibility of criticality in the Reactor Building"is precluded;

c. 'There are no canisters containing core material in the Reactor Building.'

'l l i 3. Mode 3 shall exist.when the conditions for Mode 2'are L' " ' met and no canisters containing core material are l stored on the THI-2 site. o, s l u t y l 1 ? -1 l l THREE MILE ISLAND - UNIT 2 1-6 0229P l a

p L TABLE 1.2 l FREQUENCY NOTATION ] NOTATION FREQUENCY ( 5 At least once per 12 hours. l D-At least once per 24 hours. W At least once per 7 days. H At least once per 31 days. I i. Q At least once per.92 days. l At least once per 184 days. SA A At least once per 12 months. R At least once per 18 months. i N.A. Not applicable. s t I } THREE MILE ISLAND - UNIT 2 1-7 l

7 s- ,,t-t SECTION 2.0 SAFETY LIMITS AND J LIMITING SAFETY SYSTEM SETTINGS i a l l 1 l 1 ( 0127P

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"(+- '2'.0 SAFETY LIMITS r

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

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n- ~ s 4 ) SECTION 3.0 3 LIMITING CONDITIONS FOR OPERATION i I 1 i i i 0127P a-

1.0 APPLICABILITY 3 LIMITINGCONDITIONSFOROPERATIbH. 3.0.1.' Limiting Conditions for Operation and. ACTION requirements shall be-La ? applicable during.theLFACILITY MODE.or..othericonditions specified Lfor each - l' l , W ' ; specification.J 3.0.2 ! Adherence to the' requirements of the Limiting Condition for Operation l and/or associated ACTION vithin-the specified'timelintervaloshall constitute

compliance with the specification.: In-the event the Limiting Condition for

' Operation is restored prior to' expiration of the'specified, tine interval, o completion of the ACTIONLstatement is not required. s 'In the event'a Limiting Condition for Operation and/or associated 13.0.3' ACTION ~ requirements cannot be satisfied because of circumstances,in excess of l l -those addressed'in the specification, initiate appropriate actions.to rectify the problem to!the extent possible under,the circumstances and submit a report 5 to;the_ Commission pursuant to the requirements of 50.73 of 10 CFR Part 50. a 'S r f. q ) ) 4 I THREE MILE ISLAND - UNIT 2 3.0-1 0127P j

3.1 HATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 3.1.1 BORATION CONTROL BORATED COOLING WATER INJECTION U MITING CONDITIONS FOR OPERATION 3.1.1.1 The following systems, capable of injecting borated cooling water into the Reactor Coolant System, shall be OPERABLE with a. Two operable flowpaths downstream from the Borated Hater Storage Tank and common drop line. b. Dedicated on-site equipment for a Reactor Building Sump Recirculation System. ) I c. The BHST shall contain at least 390,000 gallons of borated water at a minimum temperature of 50 degrees Fahrenheit and a boron concentration of ) between 4350 and 6000 ppm. l ] APPLICABILITY: MODE I ACTION: a. With one flowpath from the BHST inoperable, restore to OPERABLE status or l establish an alternate flowpath within 72 hours, b. With both flowpaths from the BHST inoperable, suspend all operations i involving C0RE ALTERATIONS and/or the Reactor Coolant System and restore the inoperable flowpaths to OPERABLE status within 72 hours. 1 c. With the dedicated Reactor Building Sump Recirculation System inoperable, { restore to OPERA 8LE status within 7 days. j d. With the BHST water volume, boron concentration or minimum temperature I out-of-specification, suspend all operations involving CORE ALTERATIONS and/or the Reactor Coolant System and restore the BHST to specification within 72 hours, j 4 TilREE MILE ISLAND - UNIT 2 3.1-1

l BORON CONCENTRATION - REACTOR COOLANT SYSTEM l LIMITING CONDITIONS FOR OPERATION The boron concentration of the coolant in all filled portions of the 3.1.1.2 Reactor Coolant System shall be maintained between 4350 and 6000 ppm and at a temperature above 50*f. l APPLICABILITY: MODE 1 E l ACTION If either of the above conditions are not satisfied (Boron Concentration between'4350 and 6000 ppm and temperature above 50*F) imediately suspend all activities involving CORE ALTERATION and/or the Reactor Coolant System and take action in accordance with Specification 3.0.3 to restore the concentration to within acceptable limits. I i THREE MILE ISLAND - UNIT 2 3.1-2 I 0127P _-______-_____O

r' 1.; l BORON CONCENTRATION - FUEL TRANSFER CANAL LIMITING CONDITIONS FOR OPERATION The boron concentration of the water in all filled portions of the 3.1.1.3 1 f Fuel Transfer Canal (deep end) shall be maintained between 4350 and 6000 ppm. APPLICABILITY: MODE 1 ACTION If the above condition is not satisfied (boron concentration between 4350 and t 6000 ppm), take action necessary to restore the boron concentration to within y acceptable limits. l O i .i l THREE MILE ISLAND - UNIT 2' 3.1-3 0127P r

1 l l BORON CONCENTRATION - SPENT FUEL POOL RA" 1 LIMITING CONDITIONS FOR OPERATION 1 3.1.1 ' 4 The boron concentration of the water in all filled portions of Spent Fuel LPool "A" shall be maintained between 4350 and 6000 ppm. APPLICABILITY: NODES 1 and 2 ACTION: If the above condition is not satisfied (boron concentration between 4350 and 6000 ppm), take action necessary to restore the boron concentration to within acceptable limits. ) THREE MILE ISLAND - UNIT 2 3.1-4 0127P L-_-___________________

7______ 1 3.3 INSTRUMENTATION f 3.3.1 NEUTRON MONITORING INSTRUMENTATION INTERMEDIATE AND SOURCE RANGE NEUTRON FLUX MONITORS LIMITING CONDITIONS FOR OPERATION i As a minimum, the intermediate and source range neutron monitoring 3.3.1.1 instrumentation channels of Table 4.3-1 of the RECOVERY OPERATIONS PLAN shall be OPERABLE. f APPLICABILITY: HODE 1 ACTION: I With the number of source range neutron monitoring channels OPERABLE one a. less than required by the Minimum Channels OPERABLE requirement of Table 4.3-1 of the RECOVERY OPERATIONS PLAN, restore the inoperable channel to OPERABLE status within 30 days, With no source range neutron monitoring channels OPERABLE, suspend all b, activities involving CORE ALTERATION, verify compliance with the boron 1 l concentration requirements of Specification 3.1.1.2 at least once per 24 hours by a mass balance calculation and at least once per 7 days by a chemical analysis and restore at least one source range neutron monitoring channel to OPERABLE status within 7 days. l With no intermediate range neutron monitoring channels OPERABLE, restore i at least one intermediate range channel to OPERABLE status within 7 days. l c. p THREE MILE ISLAND - UNIT 2 3.3-1 0127P i

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A %i Sk TE0!iOLOGICAL INSTRUMENTATION i LIEITINGCONDITIONSFOROPERATION s The meteorological monitoring instrumentation channels shown 3.3;& 4 in Tdble 4.3-5 of the RECOVERY OPERATIONS FLAN shall be OPERABLE. APPLICABILITY: MODES 1 AND.2 ACTION: ' With any of the.above required meteorological monitor!ng channels inoperable, l restore the inoperable channel (s) to OPERABLE status within 7 days. s , o. n. < [' t 3 .\\ ;:, 'f ',, (< )< / g e q APPLICABILITY: MODES 1, 2 and 3 L s ACTION: o y n. o. t .s. With one 4 more of the above-required Penetration Fire Barriert non-funct fo.ial :- t n. Establish a roving (at least once per hour) fire watch on at least one-J 1. side,of the affected penetration within 1 hour, except areas inaccessible due,to oc6upational exposure considerations and U i For those/ areas inaccessible due to occupational exposure considerations, .j rl L-2. 'i' .prepere and submit a Special Report to the Commission pursuint to ' Specification 6.9.2 within the nextl30 days outlining the cause of the malfunction and the means for ensuring an' adequate firewatch is maintainedintheaffectedareaandforrestoringthefirebayrier(s)to a functional status. s.;,. 'g h f (( E ). I i ./. ,i .ps Iy' N r g 1;

