ML20217Q103
| ML20217Q103 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/05/1998 |
| From: | NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | |
| Shared Package | |
| ML20217Q094 | List: |
| References | |
| NUDOCS 9803110375 | |
| Download: ML20217Q103 (130) | |
Text
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Section II )
l Markup of Proposed Changes l
l The attached markups reflects the currently issued revision of the Technical Specifications listed ,
l below. Pending Technical Specifications or Technical Specification changes issued subsegaent to i this submittal are not reflected in the enclosed markup.
i
! The following Technical Specifications are included in the attached markup:
Technical Specification Title Page(s) l Refer to Table 1.
9803110375 DR 980305 p ADOCK 05000443 i PDR Page1
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INDEX !
, 1. 0 DEFINITIONS l
SECTION PAGE 1.1 ACTI0N........................................................ 1-1
- 1. 2 ACTUATION LOGIC TEST.......................................... 1-1
- 1. 3 ANALOG CHANNEL OPERATIONAL TEST............................... 1-1
- 1. 4 AXIAL FLUX DIFFERENCE......................................... 1-1
- 1. 5 CHANNEL CALIBRATION........................................... 1-1
- 1. 6 CHANNEL CHECK................................................. 1-1
- 1. 7 CONTAINMENT INTEGRITY......................................... 1-2 1.8 CONTROLLED LEAKAGE............................................
1.9 CORE ALTERATION...............................................
1-2 1-2 g/
1.10 CORE OPERATING LIMITS REP 0RT.................................. 1-2 i l
j 1.11 DIGITAL CH/NNEL OPERATIONAL TEST ............................. 1-2 1.12 QOSE EQUIVALENT I-131........................................ 1-3 1.13 E - AVERAGE DISINTEGRATION ENERGY............................ 1-3 1.14 ENGINEERED SAFETY FEATURES RESPONSE TIME..................... 1-3 g 1.15 FREQUENCY NOTATI0N........................................... 1-3 1 1 1.16 GASEOUS RADWASTE TREATMENT SYSTEM............................ 1-3 1.17 IDENTIFIED LEAKAGE........................................... 1-3 1.18 MASTER RELAY TEST............................................ 1-4 1.19 MEMBER (S) 0F THE PUBLIC...................................... 1-4 '
1.20 0FFSITE DOSE CALCULATION MANUAL.............................. 1-4 1.21 OPERABLE - OPERABILITY....................................... 1-4 1.22 OPERATIONAL MODE - M0DE...................................... 1-4 1.23 PHYSICS TESTS................................................ 1-4 i 1.24 PRESSURE BOUNDARY LEAKAGE.................................... 1-4 \
1.25 PROCESS CONTROL PR0 GRAM...................................... 1-5 1.26 PURGE - PURGING.............................................. 1-5 1.27 QUADRANT POWER TILT RATI0.................................... 1-5 l 1.28 RATED THERMAL P0WER.......................................... 1-5 1.29 REACTOR TRIP SYSTEM RESPONSE TIME............................ 1-5 I
1.30 REPORTABLE EVENT.............................................. 1-5 1.31 CONTAINMENT ENCLOSURE BUILDING INTEGRITY..................... 1-5 1.32 SHUTDOWN MARGIN.............................................. 1-6 1.33 SITE B00NDARY................................................ 1-6 1.34 SLAVE RELAY TEST.............. 1-6 i
- 1. 35 GFLID TFICATI9Ng. (%r. B.W>h . . . ..............................
........................ 1-6 l 1.36 500RCE CHECK................................................. 1-6 1.37 STAGGERED TEST BASIS......................................... 1-6 1.38 THERMAL P0WER................................................ 1-6 1.39 TRIP ACTUATING DEVICE OPERATIONAL TEST....................... 14 1.40 UNIDENTIFIED LEAKAGE......................................... 1-7 1.41 UNRE RICTED AREA..................
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., ........ 1-7 1.42 6DTIt.A 1.43 TEXHAUST TJfEATillENT 5)(ST e r. . co). . .
V ENT I NG . . . . . . . . . . . . . . . . . . . . . . . . . . . W. .
1-7
.1-7
. .l TABLE 1.1 FREQUENCY NOTATI0N...................................... 1-8 TABLE 1.2 OPERATIONAL M0 DES....................................... 1-8
- SEABROOK - UNIT 1 i AMENDMENT NO. "
1HDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PJfaE TABLE 3.3-2 (This table number is not used)
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . .............. 3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION . . . . . ............... 3/4 3-14 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION' SYSTEM INSTRUMENTATION . . . . . ............... 3/4 3-16 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS . . . . . . . . . . . . . 3/4 3-24 TABLE 3.3-5 (This table number is not used)
TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS ....... 3/4 3-31 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations ....... 3/4 3-36 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS . . . . . . . . . . . . . . . . . . 3/4 3-37 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS . . . . . . . . . . 3/4 3-39 (THIS SPECIFICATION NUMBER IS NOT USED) ........ 3/4 3-40 (THIS SPECIFICATION NUMBER IS NOT USED) ........ 3/4 3-41 TABLE 3.3-7 (THIS TABLE NUMBER IS NOT USED). . . . . ...... 3/4 3-42 3/4 3-43 I TABLE 4.3 (THIS TABLE NUMBER IS NOT USED). ... ......
(THIS SPECIFICATION NUMBER IS NOT USED) ........ 3/4 3-44 TABLE 3.3-8 (THIS TABLE NUMBER IS NOT USED). . . . . .... 3/4 3-45 Remote Shutdown System . . . . . . . . . . . . . . . . . 3/4 3-46 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM . . . . . . . . . . . . . . . 3/4 3-47 Accident Monitoring Instrumentation ... ...... 3/4 3-49 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION . . . . . .. 3/4 3-50 TABLE 3,3-11 (This table number is not used) . . . . . . . . . . 3/4 3 .23 i
Radioactive Liquid Effluent Monitoring Instrumentation . 3/4 3-55 3
TABLE 3.3-12CRAbl04CTIyE L/0VIF EFfL%NJ f I M%J 0/ItjEf I)l5Tf1JtyfNJAJ4p 3/4 3-56 (yans, ramtc suseger 4 sex)
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a SEABROOK - UNIT 1 iv Amendment No. 60-
1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMEtHS l
SECTION~ g, m g , p pgf NST L _
. . . . . . . . 3/4 3-58
- s. -
Exytouw{@Masfotis JTffuerft) Monitoring Instrumentation 3/4 3-60 l
! TABLE 3.3-13 M IDA m V6 NITORING INSTRUMENTATION # ............ 3/4 3-61 TABLE 4.3-6 (MDiaAeTIW GASF ..L E MONITORING INSTRUMENTATION SUR CE REQUIREMENTS ....... 3/4 3-64 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) ........ 3/4 3-67 i
3/4.4 REACTOR COOLANT SYSTEM l
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, 3/4.4.1 REACTOR COOLANT l.00PS AND COOLANT CIRCULATION
- Startup and Power Operation .... .......... 3/4 4-1 i Hot Standby . . . . . ................. 3/4 4-2 j Hot Shutdown . . . . . . . . . . . . . . . . . . . . . . 3/4 4-4 Cold Shutdown - Loops Filled . . . . . . . . . . . . . 3/4 4-6 Cold Shutdown - Loops Not Filled . . . . . . . . . . . . 3/4 4-7 3/4.4.2 SAFETY VALVES l Shutdown . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-8
! Operating . . . . . .................. 3/4 4-9 l 3/4.4.3 PRESSURIZER . . . . . . ................. 3/4 4-10 3/4.4.4 RELIEF VALVES . . . .... ........ .... 3/4 4-11 3/4.4.5 STEAM GENERATORS . . . . . . . . . . . . . . . . . . . . 3/4 4-13 TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED '
DURING INSERVICE INSPECTION .. ............ 3/4 4-18 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION .......... 3/4 4-19 '
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems . . ............ 3/4 4-20 l 3/4 4-21 l Operational Leakage ..... ... ......
TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES . 3/4 4-24 3/4.4.7 CHEMISTRY . . . . . ... . .... . .. . 3/4 4-25 TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS ... 3/4 4-26 3/4.4.8 SPECIFIC ACTIVITY . . .. .... ..... 3/4 4-27 SEABROOK - UNIT 1 v Amendment No. -E&
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INQfl LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS SECTION P.&E 3/4.9.4 CONTAlletENT BUILDING PENETRATIONS ........... 3/4 9-4 3/4.9.5 C0pOIUNICATIONS . . . . . . . . . . . . . . . . . . . . . 3/4 9-5 3/4.9.6 REFUELING MACHINE . .................. 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS ........ 3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level . . . . . . . . . . . . . . . . . . . . . 3/49-8 Low Water Level . . .................. 3/4 9-9 3/4.9.9 CONTAllBIENT PURGE Als EXHAUST ISOLATION SYSTEM . . . . . 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL . . . . . . . . . . . . . . 3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE P0OL . . . . . . . . . . . . . . . 3/4 9-12 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM .. 3/4 9-13 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE .............. 3/4 9-16 -
FIGURE 3.9-1 FUEL ASSEMBLY BURNUP VS INITIAL ENRIC MENT FOR SPENT FUEL ASSEMBLY STORAGE . . . . . . . . . . 3/4 9'17 3/4.9.14 NEW FUEL ASSEMBLY STORAGE . .............. 3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . .................. 3/410-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS . 3/4 10-2 3/4.10.3 PHYSICS TESTS . . . . . . . . . . . ........... 3/4 10-3 3/4.10.4 REACTOR C0OLANT LOOPS ................. 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN ......... 3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS xD Uphoutr4tfaib JL-W.WF4rg,o,geps:. (5.4pr.dse,U. . 3/4 11-1
. . . Grtes.ste.Mic.Aufe. W .a.!s.* F.q e9 . . . . . 3/4 11-2 SUlenMaauwasm a watlmant/SystegP)Lrti!Mut.vWWS 'ffy3/4 11-3 Liquud Holdup " anis .................. 3/4 11-4 3/4.11.2 GASEQUS EFFLUENTS Via/ma .CraisypEcriurie%,iaen is ease >) . . 3/4 n-5 e- ................ . 3,4 u-.
rJa a Mr edsMta0idsts JrMidstMste@ . . . . . . . . . .
