Text

Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural....
	ML20006F471
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	02/20/1990
From:	; LONG ISLAND LIGHTING CO.
To:	;
Shared Package
ML20006F468	List: ML20006F467; ML20006F470; ML20006F471; ML20006F488;
References
	GL-89-01, GL-89-1, NUDOCS 9002280064
	Download: ML20006F471 (150)
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- DEFINITIONS rp

. SECTION- .

DEFINITIONS (Continued) PAGE L-t

1. 25 . OFidTE DOSE CAICUIATION MANUAL (ODW) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 '

1.26 OPERABLE - OPERABILITY.............................................. 1-4 >

1-4

,. 1.27 OPERATIONAL CONDITION - CONDITION................................... .

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1.28 -PHYSICS TESTS....................................................... 1-4

, 1.29 PRESSURE BOUNDARY LEAKAGE........................................... 1 1130 PRIMARY CONTAINMENT INfDGRITY....................................... 1-5 1.31: PROCESS CONTROL PROGRAM ( PCP) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1,32 PURGE ' PURGING..................................................... 1-5 1.33 RATED THERMAL POWER................................................. 1-5 1.34 REACIOR PRCTTECTION SYSTD1 RESPONSE TIME. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5

-1.35 REPORPNBLE EVENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 i e

1.36 ROD DENSITY......................................................... 1-6

-1.37 SECONDARY 00NTAINMENT INTEGRITY..................................... 1-6 1.38 SHUTDOWN MARGIN..................................................... 1-6

.1.39 SITE BOUNDARY....................................................... 1-6 1.40 SOLIDIFICATION (NOT USED) ( REFER 'IO PCP) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 1

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3.41 SOURCE CHECK.........................................s.............. 1-6 1.42 STAGGERED TEST BASIS................................................ 1-7

~ 1'. 4 3 THERMAL POWER....................................................... 1-7 '

1.44 TURBINE BYPASS SYSTDi RESPONSE TIME................................. 1-7 l 1.45 UNIDENTIFIED LEAKAGE................................................ 1-7 1.46 UNRESTRICTED AREA................................................... 1-7 1.47 VENTIIATION EXHAUST TREA'IMENT SYSTDI. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1~. 4 8 VENTING.....,....................................................... 1-7 I :SHOREHAM - UNIT 1 11 f

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INDEX LIMITING CONDITIONS IOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION: PAGE 3/4.3 INSTRUMENTATIN . ,

'3/4.3.1 REACIOR Pfum?fION SYSTEM INSTRlNENTATION. . . . . . . . . . . . . . . . . . . . 3/4 3-1 3/4.3.2 ISOIATION ACIUATION INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-9 3/4 3.3' MERGENCY CORE COOLING SYSTEM ACTUATION INSTRININTATICN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-27

'3/4.3.4 RECIRCUIATION PlNP TRIP ACIUATION INSTRINENTATICN A' INS Recirculation Pump Trip System Instrumentation. . . . . . . . . . 3/4 3-36 End-of-Cycle Recirculation Pump Trip System Instrumentation......................................... 3/4 3-40~

3/4.3.5 REACIOR CORE ISO 1ATION COOLING SYSTEM ACTUATTON INSTRINENTATION......................................... 3/4 3-46 3/4.3.6 CONTROL ROD BII)CK INSTRlNENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-51

.3/4.3.7 MONI'IORING INSTRUMENTATION Radiation Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-57 -

Seismic Monitoring Instrumentation.......................... 3/4 3-62 Meteorological Monitoring Instrumentation................... 3/4 3-65 ;

Remote Shutdown Monitorina Instrumentation.................. 3/4 3-68 '

Accident Monitoring Instrumentation......................... 3/4 3-71 :

Source Range Monitors....................................... 3/4 3-75 Traversina In-Core Probe System............................. 3/4 3-76 Chloride Intrusion Monitors................................. 3/4 3-77 Fire Detection Instrumentation.............................. 3/4 3-81 Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation (NOT USED) (Refer to CD m)............. 3/4 3-84 Explosive Gas Monitoring Instrumentation................... 3/4 3-89

. Icose-Part Detection System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-94 4 Safety Parameter Display System............................. 3/4 3-95 Diesel Generator 3300 KW Alam. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-97 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM......................... 3/4 3-98 3/4.3.9 FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM ACIUATION INSTRINENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-100 i

SHOREHAM - UNIT 1 v

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INDEX.