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~~3. 8. l'.1 As a minimilm, khe followir\\q. A.C. electricaFpowe/ cources shall' be g~~
~~OPERABLE: 'Two phpgically independent circuits between da offs)'tLki transmission..,~~
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'a. 6 _ O.- network and the onsite Class lE distribution system. % l <i; ? } gl^ b. Deleted i l u. APPLICABILITY: M02d [ k; Y r.flh C ' ./ J ~ L j .f ACTION: ,o Hithoneoffsite~circuitoftherequ,(p,(sr.C.electricallpow.Mp A,.d + >g1 r A i (j a. ' inoperable, verify the operability oi' g demonstrate the OPERABILITY of th6 0,C.tbus trains by pe;rformiemaining off-fje d in 'i / Surveillance Requirements in the AEC0VEk? OPERATIONS PLAN SMAp(yf the <,/ i - g n s, 'e tid
~~4.8.2.2.1 and 4.8.2.2.2.a.4 MithW 4 hours.' Restore the fullc cog (Q~~
'i of offsite. A.C. electrical power scarces to 0PERABLE status'witpr /' days. ~J 'H1th both offsite circuits of tlk ' abo /e required A.C. electricah pow r n / ' $ n((d. 9 sources inoperable, suspend f,T9E \\LTERATIONS and cease move. ment $f heavy l t ? dt loadsintheRea(torBu11dingl7 Restoreonecircuitwithdd,hou?s'and 9 restore the,seccad A.C. circuit to operable status within 7 d e f. ( g 1 l p' ,) 3$ -cy ~ l, t'- 1 J s i;, ': / ( / 1 c. /i 1 , n.j / 4 q ( A 9 i ) .,s W ,s .>1 i
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t ~ ) TABLE 3.8-2 f RESTORATION TIME MATRIX l Deleted 1 1 i l THREE MILE ISLAND - UNIT 2 3.8-3 0127P
L 3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 3.8.2.1 A.C. DISTRIBUTION LIMITING CONDITIONS FOR OPERATI':n l The A.C. electrical busses listed in Section 4.8.2.1.1 of the 3.8.2.1.1 RECOVERY OPERATIONS PLAN shall be OPERABLE and energized with tie breakers l open (unless closed in accodance with site-approved procedures) between i redundant busses. APPLICABILITY: MODE 1 ACTION: With less than the above compliment of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours The A.C. electrical busses listed in Section 4.8.2.1.2 of the 3.8.2.1.2 RECOVERY OPERATIONS PLAN shall be OPERABLE and energized. 1 APPLICABILITY: MODE 1 ACTION: With any of the above A.C. busses incapable of being supplied by their respective inverter, restore that capability to the affected bus within 7 a. days. With any of the above A.C. busses de-energized, restore the inoperable b. bus to OPERABLE status within 8 hours. t i i l 4 1 \\ THREE MILE ISLAND - UNIT 2 3.8-4 0127P
}.8.2.2 D.C. DISTRIBUTION LIMITING CONDITIONS FOR OPERATION The following D.C. bus trains shall be energized and OPERABLE with 3.8.2.2.1 tie breakers between bus trains open (unless closed in accordance with approved procedures): TRAIN "A" consisting of 250/125-volt D.C. bus 2-1DC, 250/125-volt D.C. battery bank A and a full capacity charger. TRAIN "B" consisting of 250/125-volt D.C. bus 2-2DC, 250/125-volt D.C. battery bank B, and a full capacity charger. APPLICABILITY: MODE 1 ACTION: a. With one 250/125 D.C. bus inoperable, restore the inoperable bus to OPERABLE status within 2 hours. i 250/125-volt D.C. battery and/or its charger inoperable, restore With one b. the inoperable battery and/or charger to OPERABLE status within 2 hours. l 4 THREE MILE ISLAND - UNIT 2 3.8-5 0 0127P l 1
3.9 RADIOACTIVE MATERIALS STORAGE SPENT FUEL STORAGE POOL "A" WATER LEVEL HONITORING LIMITING CONDITIONS FOR OPERATION 3.9.1 Two independent Spent Fuel Storage Pool "A" water level monitoring instruments shall be OPERABLE. APPLICABILITY: MODES 1 and 2 whenever any Canister containing core material l is in Spent Fuel Storage Pool "A". ACTION: i With only one Spent Fuel Storage Pool "A" water level monitoring a. instrument OPERABLE, immediately verify that the water level is within limits, re-verify.the level at least once per 24 hours and and restore a second instrument to OPERABLE status within 7 days. b. With no Spent Fuel Storage Pool "A" water level monitoring instruments OPERABLE, terminate all activities involving any Canister containing core material in or over Spent Fuel Storage Pool "A" and all operations involving changes in Spent Fuel Storage Pool "A" water inventory and restore at least one instrument to OPERABLE status within 24 hours. i l THREE MILE ISLAND - UNIT 2 3.9-1 l 0127P l
l SPENT' FUEL STORAGE POOL "A" WATER LEVEL 1 LIMITING CONDITIONS FOR OPERATION ~ 3.9.2 The water level to Spent Fuel Storage Pool "A" shall be maintained as' specified in Section 4.9.2 of the Recovery Operations Plan. APPLICABILITY:. MODES'l AND 2 whenever any Canister containing core material is.In Spent Fuel Storage Pool "A". ACTION: With Spent Fuel Storage Pool "A" water level not within the specified band,. l l terminate all activities involving any Canister containing core material-in or I over Spent fuel Storage Pool:"A" and restore the water level to within specification within 24 hours. i 4 l i 1 l l 4 i THREE MILE ISLAND - UNIT 2 3.9-2 1
l l 1 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING l' ' LIMITING CONDITIONS FOR OPERATION Two independent Fuel Transfer Canal (deep end) water level monitoring l l -3.9.3 instruments shall be OPERABLE. APPLICABILITY: MODE 1 ACTION: With only one Fuel Transfer Canal (deep end) water level monitoring- -l instrument OPERABLE, immediately verify that the water level is within a. limits, re-verify the level at least once per 24 hours and restore a second instrument to OPERABLE status within 7 days. 1 With no fuel Transfer Canal.(deep end) water level instruments OPERABLE, terminate all activities involving any Canister containing core material 'b.- in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assembly and all operations involving changes in the Fuel Transfer Canal (deep end) water inventory and restore one inoperable instrument to OPERABLE status within 24 hours. 1 I ~ l .THREE MILE ISLAND - UNIT 2 3.9-3 0127P
l FUEL TRANSFER CANAL (DEEP END) WATER LEVEL LIMITING CONDITIONS FOR OPERATION 1 '3.9.4 The water level in the Fuel Transfer Canal (deep end) shall be maintained at the level specified in Section 4.9.4 of the Recovery Operations Plan. APPLICABILITY: MODE 1 l ACTION: With the Fuel Transfer Canal (deep end) water level not within the specified I band, 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 hours. 1 i 1 { THREE mil E ISLAND - UNIT 2 3.9-4 i
r1 ) 3.9.12 : FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS FUEL NANDLING BUILDING AIR CLEANUP SYSTEM - LIMITING CONDITIONS Fok OPERATION 3.9.12.1 The-Fuel Handling Building Air Cleanup Exhaust Systen, shall be OPERABLE with one of the four system air cleanup exhaust fans OPERABLE. ,, l l -APPLICABILITY: MODES 1, 2 and 3 \\ l ACTION:' l d With the Fuel Handling Building. Air Cleanup Exhaust System inoperable, restore the system to OPERABLE. status within 4 hours or suspend all operations involving movement of liquid and gaseous radioactive wastes in the Fuel i i Handling Building (other than sampling evaluations required by the Technical Specifications or the Recovery Operations Plan) until the system is restored to OPERABLE status. ' AUXILIARY BUILDING AIR CLEANUP EXHAUST SYSTEM 3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shall be OPERABLE-with one of the four system air cleanup exhaust fans OPERABLE. ] l APPLICABILITY:. MODES 1,.2 and 3 ACTION: With the Aux 111ary' Building Air Cleanup Exhaust System inoperable, restore the system to operable status within 4 hours or suspend all operations involving L movement of liquid and gaseous radioactive wastes in the Auxiliary Building L (other than sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN) until the system is restored to OPERABLE status. 1 q i i l 1 f THREE MILE ISLAND - UNIT 2 3.9-5 ] 0127P l 4
-3.9.13 oACCIDENT GENERATED WATER
~~l 1~~
' DISCHARGE OF ACCIDENT GENERATED WATER LIMITING ~ CONDITIONS FOR OPERATION q i 3,9.13 Discharge of' ACCIDENT GENERATED-WATER shall.be prohibited until approved by the NRC. ' ACCIDENT GENERATED HATER shall be discharged in I . accordance-with.NRC-approved procedures. ' APPLICABILITY: MODES 1, 2.and 3 ACTION: None except as provided in Specification 3.0.3. 1 i 1 5 4 1 1 A i I THREE MILE ISLAND - UNIT 2 3.9-6 =
3.10 CRANE OPERATIONS CONTAINMENT BUILDING LIMITING CONDITIONS FOR OPERATION 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 i approved by the NRC: a. Reactor Vessel Incore Instrument Seal Table and Guide Tubes (includes travel by polar b. crane block) Deep end of the Fuel Transfer Canal c. Any Canister that contains core material regardless of its location d. Areas not previously analyzed in a docketed NRC approved load drop e. analysis APPLICABILITY: H0DE 1 ACTION: With the requirements of the above specification not satisfied, place the crane load in a safe condition and correct the circumstances which caused or allowed the Limiting Condition for Operations to be exceeded prior to continuing crane operations limited by Specification 3.10.1. Prepare and submit a special report to the Commission pursuant to Specification 6.9.2 within the next 30 days. t ) i l I I I i THREE MILE ISLAND - UNIT 2 3.10-1 0127P
FUEL HANDLING BUILDING LIMITING CONDITIONS FOR OPERATION Loads in excess of 2400 lbs shall be prohibited from travel over 'the 3.10.2 following areas unless docketed Safety Evaluation for the activity is approved by the NRC: Any area of the Spent Fuel Storage Pool which contains one or more a. Canisters which contain core material Any Canister that contains core riterial, regardless of its location b. Areas not previously analyzed in a docketed, NRC approved load drop c. analysis APPLICABILITY: MODES 1 and 2 ACTION: With the requirements of the above specification not satisfied, place the crane load in a safe condition and correct the circumstances which caused or allowed the Limiting Condition for Operations to be exceeded prior to continuing crane operations limited by Specification 3.10.2. Prepare and submit a special report to the Commission pursuant to Specification 6.9.2 within the next 30 days. j i ) THREE MILE ISLAND - UNIT 2 3.10-2 I 0127P
_m----.__._ BASES FOR LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l l i 0127P
,..i s. y 2 I I 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 Specificati_ons as provided in 10 CFR 50.36. e l k 1 0127P .I A