. 3/4 11-7 3/4 11-8 Exp' osive Gas Mixture - System . . . . . . . . . . . . . 3/4 11-9 3/4.11.3 W(Xm3 St%tFPp4 M'Of#-
- ,% 4 3/4-10 3/4.11.4 .CmitJercW M H 4ef4'I P'?SFN,/3,4 .... 3/4 11-12 3/4.1 RA:'IO M AL EiVIR0f#tENTAL MONITORING 3/4.12 g Wu)l (rvr FM5W WWA 4 4.#."C.*h . . .3/4 12-1 l i a
l SEABROOK - UNIT 1 ix Amendment No. it--
l INDEX l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS
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SECTION g 3/4. t)DAstkE4s@X7mr .smur mwa emyg is, o,c, ce.b. . . 3/4 12-3 3/4.12.3 GthWLAB05fA7[)MY 20!fPARIGON /PAf43Af).(rtus.rwroM we a- 3/4 12-5 y es owr usen 3.0/4.0 BASES l l 3/4 0 APPLICABILITY . . . . . . . ............... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS l 3/4.1.1 B0 RATION CONTROL . . . . ............... B 3/4 1-1 1' 3/4.1.2 B0 RATION SYSTEMS . . . . . . . . . . . . ..... . B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES . ............. B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS . ........ .. B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE . . ............... B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR ......... B 3/4 2-2 3/4.2.4 0UADRANT POWER TILT RATIO . .. .... ... . B 3/4 2-3 3/4.2.5 DNB PARAMETERS . . . . . . . . . . , ......... B 3/4 2-4 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION . . . . . . . B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION . . . . . . . . ...... B 3/4 3-3 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) ....... B 3/4 3-6 l . l \ 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTCR COOLANT LOOPS AND COOLANT CIRCULATION . .. B 3/4 4-1 3/4.4.2 SAFETY VALVES . . . . . . ...... ... .... B 3/4 4-1 3/4.4.3 PRESSURIZER . . . . . . . . ........... B 3/4 4-2 3/4.4.4 RELIEF VALVES . . . . ............. B 3/4 4-2 3/4.4.5 STEAM GENERATORS . . . . . . . . . .. ..... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE . . . . . . . . . ... B 3/4 4-3 i 3/4.4.7 CHEMISTRY . . . . . . . . .. ........... B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY . . . . ........... . B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS ....... .... B 3/4 4-7
)
FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>lMeV) AS A FUNCTION OF FULL POWER SERVICE LIFE . . . . . . . . . . . . . . B 3/4 4-9 F URE B 3/4.4-2 (This figure number not used) . ... . B 3/4
-10 )
SEABROOK - UNIT 1 x Amendment No. &
i INDEX BASES - i SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION. . . B. .3/4 . . .9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM............ B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE P00L............................................ B 3/4 9-2 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM....... B 3/4 9-2 3/4.9.13 SPENT FUEL ASSEMBLY ST0 RAGE.................. B 3/4 9-3 3/4.9.14 NEW FUEL ASSEMBLY ST0 RAGE.............................................. B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN........................................... 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.... B 3/4 10-1 B 3/4 10-1 3/4.10.3 PHYSICS TESTS............................................. 3/4.10.4 REACTOR COOLANT L00PS..................................... B 3/4 10-1 B 3/4 10-1 l 3/4.10.5 POSITION INDICATION SYSTEN - SHUTD0WN..................... B 3/4 10-1 3/4.10. 6 REACTOR COOLANT L00PS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B
. .3/4
. . 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.bEUID IFFA.UtNTbts,cTmy.re.d.en. K.4,oT. g,re,4. . . . . . . .
B3/411-1l 3/4.11.2 ~GASEQUS EFFLUENTS........................................ B 3/4 11-2 3/4.11. PIf00D/RABI0ACTAVFr' WASILD(res SM.tewav.uweM is. wr. <,t.rn). B 3/4 11-5 3/4.11. Al/ QOjD.(ys..rr.mtvAw.9 man.(t. fa.*.WF.4. . . . . . . . . . B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.[(FDM70KIAuph@DDL79. 3/4.12,22g g yyfspjgg gg g g g y , ,,,.3 N A m e n .wwgn.e.ewww.eg s f. e r. M r. .... B 3/4 12-1 B 3/4 12 1 w.e.6 3/4. fTfRgAJfQRAT03Y AOPIPMISDV Pp0$Ap.Crgr. rep.ge4 p.v.a@ B 3/4 1 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA.............................................. 5-1 5.1.2 LOW POPULATION 20NE......................................... 5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS.................... 5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA B0VNDARY..................... 5-3 FIGURE 5.1-2 LOW POPULATION Z0NE.................................. 5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION................... 5-7 5.2 CONTAINMENT 5.2.1 CONFIGURATION.............................. ................ 5-1
- 5. 2. 2 DESIGN PRESSURE AND TEMPERATURE............................. 5-9 SEABROOK - UNIT 1 xii Amendment No. P
1 DEFINITIONS
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- MASTER RELAY TEST 1.18 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay. , MEMBER (S) 0F THE PUBLIC 1.19 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to mak This category does include persons who use portionsteofforthe sie deliveries. recre-ational, occupational, or other purposes not associated with the plant. OFFSITE DOSE CALCULATION MANUAL 1.20 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall containf E ar A he C io og al4ff en s ing and/ anal s1s rogram d r di ogi al nv ro - n 1 ni ri pr gr P t B'of he CM dal con ain the t od o In par rs se in ec cu tio of ffs te ses due to di c v g eo a 1 ui eff1ent, ipth cal lati n o ga eou an li id e fl nt n ori g Al rm/T ip a nts an in e nd to th E vi on a 1 di ooi al nit in Pro am. OPERABLE - OPERABILITY f 1.21 A system, subsystem, train, component or device shall be OPERABLE or k have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, l cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s). OPERATIONAL MODE - MODE 1.22 An OPERATIONAL MODE (i.e. , MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
,j PHYSICS TESTS 1.23 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:
(1) described in Chapter 14.0 of the FSAR, (2) authorized under the ' provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission. PRESSURE BOUNDARY LEAKAGE 1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. ! l Amendment No. [, j SEABROOK - UNIT 1 1-4
r-36 1.20
% The OFFSITE DOSE - CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the' calculation of gaseous and liquid effluent monitoring
.' Alarmffrip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.7.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.8.1.3 and 6.8.1.4.
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DEFINITIONS N PROCESS CONTROL ?R0 GRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that p-ocessing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 aar restral State Regulations, burial ground requirements, and other requi,rements governing
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the disposal ofg ctive waste. PURGE - PURGING 1.26 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. QUADRANT POWER TILT RATIO - 1.27 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated - output to the average of the lower excore detector calibrated outputs, . whichever is greater. With one excore detector inoperable, the remaining.three detectors shall be used for computing the average. RATED THERMAL POWER 1.28 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 Nwt. BEE 9R TRIP SYSTEM RESPONSE TIME 1.2g ' The REACTOR TRIP SYSTEN RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip setpoint at the channel sensor until loss of stationary gripper coil voltage. REPORTABLE EVENT 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50. CONTAINIENT EutLOSURE BUILDING INTEGRITY 1.31 CONTAllOIENT ENCLOSURE BUILDING INTEGRITY shall exist when:
- a. Each door in each access opening is closed except when the access opening is being used for noma , transit entry and exit,
- b. Th Containment Enclosure Emergency Air Cleanup System is OPERABLE, i
- c. The sealing mechanism associated with each penetration (e.g., l
, welds, bellows, or 0-rings) is OPERABLE. l
.s l SEABROOK - UNIT 1 1-5 Amendment No. W
DEFINITIONS SHUTDOWN MARGIN _ 1.32 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be suberitical from its present condition assuming all full-lenrth rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE BOUNDARY 1.33 The SITE B0UNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. SL.'VE RELAY TEST 1.34 /, SLAVE RELAY TEST shall be the energization of each slave relay and verificatien of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity -heck, as a minimum, of associated testable actuation devices. (SOflDNWAT40[ C N oT- (4f6bh g r 5 S0_URCE CHECK 1.36 A SOURCE CHECK shall be the qualitative assessement of channel response when the channel sensor is exposed to a source of increased radioactivity. STAGGERED TEST BASIS ! 1.37 A STAGGERED TEST BASIS shall consist of:
- a. A test schedule for n systems, subsystems, trains, or other i designated components obtained by dividing the specified test I interval into n equal subintervals, and
- b. The testing of one system, subsystem, train, or other designated I component at the beginning of each subinterval.
THERMAL POWER A 1.38 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. h TRIP ACTUATING DEVICE OPERATIONAL TEST 1.39 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy. SEABROOK - UNIT 1 1-6 Amendment No. /I,[
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DEFINITIDNS i . l UNIDENTIFIED LEAKAGE 1.40 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE. UNRESTRICTED AREA L ! 1.41 An UNRESTRICTED AREA shall be any. area at or beyond the SITE BOUNDARY l access to which is not controlled by the licensee for purposes of protection of individuals.from exposure to radiation and radioactive materials, or any l ' area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. l [ATJfA716 EX)iAMST JREMMFJT SYSM
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! 1.4 TI H T RE E S TEM sha b an sy e de gn d d l a e t re ce ga ou r ici din or adi ac ve ter a in par i a of' ue ts y ass ng en la on v t hau g a th ou c r a1 d r rs an or EP f te f t pu os of em ing o ine o pa 1 - , i,l te f m e as us ex ust str am p for o e lea e o e vi on nt. I u a sy em s at on der d t hav an af ect n n bl g a lu nt . l Ejgi er S fe F.at s o her" C1 an SyMensa n c nsi er t ma 3 _LA ON X US RE ME SYTEM o nants. l VENTING I l 1.43 VENTING shall be the controlled process of discharging air or gas from a l confinement to maintain temperature, pressure, humidity, concentration, or l l ' other operating condition, in such a manner that replacement air or gas is not ! provided or required during VENTING. Vent, used in system names, does not imply i a VENTING proceas. I l SEABROOK - UNIT 1 1-7 AmendmentNo.[
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_ - I I I-N O _ O _ I I T ## I ' C A 7 2 66 22 3 3 7 2 2 2 5 2 44 22 8 2 8 2 3
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r o MO
- r 1 S
RP 0 . . * * . xg xg k k (J AT 1~ 2c 2c N LE A. A. A. a a O AS <- NN N <B APPLICABILITY: As shown in Table 3.3-13. ACTION: M Ex. Frost 66 y
- a. With abees+eesswe gasreve-c" - =3 monitoring instrumentation channe1~ Alarm / Trip Setpoint less conservative than required by the '
above specificationc i aietely sesa-ad +h= eel =ese a- -em aert i ==? _ : ._: mr: n re-itered by th= effected ch====1 e6 declare the' (k=n:n=el inoperablegno 'Afsf-[eNm . en % x 3.3.s3 en.osen ._ k
- b. With the number of OPERABLEc-des _e_r_p.gaQ=: =b- >a monitoring .
instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable
. instrumentation to OPERABLE status within 30 days or, if _p r unsuccessful . r=--1m n, ..... : ? __r = ^tr: E' ;ngp j ,
_J:=: Anoetepursuant to Specificatiop.:.:.&hy this
} p # S7dS.
