ML20055E387

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Amend 5 to License NPF-82,changing Administrative Section of Tech Specs & Moving Procedural Details Re Radioactive Effluent Monitoring Instrumentation,Equipment Requirements & Control of Liquid & Gaseous Effluents to ODCM
ML20055E387
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/25/1990
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055E364 List:
References
NUDOCS 9007110310
Download: ML20055E387 (92)
v • d • e


Text

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r. WA6HINGTON, D. C, 20666 LONG ISLAND LIGHTING C0p ANY DOCKET NO. 50-322 SHOREHAM NUCLEAR POWER STATION UNIT 1 1 AMENDMEMT TO FACILITY OPERATING LICEM5E j Amendment No. 5 License No. NPF-8? '1. .The Nuclear Regulatory Comission (the Comission) has found that j A. The application for amendment by Long Island Lighting Company (the licensee), dated February 20. 1990, complies with the standards and req)uirements of the Atomic Energy Act of 1954, as amended (the Act, and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the r provisions of the Act, and the rules and regulations of the Comission; C.. Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of thia amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 i of the Comission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-82 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 5 are hereby incorporated into this license. Long Island Lighting Company shall operate the facility in accordance with the Technical Specifications and the Environmental j Protection Plan. p l c e (~

s 2 3. This license amendment is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION /s/ Walter R. Butler Director Project Directorate 1-2 Division of Reactor Projects. 1/11

Attachment:

Changes to the Technical Specifications. Date of Issuance: June 25, 1990 1r t 3t [SHAMEND76052] PDI-2/D LA PDi-2/PM PDI-p/P 02 i en ETrottier: bid SBrow I WButler 90 / /90 r,//- j/g g90 g /yg/90 1

I ATTAC WEFT TO LICENSE AMENDMENT No. 5 [ FACILITY OPERATING LICENSE NO. NPF-82 DOCKET NO. 50-322 i Replace the i'ollowin the attached pages. g anges of the Appendix "A" Technical Specifications with Tie revised pages are identified by Amendment number and contain vertital lines indicating the area of change. Overicaf pages are provided to maintain document completeness *, Remove Insert i i* 11 ii y v vi vi* t xi xi t xii xii* xiii xiii xiv riv* xvii xvii xviii xviii* xix xix* xx xx xxiii xxiii* xxiv xxiv xxv xxy I 1-3 1-3* 1-4 1-4 1-5 1-5 1-6 1-6 -3/4 3-83 3/4 3-83* 3/4'3-84 3/4 3-84 3/4 3-85 3/4 3-85 3/4 3-86 3/4 3-86 3/4 3-87 3/4 3-87 3/4 3-88 3/4 3-88 t

i i' -t. - Remove Insert I .3/4 3-89 3/4 3-89 3/4 3-90 3/4 3-90 3/4 3-91 3/4 3-91 3/4 3-92 3/4 3 92 3/4 3-93 3/4 3-93 t 3/4 3-94 3/4 3-94* 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 3/4 11-4 3/4 11-4 .3/4 11-5 3/4 11-5 l 3/4 11 E 3/4 11-6 i 3/4 11-7 3/4 11-7* 3/4 11-B 3/4 11-8 3/4 11-9 3/4 11-9 3/4 11-10 3/4 11-10 3/4'11-11 3/4 11-11 I 3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4.11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4-11-16 3/4 11-16* 3/4 11-17 1/4 11-17* 3/4 11-18 3/4 11-18 3/4 11-19 3/4 11-19 3/4 11-?0 3/4 ;1-20 i 3/4 11-21 3/4 11-k -3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-2 3/4 12-3 3/4 12-3 3/4 12-4 3/4 12-4 4

7...,........_...... , j Remove insert 3/4 12-5 3/4 12-5 3/4 12-6 3/4 12-6 3/4 1? 7 3/4 12-7 3/4 12-8 3/4 12-8 3/4 12-9 3/4 12-9 3/4 12-10 3/4 12-10 3/4 12-11 3/4 12-11 3/4 12-12 3/4 12-12 3/4 12-13 3/4 12-13 B 3/4 3-5 B 3/4 3-5* B 3/4 3-6 B 3/4 3-6 B 3/4 11-1 B 3/411-1 B 3/4 11-2 B 3/4 11-2 B 3/4 11 3 B 3/4 11-3 B 3/4 11-4 0 3/4 11-4 -B 3/4 11-5 B 3/4 11-5 B 3/4 11 6 B 3/4 11-6 E 3/4 12-1 B 3/412-1 E 3/4 12-2 B 3/4 12-2 f-13 6-13* 6-14 6-14 6-14a 6-14b 6-15 6-15 ,6-16 6-16 6-17 6-17 6-18 6-1B* 6-19 6-19 .6-20 6-20* 6-?1 6-21 6-22 6-22

st i 1 1 4 INDEX i DEFINITIONS P SECTION 1.0 DEFINITIONS PAGE ( 1.1' ACTI0N..................................,.................. 1-1 1.2 AVERAGE PLANAR EXP0$URE.................................... 11 [ 1.3_ AVERAGE PLANAR LINEAR HEAT GENERATION RATE................. 1 1.4 CHANNEL CALIBRATION........................................ 1-1

1. 5 CHANNEL CHECK..............................................

1-1 t 1.6 CHAhNEL FUNCTIONAL TEST.................................... 1-1 1.7 CORE.\\LTERATI0N............................................ 1-2

1. 8 CRITICAL POWER RATI0........................................

l'- 2 1.9 DOSE EQUIVALENT I-131...................................... 1-2 1.10 E-AVERAGE DISINTEGRATION ENERGY............................ 1-2 1.11 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME......... 3-2 1.12 END-OF-CYCLE RECIRCULATION PUMP-TRIP SYSTEM RESPONSE TIME.. 1-2 1.13 FRACTION OF LIMITING POWER 0ENSITY........................ 3 1.14 FRACTION OF RATED THERMAL P0WER........................... 1-3 1.15 FREQUENCY NOTAT!0N.....................................s... 3 1.16 GASEOUS RA0 WASTE TREATMENT SYSTEM.......................... 1-3 1.17 IDENTIFIED LEAKAGE......................................... 1-3 1.18 ISOLATION SYSTEM RESPONSE TIME............................. 1-3 1.19 LIMITING CONTROL ROD PATTERN............................... 1-3 1.20 LINEAR HEAT GENERATION RATE................................ 1-3 1.21 LOGIC SYSTEM FUNCTIONAL TEST............................... 1-4 1.22 MAXIMUM FRACTION OF LIMITING POWER DENSJTY................ 1-4 1.23 MEMBER (5) 0F THE PUBLIC................................... 1-4 1.24 MINIMUM CRITICAL POWER RATI0............................... 1-4 - SHOREHAM - UNIT 1 i P 6 = e- _~- -, _ _. _ m. m

INDEX DEFINITIONS SECTION i DEFINITIONS (Continued) PAGE

1. 25 0FFSITE DOSE CALCULATION MANUAL (0DCM).....................

1-4

1. 26 OPERAB LE - OPERABI LITY.....................................

1-4 1.27 OPERATIONAL CONDITION - CONDITION.......................... 1-4 1.28 PHYSICS TESTS.............................................. 1-4 1.29 PRESSURE BOUNDARY LEAKAGE.................................. 1-5 1.30 PRIMARY CONTAINMENT INTEGRITY.............................. 1-5 1.31 PROCESS CONTROL PROGRAM (PCP).............................. 1-5 I 1.32 PURGE - PURGING............................................ 1-5 L 1.33 RATED THERMAL P0WER........................................ 1-5 1.34 REACTOR PROTECTION SYSTEM RESPONSE TIME.................... 1-5 1.35 REPORTABLE EVENT.....................'...................... 1-6 l 1.36 R0D 0ENSITY................................................ 1-6 l 1.37 SECONDARY CONTAINMENT INTEGRITY............................ 1-6 1,38 SHUTDOWN MARGIN............................................ 1-6 1.39 SITE 80VNDARY.............................................. 1-6 l 1.40 SOLIDIFICATION (NOT USED) (REFER TO PCP).................. 1-6 l 1.41 SOURCE CHECK............................................... 1-6 1.42 STAGGEREo TEST BASIS....................................... 1-7 1.43 THERMAL P0WER...............................'............... 1-7 l 1.44 TURBINE BYPASS SYSTEM RESPONSE TIME..................:..... 1-7 1 i-1.45. UNIDENTIFIED LEAKAGE....................................... 1-7 1.46 UNRESTRICTED AREA.......................................... 1-7

1. 47 VENTI LATION EXHAUST TREATMENT SYSTEM.......................