3/4.0 APPLICABILITY BASES The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveillance Requirements within Section 3/4. 3.0.1 This specification defines the applicability of each specification in terms of the FACILITY MODE or other specified conditions and is provided to delineate specifically when each specification is applicable. 3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement. 3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements or when the provisions of the stated ACTION statement are not or cannot be complied with. The intent of this specification is to require that inoperable equipment be restored to an OPERABLE status in a prompt manner, that the unit be maintained in stable conditions, and that the Commission be promptly notified of such conditions. 4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the FACILITY MODE or other conditions for which the Limiting Conditions for Operation are applicable. 4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities. The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not degraded beyond that obtained from the nominal specified interval. 4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operations. Under this criteria, equipment, systems or components 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 components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements. l THREE MILE ISLAND - Ut;IT 2 8 3/4.0-1 0127P
3/4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL AND BORATED COOLING WATER INJECTION The limitation on minimum boron concentration ensures that the core will remain subcritical under all credible conditions which may exist during the long-term cooling mode. The maximum boron concentration is provided to ensure that precipitation of boron will not occur in the RCS and thereby cause t The specification requires the OPERABILITY of possible flow restrictions. systems capable of injecting borated cooling water into the RCS within the I The OPERABILITY of equipment for a required boron concentration limits. Reactor Building Sump Recirculation System is required to provide a recirculation path from the Reactor Building Sump in the event of an unisolatable leak in the Reactnr Vessel. The required volume of borated water in the BHST provides sufficient water to provide a continuous supply of water i to the vessel during the interim period before the recirculation flowpath from j the Reactor Building Sump can be placed in service. Minimum boron concentration limits have been provided for the Reactor Coolant System, Refueling Canal (deep end) and Spent Fuel Storage Pool "A" to provide assurance that any event involving these volumes of water will not result in a In addition, margin of safety less than that analyzed for the Reactor Vessel. ) the Canister Handling and Preparation for Shipment Safety Evaluation Report f and the Defueling Safety Evaluation Report take credit for the boron concentration requirements in the refueling canal (deep end) and the spent { fuel storage pool "A" to assure that accidental rupturing of a canister in these pools will not result in a criticality potential. ) THREE MILE ISLAND - UNIT 2 8 3/4.1-1 0127P
3/4.3 INSTRUMENTATION-I BASES L 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION The neutron monitoring instrumentation, which was included in the normal -Reactor Protection System Instrumentation, provides information regarding the shutdown status of the core and it will be used to monitor changes in neutron generation. ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4.3.2 Deleted 3/4.3.3 MONITORING' INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that the radiation levels are measured in the areas served by the respective monitors. 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive This capability is required to evaluate the need materials to the atmosphere. for initiating protective measures to protect the health and safety of the public. 3/4.3.3.5 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION The OPERABILITY of the Essential Parameters Monitoring Instrumentation ensures that sufficient information is available on selected plant parameters to Reactor Coolant System temperature monitor and assess these variables. indication is provided outside the Control Room in the event that Control Room habitability is lost. 3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection systems ensures that an accidental f 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. I ) l 1 THREE MILE ISLAND - UNIT 2 B 3/4.3-1 1 d 0127P
INSTRUMENTATION BASES 3/4.3.3.8 and 3/4.3.3.9 FIRE DETECTION INSTRUMENTATION OPERABILITY of the Fire Detection Instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This j capability is required in order to detect and locate fires in their early I 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. 1 In the event that a portion of the Fire Detection Instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service, i l i THREE MILE ISLAND - UNIT 2 8 3/4.3-2 0229P i \\
3/4.4-' REACTOR COOLANT SYSTEM: BASES l 1 3/4.4'.1 REACTOR COOLANT LOOPS Deleted. I 3/4.4.2 REACTOR VESSEL WATER LEVEL MONITORING 1 The Reactor Vessel Water Level Monitor ensures.~that-indication is available to ' l monitor changes in Reactor Vessel water level. -This capability will provide warning of a leak from the Reactor Coolant System or unexplained increases in Reactor Coolant System inventory.which could result in'a boron dilution event. Two independent monitors are required to provide redundancy and to minimize.the necessity to discontinue processing because of instrument l failures. i 3/4.4.9 PRESSURE / TEMPERATURE LIMITS The Reactor Coolant System minimum temperature is maintained to prevent The maximum precipitation of the boron used to maintain subcriticality. l reactor coolant temperature is specified to provide a limit for action for any 1 unknown buildup of heat either due to loss of cooling or unanticipated heating source such as criticality.- 'l l 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. j ~ q .or components, will not occur. k l i l i e THREE MILE ISLAND - UNIT 2 B 3/4.4-1 0127P
" ~ ' - - - - - - - -.., -., _ _. _ _ _ _ _ _, _ _ _ _ BASES 3/4.5 COMMUNICATIONS 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. 9 e THREE MILE ISLAND - UNIT 2 B 3/4.5-1 0127P
3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY is maintained to ensure that radioactive materials in the Containment Building are not released to the environment in an uncontrolled manner. 3/4.6.1.2 CONTAINMENT ISOLATION Containment Isolation is maintained to assure the containment is properly maintained as a contamination barrier for the residual contamination which remains inside the containment. 3/4.6.1.3 CONTAINMENT AIR LOCKS (MODE 1) The Containment Air Locks must be maintained OPERABLE to provide the appropriate containment sealing capability. These air locks will be used during entries into the Containment to ensure that radioactive materials are not being released to the environs. The preferred method for ensuring that radioactive materials are not released during these entries is to maintain at least one door closed at all times; however, to permit the passage of long items into the Reactor Building, both doors may be open simultaneously in l accordance with site-approved procedures. During periods when both doors are i open, the activities listed in Recovery Operations Plan Section 4.6.1.3.1.b shall be prohibited to minimize the potential for an uncontrolled release to the environment. 3/4.6.1.4 INTERNAL PRESSURE The negative pressure limit provides assurance that the Containment will not exceed its design negative pressure differential. The positive pressure limit provides assurance that leakage from the Containment will be limited for off-site dose calculations. During periods when both doors in either or both personnel airlocks are open, the Containment Purge System will be operating to maintain Containment pressure within the limits of the Technical Specifications with the restrictions of 4.6.1.3.1.b and 4.6.1.6.1.b also applying. 3/4.6.1.5 AIR TEMPERATURE The average air temperature of the Containment atmosphere is currently being maintained between 50*F and 130*F. This condition will maximize the service life of the instrumentation and equipment installed in the Containment and ensure that Reactor Coolant System temperature does not drop below 50*F through LOSS-TO-AMBIENT Cooling. This temperature will ensure that boron will remain in solution. THREE MILE ISLAND - UNIT 2 8 3/4.6-1 0229P
i CONTAINMENT SYSTEMS i BASES 3/4.6.1.6 CONTAINMENT AIRLOCKS (MODES 2 AND 3) The Containment Air Locks must be maintained OPERABLE to provide assurance that the containment is properly maintained as a contamination barrier for the These air locks residual contamination which remains inside the containment. will be used during entries into the Containment to ensure that radioactive materials are not being released to the environs. One door must be closed at all times; however, to permit the passage of long items into the Reactor Building, both doors may be opened simultaneously in accordance with site-approved procedures. 3/4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM The OPERABILITY requirements for the Containment Purge Exhaust System ensure l that during Containment purge operations all radioactive particulate material will be filtered through the HEPA filters prior to release to the atmosphere. 1 i e THREE MILE ISLAND - UNIT 2 B 3/4.6-2 0127P (
3/4.7 PLANT SYSTEMS BASES 3/4.7.4 NUCLEAR SERVICE RIVER HATER SYSTEM Deleted. g 3/4.7.6 FLOOD PROTECTIGN 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 1 ft. Mean Sea Level USGS datum is the elevation at which facility flood control measures are required to be taken. 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the Control Room Emergency Air Cleanup System ensures that
1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the Control Room will remain habitable for operations personnel during and following all credible conditions. Under certain conditions (i.e.,
loss of off-site power combined with a severe accident at Unit 1), it would be required to place TMI-2 in a stable configuration with core alterations suspended. In this case, operability requirements to ensure TMI-2 Control Room habitability may be temporarily suspended. The OPERABILITY of this system in conjunction with Control Room design provisions is based on limiting the radiation exposure to personnel occupying the Control Room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A", 10 CFR 50. l 3/4.7.9 SEALED SOURCE INTEGRITY 1 The limitation on removable contamination for sources requiring leak testing, l including alpha emitters, is based on 10CFR70.38(c) limits for plutonium, i This limitation will ensure that leakage from byproduct, source, and Special Nuclear Material sources will not exceed allowable intake values. 3/4.7.10 FIRE SUPPRESSION SYSTEMS l The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring l In any portion of the facility where Safety Related equipment is located. The Fire Suppression System consists of the water system, spray and/or sprinklers, Halon and fire hose stations. The collective capability of the Fire i Suppression Systems is adequate to minimize potential damage to Safety Related i 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 l gpm. l THREE MILE ISLAND - UNIT 2 B 3/4.7-1 0229P 1 h IL__ -