e operabi'ity was not corrected in a timely mann 4,g, t g g k" c. The provisions of Specification 3.0.33are not applicable. Auh 3.0.81 SJRVEILLANCE REQUIREMENTS edusas y 4.3.3.10 Each di3Esae3%#'ga : :h;; 27 monitoring instrumentation channel' shall be demonstrated OPERABLE by performance of the CHANNEL CHECK,6ElElEPd-SiRRftHANNELCALIBRATIONandCHANNELOPERATIONALTESTatthefrequencies shown in Table 4.3-6. SEABRMK - UNIT 1 3/4 3-60 Amendment No. [
)
N O I 4 3 5 2 2 3 T 3 3 3 3 3 3 C A . Y T I L N I T O I A B A C I [
- T L N P E P M A U
R T S N I G N I R S O L . - T E 3 I N 1 N NE
- O AL 3 M HB
. CA 1 1 1 1 1 3
E ME UP R y / L MO B A [F I N _ T E I E M V S A G i n o s . Q A G E V I S 8D t i a n s e c o r m O r P cN v ga T L P X E R T I O r M Ec T e ( r o C N o Ti t gg (p M O i t $t E M iYa _ i T n 5,t m gh o S S o _ Y ) r M G . S s y e Nu y s t l r e IA t E e i p o t S 7 i T c G v m t a Sd v S o N i a iR En i A r A t e S n Ca t WM P R c l p o O c E ( e M Rm A ST E m t 1 PrM AS r D a a e F aR GY o I a S t El S t W- G u a r TA-E i n e e n c R e VG i l Age I N o l i t w p ins l TI CR M b o d o r a o m a
)ia b o
n l Sde AO N P S Uil N T 0T e g T O e N I I N E o E DN y A S r M AO x . . . . . AP . U RM O b d e G( o a R T TL S N . . . I 1 3 F2 ' 8O'Eyg g Tm a P ~ - hL C~ < k}2Is
k N
) f O
I 5 2 l 3 3 3 C Y N O I *
- I B * *
- T A * **
A C T I N L E P N U R d^ d P A T S N u I B
) G y. 5 d N e I u L u R A I n O i
t T I Ao ME9t n N 8 C o O N m 0AR ( H i m ME 7 UP 1 3 1
= M e MO I
3 i F c 3 F c E L B E 5 ? 4 [ A ^ T
.C s t A u #
r, G _ T ( S
.O U
A r H o . X t f f^ a - d ^ F E _ "I
^
S N _ N6_ E D e N p t O m a a R S A p e O' E m t 1 S a a F S l D N u c r A i - L. i t d r
. o a I P dI B
R . U b c R T S N . I m9my*' . E
< mk
>aT*3b
A TABLE 2.3-13 (Continued) TABLE NOTATIONS _ n Qt alI tich?)hei- ME%h During GASEOUS RADWASTE TREATMENT SYSTEM operation.
- Q D he c!and :::1 exhauiter is in epa: tid @er Usb
- [ Nor wrsML';ble Oe's ElUnitGi fsi thii e Elwass psiGt is biisd wii ihm asin Condense 4 evacuatica eenitar.
ACTION STATEMENTS ACTION 32 - @f th the a"=her af ch=aa.1< npEnigi r 1.c. +han th. uinimi,- grnr Ch J"2
;l OPIAAILE T*024# Z 't' Of#120't 70I : VI thi P'th" 7 00ti::t0d at IGO:t CaCe (p^yrAconti"u?
he"s . pCOVided the flew--rat- i: ACTION 33- with the au-her of c% rnels OPE 8ABLE le:: th:n the M4 4 : y
-Chann:1: OPEPABLE requirement, ef#luent relea::: vi: thi: p:the:'"
NM .:y centinue provided grab-samples-ar: t: ken :t 1:::t :nce p r
\ 12 heur:
- b. w..
.. . :nd these-samples-are-analy::d f r radic;ctivity within
- e. m. .. ou.- a_ n_ n_ a. , _n. _u.. a_ _sn_ _t w. ....a_ , .. >
__. u__ _. ._ . . . . . . .3.+....,..
. . . . . . j ACTION 34 - With the number of channels OPERABLE less than the Minimum .
Channels OPERABLE requirement, operation of this RADIOACTIVE GAS WASTE SYSTEM may continue provided grao samples are collected at least once per 4 hours and analyzed within the following 4 hours. ACTION 35 - M the nuater of channels-0":. C LE less than the "iniae- ~%
-Ch:nn:1: OPEP.^.BLE requir: :nt, ef'le nt rel!!:-: "is th- affected pathery may centiaue provided s==ples are continueusly cc11ected
-with-amili:ry :'--ling equip- nt :: r: quired 4- the 00CM OT 4
SEABROOK - UNIT,1 3/4 3-63 k( 9 w owr i
^
H C IED HCE ' W PN. IR j RLU OLQ * * * *
- FIE
- ER SV S ERS T DUI N OS E M M
E R I U L *
- Q A *
- E LN ) . .
- R EOT 2 *
- NIS ( A. Q Q E NTE M Q N C AAT N HR A CE L P L O I
E V R U N , S O LI N ET O NA ) ) . . I NR 4 3 T AB ( - ( . A. R A HI Q R N N T CL N A E C M 6 U
- R 3 T EK . . . .
. S CC 4 N RE A. A. . A. .
I UH 'N N N N N E OC L G S - B N A I T R , O T I L N EK NC NE AH E D D W D HC V . C I r S u O ~ i L T P u ' i X i - E i 7S M W r o r u E t . o 3 E S T S Y AS A i n i t A S G r k)I EM TE E t y i e e ST i p o t AS v r s t a WYS R t e i n d S AG r E D l e M o GNI o t t) s a ER is - a S t VO ns T a IT oe N e R _ TI Mc n i p CN o l i t r w nr AO b m _ T 0M eP g(
~T i o a a P S N I i I F y
E M U DS AA RG O x lP a r d R - T S N . . 1 I (2 s 7 c5e ~ 5
)hE 0
C IED E R _R / OL / *
- FI E
- ER SV S RS T UI N
E M E _ R I _ U L _ Q . E R E T E NI& 1 NTE ( A. A. A. C AAT N HR Q N N N A L L ~C PE I /0 E V / UN R W 7Ll N . S o N El ) O E NA 5
)
I NR ( A. A. d T A AB N N e T J* 6C l. u N ^ d /, n E i t M l d a E /ug i n R p o T u EK C S CC ( N E RE 6 I f UH A. N A. N
'.N A.
N 3 G N I oe( 7O C j 4 R - O c E T a L I f L B N A O s EK C T M ue / E D W [ii C r H C # D . T M' S U fC L T T X T M E r S Ec r o Ti St o R t E a
. dA Ya Sm t
o M n o E S N i d c
- 4) r I n/
EIG ISda S A'r e t y C l p e e
/i t
E alnee/.iv t. L A r a m R t a f* " .
- R t
c E S l e w P A p e o m '^" A 'f D m t El s) N a a F E "" TA as A C S Ago n G
/se L/Se G
l u c r e" Wni it e n l l E i p da br N T N E 0'A n 0 vi oP N( I R d I o dP S m a Eo dR) Sr ape a R/. T U b c T G(T S N . m l 4 f' _ m m$$7 E e s - 4
.E .
.~ -
~b 3ahk r ~
TABLE 4.3-6 (Continued) l l TABLE NOTATIONS x,
- m.
A 11 + 4 ] (,got g 1 i l l During RADI0 ACTIVE WASTE GAS SYSTEM operation. CAA a fL ('/0 07" g(IE) t.....-. .. .. . + k.a a. l. a.d c a_ m l. a__v ha n c t a r ie in nna va_t_ s a_ _ . C*th h. . . n.ot D.A.T. . . T A_ M A.t- T.fn N_e. T.~ ma_ n.4. +.a. . , k. 11
. .o .. . . . .. -
the fl. n_ w e. m + a_ __ . - - . .. r.a. n.. . e 4. e. 1
- u .,, .. 4. #. 4. e. .m +. 4. .n.. n.+ h. . _m +. .- + h.a_ D - _ _ m Ai n_t_i n_ n. A m_ t_M - _so n. - _. n, _ . .. _.C,o
.._ . =. +. . , 4.a.= /gD. ..h.u. ..c ,i4.... A. 4. , + , d,,,
N i j s. i.. no i. .n c. a. n.. .. _e 4. e + a_ n. . +. wi.tt_.h. - -- ha nnaentinnel e. t _s + ne a. #. .- -1. - A ___ 6. k. - l '-- - m y ,..-k,i.,,. c.
.. e. M. .a. n. +- + n e.f. --ar
+ h.
i c colsaca -r-- nnint-- ie hmenA --
- - - -nn - --+ -.k.a - -- m . 4. .n. ,*.A....
M DI'lO L . 4, . . a,,.u. e n_.m +.4. n. a.n_ . _ n n. i. t_n_ a e---
--. A-.--,+=io==.
At .4-(1) .ns- nuawa T P T T. o n. P w. U.A . .M - M El n.o tD. --ATT AMa---
. - - l- --T.CCT ek.11-.-- .1ea u
..6--
. . + = = = v.. 6 4. w-s.k.
- 4 e, n 1. .m +. 4. a_ n a_ f. t..h. i. c_ n,. at hum _u, a_nd ennten1 enne a l. m e. m_ m a. n. . n .u.,. 4. .+. 4. ..=. . . o .
. i. s. @gyg 6
n :-,+....--+.
.n,.. .o 4. . A.. 4. . , + a. ,. - - - - . --
, mm e u.c. aA l. a.u. a. l. e.
_. _h - a_ .. u. . + k. m n v . -.1
-- . . .. .-... .2.1 1. - w s-i +,. .L .
- v. u y.m,. e +.. A 1. _m e. m.,/Tri n, . - Catn,nint, (2) .n . .. T T. . .An I. P.U.- A M..M. . .- CA. ] D C D. .A.T. T. A. MT.aEl--_CT..c h. .a l. l _s l...e a
. _ - A......,.6..6..-
ALA -- i-- i.ne i, wwn w. w '
*T* 4
- e. n_ n_ e a_l m_e. m annuncia_tinn neettre if the_ inctenmant__ inAiem+ae
..._. _ ___ .a__ .. e n_ a_A l. a.u. m.1 ,
. .. .-...1 L +a,+ cA f_A
.t. - m. .p .6.k..- a... . ,.n.- u. a 41 1. . n. .s.a. . . . .A.1. . - .,s
. yv i n u. -
en V *A3_1 eu a ksta r t PAfTDDATTAM ha
.. , , 2. n-vus . ___v.-_ -v ____ _s (3) inz ini w a n wnnnn a.w wn .-uu.-i . k..o l. l.
-. -- , % . .#.. m. _. _ . J.