1-7 1,48 VENTING.................................................... 1-7 l l l; i l t l' SHOREHAM - UNIT 1 11 Amendment No. 5

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOL'!REMENTS SECTION PAGE l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops.................................. 3/4 4-1 Jet Pumps............................................ 3/4 4-4 Recirculation Loop F10w.............................. 3/4 4-5 Idle Recirculation Loop Startup...................... 3/4 4-6 3/4.4.2 SAFETY / RELIEF VALVES................................. 3/4 4-7 l 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE L Leakage Detection Systems............................ 3/4 4-9 Operational Leakage............/..................... 3/4 4-10 1 3/4.4.4 CHEMISTRY............................................ 3/4 4-13 1 3/4.4.5 SPECIFIC ACTIVITY.................................... 3/4 4-16 3/4.4.6' PRESSURE / TEMPERATURE LIMITS Reactor Coolant System............................... 3/4 4-19 Reactor Steam' Dome................................... 3/4 4-23 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES..................... 3/4 4-24 3/4.4.8 STRUCTURAL INTEGRITY................................. 3/4 4-25 3/4.4.9 ' RESIDUAL HEAT REMOVAL j Hot Shutdown......................................... 3/4 4-26 ll Cold Shutdown........................................ 3/4 4-27 L {. 3/4.5 EMERGENCY CORE COOLING SYSTEMS

~

3/4.5.1 ECCS - 0PERATING..................................... 3/4 5-1 l l ? 3/4.5.2 ECCS - SHUTD0WN...................................... 3/i 5-6 3/4.5.3 ' SUPPRESSION POOL Suppression Pool Water Leve1......................... 3/4 5-8 Suppression Pool Pump-Back System.................... 3/4 5-10 SHOREHAM - UNIT 1 vi

l o 1 y INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I SECTION PAGE 3 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.................. 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION 1 INSTRUMENTATION.................................... 3/4 3-27 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation.. 3/4 3-36 End-of-Cycle Recirculation Pump Trip System i Instrumentation.................................... 3/4 3-40 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION.................................... 3/4 3-46 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION.................... 3/4 3-51 3/4.3.7 MONITORING INSTRUMENTATION 1 Radiation Monitoring Instrumentition................. 3/4 3-57 Seismic Monitoring Instrumentation................... 3/4 3-62 Meteorological Monitoring Instrumentation............ 3/4 3-65 Remote Shutdown Monitoring Instrumentation........... 3/4 3-68 Accident Monitoring Instrumentation.................. 3/4 3-71 Source Range Monitors................................ 3/4 3-75 Traversing In-Core Probe System...................... 3/4 3-76 Chloride Intrusion Monitors.......................... 3/4 3-77 Fire Detection Instrumentation....................... 3/4 3-81 Radioactive Liquid Effluent Monitoring Instrumentation (NOT USED) (Refer to 0DCM)......... 3/4 3-84 Explosive Gas Monitoring Instrumentation............. 3/4 3-89 Loose-Part Detection System.......................... 3/4 3-94 t Safety Parameter Display System...................... 3/4 3-95 Diesel Generator 3300 KW A1 arm....................... 3/4 3-97 3/4.3.8 TUR8INE OVERSPEED PROTECTION SYSTEM.................. 3/4 3-98 3/4.3.9 FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION...................................... 3/4 3-100 SHOREHAM - UNIT 1 v Amendment No. 5

INDEX L]NITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration (NOT USED) (Refer to DDCM)................ 3/4 11-1 Dose (NOT USED) (Refer to 0DCM)......................... 3/4 11-5 Liquid Radwaste Treatment System (NOT USED) ( Re f e r to 00CM)...................................... 3/4 11-6 Li qui d Hol dup Tanks..................................... 3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS n Dose Rate (NOT USED) (Refer to DDCM).................... 3/4 11-8 Dose - Noble Gases (NOT USED) (Refer to 00CM)........... 3/411-12 Dose - Iodine-131. Iodine-133, Tritium, and Radionuclides in Particulate Form (NOT USED) (Refer to ODCM)......... 3/4 11-13 Gaseous Radweste Treatment System (NOT USED) (Refer to ODCM)........................................ 3/4 11-14 Ventilation Exhaust Treatment System (NOT USED) (Refer to ODCM)............................. 3/4 11-15 l Explosive Gas Mixture.................................... 3/4 11-16 Main Condenser........................................... 3/4 11-17 Containment Purging and Venting (NOT USED) (Refer to ODCM)........................................ 3/4 11-18 3/4.11.3 SOLID RADI0 ACTIVE WASTE (NOT USED) (Refer to PCP)........ 3/4 11-20 3/4.11.4 TOTAL DOSE (NOT USED) (Refer to ODCM).................... 3/4 11-21 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING 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 i 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM (NOT USED) (Refer to ODCM).............................. 3/4 12-13 \\ l i ~ SHOREHAM - UNIT 1 xi Amendment No. 5

INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY............................................ B 3/4 0-1 3/4.1-REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN................'.................. B 3/4 1-1 n 3/4.1.2 REACTIVITY AN0MALIES............................. B 3/4 1-1 i 3/4.1.3 CONTROL R005..................................... B 3/4 1-2 3/4.1.4 CONTROL ROD PROGRAM CONTR0LS..................... B 3/4 1-3 i 3/4.1.5' STANDBY LIQUID CONTROL SYSTEM.................... B 3/4 1 l 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE........................................... B 3/4 2-1 3/4.2.2 APRM SETP0!NTS................................... B 3/4 2-2 3/4.2.3 MINIMUM CRITICAL POWER RATI0..................... B 3/4 2-4 3/4.2.4 LINEAR HEAT GENERATION RATE...................... B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION........ B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.............. B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.................................. B 3/4 3-2 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION.................................. B 3/4 3-3 t 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........................ B 3/4 3-4 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION.................................. B.3/4 3-4 SHOREHAM - UNIT 1 xii i ,. + _ _. - - _. -. _ _ -. _ _ -. - _. _ _ _ _ - - - _ - - - _. - _ - _ - _ _. - _ _ -. _ - - _ _ _ - _ _ - _ - - _. _. - _ - - _ _ -. - _ - _ - - - - - - - -. _ - _ - _ _ _ -. -. _ _ _

i INDEX BASES SECTION PAGE INSTRUMENTATION (Continued) 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation............ B 3/4 3-4 Seismic Monitoring Instrumentation.............. B 3/4 3-4 Meteorol ogi cal Moni tori ng Instrumentati on....... B 3/4 3-4 Remote Shutdown Monitoring Instrumentation...... B 3/4 3-5 Accident Monitoring Instrumentation............. B 3/4 3-5 Source Range Monitors........................... B 3/4 3 5 Traversing In-Core Probe System................. B 3/4 3-5 Chloride Intrusion Monitors..................... B 3/4 3 Fire Detection Instrumentation.................. B 3/4 3-6 Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation (NOT USE9) (Refer to ODCM)... B 3/4 3-6 Explosive Gas Monitoring Instrumentation....... B 3/4 3-6 Loose-Part Detection System..................... B 3/4 3-6 Safety Parameter Display System................. B 3/4 3 3/4'.3.8 TURBINE OVERSPEED PROTECTION SYSTEM............. B 3/4 3-7 3/4.3.9 FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION..................... B 3/4 3-7 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM............................ B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES............................ B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems....................... B 3/4 4-2 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 3/4.4.6 PRESSURE / TEMPERATURE LIMITS..................... B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES................ B 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY............................ B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REM 0 VAL........................... B 3/4 4-5 1 SHOREHAM - UNIT 1 xiii Amendment No.5

i I INDEX i \\ BASES i i SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 and 3/4.5.2' ECCS - OPERATING and SHUTDOWN......... B 3/4 b*1 3/4.5.3 SUPPRESSION P00L...............'.................. B 3/4 5-2 j 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT -l Primary Contai nment Integri ty.................... B 3/4 6-1 I Primary Containment Leakage...................... B 3/4 6-1 Primary Contai nment Ai r Locks.................... B 3/4 6-1 MSIV Leakage Control System......'................ B 3/4 6-1 'I Primary Containment Struct* ural Integrity......... B 3/4 6-2 Drywell and Suppression Chamber Internal Pressure....................................... B 3/4 6 2 Drywell Average Air Temperature.................. B 3/4 6-2 Drywell and Suppression Chamber Purge System..... B 3/4 6 2 i 3/4.6.2 DEPRESSURIZATION SYSTEMS......................... B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES............. B 3/4 6-4 1 3/4.6.4 SUPPRESSION CHAMSER - DRYWELL VACUUM BREAKERS.... B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT............................ B 3/4 6-5 j 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL........... B 3/4 6 5 t 7 4 SHOREHAM - UNIT.1 xiv r -r

