ML20236M151

Proposed Tech Specs,Consisting of Tech Spec Change Request 173,removing Radiological Environ Monitoring Program from Tech Specs

ML20236M151
Person / Time
Site:	Three Mile Island
Issue date:	11/09/1987
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20236M147	List: ML20236M144 ML20236M151 ML20236M162 ML20236M205
References
NUDOCS 8711120108
Download: ML20236M151 (8)

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, . TABLE OF CONTENTS Section ,. Page 3.16 SHOCK SUPPRESSORS (SNUBBERS) 3-63 3.17 REACTOR BUILDING AIR TEMPERATURE- 3-80 3.18 FIRE PROTECTION 3-86 3.18.1 FIRE DETECTION INSTRUMENTATION '

3-86 '

3.18.2 FIRE SUPPRESSION WATER SYSTEM 3-88 3.18.3 DELUGE / SPRINKLER SYSTEMS 3-89 3.18.4 CO2 SYSTEM -

3-90 3.18.5 HALON SYSTEMS 3-91 ,

3.18.6 FIRE HOSE. STATIONS 3-92 3.18.7 FIRE BARRIER PENETRATION SEALS 3-94 , ,

3.19 CONTAINMENT SYSTEMS 3-95 3.20 3PECIAL TEST EXCEPTIONS 3-95a-3.20.1 , LOW POWER NATURAL CIRCULATION TEST 3-95a

, 3.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION 3-96 3.21.1 '

RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-96 3.21 .2 ]

RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT 3-100 '#)

MONITORING INSTRUMENTATION ,  !

3.22 RADI0 ACTIVE EFFLUENTS~ i 3-106 3.22.1 LIQUID EFFLUENTS 3-106 3.22.2 GASE0US EFFLUENTS 3-111 3.22.3 SOLID RADI0 ACTIVE WASTE 3-118 3.22.4 TOTA.L D03E 3-119 i  !

4 SURVEILLANCE STANDARDS -

4 4-1 4.1 OPERATIONAL SAFETY REVIEW 4-1 4.2 REACTOR COOLANT SYSTEM INSERVICE INSPECTION 4-11 4.3 TESTING FOLLOWING OPENING OF SYSTEM 4-28 1 4.4 REACT 0if BUILDING , 4-29 4.4.1 ~'~~ TOM 7AINMENT LEAKAGE TESTS 4-29 4.4.2 '

STRUCTURAL INTEGRITY 4-35 4.4.3 DELETED . 4-37 ,

4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, 4-39 EMERGENCY CORE C00 LING'5YSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 EMERGENCY LOADING SEQUE%CE 4-39 4.5.2 EMERGENCY CORE COOLING SYSTEM t 4-41 4.5.3 REACTOR BUILDING COOLING AND ISOLATION SYSTEM 4-43 4.5.4 DECAY HEAT REMOVAL SYSTEM LEAKAGE 4-45 4.6 EMERGENCY POWEP O *r.M OERIODIC TESTS 4-46' 4.7 REACTOR CONTRf1'%" T5 TEM TESTS 4-48 4.7.1 ' CONTROL RDI M Y SYSTEM FUNCTIONAL TESTS 4-48 4.7.2 CONTROL R0r;4 ' ARAM VERIFICATION '

4-50 l 871112010e e71109 PDR ADOCK 05000289  ;

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Amendment 72, 81, 108, 129 +

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TABLE OF CONTENTS Section Page 4.8 MAIN STEAh ISOLATION VALVES 4 -51

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4.9 DECAY H7 N.~AETAPABILITY - PERIODIC TESTING 4-52 4.9.1

• EMERGEIETTVE0 WATER SYSTEM - PERIODIC TESTING ' 4-52  ;

(REACTOR 000LANT TEMPERATURE GREATER THAN 250*F',"

4.9.2 DECAY HEAT REMOVAL CAPAPJIITY - PERIODIC TE. STING 4-52a (REACTOR COOLANT TEMPERATURE 250*F OR LESS) 4.10 REACTIVITY AN0MALIES 4-53 j 4.11 REACTOR COOLANT SYSTEM VENTS 4-54 4.12 AIR TREATMENT SYSTEMS 4 4-55 4.12.1 EMERGENCY CONTROL P00M AIR TREATMENT SYSTEM 4-55 4.12 2 . REA0 TOR BUILDING PURGE AIR TREATMENT SYSTEM 4-55b 4.12.3 AUXILIARY & FUEL HANDLING EXHAUST AIR TREATMENT SYSTEM 4-55d i 4.12.4 FUEL HANDLING BUILDING ESF AIR TREATMENT SYSTEM 4-55f 4.13 '