. i s vi
+ h.a_ c. a.f. a_ c. a_ ne_ et_a_ndmede
_. . _n_ . - - - cortified hv, t he 12 t i n_ n. .m_1. n n_ e_ -- a_ _.y o_ n. #. _c + . A . A ,. t u.D. s... e, c.. e 6- ' n e. 4. n. .n,.e + m n. A_ _m e. d_ t_ he a t_ h m u. m_ha_ m_ n n it_ _s i. n. a_d_ f. --e. ne. e ma n'-1 -4. m+k.=.+ m.=
- rr -.
-Fu. . *6 4. ' 4. F w * *
(n m..m. e n_ . _- _ n. . +. m e. _e n_t e_ n_.ne_ a_
. _. n_ c_ t i v i. t_ i a_ c_ wi. t_ h WR C . Th. .m,. .e n. e
.- . . _ _ . . + .. n.
. .A..
. A e ,e, k. 1 1,
. . --.- T' M 7-
_ m i. +_ e_ n l. i. h e. n_ t.i. n.n,t_ .h.e. c,u e t am. nua_ r. ' i. t e_
. _ . _ _ - - - - - i .nt a_.n.d_a_d_e. m a.n,a_n. f. a,. n.a. m., n,u
. a n. .d_ ma_ s e n_ e. n.
n AL A L---- L---
-48 n.+. e, _ n.n,a_ . C. a_ c.e n_h e m_
a.i _a_ t_'t.t_A.M. n +- _ M C -I.---t'.A.I T '-
-- Q D. ..A.T. n T.n.u www , . -- . w s- -
a wuu i, nous usun
- 4. a ,'..1.'.
1 - - - " - calm +_A_ +n_ + h.a. 4. n 4. +.4. _ .. , e. _m 1 4. k...=...+ .. =. - - (4) The CH.AN.NEL CALIB. RATION shall include the use of standard gas samples containing a nomina :
- a. One volume percent oxygen, balance nitrogen, and
- b. Four volume percent oxygen, balance nitrogen.
l
.......t E (5) . L..- f_a.t.T. B.D. .A.T. T. AM. c. h. ..m_i. lh_ a_na. r c. f. a. c. a_ d_ -M. . . . ., . -. n . -,, ..M... -., I m_e_ t_ i. v i + i m e enverina. the mezcurament vann.o nf the mani.+_n_e. + n_
-- _ u. n.c. 4 #.7 ,u+ . k. . + +..'n. g,yg 4 s e. m_ e,nn_ n e_i m_ . c_ linear. Sources chall he ucad tn_ u n_ ei.f,u + h. . _ - . m.a. n 4. .+.n .
- . ...e,...,.- ..
. ..au, i n.+.a. n. AaA_ a.n. . . ..
(. . 1. u, t. a. . + k.a. . .. . , . I r l SEABROOK - UNIT 1 3/4 3-66 Amendment No.
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS
~
CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.lbhe one trati of adioa ive ateri rel ased n liqui effi ents e in of d schar fr the Itip t dif user see F gure 5. -3) all - be li ted ot conc tra ons s cifi in CFR art . Appe ix B Tabl II, Col 2 fo rad onucli es et er th n dis olved r entr ned ble ga s. or ssolv or ntrai d no e gas s, th conc tratio shal be mite to x 10- mic Curie 1 to 1 ac vity. { APP CAB ITY: At a time . A.Nt 6 10 Wi the oncen ration of ra oncti e mat rial r leased n liq id effl nts a t poi of ischar from he a tipor diff er exc ding t'he abov limit , estor the ncent tion o wit in th abov imits thin 5 minut s. { 5 EIL CE RE REM S .
/ .
4.11 .1.1 dioa ve 1 quid stes all be ample and an yzed a cordin I to e sa ing ana sis ogram pecifie in Pa A of e ODCM
.11.1. 2 resul of a rad activit anal.es shal be us .in ac rdance with met olo and p. asete in th ODCM assur hat t conce rations 4 at t poi fr ase e main ained hin limit f Spe ficati 1.1. ,
i I SEABROOK - UNIT 1 3/4 11-1
//
par Q
RADI0 ACTIVE EFFLUENTS LIQUID EFFLUENTS g(Wii SPE4 FICA *d MM A 4 LIMITING CONDITION FOR OPERATI0ld i 4 3.11. ,I he do or se c
- /
tment oaM BER OF HE PUBLIC from ra oac-1 ve.ma rials n li id of ents lease from e h unit, UNREST CTED AREAS see F ure 5 -3) 11 be imited-
- a. urin any c ndar arter o less an or eq 1 to 1. mrems t the hole b dy and o less han or qual to 5 rems to any org ,
a i
- b. Durin any ca sidar y r to le s than or qual to mrems - the j whol body d to 1 s than equal to O mrems to any o gan, fAPP CABILMY: At 11 tim .
ION:
- a. W h the c culated dose from he rele e of rad oactive terials n liqui effluen exceedi any of e above imits, p epare an submit o the Co ission w) hin 30 ys, purs ant to S cificat n ,
6.8.2 a Spec 'I Report'that iden ies the ause(s) or excee ing the imit(s) nd defin the cor tive ac ons tha have be tsken
. t reduce release and the oposed rrective actions o be aken to sure tha subseque releas will be n compi nce wi the abov limits.
. The ovisions Specifi ation 3. are no applica e. '
RVEILLAt(CE REQUIRE .
/
7 i i , i i i 4.11. Cumula ve dose ntributi s from quid off uents f r the c ent cal ar quar and the urrent c 1 dar y shall dete ned in cor-da e with th methodol and p tersj the ODC at lea t once r days.
/ ,
1 1 SEABROOK - UNIT 1 3/4 11-2 [ M e M E^'T h
1
)
RADIDACTIVE EFFLUENTS 1 .. LIQUID EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM (r*S 8/F5t#M "d 4 " " '# 4'#"#O) LIMITING CONDITION FOR OPERATIO 3.11.1 hie iquid adwast reatme Syste hall e OPERAB an'd T opri-ptepo ion of the ystem ojecte doses all be sed t duce eleases radioa ivity when e e to t liqu fflue , from ch unit o
'UN STR ED AR S (see igure -3) wo d exc d 0.06 em to th whole dy O. arem t any or n in a -day p iod.
AP ICABIL : A all ti . CTIO
/a. ith rad active iquid in exc s of t ch god no in op ste bei dischar d witho treatm t and above imits a any por on of t Liquid adwaste Trea%ntSy em whi could r duce the adioact e liquid aste di ion, pr are and ubmit to the Comm sion wi in 3 days, ursuan o Speci cation .2, a S ecial Re rt that nclud the foi owing i ornatio
- 1. Exp1 ion of y liqui dwaste as bein; ischar witho -
trea ent, id tificati, of, any operabl equipmen or su ystems, nd the retson for e inope ility,
- 2. Action (s taken t
/estore inoper e equip nt to ERABLE status and
- 3. Su ary descr'ption of tion (s ken to revent- recurr ce.
P The rovisions f Specif ation 3. 3 are'n appli ble.p SURVEIL CE REQUI ENTS /
- 4. 1.3.1 Doses due t iquio rel s fr each u t to UN STRIC AREA 11 be projncted at 1 st once r 31 da A in ac rdance th th ethodo ogy nd parametfrs in the DCM when iquid R aste T eatment ystems re not eing
. fully ut (ized.
4.11 .3.2 The nstalled quid Ra aste Trpatment stem s 11 be nsidered E by me ing Spe ications/3.11.1. and 3.1 .1.2.
)
SEABROOK - UNIT 1 3/4 11-3 {[pwar
. f s
r RADI0 ACTIVE EFFLUENTS l 3/4.11.2 GASEOUS EFFLUENTS l DOSE RATE hMSSpecAcArte4 m ea_ d Aorv.36)h LIMITING' CONDITION FOR OPERATION l -3.11.2.1Th' dose rate d to ra 'oactiv materi s relgased in gaseo l ' PTTsue f at site o' areas t and yond t e SIT OUNDA -(see igure 1 5.1-1 sha be imite to the ollowi :
- a. For noble ses: ss tha or equ to 5 mrems yr to e wh e I b dy and s th or eq l to 3 0 mre /yr to he ski , and l
- b. For lo ine-131 for Io ine-133 for t itium, d for 11 ra o-nucli es in rticul e form ith h f-lives greate than days: l Les than o- equal o 1500 ems /y to any rgan.
i APPL CABILI Y: At 11 ti . TION: , With e dose rate (s) exceedi g the ove lim' s, dec7 ease t rele e rate wit 'n 15 outes t within he abo 4 limit ( .
~
' URVEILL NCE RE IREMENT l , , , ,
~z , , t 4.1h 2.1.1 he dose ate du to nobl gasesj gaseodeffl ntssha!1be d rmined o be w thin t above li its in 'ccordan with he met dology d para ters in he ODC 4.1?.. 1. 2 Th dose ra radi uclides in parti duef to late Iodine-1,lf-live with a 1, Iodi e-133, great r thantritium andi all days ga ous eff ents sha 1 be de rmined be wit in the above 1 mits in a ordance ith t ethodo gy and ameters in_the ODCM by obtaini epresen tive s es and rformi analys in a ordance with th sampi ng-andana/sispro am spe ied in rt A of he OD .
i 9 3/4 11-5 SEABROOK - UNIT 1
/ i nma
RADI0 ACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE - NOBLE GASES i __(yms (PruP(CAMM M PA8 # MDDI J LIMITING CONDITION FOR OPERATION 3.11.2.2he ir se due to no e gas s rel M d in aseous effluen s, from
- Yach it, are at a bey d the ITE UNDARY ee Fi re 5.1- ) shal be 1 mited ot follo ing:-
- a. Dur ng any calen r qu ter: ess th or eq l to 5 rads f gamma r iatio .and 1:.ss th or ual to mrads for bet radiat~on, nd
- b. Duri any alen r yea : Less an or qual t 10 mrad for ga a rad'atio and 1 s th or equ - to 20 mrads f beta rddiation f
APP ICABILI Y: t all imes. [ TION 0/ t Q
- a. ith tpe cal lated a dose rom radioactive oble gas s in ga eous efflydnts ep'ceeding ny of e abov Iimits, repare a submi to theftommiysion wit n 30 d s, pur nt to ecifica on 6.8. , a Spefcial eport t t iden fies t , cause( for ex ding t nd de limit (
the nes the correctJv)e actio)1s that ken to reduce ve been eases 9 d the pt'oposed p6rrecti actionsg o be tay en to asspre that fubseque- releas s will b in com lance w'th the a ve li its. '
- b. he p sions a Specif ation 3 .3 are no appli ble.