r PLANT SYSTEMS t BASES ) In the event that portions of the Fire Suppression Systems are inoperable, i alternate backup fire fighting equipment is required to be made available in i 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. 3/4.7.11 PENETRATION FIRE BARRIERS The functional integrity of the Fire Barrier Penetration Seals ensures that fires will be confined or adequately retarded from spreading to adjacent This design feature minimizes the possibility of a portions of the facility. single fire rapidly involving several areas of the facility prior to detection The Fire Barrier Penetration Seals are a positive element and extinguishment. in the facility fire protection program and are subject to periodic inspections. During periods of time when the seals are not functional, a roving fire watch } is required to be maintained in the vicinity of the affected seal until the ) seal is restored to functional status except in areas where the affected seal l For those seals that are inaccessible, a special report is is inaccessible. j required to be filed. i i 1 l l l l l THREE MILE ISLAND - UNIT 2 8 3/4.7-2 0127P
BASES 3/4.8 ELECTRICAL POWER SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution ' systems ensures that sufficient power Will be available when required. l I j e THREE HILE ISLAND - UNIT 2 8 3/4.8-1 0127P
3/4.9 RADIOACTIVE MATERIALS STORAGE' j BASES 3/4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING Spent Fuel Storage Pool "A" Water Level Monitoring instrumentation has been l provided to assure the capability to monitor water level in the Spent Fuel Storage Pool "A". f 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. J 3/4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING Fuel Transfer Canal Water Level Monitoring instrumentation has been provided i 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. t 3/4.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEM l l The requirement for the Fuel Handling Building / Auxiliary Building Air Cleanup System to be operating or OPERABLE ensures that all radioactive material released from operations involving movement of liquid and gaseous radioactive wastes in the Auxiliary Building will be filtered through the HEPA filters prior to release to the atmosphere. 3/4.9.13 ACCIDENT GENERATED WATER These specifications are provided to ensure compliance with the Commission's Statement of May 25, 1979, and the Commission's Statement of' Policy and Notice of Intent to Prepare a Programmatic Environmental Impact Statement of November 21, 1979, which prohibit these actions pending evaluation of the environmental l impacts of such actions. The PEIS issued in March 1981, deferred a decision on the ultimate disposal of processcd water. Further Commission action is necessary prior to release of ACCIDENT GENERATED WATER. f However, the Commission has recognized that there may be emergency situations, not at this time foreseen, which could require rap?d action. In these situations, the Commission has indicated its intention to consult with the Council on Environmental Quality to the extent practicable. 7 THREE MILE ISLAND - UNIT 2 B 3/4.9-1 0127P
3 s. . ; u.;; q [. ' ),. <. i 'k ' f.'. l f, ) ':' ; j s BASES-g r '~ g J.,, a 1 i \\< 'c i i s. [ . 3 /4 '. 9 RADIOACTIVE WASH STORAGE,,. j/ lj,. ~ ) { ~ ACCIDENTGE$TRATEDWATER-Cont'd .,y t I 3/4.9.13 ,47, 4 ACCIDENT GENERATED, WATER, as defined in the settlement of the City of f' q 1 s vi 1 I Lancaster litigation, is: l'L Water that existed intthe 1MI-2 Auxiliary, Fuel Handling, and Co di1pment n Buildings including'the primary system as of October 16,1979,With i ) a'. ) exception of water which as a result of decontamination operations. L becomes commingled with non-accident generated water such that the i f,' E commingled water has a tritium content of 0.025 uCi/ml or less before { 0 1 processing; gb l Water that has.a total activity of greater than one uC1/ml prior to u l, b. h' processing except,where such water is originally non-accident water and l p becomes contaminated by use in cleanup; {! j s { Water that contains greater than 0,025 uC1/ml of tritium before l c. E l processing. .\\ 9 j 3/4.9.14 ['<; ~, J 'i De1eted. ,I l' ,q ( r\\ ? i e 3 N t '@p* g. m; e .\\. ,h. b I a t ..e 's h 1 THREE MILE ISLAND - UNIT 2 B 3/4 9-2 0127P w S s A
~ W t.'( f :_ . f; , -)T jn : j;f f ~ 3/4.10 CRANEOPERATf0NS t* 1 .>. ~ ,i l ' ~ j BASES s'9 ' l A' F 3, >- CRAFE OPERATIONS - CONTAINMENT BORDING , cQ' 4,'3/4.10.1 l v A heavy load crop into the Reactor Vessel may cause reconfiguration of the N, ' y V, A core debris and/or structural damage which could hinder yecovery efforts. leatdrop en ti.s incore Instrument Seal Table and/or guide JubesMay result f ra s I 'I 1 , 4 , The restriqt'/on on inovemeht of . san uhWotable leak from the Reactor Vessel. 41 i! loJds in excess of the nominal.% ght of a fuel or controllrod asiembly and i aglociated handling tool over these areas is to mitigate thi potential co9 seat:ences stated above in the sent this load is dropped.,, I, .,<n, > if '13/4.10.2 CRANE OPERATIONS N E N HANDLING BUILDING , I# ,x A heavy load drop in the Fue9 Handling Building couldareholt in the rupture of The restriction'on movement of heavy a canister containing core material. loads in the. fuel handing building is to prevent the drop'of a heavy load in the fuel handling building in areas where the rupture of a fuel canister could
~~occur, it j~~
s I l l i i i e i THREE MILE ISLAND - UNIT 2 B 3/4.10-1 0127P
i ? SECTION 6.0 ADMINISTRATIVE CONTROLS I t 1 0127P
l ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY ) 6.1.1' The Office of the Director-TMI-2 consists of the Director-THI-2 and the l Deputy Director-THI-2 and shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during both of their absences. I 6.2 ORGANIZATION GPUNC ORGANIZATION 6.2.1; The GPU Nuclear Corporation (GPUNC) Organization for unit management and technical support shall be as shown on Figure 1-1 of the Organization The Organization Plan and changes the~reto shall be approved by the NRC Plan. prior to implementation. THI-2 ORGANIZATION t The unit organization shall be shown on Figure 1-2 of the Organization 6.2.2 Plan and: I During Mode 1, each on duty. shift shall be composed of at least the a. minimum shift crew composition shown in Table 6.2-1. I During Mode 1, at least one licensed Operator shall be in the control
~~b...~~
room when fuel is in the reactor. 8 During Mode 1, an individual qualified in radiation protection procedures c. shall be onsite when fuel is in the reactor. A Site Fire Brigade of at least 5 members shall be maintained onsite at d. The Site Fire Brigade shall not include 3 members ef the l all times. minimum shift crew (during Mode 1) necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency, An individual qualified in radiation protection procedures shall be e. onsite whenever Radioactive Waste Management activities are in progress. f THREE MILE ISLAND - UNIT 2 6-1 0127P
z-TABLE 6.2-1 1 : j' ' MINIMUM SHIFT CREW COMPOSITION # RECOVERY MODE LICENSE CATEGORY 1*- ,, SOL 1 -- OL 2 Kon-Licensed
Shift crew composition may be less than the minimum require-ments for a period of. time not to exceed 2 hours in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
~~During CORE ALTERATIONS an additional SOL or an 50L limited to l~~
fuel handling will be stationed on the operating floor, in the command center, or in-the Control Room to directly control the particular CORE ALTERATION activity being performed. l i 4 l l = THREE MILE ISLAND - UNIT 2 6-2 0127P
U j ADMINISTRATIVE CONTROLS l 6.3 -UNIT STAFF QUALIFICATIONS-6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI-N 18.1 of 1971 for comparable positions unless l 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 TMI-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 controls function prior to their performance of those tasks. 6.4 TRAINING 1 6.4.1 A retraining and' replacement training program for the unit staff shall be maintained under the direction of the Plant Training Manager and shall meet-or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977 and 10 CFR 55.59 except that Radiological Controls training may be under the l direction of Vice President-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 requirements of Section 27 of the NFPA Code-1976. 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEH AND CONTROL 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 preparation, review, and approval of documents required by the activities within their functional area of responsibility for TMI-2. Implementing approvals shall be performed at the cognizant 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 i -procedures except when they impact the operational status of unit systems or equipment (requires TMI-2 Division concurrence), e significant environmental impact (requires in line SRG and Environmental Licensing review), or represent an Unreviewed Safety Question (USQ) or Tech. Spec. change, including Recovery I Operations Plan Change (requires in line SRG review and NRC approval). THREE HILE ISLAND - UNIT 2 6-3
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 accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976. '6.8.2.2 DELETED. 6.8.3.1 Temporary changes'to procedures of 6.8.1 may be made provided that: a. The intent of the original procedure control is not altered, and b. 1)' For those procedures which affect the operational status of unit syrtems 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 Department having. cognizance of the procedure being a 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 l~~
resr,onsible organization..If one of the two above signatures is not.by a section manager / director within the Department having cognizance of the procedure being~ changed,-the signature,of that section manager / director within the department will also be required, and c. The change is documented, Independent Safety Review completed, and the i required reviews and approvals are obtained within 14 days, and d. Those changes to procedures required by Specification 3.9.13 are g submitted to the NRC for-review within 72 hours following approval by !"e management level-specified for implementation by Section 6.5.1.9. 6.9 REPORTING REQUIREMENTS l ROUTINE REPORTS AND REPORTABLE OCCURRENCES I 6.9.1 In addition to the applicable reporting requirements of Title 10, Code .j of Federal Regulations, the following reports shall be submitted to the NRC o Region I Administrator unless otherwise noted. i ] l' I 1 THREE MILE ISLAND - UNIT 2 6 11 1 _ O