RADI0 ACTIVE MATERIALS SOURCES SURVEILLANCE 4-56 4.14 DELE TED 4-56 l 4.15 MAIN STEAM SYSTEM INSERVICE INSPECTION 4-58 , I 4.16 REACTOR INTERNALS VENT VALVES SURVEILLANCE 4-59  ;

4.17 3H'OCK SUPPRESSORS (SNUBBERS) 4-60 )

4.18 FIRE PROTECTION SYSTEMS 4-72 l 4.18.1 FIRE PROTECTION INSTRUMENTS 4-72 j l 4.18.2 FIRE SUPPRESSION WATER SYSTEM 4-73

, 4.18.3 DELUGE / SPRINKLER SYSTEM . 4-74 4.18.4 CO2 SYSTEM ,

4-74 4.18.5 HALON SYSTEMS 4-75 4.18.6 HOSE STATIONS 4-76 4.18.7 FIRE BARRIER PENETRATION SEALS 4-76a 1 l 4.19 OTSG TUBE INSERVICE INSPECTION 4-77  !

4.19.1 STEAM GENERATOR SAMPLE SELECTION & INSPECTION METHODS 4-77 l 4.19.2 STEAM GENERATOR TUBE SAMPLE SELECTION & INSPECTION 4-77 i' 4.19.3 INSPECTION FREQUENCIES 4-79 4.19.4 ACCEPTANCE CRITERIA 4-80 4.19.5 REPORTS 4-81 4.20 REACTOR BUILDING AIR TEMPERATURE 4-86 4.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION 4-87 4.21.1 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 4-87 4.21 .2 RADI0 ACTIVE GASEOUS PROCESS & EFFLUENT MONITORING 4-90 INSTRUMENTATION 4.22 RADIOACTIVE EFFLUENTS 4-97 4.22.1 LIQUID EFFLUENTS 4-97 4.22.2 GASEOUS EFFLUENTS 4-105 4.22.3 SOLID RADI0 ACTIVE WASTE 4-115 4.22.4 TOTAL DOSE 4-116 i

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-iv-Amendment No. 11, 28, 30, 41, 47, 55,,72, 78, 95, 97, 119, 122, 129 L__

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TABLE OF CONTENTS Section Page 5 DESIGN FEATURES 5-1 S.1 SITE- 5-1 5.2 YUNTAINMENT 5-2 5.2.1 REACTOR BUILDING 5-2 5.2.2 REACTOR BUILDING ISOLATION SYSTEM 5-3 i 5.3 REACTOR

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5-4 5.3.1 REACTOR CORE 5-4 5.3.2 REACTOR COOLANT SYSTEM 5-4 ,

5.4 NEW AND SPENT FUEL STORAGE FACILITIES 5-6' I 5.4.1 NEW FUEL STORAGE 5-6 5.4.2 SPENT FUEL STORAGE , 5-6 i

5.5 AIR INTAKE TUNNEL FIRE PROTECTION SYSTEMS 5-8 l 6 ADMINISTRATIVE CONTROLS 6-1 l t

6.l' RESPONSIBILITY 6-1 6.2 ~0 ORGANIZATION- 6-1 l 6.2.1 CORPORATE 6-1 l 6. 2 .'2 UNIT STAFF 6-1 6.3 UNIT STAFF QUALIFICATIONS 6-3 >

6.4 1 RAINING ,

6-3 6.5 REVIEW AND AUDIT 6-3 6.5.1 TECHNICAL REVIEW AND CONTROL 6-4 6.5.2 INDEPENDENT SAFETY REVIEW 6-5. l

, 6.5.3 AUDITS 6-7 6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP 6-8 6.6 REPORTABLE EVENT ACTION 6-10 6.7 SAFETY LIMIT VIOLATION 6-10 6.8 PROCEDURES 6-11 6.9 REPORTING REQUIREMENTS 6-12 l

6. 9.1 ROUTINE REPORTS 6-12 l 6.9.2 DE'LETED .