SURVE LLANCE AEQUIREMEN
}
11.2.2 umulat dose contributi s for t curren calend quart!and current alendar year fora'oble g s shall e dete ed in ordan with the m odolo and paraWeters i he ODCM t least nce per days /
,/ ,
I i l v i SEABROOK - UNIT 1 3/4 11-6 n ar st
l RADI0 ACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE - IODINE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM (T-AG Stretptumo4 N04 i f4er(ASEh { LIMITING {CONDITIONFOROPERATION 1 3.11.2.?%e ose o a P MBER 0 THE P LIC fro 1,Iodigd-133, fum,an all adio ucli sinprticulteformp/ Iodine- j 8 days in g,a eou; effl ents r eased, from eachithhalf-ivesgr7terth 6 l unit, t areas a and be nd ' l the TE BOUND (se Figur 5.1-1 shall be' limited o the fo owing:
/ /
- a. Dur rig apy cale ar qua er: Ls/s than or equal t 7.5 mre s to any o an, nd
{
- b. Duriryg any c lendar ear: Less than or equal t 15 mrem to any '
o rg,ah. APPL 1 ABILITY: At all times.
/ J/
ACTION: fq Wit the calculated / dose fromjtherelea/eofIodfne-131,Idine-133, I tr/titm,andradi uclides ip particuldte form p,ith half- ives teater fian 8 d s, in gaseous effluents excq4 ding any f the abo e imits, preparef nd submit /to the Cpinmission 4ithin 30 ays , pur-suant o Specification 6 ntifies e caus9(s) for pxceeding th.4.2, a Spe'cial Rep'or,t that elimit(/)anddefinesthecorrective c- i tiops that t) ave been taken to reduce the eleases a corrective 4ctions to/be takenj f o assur thatuentsubseq)d rel ases the pro ose will be i compliancdwitht above li its. /
- b.
/
The pro isions /
/ofpecificat on 3.0. /are SURVEILLANCE REOUIREMENTs /
4 1.2.3 umulative /fose contyfbutions or the cur nt cale dar quart and urrent pa,lendar yea,r for Iodine-131, Ipdine-133, , tritium and radionupkides in particulate forpi with hal lives g ater than 8 days sha'll be determined in accfrdance with the met dology a ' per 31 days. / paramete[rdintheADCMatlegstonce sf / j
/ /- -
l SEABROOK - UNIT 1 3/4 11-7
/
u p or & i
1 RADI0 ACTIVE EFFLUENTS GASEOUS EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 N IWe VENTI ION E UST TR MENT.SY M and GASEOUS W ' TME SYSTEM all be ERABL d agipro iate p ons of th e systems hall e used t reduce elease f radio ivity the pro ted doses n 1 ays due gaseo, efflue . release .from e unit,.to eas at a be-nd the S EB RY (se igure 1) woul xceed:
. O. rad to r from amma radi on, or
- b. 0.4 mrad to air beta r iation, or
)
- c. O. mrem to ny organ o a MEMBER THE PUBLJ .
APPLICAS ITY: A all times ACE :
- a. With rad active ga us waste ing disch r'ged witho .treatmen and i xcess of above li s, prep and sub i to the q Co ir sion with 30 days rsuant t pecificapi n 6.8.2, hatinclu[,esthef owing S cial Repo i ation:
- 1. Iden ficatio
/
'f any inoperable eq J ent or s systems,
)
I reason f the i trability Action ( taken to estore t inopera equipment o OPERABL sta.ys and
- 3. maary desc iption o action (s) t ken to pr ent a rec' rence,
- b. he provisi s of Sp i ication 3 m.3 are no applicabl SU
/
ILLANCE RE IREMENTS /
/ -
,/
l 4;11.2. Doses A to gasepd's release f' rom each to areay and i beyon,d the SIT UNDARY syafi be proje edatle3stonceperJIdaysin / , a dance w .the methodology and pafaneters rf the ODCM wh6n Gaseous ; waste e teent Sy .tfes are not being full tilized. 4.11. .2 The i alled VENTI ION E T TREATM5N SYSTEM aryd GASEOUS STE TRE T SYSTEM shill be cop red OPERA 8LE by meetJn'g Specifica-ons 3.11p and 3.11pd or 3.y1 .3. / / l SEABROOK'- UNIT 1 3/4 11-8
// -
meux
i RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0A*TIVE WASTES 1 I I
-(rtCS f/suf<cArtoA A.uArtaira if NW ufEb)
LIMITING DITION FOR OPERATION l 3.11.l.8a'd activ wastes all be LIDIFIFgordewa red in a ordance i PROC CONT L PROG to me shippingandtra ortatio requirem ts
%uring l d ransi , and di osal si requirements when eceived the di osal l site PLICAEI ITY: At all ti I. !
l ACT
- a. ith 501,I IFICATI or dewa ring not eting d posal sit and ship-l ping an'd transpo,rtation r uirements suspend hipment of the inade .
quatyeiy processed wastes and corre the PR ESS CONTR PROGRAM, he pr cedures, and/or the olid Was System s necessar to preve ecurrence,/ b With 50k!DIFICATI or dewa ring no performed
- accorda e with the P CESS C0 OL PROGR , test e improper process waste in ,
eac contain o ensur that it ets buria ground a shipping ' r uirement nd take propri administ tive act n to prev t ecurrency. c The pr isions of pecific on 3.0.3 re not ap. icable. VEILLAN REQUIREMENTS /
/ , , ,
4.11. For comer 3t SOLIDIF,ICATION of, least o represen tive test s ecimen fro t least every tenth batch offach type wet radi ctive waste (e. g. .. fil er sludge,si spent yfsins, evaporator bo oms, bori acid soluti s, and fs' odium sulfate solutjons) shall e verifi in acco'r nce with th PROCESS CONTROL P GRAM: p' - a If any/ test spec. n fails o verify S IDIFICATIO ., the SOLI ICA-TIO Vof the batch under test shall b suspended il such e as apditionaltestspecime ained, alte ative SOL IFICATION{, parameters / tan be deter,M mined incancordance be o wi the PROC S CONTROL PROGRAM,4ndasubsefjuenttest erifies SOL IFICATION. SOLIDIFIC TION of ,the batch May then b resumed usi the alter ative SOLI - FICATION parametfrs determ edbythePpCESSCONTR PROGRAM;
- b. If he initia testspegibnfromabatchofwas fails to erify OLIDIFICATION, the PRACESS CONTR01,/tROGRAM sh 1 provide or the collectioff and testijig of represepfative tes pecimens from each consecjdive batch of the same type of wet te until consecutive ini fltestspecJeensdemons ateSOLIDI/atleastthr ICATION. e PR0dESS CONTR ROGRAM shaji be modif as requi d, as provid j d in Stiecificatiop .12, to assdre SOLIDIFJ ATION of bsequent b3tches of
, waste; and/
p/ j/
/
- SEABROOK - UNIT 1 3/4 11-10
/ k p r. f
RADI0 ACTIVE EFFLUENTS SOLID RADIOACTIVE WASTES SURVEILLANCE REQUIREMENTS l 4.11.3 (Continued) ( r4f t Cfretf(CAT /od M""CF/L If 4W 49%
- c. With e ins
- 3. .3 or de%1ed clared e tripment operab1 ipelpahT
(, resto ~~etgeifTcittyn-e equip nt to O RABLE atus or provid for c ct cap ity to ocess wa s as-necess to s isfy applicapi transp ation a ispos / requ ement[ l A ., t i
- l SEABROOK - UNIT 1 3/4 11-11 9( d mm-mr 5
RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE (r#S S&c4Ac4rta4nher/2.trMoT'lUEb) LIMITINGhDITIONFOROPERATION 1 3.11.4 nual ( alenda year) ose or dose co tment to y MEMBER F PUBLI due rele es of adioac vity d to rad tion fro uranium f el cyc1 sour es sha be 1 ited t less an or eq al to 25 ems to t whole bo or y org , exce the yroid, ' hich sh 1 be limi ed to les than or e ual t 75 mr s. APPL ABILIT : At 1 ti . A ON:
!a Withtheca)tulateddoses'fr the rel se of. rad oactive mat rials in iquid r gase s efflue s exceed g twice e limits o Specifi-c ion 3 1.1.2a , 3.11.1. ., 3.11 .2a., 3. ]
.2.2b., 3.1 .2.3a., or !
.11.2. ., cal ulations hall be ade inclu ng direct r diation contri tions , rom the its and rom outsi e storage t ks to deter !
/g, mine hether the above limits o Specific ion.3.11.4 ave been ex 4 ce d. If such is e case, repare an submit to e Commissi 4
8 wit'hin 30 ays, pur ant to ecificati n 6.8.2, a pecial Repo tdatdef es the c rrective action to e taken to educe subs uent s releas to prev t recurr nce of ex eeding the bove limits and in-cludes,the sche le for hieving; nformance th the abo limits. pecial port, as defined 17 10 CFR 20 5(c),shal include This/sistha an y estimat the radiation exposyte (dose) t a MEMBER T PUBLIC om uran'um fuel c le sources / including 1 efflu thways d oirec radiatio , for the c endar year hat inci s the rele e(s) co red by t s report. shall als describe evels of radi- ion an concentra ions of ra oactive ma rial inv ved, and the c se of t exposur levels or oncentratio s. If th estimated dose ) excee s the abo limits, dif.theryeaseconytionresult ing in vio ion of 40 CFR Part 1 has not ready bee corrected, ( t Specia Report s 11 includ a request r a vari ce in accor - ce wit the provi ions of 40 FR Part 19 Submit al of the r ort is cons 'dered a t' ly requ , and a va ance,is anted until staff actio on the re est is co lete.
. Th provision of Specif' cation 3.0. are not plicable. -
SURVEIL . CE REQUIR ENTS 1
/ i / / / /
4.11 1 Cumul ive dose ontribution!fromli d and gas us effluen , sha be'dete ined in a ordance wi Specifi ations 4.11 .2, 4.11. ,:and l 4.1)1.2.3,a in accor nce with t methodo gy and par ters in t e ODCM. ' 4.11.4.2 umulativ dose contr utions f a direct rp iation fro the unit and fron) adwaste torage tan 4n accordan with th method logy and rameters i .the shall 00CMbe determined,rement This requj is a plicable ly J under conditio set forth n ACTION .ofSpecification3.1.4.