i l 1 SECTION 4.0 SURVEILLANCE REQUIREMENTS -l 0084P
1 l l INDEX j SURVEILLANCE REQUIREMENTS SECTION PAGE i I 4.1 HATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS j 4.1.1 BORATION CONTROL 4.1.1.1 Borated Cooling Water Injection............................ 4.1-1 j 4.1.1.2 Boron Concentration Reactor Coolant System and............. 4.1-2 1 Refueling Canal { 4.1.1.3 Boron Concentration Fuel Transfer (Deep End)............... 4.1-2 j 4.1.1.4 Boron Concentration Spent Fuel Pool 'A'.................... 4.1-2 4.3 INSTRUMENTATION 4.3.1 NEUTRON MONITORING INSTRUMENTATION......................... 4.3-1 4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.. 4.3-1 4.3.3 MONITORING INSTRUMENTATION ) j 4.3.3.1 Radi ation Moni tori ng In s t rur,1en tation...................... 4.3-1 4.3.3.4 Meteorological Instrumentation............................. 4.3-8 4.3.3.5 Essential Parameters Monitoring Instrumentation............ 4.3-8 4.3.3.7 Chlorine Detection Systems................................. 4.3-8 4.3.3.8 Fire Detection............................................. 4.3-12 4.4 REACTOR COOLANT SYSTEM 4.4.1 REACTOR COOLANT L00PS..................................... 4.4-1 4.4.2 REACTOR VESSEL HATER LEVEL M0NITORING'...................... 4.4-1 4.4.9 PRESSURE / TEMPERATURE LIMITS................................ 4.4-1 4.S COMMUNICATIONS................................................... 4.5-1 4.6 CONTAINMENT SYSTEMS 4.6.1 PRIMARY CONTAINMENT 4.6.1.1 Containment Integrity...................................... 4.6-1 4.6.1.2 Containment Isolation..................................... 4.6-1 4.6.1.3 Containment Air Locks (Mode 1)............................. 4.6-1 4.6.1.4 Internal Pressure.......................................... 4.6-2 4.6.1.5 Air Temperature............................................ 4.6-2 4.6.1.6 Containment Air Locks (Modes 2 and 3)...................... 4.6-3 4.6.3 CONTAINMENT PURGE EXHAUST SYSTEM........................... 4.6-3 THREE MILE ISLAND - UNIT 2 I 0229P l lL__n _________
INDEX l l SURVEILLANCE REQUIREMENTS l SECTION PAGE '47 PLANT SYSTEMS I 4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEN......................... 4.7-1 4.7.6 FLOOD PROTECTION........................................... 4.7-1 4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.................. 4.7-2 4.7.9 SEALED S0URCES............................................. 4.7-4 4.7.10 FIRE SUPPRESSION SYSTEMS 4.7.10.1 Fire Suppression Water System.............................. 4.7-5 4.7.10.2 Deluge / Sprinkler Systems................................... 4.7-7 4.7.10.3 Halon, System............................................... 4.7-7 4.7.10.4 Fire Hose Stations......................................... 4.7-8 4.7.11 PENETRATION FIRE BARRIERS.................................. 4.7-8 4.8 ELECTRICAL POWER SYSTEMS 4.8.1 .A.C. SOURCES............................................... 4.8-1 4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 4.8.2.1 A.C. Distribution.......................................... 4.8-2 4.8.2.2 D.C. Distribution.......................................... 4.8-2 4.9 LIQUID RADI0 ACTIVE WASTE STORAGE 4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING......... 4.9-1 4.9.2 SPENT FUEL STORAGE POOL "A" WATER LEVEL.................... 4.9-1 4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING...... 4.9-1 4.9.4 FUEL TR ANSFER CANAL (DEEP END) WATER LEVEL................. 4.9-1 4.9.12 FUEL HANDLING BUILOINC/ AUXILIARY BUILDING AIR CLEANUP SYSTEMS.................................................. 4.9-1 TH1EE MILE ISLAND - UNIT 2 II 0084P
o SURVEILLANCE RE00fREMENTS l i 4.0.1 Surveillance Requirements of the RECOVERY OPERATIONS PLAN shall be l I applicable during the FACILITY MODE or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an Individual Surveillance Requirement. -The Surveillance Requirements shall be performed to demonstrate compliance with the OPERABILITY requirements of the Limitin; Conditions for Operations and in accordance with the RECOVERY j OPERATIONS PLAN; however, the RECOVERY OPERATIONS PLAN shall not be considered j a part of these technical specifications. Changes to the RECOVERY 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 with; a. A maximum allowable extension not to exceed 251. of the surveillance I interval, and b. A total maximum combined interval time for any 4 consecutive tests not to exceed 3.25 times the specified surveillance interval. 1 4.0.3 Performance of a Surveillance Requirement within the specified time i interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification. I J I l 1 J l 1 { l THREC MILE ISLAND - UNIT 2 4.0-1 l 0084P 4 l 4
kURVh1LLANCEREQUIREMENTS y. 'd . 4.- 1 WATER l.1JECTION COOLXNG AND REACTfVfTY CONTROL SYSTEMS 4.1.1 BORATION CONTROL-BORATED COOLING WATER INJECTION , 4.1.1.1 The systems capable of injecting borated cooling water into the Reactor Coolant System shall be demonstrated OPERABLE: a. At least.once per 31 days by verifying that each accessible (per occupational exposure considerations) valve in each flowpath that is not l locked, sealed,'or^otherwise secured.in position, is in its correct . position. b. At least once per 7 days by: 1. Verifying the boron concentration in the BWST is between 4350 and 6000 ppm. 2. Verifying the contained borated water volume in~the BWST is at 'least 390,000 gallons: l c. At leastlonce per 24 hours by verifying the BWST temperature is at least I 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 Recirculation System produce sufficient head and l flow to meet makeup requirements. 1 l l l l I THREE MILE ISLAM;.. UNIT 2 4.1-1 0084P l l
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 hours, 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 hours. 4.1.1.3 The boron concentration of the water in the filled portions of the l Fuel Transfer Canal (deep end) shall be determined to be within the specified limits by: Determining the boron concentration of the water in the filled portions a. of the Fuel Transfer Canal (deep end) to be between 4350 and 6000 ppm by a, chemical analysis at least once per 7 days. 4.1.1.4 The boron concentration of the water in the filled portions of spent fuel pool'"A" shall be determined to be within the specified limits by: Determining the boron concentration of the water in the filled portions a. of spent fuel pool "A" to be between 4350 and 6000 ppm by a chemical analysis at least once per 7 days. 4.1.3 CONTROL ASSEMBLIES I 4.1.3.1 Deleted THREE MILE ISLAND - UNIT 2 4.1-2 0084P
7 StlRVEILLANCE 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 CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the l frequency shown in Table 4.3-1. 4.3.2 ENGINEERED SAFETY-FEATURE ACTUATION SYSTEM INSTRUMENTATION t Deleted-4.3.3 MONITORING INSTRUMENTATION j 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 l THREE MILE ISLAND - UNIT 2 4.3-1 0084P
RL CC CC SE MLL EB t NA lI NR 1 2 NAE m IHP o MCO r f d S e LP d EI u NR l NT 0 0 c A x HO e CT e b S y L a .E m ON N NN t O A n I LH 2 2 e T AC m A T n T OF i N TO a 7 E t 1 M n 2 U L o R A c t T N e 1 S LO e n N EI d i 3 b I NT i NCT M M s a 4 G ANS n c E N HUE i I CFT t L B R d a O e A T t d T I N a e 7 N O c r 1 O I o 2 i M T l u LA ) ) q t N ER 1 I s e e O NB ( ( t r n R NI R R n i T AL e t b U HA n 7 o a E CC o 1 n c N p 2 m s o o t i t L c e E ) ) n e y NK 4 4 l i t l NC ( ( e b a n AE M M n a r o HH / / n C CC D D a e s h t g e c a n i a l n l d r p o x l e p r u a r e a t l i c u F d u r k q u c e n. N n aN e o e o O r s h r sI c e t rT t d g u oA u n l n e tR o a e a N cB d n R eI a e n tL e t a e et e eA r a h T t a g dC i c I aR n e d a nL n e y N i U dd R e oE o m l en t rN r h L ma ea tN y e t A r cR uA l t n N ex r eH n n o O t u ud NC O I M I nl on T I F Sa S C E N T ) ) ) ) 1 2 3 4 O U 2 N ( ( ( ( F 1 's A '" E N 'EZm aiA s >
g.. l ~ -t (: TABLE'4.3-2 s-s. ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATION Deleted j l s ? l< u } I i ) THREE MILE ISLAND - UNIT 2 4.3-3 0084P
Y T I L 0 8 5 5 1 1 I 1 BA e e e e e e C t t t t t t I o o o e o o L N N N N N N PPA S T N EM SE E MLL J EB R MNA 1 1 1 1 1 1 I U I NR Q NAE E I HP R MCO E CN A L L A L N I LO E EI V NT R NCT N W M M M N U ANS S HUL 3 CFT NO 3 I T 4 A N T O E N I L E T B M LA AT U ER A A A R NB S S R R R S T NI S AL N HA I CC G N I R L O E T NK I NC N AE D D D D D D O HH M CC NO I T ) A ) I 3 ) s D 4 e A S y 0 t R M t X o A G ) i I n ( r N B v ( ) i 3 r y g o I 1 ns t D 2 t t r O o ir i L 2 i c o X f do n I v A t I i i ( s o o USR 1 1 D M BRP t e n e u OH c t o r g Bt t GT A a M o a n n NI r l S t p T T d re d e IN o s u R s i I N e om e V LO u c O s n g T e o n N E t t p t DMA o i U M e ci e E N 1 e t I c M i C AT2 s r N o d w N l au l L I e eq e A HS2 a a O r a e o A A D RE D C U - G P M P e t l N T LAR r e lo A. O N EHP S le f D UXH O I T C a b c d FE( a b S a b D e C e N S U F 1 2 3 4 ( M A 2 =",r g"2g h= 4 m a,
YT I L 1 1 1 4 I 1 1 1 1 1 BA e e e e e C t t t t t I o o o o o L N N N N N PPA ST N EM SE E MLL R J EB MNA 1 1 1 1 1 I U INR Q NAE E I HP R MCO E C N A L L A L N I LO E EI ) d V NT R NCT H H H W H t U ANS n S HUE o CFT N C O ( I T 3 A N T O N I '3 E T M LA 4 U ER A R NB R R R S R EL T NI B S AL N HA A I CC T G N I R L O E T NK I NC N AE D D D D D O HH M CC MO I T a A e ) r s I D A e t AR r r r e o o o G o g N t t N t a i i I i r r L n n D n r or o A o o L o DY o t o f N M M I M NT t St i s G A U AI i C y y B y L n N gn e t t t GI o I no g NC M D iM a G R i "A i i IA L t p l N l E l T F a a I a LF t I t y I S c c L c D s U it g NG u B Fi n DY L N N i i i U A t O t NA t AN a l i i HI h R d a w AB O R i i L T r P r H r G x O nc o A C C K C EA E T Ei l N L L LC TK C t lo O E E EU SC A i E .r f AA UR U I U T F a F a FT a WP a R aC e C e N S U F 5 6 7 8 9 ( I E"' 3 2 "r 6* b~ w . e =