{, . LIMITING 00NDITINS FOR OPERATION MD SURVEILIANCE REQUIRmENTS SECTION - PAGE 3/4.11 - RADIQACTIVE EFFLUENTS L

3/4.11.1 ' LIQUID EFFLUINTS s

Concentration (NCrr USED) (Refer to ODm) . . . . . . . . . . . . . . . . . . . . 3/4 11-1 Dose . (NOT USED) (Re fer to ODW) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 11 Liquid Radwaste Treatment System (NOT USED) (Refer to OD m). 3/4 11-6 Liquid Holdup Tanks.......................................... 3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS Dose' Rate (NCTI USED) (Refer to ODCN) . . . . . . . . . . . . . . . . . . . . . . . . . ' 3/4 11-8 Dose-Noble Gases (NOT USED) (Refer to ODCM) . . . . . . . . . . . . . . . . . . 3/4 11-12 Dose - Iodine 131, Iodine-133, Tritium and Radionuclides in Particulate Form (NOT USED) (Refer to ODCM).......... 3/4 11/13 E

Gaseous Radwaste Treatment System (NOT USED) (Refer to ODCM) . 3/4 11-14 l Ventilation Exhaust Treatment System -[

(NOT USED) (Refer to 0D 3)........................ 3/4 11-15 ;

Explosive Gas Mixture......................................... 3/4 11-16 ;

Main Condenser................................................ 3/4 11-17 Containment Purcing and Ventino (NOT USED) (Refer to ODCM)... 3/4 11-18 3/4.11.3 SOLID RADIO 1CTIVE WASTE (NOT USED) (Refer to PCP) . . . . . . . . . . . . 3/4 11-20 3/4.11.4 'IOIAL DOSE (NCff USID) (Refer to OD W)........................ 3/4 11 , 3/4.12 RADIGIDGICAL ENVIRONMENTAL MCNTIORING 3/4 12.1 MONI'IORING PROGRAM (NOT USED) (Refer to ODCM) . . . . . . . . . . . . . . . 3/4 12-1 3/4.12.2 LAND USE CENSUS , (NOT USED) (Refer to ODCM)................... 3/4 12-12 ,

3/4.12.3 INTERLABORNIORY CmPARISm PROGRAM (NCff USED) (Refer to OD m)......................... 3/4 12-13 SHOREHAM - UNIT 1 Xi 1

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SECTION PAGE INSTRt>DfrATION (Continued) 3/4.3.7J MUIUORING INSTRLNENTATION Radiation Monitoring Instrtmentation. . . . . . . . . . . . . . . . . . . . . B 3/4 3-4 Seismic Monitoring Instrumentation....................... B 3/4 3-4 x

Meteorological Monitoring Instrumentation................ B 3/4 3-4 Remote Shutdown Monitoring Instrumentation............... B 3/4 3-5 Accident Monitoring Instrtr1entation. . . . . . . . . . . . . . . . . . . . . . B 3/4 3-5 ,

Source Range Monitors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-5 Traversing In-Core Probe Systan. . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-5 Chloride Intrusion Monitors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-5 Fire Detection Instrtmentation. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-6 Radioactive Liquid and Gaseous Effluent Monitoring :

Instrumentation (NCff USED) (Refer to CDCN) . . . . . . . . . . B 3/4 3-6 !

Explosive Gas Monitoring Instrumentation. . . . . . . . . . . . . . . . . B 3/4 3-6 4

Loose-Part Detection System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-6 !

l Safety Parameter Display Systan. . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-7 3/4.3.8 TURBINE OVERSPEED PDOTECTICN SYSTIN. . . . . . . . . . . . . . . . . . . . . . B 3/4 3-7 '

3/4.3.9 FEEDWATER SYSTEN/ MAIN TURBINE TRIP SYSTEM AC7UATION INSTRINENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 /4 3-7 i 3/4.4 REACIOR COOLANT SYSTEM ,

1 3/4.4.1 RECIBCUIATION SYSTEN. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-1 I i

3/4.4.2 SAFETY /FM M VALVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-1 j 3/4.4.3 REACIOR COOIANP SYSTEM LEAKAGE Ieakaae Detection Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 l Operational Leakage...................................... B 3/4 4-2 ;

. 3/4.4.4 CHEMISTRY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 /4 4 -2 3/4'.4.5 SPECIFIC ACTIVITY........................................ B 3/4 4-3 i 3/4.4.6 PRESSURE / TEMPERA 7URE LIMITS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOIATION VALVES. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-5 3/4.4.9 RESIDUAL HEAT reb 0 VAL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . P 3/4 4-5 SHOREHAM - UNIT 1 xiii i

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SECTION' ' PAGE: - ,

'3/4.11 RADIGAC'TIVE ITFUHWrS 1 3/4.11.1 ' LIQUID EFTLUENTS Concentration (!ct USED) . (Refer to 0D3) . . . . . . . . . . . . . . . . ' B 3/4 11-1 Dose (NOT USED) (Refer to 0D3) . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-1

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Liquid Radweste Treatment System (NCYr USED) (Refer to 0DW) . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 .11-2 ,

Liquid Holdup Tanks..................................... B 3/4:11-2 4 3/4 11.2 GASBOUS ITFMENTS Dose Rate (tcT USED) (Refer to 0D W).................... B 3/4 11-2 Dose - Noble Gases (for USED) (Refer to 0D3) . . . . . . . . . . . B 3/4 ' 11-3 ,.

t Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form (for USED) (Refer to ODCN)..... B 3/4 11-3 Gaseous Radwaste Treatment System (tcr USED) . (Refer to 0D3) . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-4 Ventilation Exhaust Treatment System (for USED) ' (Refer to 0D3) . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-4

. D: plosive Gas Mixture. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.11-5 Main Candense:. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 /4 11-5 Contairrnent Purging and Ventino (ter USED) (Refer to 0D3) . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-5 o