1 INDEX BASES SECTION pag 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration (NOT USED) (Refer'to ODCM)....... B 3/4 11-1 Dose (NOTUSED)(RefertoODCM)................ B 3/4 11-1 Liquid Radweste Treatment System (NOT USED) (Refer to ODCM).................. B 3/4 11-2 Liquid Holdup Tanks............................ B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS Dose Rate (NOT USED) (Refer to ODCM)........... B 3/4 11-2 Dose - Noble Gases (NOT USED) (Refer to ODCM).. B 3/4 11-3 Dose - Iodine-131, Iodine-133 Tritium, and Radio-nuclides in Particulate Form (NOT USED) (Refer to 00CM)................... B 3/4 11-3 l Gaseous Radwaste Treatment System (NOT USED) (Refer to 0DCM)................... B 3/4 11-4 l Ventilation Exhaust Treatment System (NOT USED) (Refer to ODCM)................... B 3/4 11-4 l Explosive Gas Mixture.......................... B 3/4 11-5 Main Condenser................................. B 3/4 11-5 Containment Purging and Venting (NOTUSED)(RefertoODCM)................... B 3/4 11-5 3/4.11.3' SOLID RADI0 ACTIVE WASTE (NOT USED) (Refer to PCP)............................... B 3/4 11 3/4.11.4 TOTALDOSE(NOTUSED)(RefertoODCM).......... B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORINGPROGRAM(NOTUSED)(RefertoODCM).. B 3/4 12 1 3/4.12.2 LANDUSECENSUS(NOTUSED)(RefertoODCM)..... B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM (NOT USED) ( b fer to ODCM).................. B 3/4 12-2 SHOREHAM - UNIT 1 xvii Amendment No. 5

INDEX + DESIGN FEATURES $ECTION PAGE L 5.1 SITE i Exclusion Area............................................. 51 Low Population Zone........................................ 51 SITE BOUNDARY for Radioactive Gaseous and Liquid Effluents................................................ 5-1 5.2 CONTAINMENT Configuration.............................................. 5-1 I Design Temperature and Pressure............................ 5-1 Secondary Containment...................................... 5-2 + 5.3 REACTOR CORE 1 Fuel Assemblies............................................ 56 Control Rod Assemblies..................................... 5-6 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature............................ 56 Vo1ume..................................................... 56 5.5 METEOROLOGICAL TOWER LOCAT10N.............................. 5-7

5. 6 FUEL STORAGE Criticality................................................

5-7 Orainage...............'.................................... 5-7 Capacity............... 5-7 i 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT........................ 5-7 1 l i L SHOREHAM UNIT 1 xviii

l } l INDEX ~ ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY..,.......................................... 6 1 6.2 ORGAN ZAT!0N.............................................. 61 6.2.1 NUCLEAR ORGANIZATION.............:................... 6-1 6.2.2 UNIT STAFF........................................... 6 2 6.2.3 INDEPENDENT SAFETY ENGINEERINGGROUP................. 6 6 FUNCTION............................................. 6 6 COMPOSITION.......................................... 6 6 RE S P0N SI BI Lli! E S..................................... 6 6 RECOR05.............................................. 6-6 6.2.4 SHIFT TECHNICAL ADVIS0R.............................. 6-6

6. 3 UNIT STAFF QUALIFICATIONS.................................

66 6.4 TRAINING.................................................. 67 6.5 REVIEW AND AUDIT.......................................... 6-7 6.5.1 REVIEW OF OPERATIONS CCMMITTEE(R0C)................. 6-7 FUNCT10N............................................. 67 C VM. 0 a..... h. r ai4v.......................................... 6-7 ALTERNATES........................................... 6-7 MEEilNG FREQUENCY.................................... 67 QU0RUM............................,.................. 6-7 RESPONSIBILITIES.............'........................ 6-8 RECOR05...............:.............................. 6-9 6.5.2 NUCLEAR REVIEW BOARD (NRB)........................... 6-9 FUNCT10N............................................. 69 COMPOSITION.......................................... 6-9 ALTERNATES........................................... 5-9 CONSULTANTS.......................................... 6-10 MEETING FREQUENCY.................................... 6 10 QU0RUM............................................... 6-10 1 SHOREHAM - UNIT 1 xix Amendment No. 2 1 i i FEB 1 1990 is..o

l INDEX i . ADMINISTRATIVE CONTROLS j SECTION PAGE' ) NUCLEAR REVIEW BOARD (NRS) (Continued) f 3 REVIEW............................................... 6-10 ( AUDITS............................................... 6-11 REC 0RDS.............................................. 6-11 6.6 REPORTA8LE EVENT ACT10N................................... 6-12 6.7 SAFETY LIMIT VIOLATION....................................' 6 12 l

6. 8 PROCEDURES AND PR0 GRAMS...................................

6-13 i 6.9 REPORTING REQUIREMENTS.................................... 6-14b 6.9.1 ROUTINE REP 0RTS..................................... 6-14b STARTUP REP 0RT.................- 6-14b ANNUAL REP 0RTS...................................... 6-15 ANNUAL kADIOLOGICAL ENVIRONMENTAL OPERATING REPORT... 6-15 i l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT....... 6-16 MONTHLY OPEkATING REP 0RTS............................ 6-18 i 6.9.2 SPECIAL REP 0RTS...................................... 6-18 6.10 RECORD RETENTION......................................... 6-18 t 6.11 RADIATION PROTECTION PR0 GRAM............................. 6-19~ L 6.12 HIGH RADIATION AREA...................................... 6-20 6.13 PROCESS CONTROL PROGRAM (PCP)............................ 6-21 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)................... 6-21 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID. GASEOUS. AND SOLID ~ WA5TE TREATMENT SYSTEMS (NOT USED)...................... 6-22 L l l SHOREHAM - UNIT 1 xx Amendment No. 5

i 1 .IN.gg i LIST OF TABLES (Continued) TABLE PAGE 4.3;4.1-1 "ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS......... 3/4 3-39 3.3.4.2-1 END-OF-CYCLE RECIRCULATION PUMP' TRIP SYSTEM INSTRUMENTATION................................... 3/4 3-42 3.3.4.2-2 END OF-CYCLE RECIRCULATION PUMP TRIP S'YSTEM SETPOINTS......................................... 3/4 3-43 i-a 3.3.4.2-3 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM e RESPONSE TIME..................................... 3/4 3-44 i i 4.3.4.2.1-1 END-OF-CYCLE RECIRCULATION PUMP TRIP ' SYSTEM SURVEILLANCE REQUIREMENTS......................... 3/4 3 45 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION L INSTRLNENTATION................................... 3/4 3-47. l 3.3.5-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION i INSTRUMENTATION SETP0INTS......................... 3/4 3-49 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION L INSTRUMENTATION SURVEILLANCE REQUIREMENTS......... 3/4 3-50 3.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION................. 3/4 3-52 i 3.3.6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS....... 3/4 3-54 4.3.6-1 CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS...................................... 3/4 3 55 ) 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION............... 3/4 3-58 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................... 3/4 3 61 3.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION................ 3/4 3 63 l 4.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION l SURVEILLANCE REQUIREMENTS......................... 3/4 3-64 3.3.7.3-l' METEOROLOGICAL MONITORING INSTRUMENTATION......... 3/4 3-66 4.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION i" SURVEILLANCE REQUIREMENTS......................... 3/4 3-67 3.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION........ 3/4 3-69 SH0REHAM - UNIT 1 xxiii . m [

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INDEX LIST OF TABLES (Continued) TABLE PAGE 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................ 3/4 3-70 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION.............. 3/4 3-72 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................ 3/4 3-74 3.3.7.8-1 CHLORIDE INTRUSION CONDUCTIVITY MONITORS......... 3/4 3 78 3.3.7.8-2 CHLORIDE INTRUSION CONDUCTIVITY MONITORS SETPOINTS........................................ 3/4 3-79 4.3.7.8-1 CHLORIDE INTRUSION CONDUCTIVITY MONITORS SURVEILLANCE REQUIREMENTS........................ 3/4 3-80 R 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION.................. 3/4 3-82 l t 3.3.7.11-1 EXPLOSIVE GAS MONITORING I STRUMENTATION.........- 3/4 3-90 i l 4.3.7.11-1 EXPLOS1VE GAS MONITORING INSTRUMENTATION l SURVEILLANCE REQUIREMENTS........................ 3/4 3-92 4 u 3.3.7.13-1 SAFETY PARAMETER DISPLAY' SYSTEM.................. 3/4 3 l 3.3.9-1 FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM i ACTUATION INSTRUMENTATION........................ 3/4 3-101 3.3.9-2 FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS.............. 3/4 3-102 4.3.9.1-1 FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION WRVEILLANCE REQUIREMENTS..................................... 3/4 3-103 1 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES. 3/4 4-12 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS.......... 3/4 4-15 i 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM................................. 3/4 4-18 i SHOREHAM - UNIT 1 xxiv Amendment No.5 f