6-14 6.9.3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6-17 6.9.4 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6-18 6.10 RECORD RETENTION 6-19 6.11 RADIATION PROTECTION PROGRAM 6 -21 6.12 HIGH RADIATION AREA 6-21 6.13 FT<DCESS CONTROL PROGRAM 6-21 6.14 DFFSITE DOSE CALCULATION MANUAL (0DCM) 6-22 0.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 6-22 6.16 POST ACCIDENT SAMPLING PROGRAMS 6-22a NUREG-0737 (II B.3', II.F.1.2)  ;

6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS 6-23 l

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-v-Amendment No. 11, 47, 72, 77, 129

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LIST OF TA'BLES: -

, n, TABLE < TITLE "f PAGEc 1.2: Frequency Notation a 11-8' <

2. 3-1 s ReactorLProtection . System Trip Setting; Limits: ,

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3.1. 6.1 = Pressure :IsolationL Check 1Yalves Between the Primary : ' "

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' Coolant' System and LPISc l 0

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3. 5-1 . Instruments Operating-Conditions. ,

3-291 3.5-2' Accident Monitoring [nstruments >

3-'40c 3.5 -

Post Accident Monitoring Instrumentation

[40d'.

3.18 Fire Deteetion Instruments . 3-87i, P 3.21 -l' Radioactive Liquid-Effluent Monitoring Instrumentation.. 3-97c 3 . 21 -2 Radioactive Liquid Ef. fluent' Monitoring-Instrumentation 2

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4.1 -1 Instrument Surveillance ~e s' Requirements <

114 - 3 4 4.1 -2. Minimum Equipment Test Frequency. L4-8i 4.1 -3 Minimum Sampling' Frequency 1 .4-9 4.1 -4 Post Accident Monitoring Instrumentation'.

L4-10a -

4.19-1 Minimum Number of Steam Generators to be. <

I4284- <

Inspected.During Inserviceilnspection:

-4.19-2 ~ Steam Generator Tube Inspection! -

4-85 4.21 -1 Radioactive Liquid Effluent Monitoring 1. . '

'4'-88 ~- g Instrumentation' Surveillance Requirements' H

4.21 -2 Radioactive Gas'eous Effluent Monitoringi c4 91 Instrumentation. Surveillance Requirements:

4.22-1 Radioactive Liquid Waste Sampling & Analysis Program f 4-.98 ;. + .i 4.22-2 Radioactive Gaseous Waste Sampling 8 Analysis Program 4-1061

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q Amendment No.'59, 72,.100, 106, 118 _

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REP 0;PT* ,.

6. 9. 3.1 Routine Radiological Environmental Operating' R$ pore 3 / overikthe ,

operation of the unit during the previous calendar y3Mr eh411 t

'" be Y submitted prior to May 1 of each year. 4 c 6.9.3.2 The Annual Radiological EnWonmental Operating Reports shalk 1. ,

include summaries, interp'retations, and an analysis of trends of '1 the results of. the radiological environmental surveillance ,

activities for the report period, including a comparison with

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preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. N ,5 '

The reports shall i.lso include the results of the land use censuses A 7

required by the Radiological Envibrmental Monitoring Program t T

Y l7 (REMP).

i The Annual Radiological Environmental Operating Reports shall include summarized and tabulated analysis resso of the g l I ~-

radiological environmental samples and environmental radiation i measurements required by the REMP taken during' t(b'$eriod. The '\

available sampling locations are specified\in the Table and Figurrd., '

in the ODCM. The format shall be aimilar to the Radio'fogica'i

( , z Assessment Branch Technical Posittu. Revision 1, November 1979 o i

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In the event that some results are 'not available for inclusion wi@

the report, the report shall be submittid noting and explainirQ tt.e reasons for'the missing results. The missing data shall be , >t 'S submit 9d as soon as possible in a supple,Rentary report. ,

a The reports shall also include the following; a surmiary N P description of the radiological environmentalsmonitoring program; a map (s) of all sampling locations keyed to a taole giving distances and directions from a point that is midway between the Reactor Buildings of TMI-l and TMI-2; and the results of ifcensee _

participation in the Interlaboratory Comparison Program; discussion of all deviations' from the sampling schedule required'by ,th REMP; discussion of all required analyses in which the LLD required by '

the REMP was not achievable. ,

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The report of changes to the REMP are required p'uesua'n t, to #

i3 Technical Specification 6.15, 1

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• A single submittal may be made for the statick.1 I'

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l Amendment No. 59, 64, 72, 77, 108, 117, 129

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.c The Radioactive Effluent ReleaseLReports shal1[ include th'e"" ,, _ MI 1'

folloying information for each; type off solid wasteiship~ pedi , ( y loysitedu' ring'te.reportperiod:- >

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'4 I',, ,[' 4,;r- %g JA l. ' = b.~U J]deasurementforf estimate), total curie- quantity (spectfy wheth y ,fl 4 >

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c. principal tradionuclidesl('speci.fyJ whether determiped Lby) #, d

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measurement or "estihte); t

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w- W ,4 kl 9-di ?typejof waste :(e.g., , spent resin;; compact' ed fdry, waste, , I evaporator. bottoms)i e ,

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type of ~contaher (e.g. ,iLSA' Type- AZType B, Largei j Q;;

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Quantityl and ,

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,q g a :f. solidification.agentle.g.',Jcement,; urea l formal hydeD d TheuRadioactiveiEffluent Release ~ Reports shalljinclude ab 1

.spliar.y of unplanned releasesifrom;theisite-to unrestricted

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'g L j( e areas'of radioactive-materials intgaseous.and liquidieffluents? -]S

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y e y; made during the reporting period.