3/4.11.3 SOLID RADIQACTIVE WASTE (NCfr USED) (Refer to PCP) . . . . . . . B 3/4 11-5 li 3/4.11.4 KfrAL DOSE (NOT USED) (Refer to OD W)................... B 3/4-11-5

[ 3/4.32- RADIOIOGICAL ENVIRONMD7fAL IGHORING 3/4.12.1 MmHORING PROGRAM (NCff USED) (Refer to OD W)........... B 3/4 12-1 I:

3/4.12.2 LAND USE CENSUS (NOT USED) (Refer to ODW) . . . . . . . . . . . . . . B 3/4 12-1 l

1 i 3/4.12.3 INTERLABORA'IORY CCNPARISW PROGRAM (tor USED) (Re fer to ODm) . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 12-2

.- SHOREITAM -- UNIT 1 xvii l

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MMINISTRATIVE CONTROIS SECTION PAGE NUCLEAR REVIEW BOARD (NPB) (Continued)

REVIH1...................................................... 6-10 AUDITS...................................................... 6-11 RE00RDS..................................................... 6-11

6. 6 - REPORTABLE EVENP ACTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 ..

'6.7 SAFETY LIMIT VIOIATI N........................................... 6-12 l 6_. 8 PROCEDURES AND PR0 GRAMS.......................................... 6-13

' _6 . 9 ' REPORTING REQUIRD4INTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14b-l 6.9.1 ROUTINE REPORTS............................................. 6-14b ;

STARTUP REIORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14b j ANNUAL REPORTS.............................................. 6-15 ANNUAL RADIOIOGICAL ENVIRONMENTAL OPERATING REIORT. . . . . . . . . . 6-15 SD4IANNUAL RADIOACTIVE EFFLUENP RELEASE REPORT. . . . . . . . . . . . . . 6-16 MONTHLY OPERATING REPORTS... 4.............................. 6-18 6.9.2 .SPECIAL REPORTJ............................................. 6-18 t 6 .10 RECDRD RETENTIN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18' 6.11' RADIATION PROTECTIm PROGRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-19 6.12 HIGH RADIATIm AREA.............................................. 6-20

' 6.13 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21 n'

! 6.14 OFFSITE DOSE CAICULATION MANUAL (0DG) . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21 1

6.15 MAJOR CHANGES 10 RADIOACTIVE LIQUID, GASEDUS, AND SOLID WASTE TREA1NENT SYSTENS ( NCYP US ED ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-22 SHOREHAM - UNIT 1 xx a ,

l INDFX LIST OF TABLES -(Continued)

TABIE PAGE

.L 4.3.7.4-1 RIM 7fE SHUTDOWN MNITORING INSTRUMENTATION SURVEIILANCE REQUIRDIEt7fS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-70 .

3.3.7.5 ACCIDENT FKNITORING INSTRUMEt7fATION. . . . . . . . . . . . . . . . . . . . 3/4 3-72 '

4.3.7.5-1 AOCIDE!7T MJNI70 RING INSTRUMDTTATION SURVEILIANCE REQUIRD5ENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-74 3.3.7.8-1 CMORIDE INTRUSION CONDUCTIVITY MONI70RS. . . . . . . . . . . . . . . 3/4 3-78 3.3.7.8-2 CHIDRIDE INTRUSION CONDUCTIVITY MONI'IOPS SLTPOINTS.............................................. 3/4 3-79

.4.3.7.8-1 CHIORIDE INTRUSIm CONDUCTIVITY FDNITORS SURVEILIANCE REQUIRDD7fs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3 3.3.7.9-1 FIRE DETECTION INSTRUMEt7TATION.......................... 3/4 3-82 ,

3.3.7.11-1 EXPIDSIVE GAS FDNI70 RING INSTR &!Et7fATION. . . . . . . . . . . . . . . 3/4 3-90 4.3.7.11-1 EXPIOSIVE GAS MONITORING ' INSTRUMENTATION SURVEIILANCE REQUIRDIENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-92 3.3.7.13-1 SAFEIY PAPNETER DISPLAY SYSTD!. . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-96 3.3.9-1 FEEDWATER SYSTD1/ MAIN TURBINE TRIP SYSTD1 AC7UATION INSTRG E7TATION.............................. 3/4 3-101

'3.3.9-2 FEEDWATER SYSTD1/ MAIN TURBINE TRIP SYSTDI AC7UATION INSTRUMENTATION SETPOINTS.................... 3/4 3-102 4.3.9.1-1 FEEDRATER SYSTD1/ MAIN TURBINE TRIP SYSTD1 AC7UATION INSTRUMEfffATION SURVEILLANCE REQUIRENDTfS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-103 3.4.3.2-1 REACIOR COOIANT SYSTD1 PRESSURE ISOIATION VALVES..... .. 3/4 4-12 1

3.4.4-1 REACIOR COOIIRT SYSTD1 CHD1ISTRY LIMITS . . . . . . . . . . . . . . . . 3/4 4-15 1 4.4.5-1 PRIMARY COOIANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM....................................... 3/4 4-18 SHOREHAM - UNIT 1 xxiv l l

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iLIST OF TAmTS '(Continued) -

TABLE PAGE i

4.4.6.1.3-1 REACIOR VESSEL MATERIAL SURVEILLANCE PROGRAM- .