c ey w-..- INDEX LIST OF TABLES (CONTINUED) TABLE PAGE 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM-- WITHDRAWAL SCHEDULE.............................. 3/4 4 22-3.6.3 PRIMARY CONTAINMENT ISOLATION VALVES............. 3/4 6-23 3.6.S.2-1 REACTOR BUILDING VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES....................... 3/4 6-39 3.7.7.5-1 FIRE HOSE STATIONS............................... 3/4 7-4 3.7.7.6-1 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE STATIONS.................................... 3/4 7-33 3.7.9-1 AREA TEMPERATURE MONITORING...................... 3/4 7-37 3.7.11.1-1 LIMITING VALUES OF SETTLEMENTS OF REACTOR BUILDING (RB)............................ 3/4 7-42 4.8.1.1.2-1 DIESELGENERATORTESTSCHEdULE................... 3/4 8 8 4.8.2.1-1 BATTERY SURVEILLANCE REQUIREMENTS................ 3/4 8 12 3.8.4.1-1 4.16 kV PRIMARY CONTAINMENT PEN 6TRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES................... 3/4 8-20 3.8.4.1-2 LOW VOLTAGE CIRCUIT BREAKER PENETRATION CONDUCTOR PROTECTION............................. 3/4 8-21 3.8.4.2-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION....................................... 3/4 8-25 B3.2.1-1 SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT ANALYSIS................ B 3/4 2-3 B3/4.4.6-1 REACTOR VESSEL TOUGHNESS......................... B 3/4 4-6 5.7.1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS............. 5-8 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION - SINGLE UNIT FACILITY............................. 6-5 i SHOREHAM - UNIT 1 xxy Amendment No. 5

_. _ ~. _ _ _.. i DEFINITIONS L-FRACTION OF LIMITING POWER DENSITY 1.13 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given location divided by 13.4 kW/ft. FRACTION OF RATED THERMAL POWER 1.14 The FRACTION OF RATED THERMAL POWER (FRTP) thall be the measured THERMAL POWER divided by the RATED THERMAL POWER. FREQUENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. GASEOUS RADWASTE TREATMENT SYSTEM 1.16 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed i to reduce' radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpase of reducing the total radioactivity prior to release to the environment. IDENTIFIED LE/.KAGE 1.17 IDENTIFIED LEAKAGE shall be: Leanage into collection systems, such as pump seal or valve packing'or a. leaks, that is captured and conducted to a sump or collecting tank, t b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the opera-tion of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE. ISOLATION SYSTEM RESPONSE TIME 1.18 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include die]al generator starting and sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured. LIMITING CONTROL ROD PATTERN 4 1.19 A LIMITING CONTROL R00 PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operatir.g on a limiting value for APLHGR, LHGR, or MCPR. LINEAR HEAT GENERATION RATE 1.20 LINEAR HEAT. GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod. It i's the integral of the heat flux over the heat transfer area associated with the unit length. L SHOREHAM - UNIT 1 1-3 L

} t I pef 1NITIONS' E LOGIC SYSTEM FUNCTIONAL TEST 1.21 A LOGIC SYSTEM FUNCTIONAL TEST shall-be a test of all logic components, i.'e., all. relays and contacts, all' trip units, solid state logic elements,.etc, of a logic circuit', from sensor-through and including the actuated device, to verify OPERABILITY, The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system stepsJsuch that the entire logic system-is tested. -MAXIMUM FRACTION OF LIMITING POWER DENSITY. i 1;22 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be highest i value of'the FLPD which exists in the core. MEMBER (S) 0F THE PUBLIC 1.23 MEMBER (S) 0F THE PUBLIC.shall include all persons who are not occupation-ally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this. category ar9 persons who enter the site to service equipment-or to make deliveries. This category does include persons who use portions of the ' site for recreational, occupational or other purposes not associated with-the plant. . MINIMUM CRITICAL POWER RATIO 1.24 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the-core. OFFSITE DOSE CALCULATION MANUAL (ODCM)- 1.25 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters.used in the calculation of offsite doses'resulting from radioactive gaseous and liquid effluents effluentmonitoringAlarm/Trlp.inthecalculationofgaseousandliquid Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent-Controls-and Radiological Environ-mental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological u Environmental Operating and Semiannual Radioactive ~ Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7. OPERABLE - OPERABILITY 1.26 A system, subsystem, train, component or device shall be OPERABLE or have l OPERABILITY'when it is capable of performing its specified function (s) 'and when all necessary attendant instrumentation, controls, electrical power,. cooling or seal water, lubrication or other auxiliary equipment that are required for the s to perform its function (s) ystem, subrystem, train, component or device are also capable of performing their related support, function (s). OPERATIONAL CONDITION - CONDITION 1.27 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specif.ied-in Table 1.2. PHYSICS TESTS 1.28 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation aml (1) described in Chapter 14 of the USAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission. SHOREHAM - UNIT 1 1-4 Amendmeet ao. 5 ' n

o DEFINITIONS- ! PRESSURE BOUNDARY' LEAKAGE ?1.29' PRESSURE BOUNDARY LEAKAGE shall be leak ge through a nonisolable fault in-a' reactor coolant system component body, pipe wall,-or vessel wall. PRIMARY CONTAINMENT INTEGRITY

1.30 PRIMARY CONTAINMENT INTEGRITY shall exist when:

a. All primary containment penetrations, required to be closed during accident conditions are either: 1. Capable of being closed by an OPERABLE primary containment automatic isolation system, or 2. Closed.by at least one manual valve, blind flange, 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 equipment hatches are :losed and sealed, c. Leach primary containment air lock is in compliance'with the require- <ments of Specification 3.6.1.3. d.- The primacy containment leakage rates are within the limits of Specification 3.6.1.2. e. ~ The suppression chamber is in compliance with the requirements of ' Specification 3.6.2.1.- f.. The sealing mechanism associated with.each primary containment a penetration;: e.g., welds, bellows, or 0-rings, is OPERABLE. PROCESS CONTROL = PROGRAM-1 1.31 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling,Lanalyses, tests', and determinations'to be made'to ensure that t processing and-packaging of solid radioactive wastas based on demonstrated

processing ~ of actual or simulated wet solid waster will be accomplished in-

-such a way as to assure compliance with 10 CFR Parts 20, 61,.and 71, State regulations, burial ~ ground requirements, and other requirements ]j governing the disposal of radioactive waste. PURGE - PURGING. fj -1.32 PURGE'or-PURGING shall be the controlled process of. discharging air or gas from a confinement to maintain temperature, pressure,' humidity, concen-tration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. RATED ~ THERMAL ^ POWER 1.33 RATED THERMAL POWER shall be a-total reactor core heat transfer rate to the' reactor coolant of 2436 MWt. REACTOR PROTECTION SYSTEM RESPONSE TIME 1.34 REACTOR. PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until deenergization of the scram pilot valve solenoids. The response time may be measured by any series of sequential, oserlapping, or total steps such that the entire response time is measured. SHOREHAM - UNIT 1 1-5 Amendment No. 5

DEFINITIONS REPORTABLE EVENT 1.35 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. ROD DENSITY 1.36 ROD DENSITY shall be the number of control rod notches inserted as a fraction of the total number of control r9d notches. All rods fully inserted is equivalant to 100% R0D DENSITY. SECONDARY CONTAINMENT INTEGRITY 1.37 SECONDARY CONTAINMENT INTEGRITY shall exist when: a. All secondary containment penetrations required to be closed ou-accident conditions are either: 1. Capable of being closed by an OPERABLE secondary containment automatic isolation systsm, or 2. Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as provided in Table 3.6.5.2-1 of Specification 3.6.5.2. b. All secondary containment hatches are closed and sealed, c. The Reactor Building Standby Ventilation System is in compliance with the requirements 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 containment penetration, e.g., welds, bellows, or 0-rings, is OPERABLE. f. The pressure within the secondary containment is less than or equal to the value required by Specification 4.6.5 la. SHUT 00WN MARGIN 1,38 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is subcritical or would be suberitical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e., 68 F; and xenon free. SITE BOUNDARY 1.39 The SITE B0UNDAk,' shall be +%t line beyond which the land is neither ~ owned, nor leased, nor otherwise controlled by the licensee. SOLIDIFICATION 1.40 (NOT USED - REFER TO PCP) SOURCE CHECK 1.41 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. SHOREHAM - UNIT 1 1-6 Amendment No. 5