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The Radioactive Effluent; Release ~ Reports 7shall includelanyi

, ', f changes mad 4during .the' reporting period to the" Process ]H Control Pr'ogrA(PCP);and,to 1the Offsite' Dose Calculation.

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Nanual (ODCM), af.well as a listing of neWlocationsifor dose: ,d

, i calcu'lations fand/or- environmental (monitoring identified by: the; ,4 j 9 3Y

• Radiological Envi onmental : Monitoring' Program?(REPF),JlandLuse : 9 Census.

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lf [ Q 6.10 RECORD RETENTION-

. , , J 6.10.1 The following records shalt be retained for >at[least five; years: 4

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a. Records'of ' normal, station operation includin'g;p'ower le'vels and -

ld perio4,s of

# operation at each power 1. eve 1.; ' ' % -

" + ?q c4 at b', Records of pIincipal maintenance activities,iinciddingL . .

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l inspetqn . repairs, . substitution, or. replacementfoff principal; ,,

; items iyysipmentimportantto

safety. '

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b M. Records'of pc adic checks,~ test'

,a4 s and calibrations]

t b( N y1 e. Records of reactor. physics tests _and!otherispecialt tests yj 1 ;j

-, 7y importantito safety. 7c ,Q h )

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, ' Clhngesgo operating 'proceduresLimportant: to safety. 4 <

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[ga, / g. Records efcsolid radioactive shipmentsh M/ : h[

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c. documentation that -the changes have been reviewed and .

approved pursuant-to 6.8.2. i

2. Shall bc.come effective upon review and approval by GPUNC Management,

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j 6.14 0FFSITE DOSE CALCULATION MANUAL-(0DCM) 6.14'.1 The ODCM shall .be' approved by the Commission prior to implementation.

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6.14.2 GPU Nuclear . Corporation. initiated ' changes .to~ the ODCM:- I 1.- Shall be' submitted to the NRC in the Semiannual' Radioactive .

Effluent Release Report for the period in which the changes were l

'made. -This submittal shall contain: .:

a. .sufficiently? detailed information .to justify the changes without benefit of additional or supplemental information;

b. a determination that~the changes-did not reduce the. accuracy or reliability of dose ' calculations or setp'oint determinations;'and

c. documentation that the changes have'been. reviewed and approved pursuant to 6.8.2.

2. Shall become effective upon review and approval by GPUNC i Management.

6.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 6.15.1 The initial REMP shall be approved by the Commission prior to l implementation.

6.15.2 Changes to'the REMP after removal from the Technical Specifications shall be as follows:

1. Changes that reduce the effectivess of this initially approved T.MP shall be submitted to the NRC for review and approval prior -

to implementa?. ion.

2. Changes that do not reduce the effectiveness of the initially approved REMP shal1 ~ be reviewed and approved by GPUN consistent .

with controlled procedure pract :e. The results of these changes shall be submitted to the NRC in the Annual Radiological Environmental Operating Report for. the period in which the.

hanges were made. This submittal shall contain sufficiently Atailed information to justify the changes without benefit of ada.'tional or supplemental information. '

These changes- shall become-effective upon review and approval by q GPUNC Management.

6-22 l

Amendment No. 72, 77, 102 1 q

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'j s . 6.16 -POSTJACCIDENT SA> FLING PROGRAMS - NUREG 0737 (II.B.3, II.F.1.2)

Programs which will'. ensure the capability 'to adcurately sample. and . .R

. analyze vital areas l under accident; conditions. have been implemented' .

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' l The followingl programs 'have been' established:L. ]

1.- . lod'ine. and = Particulate . Sampling '

2 .' Reactor. Coolant Sampling ,

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3. Containment Atmosphere: Sampling, Each program shall be maintained.and shall include lthe following:' q 1.. Training of personne1'

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2. ' Procedures, and l- 3. Provisions for maintenance of sampling and analysis equipment - 1 l

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Amendment No. 72, 77,102-e.