< WITHDRAWAL SCHEDULE.................................... 3/4 4-22 ;

3.6.3-1 PRIMARY CONTAINMENT ISOIATION VALVES................... 3/4 6-23 ,

3.6.5.2-1 REACIOR BUILDING VINTIIATION SYSTEM AUIOMTIC ISOIATION VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-39

'3.7.7.5-1 FIRE HOSE STATIONS..................................... 3/4 7-30

-t 3.7.7.6 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE STATIONS.......................................... 3/4 7-33

.3.7.9-1 AREA TEMPERA'IURE M0NI'IORING. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-37 3.7.11.1-l' LIMITINC VALUES OF SETILDiINPS OF .'

i REACIOR BUILDING (RB).................................. 3/4 7-42

-4.8.1.1.2-1 DIESEL GENERA'IOR TEST SCHEDULE. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-8 4.8.2.1-1 BA'I'IERY SURVEILIANC'E REQUIRDIENTS. . . . . . . . . . . . . . . . . . . . . . . 3/4 8-12 3.8.4.1-1 4.16 kV PRIMARY CONTAINMENT PENLTRATION CONDUCIOR OVERCURRENT PIKnwnVE DEVISES. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-20 3.8.4.1-2 IDW VOLTAGE CIRCUIT BREAKER PENLTRATION 1 CONDUCIOR PRCTTECTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-21 3.8.4.2-1 ITTIOR-OPERATED VALVES THERME OVERIDAD Piu1wn ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-25 h

-SHOREHAM - UNIT 1 xx v

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14XIIC SYSMN FUNCPICNAL TEST 1.21 A 1DGIC SYrm4 FUNCT1 MAL TEST shall be a test of all loaic components.

i.e., all relays and contacts, all trip units, solid state logic elements, etc, of a logic circuit, from sensor throuch and including the actuated i device, to verify OPERABILITY. The ILGIC SYSTIM ITNCTIONAL TEST may be l perforned by any series of sequential, overlappino or total systs steps such j

! that the entire loale system is tested.

1

.MAXIMLN FRACTION OF LIMITING IWER DD4SITY l

'I.22 The MAXIMUM FRACIICN OF LIMITING IGI:R DENSITY (MFLPD) shall be highest value of the TLPD which exists in the core.

MEMBER (S) OF THE PUBLIC 1.23 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally

. associated with the plant. This cateaory does not include ernployees of the '

utility, its contractors or vendors. Also excluded from this cateoory are persons who enter the site to service equipnent or to nake deliveries. This ,

cat'eoory does include persons who use portions of the site for recreational, ;

occupational or other purposes not associated with the plant. l t

MINIMN CRITICAL TWER RATIO i 1.24 The MINIMLN CRITICAL IWER RATIO (MCPR) shall be the smallest CPR which exists in the core. :

OFPSITE DOSE CAICULATION MANUAL (ODm) 1.25 The OFFSITE DOSE CALCU1ATION MANUAL (C4XN) shall contain methodology and {

parameters used in the calculation of offsite doses resultino frcan L radioactive caseous and liquid effluents, in the calculation of caseous and :

liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Envirorrnental Radioloalcal Monitoring Program. The ODm shall also contain ;

(1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the .

information that should be included in the Annual Radiological Environmental Cperatino and S mi-annual Radioactive Effluent Release Reports required by ;

Specifications 6.9.1.6 and 6.9.1.7.

OPERAHLE - OPERABILITY 1.26 A system, subsysts, train, ocznponent or device shall be OPERABLE or have OPERABILITY when it is capable of performina its specified function (s) and >

when all necessary attendant instrumentation, controls, electrical power, coolina or seal water, lubrication or other auxiliary equipnent that are required for the system, subsystem, train, cw ra nt or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL CONDITION - OJNDITION 1.27 An OPERATIONAL CONDITION, i.e., CCNDITION, shall be any one inclusive ?

ocrnbination of mode switch position and averace reacter coolant tmperature as specified in Table 1.2.

PHYSICS TESTS

.1.28 PHYSICS TESTS shall be those tests perfomed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14 of the USAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Comission.

SHORI21AM - UNIT 1 1-4

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, 1 i Y DEFINITICNS PRESSURE BOUl&Jr/ ITMAGE I.29 PRESSURE BOUNIARY LIKACE shall be leakaoe throuah a nonisolable fault in a reactor coolant systm cmponent body, pipe wall, or vessel wall.