^f' h y y TABLE 3.3.7.9-1 (Continued) FIRE DETECTION INSTRUMENTATION "i SAFETY-RELATED ZONE-TOTAL NUMBER OF INSTRUMENTS

  • HEAT-SM0KE-FLAME Ix79}

{x797 (x/y) x '. 3 HG. Room 1138 El. 161'-0" 3/0 MCC West Room El. 112'-9" I/u MCC East Room El. 112'-9" '3/0 Remote Shutdown Panel Enclosure E1. 63'-0" 0/2 HPCI Turbine E1. 8'-0" 0/6 RCIC Turbine El. 8'-0" 0/5- -1TK607R Horizontal Cable Trays 2/0 -1TX600R Vertical Cable Trays 5/0 RBSVS'- FLT - 1A E1. 112'-9" 2/0 RBSVS - FLT - 1B El 112'-9" 2/0 MCC Room El. 40'-0" 2/0 3. Turbine Building Electrical Manhole No.1 El S'-8" 0/2 2/0 (located in normal switchgear room) 4, Screenwell Pump House. Pump Cubicle A 3/0##2 Pump' Cubicle B 3/0## '5. ' Yard p 1 ' Emergency Diesel F.O. Transfer Pump -House A 2/0 Emergency Diesel F.0. Transfer Pump 4 p' House B 2/0 . Emergency Diesel F.O. Transfer Pump n House C 2/0 t TABLE NOTATIONS

  • (x/y): x is number of Function A (early warning area fire detection and noti--

fication) instruments, y is number of Function B (actuation of fire suppres-aion-system and notification) instruments. -#The fire detection instruments located within the primary containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

    • Heat detectors are non-restorable spot type fixed temperture.
    1. Includes projected beam type smoke-detector SHOREHAM - UNIT 1 3/4 3-83

INSTRUMENTATION RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3/4.3.7.10 (NOT USED) (Refer to Section 6.8.4 and ODCM). E BL SH0REHAM - UNIT 1 3/4 3-84 AMENDMENT NO. 5

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[', INSTRUMENTATION-l EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION' '3.3.7.11 The explosive gas monitoring instrumentation channels shown in LTable 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set ?to ensure that the limits of Specification 3.11.2.6 are not exceeded.. i LAPPLICABILITYi As shown-in Table 3.3.7.11-1 ACTION:- a.- With an explosive gas monitoring instrumentation channel alarm / trip. setpoint 1ess conservative than required by the above specification,. L declare the ch nnel inoperable and take ACTION shown in B ~ Table 3 3.7;11-1. b. With less than the minimum number of explosive gas monitoring l 4. instrumentation channels OPERABLE,;take the ACTION shown.in. Table 3.3,7.11-1. Restore the inoperable instrumentation to OPERABLE status within the-time specified in the ACTION or prepare.and submit a Special; Report to the Commission pursuant to Specification 6.9.2:to explain why this inoperability was not corrected within the time specified. 'c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. -SURVEILLANCE REQUIREMENTS 4.3.7.11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in- .Tabl e : 4. 3; 7.11-1, s i SHOREHAM - UNIT 1 3/4 3-89 AMENDMENT NO. 5 w

3, t n '(:a r TABLE 3.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION g c-MINIMUM CHANNELS 4 INSTRUMENT OPERABLE-APPLICABILITY; 4CTION-1.- (NOT-USED). ' ' 2. MAIN CONDENSER OFFGAS~ ' TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a, . Hydrogen Mdnitor m -(downstream of - recombiner)- 1# 121 ne f 9 Y 0 L s E E ?; II 5 6 f - g p c .SHOREHAM - UNIT l' 3/4 3-90 AMENDMENT NO 5 3:3

TABLE 3.3.7.11-1 (Continued) TABLE NOTATIONS

  • (NOT USED)
    • During main condenser offgas treatmert system operation.
  1. A monitor connected to the operating offgas, loop shall be OPERABLE.

ACTION STATEMENTS ACTION 121 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of main con-denser offgas treatment system may continue for up to 30 days provided grab samples are collected at least once per 4 hours and analyzed within the following 4 hours. 1 SHOREHAM - UNIT 1 3/4 3-91 AMENDMENT NO. 5

In

.
h LTABLE 4.3.7.11-1 EXPLOSIVE' GAS ~ MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

=- 4 -MODES" CHANNEL IN WHICH' CHANNEL-SOURCE' CHANNEL'. FUNCTIONAL' SURVEILLANCE INSTRUMENT-CHECK-CHECK 1 CALIBRATION TEST REQUIRED p.. 1., '(NOTtSED). ' 2.- MAIN ()NDENSER OFFGAS TREATMINT SYSTEM. et . EXPLOSIVE GAS. l MONITORING SYSTEM a.' Hydrogen Monitor D N.A. .Q(3) M -(downstream of recombiner) t + + s SHOREHAM - UNIT 1 3/4 3-92 AMENDMENT NO. 5

J-h. ' TABLE 4.3.7.11-1 (Continued)' TABLE NOTATIONS I ~

  • (NOT'USED).
    • During main condenser offgas treatment system operation.

t (1) (NOT USED)- -(2)_ (NOT.USED).: (3) The. CHANNEL CALIBRATION shall include the use of standard gas. samples containing.a nominal one. volume percent hydrogen,' balance. nitrogen.- , y.. ? ,p' p s ~ + ?' i t h 4

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7 i 4 SHOREHAM - UNIT 1 3/4 3-93 AMENDMENT NO 5 .l

i llSTRUMENTATION LOGsE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.12. The loose part detection system ~shall be OPERABLE. APPLICABILITY:, OPERATIONALCONDITIONSIand5. 4 ' ACTION: a '. - With one or more loose part detection system channels inoperable for. ~ more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the-next 10 days. outlining the cause of the malfunction and the plans for restoring .the-channel (s) to OPERABLE status, b.- The provisions of Specification 3.0.3 and 3.0.4 are not applicable. !S_URVEILLANCE-REQUIREMENTS .4.3.7.12 Each channel of'the. loose part detection system shall be demonstrated OPERABLE by performance of. a: a. CHANNEL CHECK at least once per 24. hours, b. CHANNEL FUNCTIONAL TEST at least once per-31 days, and c. . CHANNEL CALIBRATION at least once per 18' months. De SHOREHAM - UNIT 1 3/4 3-94

1, ; .g s,. .r - 3/4M1' RADIDACTIVE EFFLUENTS.: J! 4 I3/4fl.'.1LIQUIDEFFLUENTS~ - CONCEN1,*tATION ' 'i 3 g LIMITING CONDITION FOR OPERATION-t 3/4'.11.1.1 (NOTfUSED)< (Refer to'Section 6.8.4 and ODCM). i la f. !i ,/,i (

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3/4.11.1.3- - (NOT USED) (Refer to Section 6.8.4 and ODCM) 1 ,,-p i. 1.: e' 1 4 443 ( h { ' b '; I SHOREHAM - UNIT 1 3/4 11-6 AMENDMENT NO. 5 1

RADI0 ACTIVE EFFLUENTS i ~ LIQUID HOLDUP TANKS 'l LIMITING CONDITION FOR OPERATION 3.11.1.4' The quantity of-radioactive. material contained in each outside . temporary tank shall.be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble ggses. ,e APPLICABILITY: At'all times. -1 i. d' . ACTION: a. _ With the quantity of radioactive material-in any outside temporary tank exceeding the above limit, immediately suspend all-additions of radioactive material to the tank and within 48 hours reduce-the tank contents to within the limit, and describe the events. leading to this-

condition in the next Semiannual Rad'oactive Effluent Release Report.

l b. The provisions of Specifications 3.0.3 and 3.0.'4 are not applicable. . SURVEILLANCE REQUIREMENTS ~ l 4.11.104 The quantity of. radioactive material centained in each outside i temporary' tank shall be determined to be-within ti'e above limit-by analyzing a l representative sample of the tank's contents at-least once per:7 days when radioactive materials are being added to'the tank, y i I i r l SHOREHAM - UNIT 1. 3/4 11-7

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S, ,. A c,r-: n ,'{(lg?{,.* l-l196 i 6 +. o t ')'l ' i k. 2Nk ! 56 ' M W,, L, RADIDACTIVE EFFLUENTS ,4 g,. e. e lg, l DOSE - NOBLE GASESB. L . rp ,W !? V LIMITING CONDIT' ION FOR OPERATION -'a.:n . r. E. .y. ly, -3/4.11'.2'2ll(NOT'USED.F(RefertbSection6.8.4andthe0DCM) '*/(~ - IJ is,f I 'yl} t 4 "k,- i k' 6 ' ' i.-], y 1.!c i i k. t.- ( -D. ~ f.. ?'! i:. i j ', s O \\ t i bi 1 4 ) f > ' - i,,. i) : j' ,c s ; k k < '- :i E f 1i <(k I' 1 :,i) j i 7-C, Q. ; I I t SHOREHAM,- UNIT 1-3/4 11-12 AMENDMENT N0. 5 I t 4 ,( f.. 9 i

q4 ..n \\s i ,i e;j^ ( .6 - RA010ACTIVElEFFLUENTSi ~t 1 ' DOSE -'10 DINE-131, 10 DINE-133. TRITIUM AND RADIONUCLIOES IN PARTICULATE FORM y 4 s x(, ' LIMITING CONDITION FOR OPERATION + L3/4.11.2.3) (NOT USED);-(Refer to Section 6.8.4 and the ODCM): '} 1 e c. 1,,," /. Y I y -. i f P .I'. l .h 't -t J 't e B..