TABLE 4.3-3 (Cont'd) l RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES: J 1. During operation of the monitored system. 2. If monitor becomes inoperable, repair or replace by equivalent equipment within 24 hours. If not completed within 24 hours terminate operation of I the monitored system and restore the inoperable monitor (s) to operable status. 3. Deleted 4. If lon exchange effluent monitor is inoperable, sample on 4 hour frequency for gross beta. If inoperable longer than 24 hourc then terminate operation of ion exchange system and restore the inoperable monitor to operable status. 5. Hodes I and 2 with radioactive waste in the. fuel handling building. 6. With the required instrumentation inoperable, suspend all operations involving movement of radioactive waste in the fuel handling building; restore the inoperable equipment to OPERABLE status within 48 hours. 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. 8. Mode 1, during operation of the monitored system. 9. Two filter trains and associated monitors are normally available. If one monitor becomes inoperable, discontinue operation through the effected filter train and transfer operations to the operable filter train. If both monitors become inoperable, repair or replace by equivalent 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, terniinate operation of the system until at least one monitor is returned to operable status. 10. With both reactor building equipment hatch airlock doors open simultaneously. THREE MILE ISLAND - UNIT 2 4.3-6 0084P
h. TABLE 4.3-3 (Cont'd) RADIAT!ON MONZTORING INSTRUMENTATION,5URVEILLANCF RE00MEMENTS , NOTES: (Cont'd)
~~11. During either of the following operations, i~~
~~a. 1-iandling 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 materials. 13. With the required monitor inoperable, secure the ventilation system and suspend all operations involving movement of radioactive materials or j generation of airborne contamination until the inoperable monitor is restored to operable status. 14. During periods when personnel are in the containment and end fittings are being transferred to or stored in their designated location outside the Reactor Vessel. 15. With less than one channel operable, terminate the following operations: a. Handling of end fitting storage containers outside the Reactor Vessel.** b. Handling of any heavy load over the end fitting storage container area.
This shall not prohibit placing a canister in transit in a safe storage location.
This shall not prohibit placing an end fitting storage container in transit in a safe storage location.
THREE MILE ISLAND - UNIT 2 4.3-7 0084P
l SURVEILLANCE REOUfREMENTS METEOROLOGICAL INSTRUMENTATION \\ 4.3.3.4 Each of the meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5. ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION 4.3.3.5 Each of the Essential Parameters Monitoring Instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7. I CHLORINE DETECTION SYSTEMS 4.3.3.7 Each chlorine detection system shall te demonstrated OPERABLE by performance of a. CHANNEL CHECX at least once per 24 hours, and a CHANNEL l j. FUNCTIONAL TEST at least once per 31 days. At least once per IB months, the following inspections and maintenance shall be performed: a. Check constant head bottle level and refill as necessary, l-b. Clean the sensing cells, l c. Check flow meter operation and clean or replace filters and air lines as l necessary, d. Check air pump for proper operation, and e. Verify that the detector responds to HCL. THREE MILE ISLAND - UNIT 2 4.3-8 0084?
TABLE 4.3-5 M_ METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MINIMUM CHANNEL CHANNEL i INSTRUMENT OPERABLE CHECK CALIBRATION 1.- MIND SPEED a. Nominal Elev. 100 ft. 1 0-SA 2. WIND DIRECTION a. Nominal Elev. 100 ft. I D SA 3. AIR TEMPERATURE - DELTA T a. Nominal Elev. 33. ft. 1 D SA b. Nominal Elev. 150 ft. 1 D SA-THREE MILE ISLAND - UNIT 2 4.3-9 0084P
ES r MLL ) e m UBE 2 n o MAN ( e r G f a IRN 2 1 1 NEA / IPH 1 d n MOC e i p d o u s S h l t T N S c l r x u EM o t e s n e E m gre m e r R ) o dom o b I u o t S om l U ( R o Bt r R y a Q N o st a h E m T TO R l es l l R UI o oWn o OT re r I r A t Ct E C DA tl t a t N n N AC nb net n e re EO oa oro o m om AL RL CC CAH C n L ia Bi I t E n ,q V o Ae N R ) O c U s I I S e t s ( T LA d ni N ih ER A A i O NB R S R N s ot I NI n P T A AL i 7 T HA 6f N CC d 0s e 1 i 3 E t M a 1 a 4 U c T s R o L E T C E l L S B N NK R s NC A A s A I T AE D N D N t ro G HH n ot N CC en I o st R p ee O a. m l d T o p 4 I c ue N or 1 O l cu M l e ot 6 e n m S R 4 v n rr e a ee E T n l L h h p E o e c t 8 v k 8 8 i M t e n l et A l r 3 3 3 S L a R a a o C T c A 4 R r 4 4 cl i P f /s e e l d nb e sr t g e e e n i i L aN eo a a v l l c l A e b l t W r e b b O f I T p a pc o L a a sI op N S T ue g t T T rT ot n S r oA n E o o o tR o o o ce i S t t oD d r t t t cB iw S l e a eI tt m E i t r d d tL a d d re e e er u a e e e eA nf r r h u B W n r r dC i r r Tt e r r b e e a r d G e e rL m T f f er o e f f aE o N s s re t t m s s eN c E n n op c a a n n l N M a a cm a r e a a cA yn U r r ne e o t r r uH ni R T T IT R B S T T S NC A T E S TO N I 1 2 3 4 S 6 7 8 N 2 1 I 5 ] = m g $ [_5aN a, E5
t ES c ) ) ) a MLL e BE I I 1 MAN R ( ( ( IRN 2 2 2 e NEA IPH h t MOC y-an di g ) ) n ) g I I i I d ne eb ( ( l ( l S m md mB v T ) o on o ey N S o oa or Sa E ( R RH R o m M N t l l l l c .t E TO R UI o oe oa eu re po I OT r ru U DA t tF g tR id Q AC n n d n pa E EO o orl or e R RL C cob Co d r. n an F t o C si N t A l a L L N ec I ) O vin ed o E 1 I l ni V ( T i s R LA U ER A A A a i l v S NB S S S NI sae N AL aul 8 se O HA hit I CC 3 cV T u e A 4 s t T .o E N nym E L ol e B M inr A U L ) ) ) t o R E 1 1 1 T a y T NK ( ( ( S NC H H H cnbo i N AE / / / I HH D D D di r CC nt o a i G c, N l ig I ad n R uni O sid T i l I N vl iau O auB M s fi g L l E e ovn i V v t ol E e l std o L l l i n o e R r P v ssa E e l e neH T t e aL oi A a g n cl l W W a ar pe rl Ce ypu oe t aaF le t v ra m s Se eH er co s L f l e l s) en V er nd na, ue an nl g r Ft re al n T o a T hii N t tW p ced E c n l e vl e ee eri M a p "A ud nuu U e OsB R R S" F( T E S TO N I 1 2 3 N 1 YA]Fm E[ EU m
~~.9C~~
SURVEILLANCE REQUIREMENTS 4.3.3.8 FIRE DETECTION L 4.3.3.8.1 Each of the required fire detection instruments shall be demonstrated OPERABLC 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 i the detector alarms of each of the required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. 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 site-approved procedures. THREE MILE ISLAND - UNIT 2 4,3-12 0084P
TABLE 4.3-11 FIRE DETECTION INSTRUMENTS REQUIRED INSTRUMENT' LOCATION INSTRUMENTS OPERABLE ALTERNATE INSTRUMENT I NEAT FLAME SM0KE NEAT -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 NA NA 1 i 305', 293', 280' Elevations-NA NA 1 NA NA 7 j 3. Control Building Area NA NA 1 NA NA 13 4. Diesel Generator Building A Diesel NA 1 1 NA NA 1 B Diesel NA i 1 NA NA 1 5. Fuel Nandling Building NA NA 3 NA NA 1 6. Reactor Building NA NA 1 NA NA 1 RC-P-1A/2A NA NA 1 NA NA 2 RC-P-1B/2B NA NA 1 NA NA 2 7. River Water Pump Nouse 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 I 1 i l i 1 { THREE MILE ISLAND - UNIT 2 4.3-13 0084P
l SURVEILLANCE' REQUIREMENTS 1l 4.4~ REACTOR COOLANT SYSTEM 4.4.1 REACTOR COOLANT LOOPS 4g Deleted. 4.4.2 REACTOR VESSEL WATER LEVEL MONITORING The Reactor Vessel Water Level Monitoring Instrumentation shall be demonstrated OPERABLE as required by Table 4.3-8. 4.4.9 PRESSURE / TEMPERATURE LIMITS 4.4.9.1 REACTOR COOLANT SYSTEM 4.4.9.1.1. The pH of the reactor coolant shall be determined to be greater l than or equal to 7.5 and less than 8.4 at least once per 7 days. j 4.4.9.1.2 The chloride concentration in the reactor coolant shall be determined to be less than or equal to 5 ppm at least once per 7 days. a ) l I l 1 I 1 1 THREE MILE ISLAND - UNIT 2 4.4 1 0084P 4
SURVEILLANCE REQUIREMENTS 4.5 COMMUNICATIONS Verify that communications channels are OPERABLE between the Control Room or the Command Center and personnel in the Reactor Building once each day prior to the initiation of any activities involving CORE ALTERATIONS. Also verify that the additional SOL or 50L limited to fuel handling has OPERABLE communication channels once each day prior to the initiation of any activities ' involving core alterations. THRCE MILE ISLAND - UNIT 2 4.5-1 0084P
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~~.s. 'SURVEILObuTREOUIREMENTS' ) w. 1 4sidCONTAINMENT SYSTEMS .l 4.6,l ' PRIMARY CONTAINMENT ))A / ,a 1> s 4.6.1!1 CONTAINMENT INT _EGRITY-j~~
~~4. 6.1.1. a Primary CONTAINMENT INTEGRITY-shall be-demonstrated at-least once I~~
per 31 ' days. 4.6.hl.b. Modifications to Containment penetrations shall be che.cked dally bh .verifyingthatthepentrat16rfisclosedbyavalve,blindflangegor %q deactivated auton:atic valvej.tecured in its position.:' y3 s, CONTAINMENT}$0LAT10N 9' '; ;p N (.L r! w W j i + 4.6.1.2 ~ Prima'ry! CONTAINMENT ISOLATION shall be verified quarterly. Penetrations'which are closed by bolted or welded bl.ind flanges are not i required to'be surveilled. J Y.c. .,s. CONTAINMENT-AIR LOCKS (MODEil) 1 I. .w. t 4.6.1.3' Each ContahSent Air Lock shall be demonstrated OPERABLE: J H/
~~a..~~
After each opening, except.when'the' Air Lock'1s bei.ng used for multiple entries, then ataleast once per 72 hours, Ey,0terifying less than.or equal to 0.01 Ly seal,ileakage when the volume bet % en' the door seals is M stabilizeo to a pressure of 6.5 psig. li b. At least once M r'three months by performin $ mechanical operability check of each Air Lock, including a visual'Nnspection of the components and lubrication if necessary. ] ,/ j n .i e i 1 !;w i ) .I J J + { THREE MILE ISLAND - UNIT 2 4.6-1 o
S g,EILLANCE REQUIREMENTS CONTAINMENT AIR LOCKS (MODE 1) 4.6.1.3.1 When.both Equipment Hatch Personnel Airlock doors are opened simultaneously,. verify the following conditions: a. The capability exists to expeditiously close at least one Airlock door. b. The Airlock doors and containment purge are configured to restrict the outflow of air. During periods when both Airlock doors are open, the following activities will.be prohibited: 1. Core Alterations. 2. Heavy load lifts in the Reactor Building
3.
. Activities wich could result in a fire in the Reactor Building (e.g., welding, burning). c. The Air 1cck doors are cycled to ensure mechanical operability within seven days prior to opening both doors.
~~- This does not preclude completion of those activities necessary to place the plant in a safe configuration.~~