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PRIMARY 00t#AINMNT IlFIGtITY 1.30 PRIMARY 06tEAINMI2C INTDGRITY shall exist when 9

a. All primary containment penetrations required to be closed durino accident conditions are either:

1. Capable of beino closod by an OPERABLE primary containment i autmetic isolation systs , or

2. Closed by at least one nanual valve, blind flance, or deactivated automatic valve secured in its closed position, except as provided in Table 3.6.3-1 of Specification, 3.6.3.

b. All primary containment equipnent hatches are closed and sealed.

c. Each primary containment air lock is in empliance with the requirenents of Specification 3.6.1.3. ,

d. The primary containment leakaae rates are within the limits of Specification 3.6.1.2.

e. The suppression chamber is in ccupliance with the requirements of Specification 3.6.2.1.

f. The sealino nechanism associated with each prirary containment penetration; e.a. , welds, bellows, or 0-rinas, is OPERABLE.

PROCESS OCNTROL PROGRAM 1.31 The PROCESS COClOL PROGRAM (TCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processina and packagina of solid radioactive wastes based on dmonstrated processing of actual or simulated wet solid wastes will be acomplished in such a way as to assure empliance with 10 CPR Parts 20, '1, and 71, State reaulations, burial around requirments, and other recuircents coverning the disposal of rolid radioactive waste.

PURGE - PURGING 1,32 PURGE or PURGING shall be the cor. trolled process of discharainq air or cas frm a confinement to maintain temperature, pressure, humidity, concentration, or other operatino condition, in such a manner that replacm ent air or cas is required to purify the confinement.

l - RATED THPJNAL POWER 1.33 RATED THEWAL POER shall be a total reactor core heat transfer rate to the reactor coolant of 2436 M9t.

REACIOR PlutLTION SYSTIN RESPONSE TIME 1.34 REACIOR PIUfDCTION SYSTEN RESPONSE TIME chall be the time interval from when I l

the monitored parameter exceeds its trip setpoint at the channel sensor until l deenercization of the scram pilot valve solenoids. The response time may bo

neasured by any series of sequential, overlappina, or total steps such that j the entire response time is measured.

L SHOREHAM - UNIT 1 1-5 l

i IEFINITICNS I

RENRmBLE INENT 1.35 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

RCD DENSITY l'.36 KD DINSITY shall be the ntmber of control rod notches inserted as a fraction of the total nunber of control rod notches. All rods fully inserted is equivalent to 100% RCD DINSITY.

SBOCNDARY CONTADMNP INTEGRITY 1.37 SD00NDARY CONTADMNT IhTEGRITY shall exist whent

a. All secondary containment penetrations required to be closed durino accident conditions are either:

1. Capable of being closed by an OPERABLE secondary contairment automatic isolation systen, or

2. Closed by at least one manual valve, blind flange, or deactivated automatic valve eecured in its closed position, except as provided in Table 3.6.5.2-1 of Specification 3.6.5.2.

b. All secondary containment batches are closed and sealed.

c. 'Ihe Reactor Duildino Standby ventilation Systesn is in ccanpliance with the requirunents of Specification 3.6.5.3.

d. At least one door in each access to the secondary containment is closed.

e. The sealing mechanism associated with each secondary contalment penetration, e.a.,. welds, bellows, or 0-rings, is OPERABLE.

f. 'Ihe pressure within the secondary contaiment is less than or equal to I the value reauired by Specification 4.6.5.la.

SJRrrDOWN MARGIN l

1.38 SHtTfDOWN MARGIN shall be the amount of reactivity by which the reactor is suberitical or would be suberitical assuning all control rods are fully inserted except for the sinole control rod of hiahest reactivity worth which i

1 is assuned to be fully withdrawn and the reactor is in the shutdown l condition; cold, i.e., 68'F; and xenon free.

- SITE BOUNDARY i

1.39 The SITE BOUNDARY shall be that line beyond which the land is neither owned, l nor leased, nor otherwise controlled by the licensee.

SOLIDIFICATION l.

l 1.40 (NCff USED - REFER 'IO PCP) i mURCE CHBCK 1.41 A SOURCE CHDCK shall be the qualitative assestment of channel response when the channel sensor is expored to a radioactive source. ;

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RADIOACTIVE IJOUID AND CA9DUS EmlHE MONMORING INSTRtMNTATICN

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. INSTRUMENTATIm ,

i EXPIDSIVE GAS MNI'IORING INSTRtNWTATIN i

LIMITING CDNDITIN FOR OPERATION i 3.3.7.11 'Ihe explosive gas monitoring instnmentation channels shown in Table l 3.3.7.11-1 shall be OPDaBLE with their alann/ trip setpoints set to ensure that the limits of Specification 3.11.2.6 are not exceeded.

APPLICABILITY: As shown in Table 3.3.7.11-1 ACTION:

a. With an explosive cas monitorina instrunentation channel alarm / trip setpoint less conservative than required by the above specification, ]

declare the channel inoperable and take ACTIN shown in Table l 3.3.7.11-1. '

b. With less than the minimum number of explosive cas monitoring I instrunentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1. Restore the inoperable instrumentation to OPERABLE status i within the time specified in the AcrION or prepare and sutanit a Special Report to the Ocamission pursuant to Specification 6.9.2 to explain why this inoperability was not corrwied within the time specified.

c. The pmvisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILT1JCE RDOUIREMNTS 4.3.7.11 Each explosive cas rionitoring instrumentation channel shall be l demonstrated OPDGBLE by performanm of the CHANNEL CHDCK, SOURCE CHECK, CIANNEL CALIBRATION, and CIANNEL FUICTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1.