/
SEABROOK - UNIT 1 3/4 11-12 l1
/dA peibmAT~
3/4.12 ' RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM (r;gS Specgp(CMted MM M ' S N0Y Wh LIMITING OR OPERATION 3.12.1 e adioso icai t viro ntal Mo itoring rogram REMP) sh 1 be rcondu ed a speci ied in the OD M. APP CAB ITY: t all imes. A ION * /. a. W th the Radiol gical vironmeptal Mon toring P, gram no being onduc .d as ecifie , prepar/ and s mit to_t e Commis lon, in the Radio ogical nvirons ating'Re ort requ red by f Annua}icati Spec f n 6.8.1.3, a des'pital criptioOp of the r asons f not c ductint the progr as re ired an the pl ns for p venting ' recur ence. l
. ythth level f radio tivity s the re uit of p ant eff uents i an env ronmen 1 sampi g medi at a s cified cation xceedi the r portin levels the R P when eraged er any calenda quar j er, pr are an submit o the C ission ithin 3 days f m receiptofthelabjatory alyses, ursuant o Spe ication 6.8.2, ifies t cause( for a eeding he a/Specia/anddel imit(s Report nes th piat i orrecti e action to be ken to educe radio ive of uents s that th potenti/1 annua dose
- a MEM R OF TH PUBLIC s less han the alendar fear liyits of 5 cifica ions 3.1 1.2, 3 .2.2, 3.11.2 . When ore th n one o the ra o- i nup ides i he REM are det cted in e samp ing med m, thi report j s all be~ bmitte if:
/ /
concentra1rion (1) concentration (2) i r porting / level ( + reporAing levdl (2) '*d Who radion lides o er than hose 1)stedin e REMP are det cted ar are th result plant ffluent,s, this r port shall be s bmitted ; the po ential nual do *toaNEMBEROFTHEPU%ICfro j all ; radionupfidesis qual to r greater than e calepdar yea limit ok Specif cation 3 1.1.2, .11.2.Z[or3.112.3. Tfis rep is n t requ d if t measur leveljff radioadtivity )as not he res it of ant eff ents; h ver, n such a/ event, he cond tion all be reporte nd desc ibed i the Annus'1 Radio) gical E6 viro ntal erating port r uired Specif dation 6 8.1.3. arameter used,to stima he p ential annual ose t thododgy andem sh.1 a TpheRf 1,ej,e he ind, tedy,s, . o,t.
. SEABROOK - UNIT 3 3/4 12-1 M C M > pp t A1 T
RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORINGPRDGRAM LIMITING CONDITION FOR OPERATION 3.12.1 (Continued) ( re+d FPecmcen4a gwsg it aor Wh I M I mil leaf vegetab c W or f s unavai)able fr one or re o the s le lo tions re utrad the dologica Environy menta,1 Monit g fy sp fic loc ions for obtainin p acem t gram sampi (RE' an )d ad,ide em w in 30 ys to t ) REMP giv n.th DCM. T specif c locat ns from hich s les i w4re unt 11abl may then e dele d from e monit ring pr ram. Parsuanf. to S e ificati 6.13, bait i the nex Annual dioac-tive Effluen Release port d umentat n for a hange i the 0 M inc nd tabi for the ODCM re actin he new)6 ding af evised location f gure(s) wit suppo ng info tionip6ntifyin the e se l pftheunnva-(s)bil)tyofs la les an justifyngthe actio of j the new/1ocation 4) for aining amples. d T rovision f Spect ication .0.3 ar not app icable SURVEILLANCE /REQUIREM TS , , ,
/
4.12.1 fThe radio) gical vironme al mont ring s
/
les sht11 be
/
11ect pursupt to the RE P fro the spe fic loc ions g in fie tabl and f - ure( ) in the C ant'shall b analyze pursuan to the requir nts and etecti e REMP. iijtiesreyredby i SEABROOK - UNIT 1 3/412-2 Amendment N
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS { rHV J/ec W (M <*4 MM ' # /0 OI "# LIMITINGfCONDITIONFOROPERATION y 3.12.2 and Use cens - shall b onducted^ d shall i entify w hin a di ance r 8 km (5 alles the loca n in each of the 16 teorolo ical sect s of th th earest re dance, an the near st garden of ! grea er nearetmi]kaimalf tha 50 m ( 0 ft ) p ucing bro d leaf ve tation. l AP LICABILITY: At all timest TION
- a. h a Land a loca on(s) tha yields a W}lculated
'a dose or dse Census e commit nt identifyi great than the values currently being cal lated in pecifica on 4.11. 3, pursuant o Specific 4 tion 6.8. 4, ident y the ne location ) in the ne t i Annual adioactiv Effluent elease port.
b With Land Us Census i ntifying a locatio s) that yie ds a calf lated do e or dose ommitme (via the ame exposur pathway) L 20% greater,than at a cation om which mples are rrently b4ing obta)hed in acc rdance h Specif tion 3.12. , add the new 1 ocation( ) within 3d days to he Radio gical Envir nmental I
, Monitori Progra iven in he ODCM, permissio from the own I
to collfet sample can be tained a sufficient ample volum is' availpble. The ampling cation (s) excluding location, havi the low, t calcul ted dose or ose e control s tion commitme t(s),
/ vi 4/the same posure pithway, ma be delete rom this mo toring '
l Q pr;6 gram afte Octobe"/31 of the ear in whic this Land U e Census yas conduc d. Pur.tuant to Sp ification 6(13, submit the next documentati for a
/ Annual change if Rap the OMonctive including /a the 000)1 reflec g the neW1ocation(s fffluent revised f Release Repofor ure(s) and able(s th inform ion supp) ortg the c nge in sampling lo stions.
- c. The provision of Speci ication 3.0 are not a licable.
1 f road lea vegetati samplin f at leastf hree differ t kinds vegetatio may be M rformed a the SITE NDARY in ach of two fferent di ection se i tors w)".n the highest predic d relative eposition y lues (D/Q ) in lieu the arden census. Specifi tions fo broad leaf vpgetation ampling i e REMP shall begollowed, luding ysis of c rol sam s. SEABROOK - UNIT 1 3/4 12-3 Amendment No. Y I
RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS (,ggy 3pguptcArroh N w eba SS Hor a& SURVEILLANCEdEQUIREMENTS
~
~
4.12.2 e and se us s 1 be c ducted urin he groging s son a eas onc per mo usi a met d such s by oor- -door urvey fae 1 rvey or b onsu ng lo 1 agri ltur thori les, descr' ed i 0 M. J e re ts of the La Use C sus s 1 be ciud in th Annup ad' log gi 1 En onme al Ope ting R ort uant) Spe ficati l 6.f... 8 3 l l l l l w O g
&gahMdT
}
RADIOLOGICAL ENVIRONMENTAL MONITORING i- 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM or RS b) _( rt+t.C f/EctFMMOA N MG FA- Ig LIMITING ITION FOR OPERATION M2. 3 n yses s all be rformed n all r dioactiv materi s, supp11 d as par o a Inter borator Compari n Progr m that s been proved b the C issi n, tha corres nd to s les re uired by he REMP PLI BILI . At al times. . ACT N: 5
- a. With alyses ot bein perfo d as req red abov , report he f corr etive a ions t en to p vent a r currence o the Co ist;io in he Annu Radio ogical vironmen 1 Operat.ng Repor pursJa t Specif ation .8.1.3.
- b. The pr isions f Speci 1 cation 3 .3 are t app 11 ble.
\
SURV ILLANCE_ EQUIR NTS
/ .12.3 A summ Compa son P Oper ting of Int aborat y Compari n Prog resul obtained s part ram sh 1 be inc ed in shall ident ied in Annual adiolo cal Env' onment e 00CM.
the abo e requi ed Inter aborato ort pu uant to 5 ificat n 6.8.1. . l I, , , S S O
. - . I, ,
yn AME~4batEAJY" e g%t l
l l 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS g(r$S ffEctFICRM N#-M # U 3/4.11.1.1bCONCENTRefl0N/ - Thi spe ific ion is ovid d to nsure hat ac ve ter als elea ed"i liq id warft e eff uents e at co centr tion f ra io-t e poi t of isch rge f om t e m tipa t di fuse wil be Igts th the once rati n lev is s ci-ied n1 CFR art 0, A pendi B, Table I , Col mn 2. Thi limit,ation pro- } vid ad itio I as uran e tha the evels of radioact ve m erials in odie of wate in REST CTE AREA will resul) in es osur s wit in: on .Ad ign jec ves gf App dix I/,10 C/R Pa 50, oa UBL , an (2) e li its t 10 C R Par,( 20.106 e) o th 1) t e Se - @ EMBE OF E tio T A7 conentraionliitfrdisolved/oren,trainefno(bl gas popu)ased is pon he as umpti n tha Xe-1 is he co troll'ng rapioiso ope d its MPC 'n ai (sub rsio was nyer d to an e vale t con ntra ion i wate usi g th meth ds escr' ed in nter tion Co ssio on R iolo cal P/ otec ion CRP (Publ* ation .
/
\ 3/4.11.1.2 t N(TM M f'M - Thi sp cifi ation i provid d to imp ement t e requi ements o Sec-t ons I .A III. , and I .A of A pendix I to 10 C Part 0. The imitin Con-
. itio for Oper tion im ements the guid s, set f rth in ection I .A of pen-dix .
T e AC ION sta ments rovide t e requiyed oper ting fle ibility and at the ame time impleme the g ides set forth ir/ Sectio IV.A of Appendi I to as re hat Ane rele es of adioactiematerfalin1)quideffuentst UNRE-S ICT D AREAS will e kept as low a is reag6nably The ose cal-lat on m('thodolo andprametersinthe00CMimp}pchievabl. ement th requir ents in . ectonIJI.Aof pendix that c nformancf with e guide of App dix I b shonby/calcula onal p ocedure ased o models nd data such t t the ac ual xposure f a ME ER OF T PUBLI throug appropr' te pat ays is u - 1 kely to be s stanti ly unde sti' mate . The quation specifi d in the ODCM l ' or c iculati the dpses due the act'ual rel ase rat of rad oactive ate-rial in liq d effl ents are Aonsistep't with logy p ovided i Regu '
< 1atory Guid 1.109, ' Calculation of Annual es toDop/he M meth Rel ases (
for tht Purpose /of Evalgating C from Rithutine liance 10 R Part 50, Appendix " Revis/l on 1, October 1977 and R ulator Guide 1. 13, g
/
of/ Reactor /Efflue stimat nd Routi e Reactor ! /' eleases'j'ng
/
for t Aquat
/ /
c DisperAion of Effluentp' from Purpose 6f Implementing ppen' dix I'" April 1977. hisspepficatio to the lease o /ra,dioac ive mater als in l liq Sys ems deffluntsfrom/njapplies/atthe/ona. ach uni are sed by more than ne unit ite si W n share Radwast Treatmen
, the w are t mix,ed for ared tren'tment; b such ixing, t effluep/stesfromallunitt release cannot curatel be ascri d to a pecifi unit. estima ontribu ions fro ach uni based input onditio)eshouldbemadeofthe
,e.g.,flowratesand
, radioactivity con.entratio s, or, f not prActicabl , the tre ted efflu nt releassmaybe/llocate/equallytoeachpfther ioactive aste pro ucing units sharing t e Radwa e Trea For eterminin conform nce to entSyst/m.