INTERNAL PRESSURE-4.6.1.4.a The primary Containment internal pressure shall be determined to be i within the limits at least once per 24 hours, except during periods when the Containment Building is open to the atmosphere. The instrumentation surveillance requirements are as follows: 1. Minimum Operable Channels 2 2. Channel Check' D 3. Channel Calibration R 4. Readout Location Control Room 4.6.1.4.b DurfngperiodswhentheContainmentBuildingisopentothe atmosphere, methods to ensure airflow into the Containment Building shall be implemented in accordance with approved procedures. The restrictions of 4.6.1.3.1.b,'"Contal.nment Airlocks (Mode 1)," and 4.6.1.6.1.b, " Containment Airlocks (Modes 2 and 3)," shall also apply. AIR TEMPERATURE 4.6.-l.5 The primary Containment average air temperature shall be the arithmetical average of the temperatures at the following locations and shall be determined at least once per 24 hours. Location a. RB nominal Elev. 350' (1 temperature indication) b. RB nominal Elev. 330' (1 temperature indication) c. RB nominal Elev. 305' (1 temperature indication) THREE MILE ISLAND - UNIT 2 4.6-2 j L
SURV2ILLANCE REQUIREMENTS P CONTAINMENT AIRLOCKS (MODES-2 AND 3)' L4.6.1.6 Each Containment Airlock shall be demonstrated OPERABLE: . a.. 'Aftereachopening...ifnotperformedwithinthelast72 hours,bs verifying-less than or equal.to 0.01 La seal leakage when the' volume between the door seals is stabilized to a pressure of 6.5 psig. 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. 4.6.1.6.1 'When both Equipment Hatch Personnel Airlock doors are opened simultaneously, verify the following conditions: .a. The capability exists to expeditiously close at least one Airlock door. l b. The Airlock doors and containment purge are configured to restrict the outflow of air in accordance with site-aporoved procedures. c. The Airlock doors are cycled to ensure mechanical operability within seven days prior to opening both doors. ' 4.6.3 CONTAINMENT VENTILATION CONTAINMENT PURGE EXHAUST SYSTEM - 4.6,3.1,The Containment Purge Exhaust system shall be deraonstrated OPERABLE: a. Prior.to system operation if not performed within the previous 31 days and thereafter at least once per 31 days'during operation by verifying that the Purge Exhaust System in the normal operating mode meets-the foilowing conditions: 1. . Filter Pressure Drop: the d/p across the combined HEPA filters shall not exceed 6 inches water gauge while the system is operating. b. Prior to system operation if not performed within the previous 18 months I and thereafter 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 j Regulatory Position C.5.a of Regulatory Guide 1.52, Revision 2, { March 1978. The inspection should be performed prior to the DOP j test of this section. 1 l ) l ) i i i THREE MILE ISLAND - UNIT 2 4.6-3 I \\ i
i SURVEILLANCE REQUIREMENTS CONTAINMENT PURGE EXHAUST SYSTEM (cont'd) 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 accordance with ANSI N510-1980, Section 8.3.1, paragraphs 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.5.c of Regulatory Guide 1.52, Revision 2, Mr ch 1978. l NOTE: Installed system flow instrumentation is adequate for the test described in Section 4.6.3.1.b.3 above. c. After 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 4 surveillance prescribed in Section 4.6.3.1.a.1 for the affected filter train (s). 2. DOP Test: Each affected filter train shall be retested in accordance with Section 4.6.3.1.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 eith Section 4.6.3.1.b.3. i i THREE MILE ISLAND - UNIT 2 4.6-4
~ SURVEILLANCE REQUIREMENTS
~~4.7 PLANT SYSTEMS 4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM l~~
'4.7.4.1 Deleted 4.7.6 FLOOD PROTECTION 4.7.6.1 The water level at the Unit 1 intake structure shall be determined to be within the limit by: l -a. Measurement at least once per 24 hours when the water level is below j elevation 301 feet Mean Sea Level USGS datum.. j b. Measurement at least once per 2 hours when the water level is equal to or above elevation 301 feet Mean Sea Level datum. 4.7.6.2 The dike' surrounding the island and the dike eresion protection shall be: q Inspected at least once per 6 months and within 31 days after every flood a. which exceeds 485,000 cfs at the Harrisburg gauge. This inspection shall include: 1. Dike slope and notation of any location where slope is steeper than 2:1. l 2. Depressions and notation of their size and location. 3. Stone degradation and notation of any areas uhere splitting, spalling or weatherir.g of stone appears excessive. 4. Vegetation and notation of location, quantity, and type. 5. Operability of inside and outside gates of the Southeast Drainage Culvert. 4.7.6.3 A Special Report shall be prepared and submitted to the Commission within 30 days if evidence of degradation is noted during an inspection. This report shall describe the extent and nature of the degradation and the plans and schedule for restoring the dike and :trrosion ' protection to a status equivalent to the original design provisions. I I THREE MILE ISLAND - UNIT 2 4.7-1 0084P
SURVEILLANCE REQUIREMENTS 4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM 4.7.7.1 The Control Room Emergency Air Cleanup System shall be demonstrated OPERABLE: a. At least once per 12 hours by verifying th'at the control room air temperature is less than or equal to 80*F. b. At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers 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. 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.S.c' and C.5.d* of Regulatory Guide 1.52, Revision 2, Match 1978, and the system flow rate is 14,350 cfm i 10%. 2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with 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 5% penetration maximum. 3. Verifying a system flow rate of 14,350 cfm i 10% during system operation when tested in accordance with ANSI N510-1980, Section 8.3.1 Paragraphs 3 and 4.
~~The prerequisites of Section 10.3 and 12.3 of ANSI-N510-1980 do not apply.~~
THREE MILE ISLAND - UNIT 2 4.7-2 0084P l
SURVEILLANCE REQUIREMENTS CONTROL ROOH EMERGENCY AIR Ct.EANUP SYSTEM (Cont'd) d. .After every 720 hours 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 Iodide, 30'C, 95% RH testing.per Table 5-1 of ANSI H509-1980 meets an acceptance criteria of 5% penetration ~ maximum. e. At least once per 18 months by: i 1. Verifying that the pressure drop across the combined HEPA filter 1 .and charcoal adsorber banks is less than 6 inches water gauge while i operating the system at a flow rate of 14,350 cfm g 10%. l l 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 water 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 l 99.95% of the DOP when they are tested in place in accordance with ANSI N510-1980* Section 10 while operating the system at a flow rate of 14,350 cfm i 10%. g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to l I 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980,* Section 12, while operating the system at a flow rate of 14,350 cfm 1 10%.
~~The prerequisites of Section 10.3 and 12.3 of ANSI-510-1980 do not apply.~~
1 THREE MILE ISLAND - UNIT 2 4.7-3 0084P
i SURVEILLANCE REQUIREMENTS 4.7.9 SEALED SOURCES 4.7.9.1 Test Reautreinents - Each sealed source shall be tested for leakage and/or contamination by: .a. The licensee, or b. Other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity'of at least 0.005 microcuries per test sample. 4.7.9.2 Test Frequencies - Each category of scaled sources shall be tested at the frequency described below. a. Source in use (excludina startup sources and fission detectors previously subjected to core flux, at least once per six months for all sealed sources containing radioactive material: 1. With a half-life greater than 30 days (excluding Hydrogen 3) and 2. In any form otner than gas, b. Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use. j c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to'being subjected to core flux or installed in the core and following repair or maintenance to the source. 4.7.9.3 Reports - A report shall be prepared and submitted te the Commission i on an annual basis if sealed source or fission detector leakage tests reveal the presence of 2 0.005 microcuries of removable contamination. L THREE MILE ISLAND - UNIT 2 4.7-4 0084P 1
SURVEILLANCE REQUIREMENTS 4.7.10 FIRE SUPPRESSION SYSTEMS l 4.7.10.1 -FIRE SUPPRESSION WATER SYSTEM l 4.7.10.1.1 The FIRE SUPPRESSION WATER SYSTEM shall be demonstrated OPERABLE: 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. c. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position. 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 2. Cycling each testable valve in the flow path through at least one complete cycle of full travel. e. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system (i.e., pumps start at set pressure 110 psig), and: 1. Verifying that each pump develops at least 2500 gpm 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 plant operation through at least one complete cycle of full travel, and 3. Verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure greater than or equal 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 4.7-5 0084P
. SURVEILLANCE REQUIREMENTS i FIRE SUPPRESSION WATER SYSTEM (Cont'd) 4.7.10.1.2 Each fire-pump diesel engine shall be demonstrated OPERABLE: a. At least once per 31 days by verifying; 1. Its associated fuel storage tank contains at least 250 gallons of fuel, and 2. The diesel starts from ambient conditions and operates for at least 20 minutes. b. At least once per 92 days by verifying that a sample of diesel fuel from each fuel storage tank, obtained in accoraance with ASTM-D270-65., is within tne acceptable limits specified in Table 1 of ASTM 0975-74 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 in conjunction with its manufacturer's recommendations for the class of service, and 2. Verifying each diesel starts from ambient conditions on the auto-start signal and operates for greater than or equal to 20 minutes while loaded with the fire pump. 4.7.10.1.3 Each fire pump diesel starting battery bank and charger shall be demonstrated OPERABLE: 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 i 2. The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material. j l 1 THREE MILE ISLAND - UNIT 2 4.7-6 j 0084P 1
SURVEILLANCE REQUIREMENTS 4.7.10.2' DELUGE / SPRINKLER SYSTEMS Each of the required deluge and/or sprickler systems shall De demonstrated OPERABLE: At least once per 12 months by cycling each testable valve in'the flow a. path through at least one ccniplete cycle of full travel. b. At least once per 18 months: ) ) 1. By performing a system' functional test which includes tripping detectors and verifying actuation of trip devites 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. 3. By visual inspection of the deluge headers to verify their integrity. 4. By visual inspettlon of each nozzle to verify no blockage. Atleasto(eper3yearsbyperforminganairorgasflowtestthrough c. each delugs header and verifying each deluge nozzle is unobstructed. 4.7.10.3 HALON SYSTEM 4.7.10.3.1 The Cable Room and Transformer Room Halon system shall be demonstrated OPERABLE at least once per 6 months by verifying each Halen storage tank weight and pressure. 4.7.10.3.2' The Air Intake Tunnel Halon System shall be demonstrated OPERABLE: At least once per 6 months by verifying pressure in each halon storage a. tank, and b. At least once per 18 months by verifying storage tank weight, i i THREE MILE ISLAND - UNIT 2 4.7-7 0084P i