SilORDIAM - UNIT 1 3/4 3-89

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TABLE 3.3.7.11-1 !

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' EXPLOSIVE GAS WWI'!ORING INSTRtMNTATICN :

MINIMLN OIANNELS INSTRLM NT OPERAB_IE APPLICABILITY ACTICN,

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2. MAIN CONDENSER OITGLS TREA'LMENT SYSTIM ;

EXPIOSIVE GAS MONI'IORING SYSTEM

a. HyCuvceJi Monitor (downstream of reconbiner) 16 ** 121 l

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l' TABIE 3.3.7.11-1 (Oontinued)

TABLE NCYTATIWS *

(NOT USED)

- Durina main condenser offaas treatment system operation.

I f A monitor connected to the operatino offaas loop shall be OPERABLE.

JCTION STATDMTPS l ACTION 121 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirenent, operation of nain condenser ,

offaas treatment system nay continue for up to 30 days provided -

grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . l 1

i SIIDIGIAM - UNIT 1 3/4 3-91

I I TABLE 4.3.7.11-1 l EXPLOSIVE CAS MJNI'IORING INSTRINEhTTATIQJ StHVEIIIANCE RDQUIRIMFNIS l

l N L- QIANNEL IN MIIQI CHANNELS $0URCE QiANNEL IUCTIONAL StmVEll2ANCE l- INSTRtNFNT OIDCK OIDCK CALIBRATIQ4 TEST RDQUIRED ;

l 1. (NOT USED) I l

2. FAIN OCNDDiSER OFITAS !

TREA'IMENT SYSTIM l t, EXPIDSIVE CAS l

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J INSTRtNENTATIN 1 BASES I KNI70 RING INSTRIMENTATION~ (Continued) ,

3/4 3.7.9 FIRE DFTECTION INSTRIMNTATIN l

OPE:RABT.LITY of the fire detection instnmentation ensures that adequate -l warninc capability is available for the prmpt detection of fires. This .

capability is required in order to detect and locate fires in their early stages. 1 Prmpt detection of fires will reduce the potential for dmage to safety-related '

equiptent and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire watch patmis in the affected areas is required to provide detection capability until the inoperable instrmmentation is restored to OPERABILITY, 3/443.7.10 RADIOACTIVE LIQUID AND GASEQUS EFF7UENT KNI70 RING INSTRUMENTATION .

(NCfr USED) (Refer to ODCN) 3/4.3.7.11 EXPIOSIVE GAS KNI70 RING INSTRINENTATICN The instrumentation includes provisions for monitoring (and controllina) the concentrations of potentially explosive cas mixtures in the Inain condenser offaas treatment systs. The OPERABILITY and use of this instrumentation is consistent

with the requirements of General Desian Criteria 60, 63, and 64 of Appendix A to

--10 CPR Part 50.

3/4.3.7.12 ILOSE-PART DETBCTION SYSTEM The OPERABILITY of.the loose-part detection system ensures tret sufficient capability-is available to detect 1cose rnetallic parts in the primary aystem and avoid or mitigate damaae to primary system components. The allowable out-of-service times and surveillance recuirments are consistent idth the reemnendations of Regulatory Guide 1.133, " loose-Part Detection Program for the Primary Systs of Licht-Water-Oooled Reactors," May 1981.

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3/4.11.1.3 IJOtr1D RADWASTE TREA'DEWP SYSTEM t (Icf USED)4 (Refer to ODCN) r 3/4.11.1.4 IJOUID HOUUP TANKS Bestrictina the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' ccmtents, the resulting concentrations would be less than the limits of 10

' CFR Part 20, Appendix. B Table II, Coltmn 2, at the nearest potable water supply

.and the nearest surface water supply in an UNRESTRICTED AREA.

'3/4.11.2 GASEOUS EFTLUINPS 3/4 11.2.1 DOSE RATE (NCff USED) (Refer to ODCN) ;

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F 3/4.11 NADIOACTIVE EFFIUSTTS BASES 3/4.11.2.6 EXPIOSIVE GAS MIX'IURE This specification is provided to ensure that the concentration of

'potentially explosive gas mixtures contained in the main condenser offgas treatrnent systen is maintained below the flamability limit of hydrogen. 'Ihe limits of Specification 3.11.2.6 are based upon the system's= explosion-proof design. The only non-explosion-proof portion of the system is upstream of the r~=h%er, booster ejector, where the gas mixture is belcw the flamability limit. Maintaining the concentration of hydrooen below its flamability limit provides assurance that the releases of radioactive naterials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. ,

3/4.11.2.7 MAIN OCNDENSER-Restricting the gross radioactivity rate of noble gases frun the main condenser provides reasorad:,le assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of ~10 CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification impletenta the requirements of General Desion Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

3/4 11.2.8 CntrAIf4fDTP PURGING AND VINTING l L

(NOT liSED) (Refer to ODCM) 3/4.11.3 SOLID RADIOACTIVE h7STE (NCff USED) (Refer to ICP)

[ 3/4.11.4 'IUTAL DOSE (NCTI USED) (Refer to OD W)

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3/4.12^ RADIOIDGICAL I!NVIR0tMNIE MJNTIORDIG

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\ l 3/4.12.3 ~ IhWe0RA10RY OCMPARISON PROGRAM )

-: (17J1' USED) (Refer to ODCM)-

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~ ADMINISTRATIVE CONTROLS

, PROCEDURES AND PROGRAMS (Continued)

The program shall. include the following:

1. Preventive maintenance and periodic visual inspection requirements, and' *

2. Integrated leak test requirements for each system at refueling cycle '

intervals or less,

b. In-Plant Radiation Monitoring i A program which will ensure the capability to accurately determine the airborne iodino concentration in vital areas under accident conditions.