l SEABROOK.- UNIT 1 B 3/4 11-1 /
/}MMWENs 3
RADI0 ACTIVE EFFLUENTS BASES LIQUID EFFLUENTS f(T*ts mumn=h 4% DEA. t P cor u. reb) 3/4.11.1.2kDME ( ntInu f b0,the al catio ared adwas Treat Sy ems are o be ad d t the lea ! s speS fical attr uted eacfhItit to btain t total ( ele sp unit /~ i
-lT*C CPenmeAnea n u mea.82 ru.te%)
3/4.11.1.3k5UIDBADWASTETRE&THENTStSTEM r I he O RABI TY o the quid dwast Treatm nt Syst 'm ensur s that this sy em w 1 be vaila e fo use w enever liquid ffluen requi trea ent for t rele e to he e irons t. T requi ement t t the propr te por-i tions f thi syst be ed wh spec *fied pr vides a surance that t e relea s of r dioac ve m erial in 11 uid ef luents ill be ept as ow as s reaso - ab achi vable Thi speci catio implem nts the equire nts o 10 CFR,0.36a, ' pneral esig Crite ion 60 of App ndix A o 10 CF Part 5 , and e desi ob-
#.jectiv give in 5 tion .D of ppendi I to 10 CFR Par 50, he spec ~fied j limi gove ning e use of app opriat ortion of the iquid adwaste reat- f
, men Syst were specif ed as suitat} fract n of t e dose esign jectiv l 1 s. fort in < Qn J . A of ppendif I to 10 FR Par 50 fo liquid efflu 3/4.11.1.4 LIQUIDHOLDUPiANKS , i The temporary tanks include all those outdoor radwaste tanks that are not i surrounded by liners, dikes, or walls capable of holding the tank contents and l that ao not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System. j Restricting the quantity of radioactive material containsd in the speci-fied tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less the the limits of 10 CFR Part 20, Appe,wh B, Table II, Column 2, at the nearest F.:.able water l supply and the nearest si face water supply in an UNRESTRICTED AREA. 3/4.11.2 GASEOUS EFFLUENTS j(yatI spec #cAnod N64 'S Aorureb}
~
l 3/4.11.2.lbOOJE RATE / J p his s ecific ion / is rovided to ensur that th dose at ny time t and be nd th SITE B NDARY rom gas us effl nts fro all unit on the te wil i b withi nnual ose theli a ual dos limits f 10 CF Part 20 oUNRESTpCTEDARAS. T
} ts are he dos associa d with e concentrations f 10 C Part , Appe dix B, Jable II Column These imits pro /ide rec nable s-sur ce tha radioa tive mat rial dis arged i gaseous g(fluents ill n re-in th exposu of a MBER OF E PUBLI in an UN STRICTE. AREA, ither su)
(th in or outside the SIT x-eeding he lim s speci iedBOUNDARY,dixB/TableIItoann941averageconcentr/tion
'in pen f 10 CF Part (10 CFR i
j Part 2 For MBERS HE PUBLI'C who may t times e wit n the l j (SITE)J.106(b). l0UNDARY, the oc upancy o that ME3ElER OF THEj UBLIC w 11 usu ly be j SEABROOK - UNIT 1 B 3/4 11-2 is&R q[ $ C mac
RADI0 ACTIVE EFFLUENTS ' BASES l GASE0US EFFLUENTS j@G JtNNod h43M 'T No T Llf80) 3/4.11.2.lfDESERATE(Con nued) / J , 1 suff cient lo o comp nsate f r any i crease n the tmosph ic dif usion ia f or a ve th for t e SITE OUNDAR . Exam es of alcula ions f such BERS F TH PUBLIC with t e appro riate cupanc factor , shal be giv n Tb n th ODCM. elease ate li its re rict, all t*mes, t j corr pondi g gamm Thesp'cified/adose and bet ates a ve ba round o a ME ER OF
$ E k
PUB C at r beyo theSJTEBOU ARY to ess t n or e al to 0 mre / year t the w ole bod less th n or e al to 2000 mre s/ year o the in. I k ese r lease r te ortoIsals li restri , at 4(1 ti , the c respon ing I thyrojddose bac round 1500 rems /yp r. a chiffi via inhaltionpphway Qess/thanor[eteab qual J
-3 ~ 3/4.11.2.2kD05E-NOBlfGASES 3" r inis
/
ecifica n is pro ded to " plement t
/requirem ts of Sect' ns II , III and IV of Appe ix I to CFR Part 0. The 'miting Con ' tion f~
f r Oper tion is ments th guides he AC ON stat ents prov'de the t forth i Section I of Append I. uired op ating fle bility and t the f same ime impipment the ides se forth in etion IV. of Appendi I at the
%( SIT OUNDARY/that the eleases radioac ve materi in gaseou effluents y to NRESTRI ED AREAS" ill be ) pt as low as is reas nably achie able. The S rveilla e Requir ents impTement the equiremen in Sectio III.A of F
ppendix that co ormance ith the 9 ides of Ap endix I be own by ca ula-tional rocedure ased o models an data such hat the ac al exposu of a MEMBEjl0FTHEP LIC thr agh approp fate path ys is unli y to be s stan-tial)yundere imated. he dose 1culation methodology nd parame rs esta li hed in th ODCM fo calculat g the dus due to th actual rel se rate o radioac ve nobl gases in aseous eff uents are c sistent wi h the m od-logy pro ided in egulatory uide 1.10 , "Calculat n of Annu Doses t Man
, from Roptine Rei ses of R ctor Effl nts for the urpose of valuatin Com-plianct with 10 FR Part , Appendi I," Revisi I, Octobg 1977 a Regu-latop Guide .111, "Me ods for Ep imating At spheric Trjrhsport a Di sper-O sio of Gas us Efflu ts in Routjrne Releases rom Ligh Water Co d Reacto s,"-
kW R ision 1 July 19 The OD equations ovided fo etermin the ai oses at nd beyonc$ he SITE UNDARY are)(ased upon J. e histor) al aver e ; I atmospheric conditions, j f f f eq '
*% C 3/4.11.2.97 DOSE -/ IODIN 7-131,/0 DINE-433, TRI7f 0M, ANQ/ RAD 10KTIVE MATE 41A I h
-8 ~$ ,
"IN imRTIC)lLATE FORM ;
'q j T s spe fica on is provid d to im ement t e requir ents II.C, III.A d IVf of pendi I to 10 FR Par 50. Th Limit Secti s Condi ons i
l
; for perati n are/the ides s forth n Secti n II.C o Appe x I. e 4
& ACJ ON sty emeri pro de th require operatJgflexiblity d at t same
'ymeim/pemenfthepidess forth n Sectign IV.A o Appe g
d'/ j x I to/ v ssure I SEABROOK - UNIT 1 B 3/4 11-3 . kf penac
I l RADI0 ACTIVE EFFLUENTS f BASES GASEOUS EFFLUENTSgwr yrc,pu.arnA 4&dfA tS AT4f 6b) l 3/4.11.2.3 EOSE - 10DTNE-131/ IODINE-Id3, TRITJbM, AND dDI0ACTIVF< MATERIAL l IN#ARTJCULATE FORM Contin d) l l ha the lease of rad active terials in gaseo effluen at the S E
- B DARY ill kept low as s reaso bly ach vable. T e ODCM ca ula-l '
onal thod specif d in th Survet ance Re rements plement e require-
- ment in Se ion II .A of Ap ndix I at conf ance wit the guid of Appen-
! di 'be s own by alculati nal pro dures b ed on mod s and da such that I l t actu expos e of a MBER OF HE PUBL thrcugh ppropriat pathways l niike y to be ubstant . The OD calcula onal metho ol-ogy a d para tersfor)calcula11y und estimat ng the dyses due t the actu release r es of j
, l i the ubject aterial are co istent w th the me vided in gula-t y Guid 1.109, " alculat n of An al Doses ~ odology Man fr p/R outine Re eases of ]
ffluents for th urpose o Evaluati Complian H +h 10 R Part 50, f f eactor I," Re-sion 1 ctober 7 and Re latory G de 1.111, ' ethods for [ Append Esti ting At spheric ransport and Dispe ion of Ga eous Efflu ts in Rout e I l Re1 ases fro Light- ter-Cool Reactors, ' Revisio 1, July 7. These ua-l t ons also rovide r dete ning the tual dos based up the histor' cal l verage 4tmosphe condit s. The r lease rat specifica ons for Io ne-131 I Iodine 33, tri um, and ionuclid s in part ulate fo ith half- ves s grea than8daysare/ependent on the ex' sting rad uclide pa ways to
- - man the a as at an# beyond t SITE BOU ARY. The athways th were ex -
in th developogrft of the 1culatio were: ( individua inhalati of i
-9 pi'rborne adionuel ks, (2) d osition o radionuc1J es onto gr en leafy ege-h tation th subse ent cons ption by n, (3) dep6sition of adionucli s onto Y grassy areas wh milk an' als and at produciig f animals aze foll ed by g humar( consumpt) n of tha milk and at, and (f) depositi of radi uclides on h ound fM1 owed by ubsequent usan exposdre.
Q , 3/4.11.2.4l TGG5EOUS JtADWASTE)fREATMEN/ SYSTEM I {TI EX he J RABI TY of ST T ATMENT e GASE0 RADWAS STEM e ures th TREATME the sys SYSTEM a the VENT will b available or aw never aseous fluents require reatment or to r fease to t l envi noen The iremen that th appropri e portio of these ystems b l us , wh specif , prov es rea able ass ance tha the relea s of l dioac ve mate ials in aseous fluents w 1 be ke aslowafisreaso y{ j achie ble. T s speci ication pienents he requipements of fl0 CFR 50 a, Gen al Desi Criter on 60 o ppendix to 10 CF Part 50,j dnd the d gn j opfectives iven in ectionI.DofApp/ndixIt 10 CFR Pp t 50. Th specifief U j Ximits g. erning a use o /appropri Ke portio of the jfstems we specifie i
- as a syd.able fr ction o the dose esign ob ctives s forth i ections .B I .C of A endix I o 10 CFR rt 50, r gaseou, efflueg/
SEABROOK - UNIT 1 8 3/4 11-4 4l me~a
RADICACTIVE EFFLUENTS v BASES GASEOUS EFFLUENTS 3/4.11.2.5 EXPLOSIVE GAS MIXTURE FOR THE GASEOUS RADWASTE SYSTEM This specification is provided to' ensure that the concentration of poten-tially explosive gas mixtures contained in'the GASEOUS RA0 WASTE SYSTEM is main-tained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hy6rogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with tha requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. j w g p p,c w u rn st cor use Q 3/4.11.3 I9{.ID RA6IOACTIVE WMlTES Thi spec icat ni ments the re ireme s of 1 CFR 50 36a a ral esi Crit ion of A endix t.o 10 FR' Par 50. e pro ess , ram ers clude in e tablis ing th PROCE CONTR PROGR may nelud , m ut e no limi d to waste ype, w ste pH waste / iquid/ LIDI ATION i ? , i ag t/ca lyst atios waste il coy (ent, w ste pr cipal mix g an curi emic cons tuents, .g times /- Q f, ' ~ [3/4.11.43TOTKDOSE S no j F This'"s ecifica on is pro ded to P t 190 et the d e limit ions of 4 CFR at have een incor orated i to 10 CF Part 20 46 FR 18 5. The ecific tion re ires the eparati and su ttal of Special port whe -
]'2 ever t calcul ed doses ue to r eases of adioacti ty and to radiatio g from anium f 1 cycle urces e eed 25 m ms to t whole bo or any rgan, .