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.t I I i RADI0 ACTIVE EFFLUENTS i GASEOUS RADWASTE TREATMEhT SYSTEM i LIMITING CONDITION FOR OPERATION i h 3/4.11.2.4 (NOT USED) (Refer to Section 6.8.4 and the ODCM) a ? t I 1, I ,i. I t i t 4 i SHOREHAM - UNIT 1 3/4 11-14 AMENDMENT NO.5

t t - R.A.f!0AcTIVEEFFLUENTS VENTILAT7pN EXHAU$T TREATMENT SYSTEM - I LIMITING CONDITION FOR OPERATION ~ i 1 3/4.11.2.5 (NOTUSED) (Refer to Section 6.8.4 and the ODCM) l O P i .i + e SHOREHAM - UNIT 1 3/4 11-15 AMENDMENT NO. 6

l RADIDACTIVE EFFLUENTS i EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION i. 3.11.2.6 The concentration of hydrogen in the main condenser offgas treathent = system shall be limited to less than or equal to 4% by volume. APPLICABILITY: Whenever the main condenser steam jet air ejector system is in ACTION: With the concentration of hydrogen in the main condenser offgas a. treatment system exceeding the limit, restore the concentration to within the limit within 48 hours, b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determised to be within the above limits by con-tinuously monitoring the waste p15es in the main condenser offgas treatment system with the hydrogen monitoi required OPERABLE by Table 3.3.7.11-11 of Specification 3.3.7.11. [ i t e \\ . IHOREHAM - UNIT 1 3/4 11-16

RADICACTIVE EFFLUENTS MAIN CONDENSER LIMITING CONDITION FOR OPERATION 3.11.2.7 The gross radioactivity (beta and/or gamma) rate of noble gases measured at the main condenser steam jet air ejector shall be limited to less than or equal to 244 mil 11 curies /second. APPLICABillTY: OPERATIONAL CONDITIONS 1, 2*, and 3*, ACTION: With the gross radioactivity (beta and/or gamma) rate of noble gases at the main condenser steam jet air ejector exceeding 244 mil 11 curies /second, restore the gross radioactivity rate to within its limit within 72 hours or be in at least HOT SHUTDOWN within the next 12' hours. SURVEILLANCE REQUIREMENTS 4.11.2.7.1 The radioactivity rote of noble gases at the outlet.of the main condenser steam jet air ejector shall be continuously monitored in accordance with Specification 3.3.7.11, 4.11.2.7.2 The gross radioactivity (beta and/or gamma) rate of noble gases from the main condenser steam jet air ejector shall be determined to be within the limits of Specification 3.11.2.7 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the discharge (prior to dilution and/or discharge) of the main condenser steam-jet air ejector: a. At least once.per 31 days, b. Within 4 hours following an increase, as indicated by the Main Condenser Air Ejector Noble Gas Activity Monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady-state fission gas release from the reactor coolant. ^When the main condenser steam jet air ejector is in operation, i SHOREHAM - UNIT 1 3/4 11-17

g ll l 1 RADI0 ACTIVE EFFLUENTS i CONTAINMENT FURGING AND VENTING t LIMITING CONDITION FOR OPERATION 3/4.11.2.8 (NOT USED) (Refer to Section 6.8.4 and the ODCM) j ( i E-s P - t - I 5 -l i i - ) I - r t i i 'SHOREHAM - UNIT 1 3/4 11-18 AMENDMENT NO. 5 . - ~. ...n

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j t [ i i [' t RADI0 ACTIVE EFFLUENTS ) 3/4.11.3 SOLID RADI0 ACTIVE WASTE I (NOT USED) (Refer to PCP) e t P s L 9 y f i 6 b .SHOREHAM - UNIT 1 3/4 11-20 AMENDMENT N0.5

t l ~ RADI0 ACTIVE EFFLUENTS ' 3/4.11.4 TOTAL DOSE (NOT USED) (Refer to Section 6.8.4 and ODCM) O SHOREHAM - UNIT 1 3/4 11-21 AMENDMENT NO.5 i

3/4.12'RADIOLOGJCALENVIRONMENTALMONITORING (NOT USED) L ,3/4.12.1 MONITORING PROGRAM (NOT USED) (Refer to Section 6.8.4 and ODCM) I ) i l i I i .j 1 ) i t ? s l -SHOREHAM - UNIT 1 3/4 12-1 AMENDMENT NO. 5 ( l

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RADIOLOGICAL ENVIRONMENTAL MONITORING -(NOT USED) 3/4.12.2 LAND USE CENSUS (NOT USED) (Refer to Section 6.8.4 and ODCM) k 'i f I P f l t j. 4 t o l u 1. !SHOREHAM - UNIT 1 3/4 12-12 AMENDMENT NO,5 I

i.. i' = RADIOLOGICAL ENVIRONMENTAL MONITORING (NOT USED) I 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM ~ (Refer to Section 6.8.4 and ODCM) (NOT USED) k i t 1 lSHOREHAM-UNIT 1 3/4 12-13 AMENDMENT NO.5

l INSTRUMENTATION l BASES { MONITORING INSTRUMENTATION (Continued) 3/4.3.7.4 REMOTE SHUTOOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50. l 3/4.3.7.$ ACCIDENT MONITORING INSTRUMENTATION l The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an' accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980. 3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted. 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core, r 3/4.3.7.8 CHLORIDE INTRUSIM MONITORS r The chloride intrusion monitors provide adequate warning of any leakage in the condenser or hotwell so that actions can be taken to mitigate the consequences of such intrusion in the reactor coolant system. With only a minimum number of instruments available increased sampling frequency provides adequate information for the same purpose. SHOREHAM - UNIT 1 B 3/4 3-5 s

to p - INSTRUMENTATION BASES $NITORINGINSTRUMENTATION(Continued) 3/4.3.7.9 FIRE DETECTION INSTRUMENTATION l OPERABILITY of the' fire detection instrumentation ensures that adequate t warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire watch patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. i 3/4.3.7.10 RADIOACTIVE IIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (NOT USED) (Refer to ODCM) l 3/4. 3. 7. "'. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The instrumentation includes provisions for monitoring (and controlling) the concentrations of.potentially explosive gas mixtures in the main conden6er offgas treatment system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of l Appendix A to 10 CFR Part 50. L 3/4.3.7.12 LOOSE-PART DETECTION SYSTEM l The OPERABILITY of the loose-part detection system ensures that suffi-cient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allow-able out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981. l 1 SHOREHAM - UNIT 1 B 3/4 3-6 AMENDMENT N0.5

E 3/4.11 RADI0 ACTIVE EFFLUENTS-BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1' CONCENTRATION (NOT USED) (Refer to ODCM) 3/4.11.1.2 DOSE (NOT USED) (Refer to ODCM) SHOREHAM.- UNIT 1 B 3/4 11-1 AMENDMENT NO. 5

c RADI0 ACTIVE EFFLUENTS I i BASES a 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM (NOT USED) -(Refer to ODCM) 3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the cuantity of radioactive material contained in the specified tanks provices assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less i .than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the r,earest potable water supply and the nearest surface water supply in an UdRESTRICTED AREA. i 3/4.11.2 GASEOUS EFFLUENTS 1 3/4.11.2.1 DOSE RATE I (NOT USED) (Refer to ODCM) ) 1 b '] F SHOREHAM - UNIT 1 B 3/4 11-2 AMENDMENT NO. 5

r i RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.2 DOSE - NOBLE GASES (NOT USED) (Refer to ODCM) 3/4.11.2.3 DOSE - 10 DINE-131,10 DINE-133 TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM ~~~ (NOT USED) (Refer to ODCM) i 'l i SHOREHAM - UNIT 1 B 3/4 11-3 AMENDMENT NO.5 i

~.%,-- i i 1 !' : (; s RADIOACTIVE EFFLUENTS e i BASES 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM 4 t (NOT.USED) (RefertoODCM) l t 3/4.11.2.5 -VENTILATION EXHAUST TREATMENT SYSTEM i (NOT USED). (Refer to ODCM) 5 l 4 e f 'W I P i 6 l j. t . SHOREHAM UNIT 1 8 3/4 11-4 AMENDMENT NO.5

L RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the mun condenser offgas treatment system is maintained below the flammability limit of hydrogen. The 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 recombiner, booster ejector, where the gas mixture is below the flammability limit. Main-taining the concentration of hydrogen below its flammability limit provides assurance that the releases of radioactive materials will be controlled in con-formance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50, 3/4.11.2.7 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable 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 implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50. 3/4.11.2.8 CONTAINMENT PURGING AND VENTING (NOT USED) (RefertoODCM) 3/4.11.3 SOLID RADI0 ACTIVE WASTE (NOT USED) (RefertoPCP) 3/4.11.4 TOTAL DOSE (NOT USED) (RefertoODCH) SHOREHAM - UNIT 1 B 3/4 11-5 AMENDMENT NO. 5

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ADMINISTRATIVE CONTROLS 6.61 PROCEDURES AND PROGRAMS

6. 8.1 - Written procedures shall be established, implemented.: and maintained covering-the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. b. Tlieapplicableproceduresrequiredtoimplement:therequirementsof v NUREG-0737 c. Refueling operations. d. Surveillance and test activities of safety-related, equipment. e. Security Plan implementation. f. Emergency Plan implementation.- g. Fire Protection Program implementation. h. PROCESS CONTROL PROGRAM implementation. i. OFFSITE DOSE CALCULATION MANUAC implementation, j. Quality Assurance Program for effluent and environmental monitoring. 6.8.2 Each procedure of Specification 6.8.1, and changes thereto. shall be reviewed by the ROC prior to implementation. The Plant Manager shall approve l Station Administrative procedures Sec4rity Plan implementing procedures and Emergency plcn implementing procedures prior to-implementation. Other procedures of Specification 6.8.1 shall be 6pproved by the appropriate plant Division Manager or by the Plant Manager' prior to implementation. Each Plant Division Manager shall be responsible for a designated set of procedures._ Th!.se procedures shall be reviewed periodically as set forth in administrative procedures. 6.8.3 Temporary changes to procedures _of Specification 6.8.1 may be made provided: 4 a. 'The intent of'the original procedure is not altered; b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's license on-the unit affected; and .c. The change is documented, reviewed by the ROC. and approved ~by the Plant Manager within 14 days of implementation. 6.8.4 The. following programs shall be established, implemented, and maintained: a. Primary Coolant Sources Outside Containment A program to recace leakage from those portions of systems outside containment that could.contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, Hydrogen Recombiners, Reactor Water Cleanup, Coolant Sampling, Reactor Building Equipment Drain, Reactor Building Floor Drain, and Reactor Building Standby Ventilation System,. Instrumentation Lines and Post Accident Monitoring System. 1 SHOREHAM - UNIT 1 6-13 Amendmt;nt No. 1 JAN 161990 I t

gg n 'I 1; ,n bdi L y. , ADMINISTRATIVE CONTROLS l L PROCEDURES AND PROGRAMS (Continued)' [ The program shall include the following: [ J ], '1. Preventive maintenance and periodic visual _ inspection require-I .ments, and [ 2. Integrated leak test. requirements for each system at refueling _. cycle intervals or less. .b.- In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine-a the airborne iodine concentration in vital areas under acciderit conditions. This' program shall include the following: + 1. Training of personnel, ] 2. Procedures-for monitoring, and-3. Provisions'for maintenance of sampling and analysis equipment, c. . Post-accident Sampling g 'Aprogramwhichwillensurethe.capabilityftoobtainand. analyze -reactor coolant, radioactive iodines and particulates in' plant- =i gaseous effluents, and containment atmosphere samples under accident j conditions. The program shall' include the;following: 1. Training of personnel, 2. Procedures for sampling and analysis, and. i 3.- Provisions for maintenance ^of sampling and analysis equipment. d. -Radioactive Effluent Controls Program I w A-program shall be provided conforming with 10 CFR 50.36a for the' i control of radioactive effluents-and for maintaining the doses to MEMBERS OF THE'PUBLIC from radioactive effluents as low as a V reasonably achievable. The' program (1) shall be contained in the j 10DCM, (2) shall be implemented by operating procedures, and (3)' -shall include remedial actions to be taken whenever the program 3 limits are exceeded. The program shall include the following i elements: 1. Limitations-on the operability of radioactive liquid and gaseous' monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology I. in the ODCM,- 'W f 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, 3. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, SHOREHAM - UNIT 1 6-14 Amendment No. 5 1 r -

p,- .x, _) ,c ') ADMINISTRATIVE' CONTROLS 1 u Radiosctive Effluent' Controls Progras'(Continued) ~ 4.. Limitations on the annual and quarterly doses or dose l commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid affluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, t 5. Determinationof-cumulativeand'projecteddosecontributiont from radioactive effluents for the current calendar quarter j current calendar year in accordance with the methodology er. parameters' in the ODCM at least every 31 days. 6. Limitations on the operability'and use of the liquid and; e gaseous effluent treatment systems to ensure that the-appropriate portions of these systems are used to reduce releases-of radioactivity when the projected doses in a 31-day. 4 L period would exceed 2 percent of the guidelines for the annual i f dose or dose commitment conforming to Appendix I to= 4 10 CFR.Part 50, 7. Limitations on the dose rat.e resulting from radioactive material released in gaseoos effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 4 10 CFr. Part 20, Appendix B, Table II, Column 1, 8. Limitations' on the annual and quarterly air doses resulting g from noble gases released in gaseous effluents from each unit a to areas beyond the' SITE BOUNDARY conforming;to Appendix I to L 10 CFR Part 50, l ? p 9. Limitations on the annual and quarterly. doses to a MEMBER OF l u THE:PUBLIC from Iodine-131, Iodine-133, tritium, and all _ l radionuclides in particulate form with half-lives greater than a 8 days in gaseous effluents released from each-unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, a a 10. Limitations on Venting and purging of the Mark II containment j through the Standby Gas Treatment System to maintain releases as low as reasonably achievable, and a 11. Limitations on the annual dose or dose commitment to any MEMBER-l 0F THE PUBLIC due to releases of radioactivity-and to radiation from uranium fuel cycle' sources conforming to the 40 CFR q Part 190, [ e. Radiological Environmental Monitorina Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall i provide (1) representative measurement of radioactivity in the highest potentit.1 exposure pathways, and (2) verification of the i SHOREHAM - UNIT 1 6-14a Amendment No. 5

7 - ~ -ADMINISTRATIVE CONTROLS 1 '~ Radiological' Environmental Monitorina Program (continued)' l - accuracy of the effluent monitoring program and modeling of-environmental exposure pathways. The program shall (1) be_ contained. in:the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following: 1. Monitoring, sa.s ing, analysis,'and reporting of radiation and' ~ radionuclides in the environment.in accordance with the i methodology and parameters in the-ODCM, t 2.1 A Land Use Census to ensure that changes in the use of areas at' and beyond the SITE BOUNDARY are identified and that g modifications to the monitoring program are made if required by-the results of this census, and-t i [ 3. Participation in a Interlaboratory Comparison Program to ensure ~ that, independent checks on the precision and accuracy of the l" measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program l; for environmental monitoriryg. 6.9 REPORTING REQUIREMENTS ROUTINE REPORTSL g 6.9.'1..In addition to the applicable reporting requirements of Title 10,' Code F <of Federal Regulations, the following reports shall be submitted to the i E* . Regional: Administrator of the Regional Office of the-NRC unless otherwise noted. l l^ f TARTUP' REPORT I S - 6.9.1.1' A' summary report of plant startup-and power escalation testing shall r be submitted following (1)~ receipt of an-Operating License, (2)' amendment to~ -the license involving a planned increase in power leve1~, (3) installation of-fuel that.has a different design _or has been manufactured by a different fuel supplier, and (4) modifications ~that;may have significantly altered:the. i

nuclear, thermal, or' hydraulic performance of'th station.

6.9.1.2, The startup report shall address each of-the tests identified in the Final? Safety Analysis Report a.1 shalliinclud. a description of the met.sured. values ofc the operating conditions or characteristics obtained during che test program and a comparison of these values with design predictions-and specifi- . cations. Any corrective actions that were required to obtain satisfactory I operation shall also be described. Any additional specific' details required in~1icense conditions based on'other commitments shall be included in this report. i SHOREHAM - UNIT 1 6-14b Amendment No.5 t

' ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) - 6. 9.1. 3 Startup reports shall be submitted within (1).90 days following completion of the startup test program, (2) 90 days following. resumption or connencement of commercial power operation,'or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, comp 1 tion of startup test program, 9 and resumption or commencement of commercial-operation) supplementary reports-shall be submitted at least every 3 months until all three events have been completed. ANNUAL' REPORTS 6.9.1.4' Annual reports covering the activities of ihe unit as described below -for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following -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) receiving exposures greater than 100 mrams/yr and their associated nntem exposure according to work and job
  • functions * (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special mainte-nance (describe maintenance), waste processing, and refueling).