This program shall include the following:

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipnent.

c. Post-accident Samplina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

g 'Ihe program shall include the following:

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1. Training of personnel,

l. .2. Procedures for sampling and analysis, and i

3. Provisions for maintenance of sampling and analysis equipnent.

d. Radioactive Effluent Controls Prtx:rram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to M m BERS OF THE PUBLIC from radioactive effluents as low as reasonably '

achievable. The program (1) shall be contained in the ODm, (2) shall be implenented by operating procedures, and (3) shall include remedial actions to be taken whenever the procram limits are exceeded. The ,

program shall include the following elements:

1) IJmitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODW,

'2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, "SHOPEHAM UNIT 1 6-14

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w AIMINISTRATIVE CONTROLS 1

.d. - Radioactive Effluent Controls Pmaram (continued)

3) Monitoring, sarrplino, and analysis of radioactive liquid and i caseous effluents in accorrlance with 10 CFR 20.106 and with the

. methodology and parameters in the ODN ,

l 4)- Limitations on the annual and quarterly doses or dose ecmnitment to d a MEMBER OF THE PUBLIC frun radioactive materials-in liquid-effluents released frm each unit to UNRTETRICTED AREAS conformino to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current - 3 calendar year in accordance with the methodology and parameters in '

the OD 3 at Innst every 31 days,

6) . Limitations on the operability and use of the liquid and gaseous '

efflvent tree.unent systens to ensure that the appropriate portions of there systems are used to reduce releases rf radioactivity when the projected doses in a 31-day period would exceed 2 percent of the quidelines for the annual dose or dose ccrnmitment conforming to Appendix I'to 10 CFR Part 50, - '

7) Limitations on the dose rate resultino from radioactive material

released in caseous effluen':s to areas beyond the SITE BOUNDARY conforming to the doses asscciated with 10 CFR Part 20, Appendix B, f Table II, Column-1,

8) Limitations on the= annual and quarterly air doses resulting frun

. noble cases released in caseous effluents frcm each unit to areas v beyond the SITE BOUNDARY conforming to Appendix I to 10'CFR Part ,

50, _

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC frcrn Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives creater than 8 days in caseous effluents released frcrn each unit to areas beyond the SITE DOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on venting and purging of the Mark II containment .

throuch the Standby Gas Treatent System to maintain releases as l low as reasonably achievable, and i 11). Limitations on the annual dose or dose ccmnitment to any MEMBER OF l L- THE PUBLIC due to releases of radioactivity and to radiation frrrn uranium fuel cycle sources conforming to the 40 CPR Park 190.

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AENINISTRATIVE CONTROIS h

e. Radiolooical Environmental Monitorina'Procram A program shall be provided to nonitor the radiation and radionuclides

'.in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the hiahest potential exposure pathways, and (2) verification of the accuracy _of the effluent nonitoring program and modeling of envircnmental exposure pathways. 'The program shall .(1) be contained in the ODW, (2) conform to the cuidance of Appendix I to 10 CFR Park 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and e

radionuclides in the environment in accordance with the methodology '

and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that nodifications to the monitoring program are made if required by the results of this

, census, and- .

3) . Participation in a Interlaboratory Ccxnparison Program to encue l that independent checks on the precision and accuracy of the ,

measurements of radioactive materials in environmental sample matrices are. performed as part of the quality assurance program for environmental monitoring.

6.9 - REPORTING REQUIRENDVTS ROUTINE REPORTS, 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of~

Federal Regulations, the following reports shall be subnitted to the Regional Administrator of the Recional Office of the NRC unless otherwise noted. .

-STARTUP REPORT -

6.9.1.1 A sunmary report of plant startup and power escalation testino shall be subnitted following (1) receipt of an Operatino License, (2) amendment to the license involving a planned increase in power level. (3) installation of fuel that !

has a different desian or has been manufactured by a different fuel supplier, and i (4); modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the station.

6.9.1.2- The startup report shall. address each of the tests identified in the

..- Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test

-program and a camparison of these values with design predictions and

. specifications. Any corrective actions that were reauired to obtain satisfactory

, operation shall also be described. Any additional specific details required in

' license conditions based on other conmitments shall be included in this report.