- >. ! i q a j s ) ,i ,. jp ifi. 'EURVEill5NCE' REQUIREMENTS .] ? ~ t : FIRE HOSF STATIONS 1 7 -C7.10.4
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['i, .Each fire l hose, station, listed in Table 4.7-1 shall be verified OPERABLEP q p. +,. At-..least once per 31 days by visual'inspectio'n of!the station' tol assure. 4. .a.: ;all, required equipment is'at the station. f 1 7 'b. At least once per,18 months by: [ ,1..l Removir.g.the hose for inspection and re-racking, and t 'D, 2,- Replacement of all degraded gaskets'.in couplings, { c. At least once per-3 years by: i l. Partially opening each hose stat'lon valve to verify valve ) OPERABILITY and no flow blockage. t 2. Conductingahosehydrostatictestatapressureatleast50psig i greater than the maximum pressure available at that hose statton. ~ 4.7.11 PE,NETRATION FIRE _BAR3IERS The required (accestible per occupational exposure considerations) penetration H fire barriers shall be verified to be' functional: . a.- At least once per 16 months-by a visual inspection. 1 b '. Prior to returning a_per.etration fire barrier to functional status 1 following repairs or maintenar.ce by performance of a visual inspection of m .the affected penetration fire barrier (s). j l 1 1 t 'I ( l J l l 1 i e F THREE MILE ISLAND - UNIT 2 4-7.B 0084P i il
FIRE HOSE STATIONS t' Auxiliary Building l.- Fliehose near stairway at South end of building near Decay Heat Closed i Cooling Surge Tank, 328' elevation. l 2. ~ Fire hose near entrance to Chemical Addition area, 328' elevation. 3. Fire hose near Miscellaneous Haste Holdup Tank room, 305' elevation. 4. Fire hose near Intermediate Closed Coolers, 305' elevation. 5. Fire hose near Ev.aporator Condensate Test Tank Room, 280' elevation. 6. Fire hose near Reactor Building Emergency Cooling Booster Pumps, 280' elevation. Control Buildina Area 1. Fire hose near 480 Volt Bus 2-34 282'6" elevation. 2. Fire hose near ertrance to Service Building 282'6" elevation. Reacter ButirHng* 1.- Doleted. 2. Deleted. 3. Fire. hose near West stairway, 305' elevation 4 Fire hose near Southwest stairway, 305' elevation. 5. Fire hose on Fast 0-ring, 357' elevation. 6. Fire hose on West D-ring, 367' elevation. Cont'rol Buildinj 1. Fire hose near doorway on North wall, 305' elevation. 1 Fuel Handling Building 1. Fire hose on East wall, 347'6" elevation. l
Ftre hose stations in the Reactor Buildino shall be OPERABLE prior to initiating operations which generate combucible materials, and prior to initiating operations which involve the 'jse of open flames, welding, burning, j
grinding, etc. i THREE MILE ISLAND - UNIT 2 4,7-9 l 0084P i
11]RVEILLANCE REQUIREMENTS j 4.8 ELECTRICAL POWER SYSTEMS 4.8.1 A.C. SOURCES 4.8.1.1 Each of the required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability. 4.8.1.2 Deleted 4.8.1.3 Deleted l . I THREE MILE ISLAND - UNIT 2 4.8-1 0084P
l SURVEILLANCE' REQUIREMENTS l ONSITE POWER DISTRIBUTION SYSTEMS l: 4.8.2 { 4.8.2.1 A.C. DISTRIBUTION 4.8.2.1.1 The specified A.C. busses shall be determined ccrrect breaker alignment and indicated power availability. 4160 Volt Bus 2-lE, 2-2E, 2-3, and 2-4 480 Volt Bus 2-ilE, 2-12E, 2-21E, 2-22E, 2-32, 2-35, 2-36, 2-42, 2-45 and 2-46 The specified A.C. busses shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignment and indicated power 4.8.2.1.2 availability. 120 Volt A.C. Vital Bus 2-IV, 2-2V, 2-3V, and 2-4V 4.8.2.2 0.C. DISTRIBUTION l Each D.C. bus train shall be determined OPERABLE and energized with tie breakers open at least once per 7 days by verifying correct kreaker 4.8.2.2.1 alignment and indicated power availability. Each 250/125-volt battery bank and charger shall be demonstrated 4.8.2.2.2 OPERABLE: At least once per 7 days by verifying that: l a. The electrolyte level of each pilot cell is between the minimum and 1. max'imum level indication marks. The pilot cell specif'c gravity, corrected to 77'f and full electrolyte level, is greater than or equal to 1.20. 2. The pilot cell voltage is greater than or equal to 2.13 volts. 3. 250/125 The overall battery voltage is greater than or equal to 4.
~~volts, t~~
4.8-2 THREE MILE ISLAND - UNIT 2
~ 10RVEILLANCE REQUIREMENTS I D.C. DISTRIBUTION (Cont'd). I I .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 1 from the value observed during the original acceptance test. j 4 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. J 1 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: i 1. The cells, cell plates and battery racks show no visual indication of physical damage or deterioration. - 2. The cell-to-cell and terminal connections are clean, tight and coated with anti-corrosion material. THREE HILE ISLAND - UNIT 2 4.8-3 0084P
SURVEILLANCE RF0HfREMENTS l '4. 9 LIQUID RADWASTE STORAGE - SPENT FUEL STORAGE POOL"A" NATER LEVEL MONITORING '4.9.1 The Spent Fuel Storage Pool "A" water level monitoring instrumentation .shall be demonstrated OPERABLE as required by Table 4.3-8. l 4.9.2 Pool "A" water level is between elevations 326'-10" and 328'-01 FUEL TRANSFER CANAL MATER LEVEL MONITORING '4.9.3 The Fuel Transfer Canal (deep end) water level monitoring Instrumentation shall be demonstrated OPERABLE as required by Table 4.3-8. I. 4.9.4 (deep end). water level is between elevations 326'-10" and 328 4.9.12 FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SY 4.9.12.1 demonstrated OPERABLE:The Fuel Handling Building Air Cleanup Exhaust System sh At least once per 31 days by verifying that the Air Cleanup Exhaust a. System in the normal operating mode meets the following conditions: 1. Deleted 2. Filter Pressure Drop: The d/p across the combined HEPA filters and charcoal adsorbers shall not exceed 6 inches wkter 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 building openings to achieve the required value. l l ) THREE MILE ISLAND - UNIT 2 4.9-1 0084P i h .___m___.1-___
F SURVEILLANCE RF0HIREMENTS' b. At.least'once per 18 months by veriff ng'that the ventilation system i meets the following conditions:. 1. Visually inspect each filter train and associated components in } accordance with Section 5 of ANSI M510-1980, as required by ) Regulatory Position C.5.a of Regulatory Guide 1.52, Revision 2, j March 1978. The inspection should be performed prior to the flow. and DOP 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 accordance with-ANSI N510-1980, 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 trainLbeing tested shall be as prescribed for the flow test in Svetion 4.9.12.1.8.2 above. NOTE: Installed system ficw instrumentation is adequate for the test described in 4.9.12.1.B.3 above. 4. Fuel Handling Building Pressure: Demonstrate that the system is j 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 coors and r other building 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 housings, or following fire or chemical release in any ventilation zone . communicating with the system by verifying that the ventilation system j meets the following conditions: 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 i survelliance prescribed in Section 4.9.12.1.A.2 for the affected I filter train (s). 3. DOP Test: Each affected filter train shall be retested in accordance with Section 4.9.12.1.B.3. I l lI THREE MILE ISLAND - UNIT 2 4.9-2 0084P i:
SURVEILLANCE ' REQUIREMENTS d. After each complete or partial replacement of a HEPA filter bank by. verifying that the ventilation system meets the following conditions: 1. 00P Test: Each affected . iter train shall be retested in. accordance with Section 4.9.12.1.B.3. e, At least once per 24 hours by checking a d/p alarm or d/p indication. NOTE: Supply fans may be operated as desired except that the number of operating supply fans shall not exceed the number of operating exhaust fans. 4.9.12.'2 The Auxiliary Building Air Cleanup Exhaust System shall be demonstrated OPERABLE: a. 'At least cace per 31 days by verifying that the air cleanup exhaust system in the normal operating mode meets the following conditions: 1. Deleted 2. Filter Pressure Drop: The d/p across the combined HEPA filters and charcoal adsorbers shall not exceed 6 inches water gauge. ~ 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, g 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 shoula be performed prior to the flow and 00P 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 one exhaust ran operating. Testing shall be in accordance with ANSI N510-1980, Section 8.3.1, Paragraphs 3 and 4. l i THREE MILE ISLAND - UNIT 2 4.9-3 0229P E --- --
SURVEILLANCE RE00fREMENTS 3. DOP 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 3 J through the filter train being tested shall be as prescribed for the flow 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. Auxillary Building Pressure: Demonstrate that the system is ccpable of achieving a negative pressure within the building equal to or greater (more negative) than 1/8 inch water gauge with l respect to atmospheric. It may be necessary to close doors and other building openings to achieve the required value. A test i instrument, such as an inclined manometer or equivalent, shall be used in the performance of this test. After structural maintenance of the HEPA filter or charcoal adsorber housing,.or following fire or chemical release in any ventilation zone { c. 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. l 2. Filter Pressure Drop: Reverify the filter pressure drop I surveillance prescribed in Section 4.9.12.2.a.2 for the affected filter train (s). l 3. DOP Test: Each affected filter train shall be retested in accordance with Section 4.9.12.2.b.3. d. After each complete or partial replacement of a HEPA filter bank by verifying that the ventil4 tion system meets the following conditions: l I 1. DOP Test: Each affected filter train shall be retested in accordance with Section 4.9.12.2.b.3. l l At least once per 24 hours by checking a d/p alarm or d/p indication. l e. 1 I NOTE: Supply fans may be operated as desired except that the number of operating supply fans shall not exceed the number of operating exhaust fans. THREE MILE ISLAND - UNIT 2 4.9-4 0229P .}}

ML20236H576

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