The dose assignments to.various duty functions may be estimated based on pocket dosi-meter, thermoluminescent dosimeters (TLD) or film badge measurements. Small exposurestotallinglessthan20%oftheIndividualtotaldoseneednotbe accounted for. In the aggregate, at least 80% of the total wholebody dose received from external sources should be assigned to. specific major work functions. -ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6. 9.1. 6 That Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall be include summaries . interpretations,andanalysisoftrendsoftheresultsoftheRadIological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and-(2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

  • This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

SH0REHAM - UNIT 1 6-15 Amendment No. 5

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f> ADMINISTRATIVE CONTROLS' y.. < - e SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT d '6;9.1.7.The Semiannual Radioactive Effluent Release Report covering the aperation of the unit during the previous 6 months'of operation shall be : Jiiubmitted within-60-days. after January 1 and July 1 of each year.,The report-shall. include a summary of the quantities of radioactive liquid and gaseous e?fluents and' solid waste released from the unit.1.The material provided shall 'be (1) consistent-with'the objectives outlined inithe ODCM and PCP._and (2) in-1, conformance'with 10 CFR 50.36a-and Section IV.B.1 of Appendix I to-10 CFR. 'Part 50. 'j l 1 r' t t I ,1 -i a t i i 'SHOREHAM - UNIT 1 6-16 Amendment No. 5 ?,

I 1 4 t I '.' k i ? u _ y l '; ADMINISTRATIVE CONTROLS c, 4, il c \\ t i

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fI .SHOREHAM - UNIT 1 6-17 Amendment No.5 7 \\ i.;pfi f

P c 1 E d y oi p' ADMIN'ISTRATIVE CONTROLS it I. .e i e -MONTHLY OPERATING! REPORTS I 6.9.1.8 Rout'ine reports of operating statistics _and shutdown experience, ( including documentation of all' challenges to the main steam system safety-i relief valves,-shall be submitted on a monthly basis to the Director, Office ~ of. Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a.' copy to the Regional Administrator of.the Regional.0ffice of the NRC no later than the 15th'of each month following the calendar month covered t M by_the. report. j ns .SPECIAL-REPORTS <

l 6.9.'2T Special-reports shall-be submitted to the Regional-Administrator of.the j

g-s g ._ Regional Office'of the NRC1within the time period specified for each report. f 6.10 RECORD RETENTION' 6.10.1 In; addition to.the applicable record retention requirements of Title-E 10', Code of Federal Regulations, the following records shall be retained for at-least the minimum period' indicated. l ! 6;10.2 The following records 'shall be retained _-for at -least 5 years-Records and logs of station operation covering time interval at each a.- + power-. l evel. -b. Records.and logs'of principal maintenance activities,_ inspections, repair, and replacement of-principal items of equipment related to j nuclear safety. n b 1 c. All REPORTABLE EVENTS.

1. -

~ Y Records of surveillance activities, inspections, and' calibrations i d required by.these Technical Specif.ications. s ,y.-" - e. . Records of changes made to the procedures required by-Specification 6.8.1. 5 y l1 - f.

Records-of radioactive shipments.

i 1 'i g. -Records of sealed source and fission detector leak tests and

results.

'1 L . h,' . Records of annual physical inventory of all sealed source material l of record. I 4' 6.10.3 The'following records shall be retained for the duration of the unit Operating License: L Records and drawing changes reflecting station design modifications L a. made.to systems-and equipment described in the Final Safety Analysis Report. SHOREHAf-UNIT 1 6-18 l 3

41. d ' 5/

4

s f .M 1f ^ ADMINISTRATIVE CONTROLS [ s o . RECORD RETENTION (Continued) b. _ Records of. new and irradiated fuel inventory, fuel transfers, and assembly burnup histories. i c. Records of radiation exposure for all individuals entering radiation'- j control areas, d.- Records of gaseous and liquid radioactive material ~ released to the. environs. s e. Records of transient or operational cycles for those unit components-identified in Table 5.7.1-1. f.. Records.of-reactor tests and experiments. g. Records of training and qualification for current members of the i . unit staff, i h. Records of inservice inspections performed pursuant to these L Technical Specifications.. i 1. Records of quality assurance activities required by the Quality.- Assurance. Manual which are not listed in Section 6.10.2. i ~j. Records of reviews performed for changes made to procedures or b equipment.or' reviews of tests and experiments pursuant to 10 CFR 50.59. k. Records of meetings 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 ser-vice life commences and associated: installation and-maintenance .1 records. m. Records of analyses required by the radiological environmental moni-toring program 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. n. Records of reviews performed for changes made to the OFFSITE DOSE. CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 snd shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

SHOREHAM - UNIT 1 6-19 Amendment No. 5

k ( - ADkINISTRATIVECONTROLS 6.12 HIGH RADIATION-AREA 6.-12.1 In lieu of the " control device" or " alarm signal" required by para-graph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the o intensity of radiation is greater than 100 mrems/h but less than 1000 arems/h , shall'be barricaded and conspicuously posted as a high radiation area and entrance thereto;shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall-be provided with or accompanied by.one or more of'the following: a.- 'A rsdiation-monitoring device which continuously indicates-the radiation dose rate in the area. b. A radiation monitoring device which continuously integrates the. radiation dose rate'in the area and alarms when a preset integrated dose is Nceived. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been estab-lished and personnel have been made knowledgeable of.them. c.' -A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device, who is responsible for providing positive control'over the acti,vi-ties within the area and shall perform periodic-radiation surveil-lance at the frequency specified by the Health Physics Engineer in the RWP. 6.12.2 -In addition to the requirements of Specification 6.12.1, areas. accessible to personnel with radiation levels such that a major portion of-the body could receive in'1-hour a dose greater than 1000 mreas shall be provided with. locked doors.to prevent unauthorized entry, and the keys shall be maintained under the administrative control of1the Watch Supervisor on duty. and/or the-Health Physics Engineer. Doors shall remain locked.except during- - periods of access by personnel under an approved.RWP which shall specify the dose rate levels'in the immediate work area and the maximum allowable stay time for individuals in that area. ~For individual areas accessible to personnel-with radiation levels such that a major portion of-the body could receive in'1 hour a dose in excess of 1000 mrems** that are located within lar0e areas, such as the containment, where no enclosure exists for purposes i of, locking, and no enclosure can be reasonably constructed around the individual . areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device. In lieu of the stay time specifi-cation of the RWP, continuous surveillance, direct or remote (such as use of . closed circuit TV cameras) may be made by personnel qualified in radiation pro-tection procedures to provide positive exposure control over the activities within the area.

  • Healthphysicspersonnelorpersonnelescortedbyhealthphysicsiersonnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
    • Measurement made at 18 inches from source of radioactivity.
SHOREHAM - UNIT 1 6-20

,g a s j; i ADMINISTRATIVE CONTROLS: l 6.~13. PROCESS CONTR0LtPROGRAM'(PCP) Changes to the PCPi i .a. Shall be' documented and records of reviews performed shall be retained as required by Specification 6.10.3n. This documentation. shall:contain: 1. Sufficient information to support the change together with the l ' appropriate analyses or evaluations justifying the change (s) and 2. A determination that the change will maintain the-overall conformance of.the solidified waste product to existing i requirements of Federal, State, or other applicable regulations. L

b.=

Shall-become effective after review and acceptance by the ROC and the' approval of the Plant Manager, e 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) Changes to the ODCH:

a. " Shall-be documented and records'of reviews performed shall be c-retained as required by Specification 6.10.3n.

This documentation i shallt contain: c 1; Sufficient information to support the change together with the . appropriate analyses or evaluations justifying the change (s) and. .i ) 2. A. determination that the change;will maintain the level of ~40 CFR Part 190,-10 CFR 50.36a, quired by 10 CFR 20.106, 3 radioactive effluent control re .and Appendix I to 1 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. h b. Shall become effective after review and acceptance by the ROC and { D the. approval of the Plant Manager, j c. Shall'be submitted to the Commission.in the form of a complete .i 11egible copy of the entire ODCM as'a part.of or concurrent with the P' Semiannual Radioactive ~ Effluent Release Report for the period of the i . report in which any change to the 0DCM was made. Each change shall l =be identified by markings in the margin of the affected pages, L clearly indicating the area of the pa j ~ indicate the date (e.g., month / year) ge that was changed, and shall the change was-implemented. 'l m i l 1 SHOREHAM - UNIT 1 6-21 Amendment No. 5 i

<+ ,t .s..' l.. N,;, iADMINISTRATIVE CONTROLS '6:15 MAJOR CHANGES TO RADI0 ACTIVE. LIQUID, GASEOUS,.AND SOLID WASTE TREATMENT 2 '5Y51EM5 r (NOT USED): p t e r v t'f 3, s - i y c ',,e d, i, I r '3 f . t.- i t'$l ,h, i-1.,w l- ' ' SHOREHAM'- UNIT 1 6-22 Amendment No. 5 -1: - gi 'j' ')' ,}}

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