SHOREHAM - UNIT 1 6-14b

AtHINISTRATIVE OCNTROIS STARIUP REIORT (Continued) 6.9.1.3 Startup reports shall be sulnitted within (1) 90 days followino conpletien of the startup test proaram, (2) 90 days following resmption or comencenent of comercial power operation, or (3) 9 nonths following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, empletion of startup test proaram, and resumption of comiencement of ecmterrial operation) supplementary reports shall be sutuitted at least every 3 nonths until all three events have been empleted.

ANNUAL i<uwis 6.9.1.4 Annual reports covering the activities of the unit an descriled telow for the previous calendar year shall be sulnitted prior to March 1 of each Scar.

Tin initial report shall te sulnitted prior to March 1 of the year followina initial criticality.

6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receivino exposures creater than 100 mrms/yr and their associated manrem exposure accordina to work and job functions * (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processina, and refueling) . The dose assianments to various duty functions may be estimated based on pocket dosimeter,

.hermoluminescent dosineters (TLD), or film badge reasurments. Small exposures totallina less than 20% of the individual total dose need not be acccunted for.

In the accrecate, at least 80% of the total wholebody dose received from external sources should be assigned to specific mrior work functions.

AtNUAL RADIOLOGICAL DNIRCN4 ENTAL OPERATING REPORT 6.9.1.6 That Annual Radioloaical Environmental Operating Report covering the operation of the unit during the previous calendar year shall be sutmitted before May 1 of each year. The report shall include sumaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Procram for the reporting period. The material provided shall im consistent with the objectives outlined in (1) the OD04 and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CPR Part 50.

7his tabulation supplenents the requirements of paragraph 20.407 of 10 CFR Part I 20.

SHOREHN4 - UNIT 1 6-15

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M MINISTRATIVE 00tm OIS _

SEMIMMTAL RADIOVSIVE EITIUDC RPITASE REPORT !

t 6.9.1.7 'Ihe Semiannaul Radioactive Effluent Release Report coverino the I operation of the unit during the previous 6 months of operation shall be suhnitted ,

within 60 days after January 1 and July 1 of each year. The report shall include t a sunmary of the quantities of radioactive liquid and caseous effluents and solid l waste released from the unit. The material provided shall be (1) consistent with '

the objectives outlined in the OD N and PCP and (2) in conformance with 10 CFR 3 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. !

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I ADMINISTRATIVE 00ffrROIS i s

RIXDRD REPD7T3m (Continued)

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

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the :

environs.

e. Records of transient or operational cycles for those urdt cuupcwnts identified in Table 5.7.1-1.

f. Records of reactor tests and experiments,

c. Records of training and qualification for current menbers of the unit staff.

h. Records of inservice inspections performed pursuant to these Technical Specifications. ,

1. Records of quality assurance activities required by the Quality Assurance Manual which are not listed in Section 6.10.2.

j. Records of reviews performed for changes made to procedures or equipnent or reviews of tests and experiments pursuant to 10 CFR 50.S9.

k. Records of meetinas of the ROC and the NRB.

1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.5 including the date at which the service life conmences and associated installation and maintenance records. i

m. Records of analyses required by the radioloaical environmental ,

monitoring procram that would permit evaluation of the-accuracy of the analysis at a later date. This should include procedures effective at -

specified times and QA records showing that these procedures were followed.

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n. Records of reviews performed for chances made to the OFFSITE DOSE CAICUIATION MANUAL and the PIOCESS CC17fROL PROGR7M.

6.11 RADIATION PRCfrECTION PROGR/M 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CPR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

I SFDRDIAM - UNIT 1 6-19

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AININISTi&TIVE COfrRGS 6.13 PIOCESS OCNITOL PIOGRAM (IrP)

Changes to the ICP:

a. Shall be docannted and recorris of reviews performd shall be retained as required ? Specification 6.10.3n. 'this docuentation shall contains i

1) Suffica at *mation to support tre chance tooether with tle a;propriate ;yses or evaluations justifying the chanoe(s) and

! 2) A determination that the chance will maintain the overall conformance of the solidified waste product to existing requirments of Tederal, State, or other applicable requiations.

b. Shall becme effective after review and acceptance by the IOC and tie apprtwal of tle Plant Manaaer.

6.14 OITSITE DOSE CATCUIATION MANUAI, (ODCM)

Chances to the 0001:

a. Shall be docmented and records of reviews performed shall be retained as required by Specification 6.10.3n. 'Ihis documentation shall contain:

1) Sufficient infornation to support the chance together with the appropriate analyses or evaluations justifying the chanoc(s) and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CPR Part 190,10 CPR 50.36a, and Appendix I to 10 CPR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or octpoint calculations,

b. Shall locame effective after review and acceptance by the ROC and the approval of the Plant Manager,

c. Shall be sulznitted to the Canmission in the form of a emplete legible copy of the entire OD01 as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any chance to the 0001 was made. T,ach chance shall be identified l by markings in the margin of the affected paces, clearly indicating the area of the page that was chanced, and shall indicate the date (e.g.,

month / year) the change was implemented, i

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ADMINISTRATIVE CXWPRSIS

,.6.15 MMOR OIANGfE 10 RADI&crIVE LIQUD, GASD00S, AND SOLID h7STE TRPRIMWT l nmue ,

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ATTACHMENT 3 TO SNRC-1666 i

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ML20006F471

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