E exce t the t roid, whi shall e limite to less an or eq 1 to 75 rems. 3 For sites c taining to fou reactors .it is hi hly unli y that e resul-ii. nt dose o a MEMB 0F THE UBLIC wi exceed e dose 1 its of CFR
'{u art 190 f the individual actors r ain wit n twice
.tives o Appendi , and i direct r diation ses from he e dose d sign obje unit (includi e outsi stora anks, e) .)'are k t small. The Spep al Rep will des ibe I a co se of a on that/should r uit in t limita fon of t annual d e to a b ME ER OF TH PUBLIC ,t'o within e 40 CFR/Part 190 imits. or the p poses of t 'Special eport, t the d e commi ent to th MEMBER 0 E PUBLI fromote/tmaybe,ssumedt r uraniug fuel cy e sourc is ne gible, wi the exc -
tion th dose ributiopt from ot er nuc1 fuel le facil ies at t same s f.e or w in a ra fus of 8 must conside . If th dose to ny MEMB 0F TH BLIC is' stimated to excee the requ rements 40 CFR rt 190, the pecial esort wi a reque for a yfriance firovided e releasy condi~ tjnsresu lation o 40 CFR fart 190 ave not ready be correcte Jnaccorda)ncewithinginv)heproviyonsof 0 CFR 19 .11 and 1 FR 20.4 c, is co fsidere o be a t ly requ st and IfillsJ,herequir nts of CFR Par 90 until C staff ction is omplet . The yariance o relate to the li ts of CFR Part 90, and oesnotApplyit the othe require ts for do limitatfonof10 R Partf 20, as a )/any ressedway i Specifica(ions 3.11(1.1 and i .11.2.1. n individ al is t cons ed a ME R OF THF/PUBLIC ing any eriod in hich he/ e is aged fr) carrying tanyopgrationt t is par of 4, thenucJearfuel cle. f ./ l SEABRODK - UNIT 1 B 3/4 11-5 q[
l
. I 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING yts Spec 4AcetTig pwg We r u d 3/4.12. F @0 NIT 0RfNG PROC #AM N a ogical nvironm tal Mo rir.g ogram requir by this s (ifi-cati prov' es rep sentati measur ments o radiation an of radioac ma rials n tho exposur pathway and for those radion ides that ead to e hig 't potg ial ra tion & ,.osures f MEMBERS OF 7 E PUBLIC sulting i
from e pian operati This onitori p program impJ ,ements Sec) on IV.B. of pendix to 10 CJ Part and th eby supplem3 Mis the Rad 61ogical uent M itorin /Prngram y verif ng that the easurable ncentrati ns of
/EdioactJ4emate the b is of th is andj ievels o radiation ar not highe than exp ted on f flue t' measur ents and th odeling o the envir nmental
' expo re pat ys. Gyi ance this monitoring progra is provi d by the Raptlogica ssessmeht Bra . Technical P fition on vironmen Monitori vision Novem9 f 1979, he initiall specified onitorin program wi be ffective'for at Ae6 n th first 3 ye s of comme ial operp ion. Foll ing
, fthispefiod.p,4granc p ffges may be nitiated b ed on op ational e erience. The required ction ca bulated/in term f the low /p 111 ties fo environm tal sampi analyses y the DCM are limits of etection _f {LLDs). T LLDs requ' ed imum for utine en fronmental easurement in indu ial labor, considered atories. should b recogni that the D is defi ed as an a prioriffefore the act) limit epresenti g the capatfility of measure-mpit systep and not a an a poste ri (after the fact / limit for particula
,4easure nt. -
J tailed d cussion of he LLD a und in rrie, L. A). , " Lower Litnit of Detiction:other de) ction lin}i s can be Definition ar(d Elaborat n of a posedPositionfor3ad'iologica)' Effluent fid Enviro Iental Mea rements," UREG/CR 07 (Septe er 1984 /and in t ASL Pro ures Manup , HASL-300 revise,d annually) / 3/4.12.2 [AND USE CENSUli b~ SN'N C ili s e ficat is provi to ens thatchanp[sintheus/ofareas at a d be the SI E BOUNDA are ident ied and thjt modificat'infis to the Ra olog 1 Envi nmental itoring P afe made i uir by the esults o his censy . gra?. Informathngiven,A fromnme the ODCM,ds such the a h oor- door y rvey, fr. aerial sitr'vey, or fros'consultin th local < gricul- ( tur.I autho ities shal 'be used. his censu atisfies t requiremen,ts of ' Se ion I .3 of App ndix I t 0 CFR Pa 0. Restri ing the pensus to rdens p greate /than 50 m2 provides as urance tha pathways via le vegeta ignifica,pt exposure s will be *dentified a monitor , since a parden of this size the mini m require o produce he quanti 26 kg/y f) of leaf'y veget3b es assume in Regula ry Guide f I l}09 for con umption child. dete de this mijdmum garde / size, the 110 wing siimptions w e made:
- 1) 20% the ga en was usep or growing road-lea vegetatio 1.e., ilar (to le)4uce and cg bage) andX2) there yas'a vegeta)fon yield p 2 kg/m2 _ J SEABROOK - UNIT 1 B 3/4 12-1 pe
( - _ _ - - _ _ _ _ .a
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES (
~
^
3/4.12.3TINTERLASORATQRY COMPARI5ON fROGRAM/
/
he equi men for p ticip on in d Inte borat y Comp 1 son Pr ra is pr vide to e ure t n.appro, inde ndent : c ks on e pre 'sion a cur y of he asur ents o radio tive ma rial i nviro ntal s pie matr ces te perfo as par of th quality assuran prog for e iron-me tal itoying i rder o demo trate t t the ults val'd for th rposesoffecti IV.B.)ofAppndixI 10 CFR j fart 5 y G 4
,~ a 1 . ._ __ _---- -_-__
~ ADMINISTRATIVE CONTROLS PROCEDURES AM) PROGigi 6.7.6 (Continued) l
- d. mein = Method for Determinino Subcoolina Marain
~
A program that will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall include the following:
- 1) Traiaing of personnel, and .
- 2) Procedures for monitoring.
- e. Post-Accident ! = lina A program that will ensure the capability to obtain and analyze reactor coolant, radioactive iodines end particulates in plant ,
gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:.
- 1) Training of personnel,
- 2) Procedures for sampling and analysis, and
- 3) Provisions for maintenance of sampling and analysis equipment.
- f. Accident Monitorina Instrumentation l A program which will ensure the capability to monitor plant variables and syrtens operating status during and following an accident. This program shall include those instruments provided to indicate system operating status and furnish information regarding the release of radioactive materials (Category 2 and 3 .
instrumentation as defined in Regulatory Guide 1.97, Revision 3)* l and provide the following:
- 1) Preinntive maintenance and periodic surveillance of instrumentation,
- 2) Preplanned operating procedures and backup instrumentation to be used if one or more monitoring instruments become inoperable, and 3)' Administrative procedures for returning inoperable 4 instruments to OPERABLE status as soon as practicable, gW Og f% 3.
*Seabrook has taken exception to the categorization or instrumentation provided in Reculatory Guide 1.97, Revision 3. The Seabrook exceptions are provided in FSAR fable 7.5-1, which has been reviewed by the NRC staff in SER Supplement No. 5.
SEABROCK - UNIT 1 6-14 Amendment No.
)
ADMINISTRATIVE CONTROLS
% PROCEDlIREs AND PROGRAMS 6.7.6 (Continued)
- g. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive emuents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive emuents as low as reasonably achievable. The program (1) shall be contained in the ODCM,(2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
- 2) Limitations on the instantaneous concentrations of radioactive material released in liquid emuents 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, l 4) Limitations on the annual and quarterly doses or dose commitment to a l MEMBER OF THE PUBLIC from radioactive materials in liquid emuents i released from each unit to UNRESTRICTED AREAS conforming to l Appendix 1 to 10 CFR Part 50, I
- 5) Determination of cumulative and projected dose contributions from radioactive emuents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least
( every 31 days, i
- 6) Limitations on the operability and use of the liquid and gaseous emuent j 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 period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, I
StiABROOK - UNIT I 6 Amendment No.
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS ' C,5 6.7.6 (Continued) -
- 7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY shall be limited to the following:
a) For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and b) For lodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 daya less than or equal to 1500 mrems/yr to any organ,
- 8) Limitations on the annual and quanerly air doses resulting from noble gases released in gaseous effluents to areas 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 from lodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50,
- 10) (Not Used), and i1) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Pan 190.
- h. Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the ellluent 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, sampimg, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, W
SEABROOK - UNIT I 6- Amendment No.
f f ADMINISTRATIVE CONTROLS ' O I p PROCEDURES AND PROGRAMS
.' .Co 6.7.6_ (Continued) - 1
{ 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring ; program are made if required by the results of this census, and j
- j. i
- 3) Participation in a Interlaboratory Comparison Program to ensure that -
independent checks on the precision and accuracy of the measurements of 9 radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. l l i l I
)
l-l l SEABROOK - UNIT I 6- Amendment No.
ADMINISTRATIVE CONTROLS l i 6.8 REPORTING REOUIREMENTS ROUTINE REPORTS 6.8.1 In addition to the applicable reporting requirements of Title 10. C;de of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted. STARTUP REPORT d,8.1.1 A summary report of station startup and power escalation testing shall be submitted following: (1) receipt of an Operating License. (2) amendment to the license involving a planned increase in power level. (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 nuclear, thermal, or hydraulic performance of the station. I l l e
- gB. !
#'R SEABROOK - UNIT 1 6-1 , AmendmentNo.[
W4-
ADMINISTRATIVE CONTROLS _~ The Startup Report shall address each of the tests id.entified 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 comparison of these values with design predictions and specificationc. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license condi-tions based on other commitments shall be included in this report. Startup Reports shall be submitted within: (1) 90 days following completi,on of the Startup Test Program, (2) 90 days following resumption or commencement 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, completion of Startup Test Program, 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
- 6.8.1.2 Annual Reports covering the activities of the station 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.
Reports required on an annual basis shall include:
- a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures -
greater than 100 mrem /yr and their associated man-rem exposure 4 according to work and job functions ** (e.g., reactor operations and
- surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling).
The dose assignments to various duty functions may be estimated u based on pocket dosimeter, thermoluminescent dosimeter (TLD), or p 'g @ film badge measurements. Small exposures totalling less than 20% of
., the individual total dose need not be accounted for. In the aggregate, 6 at least 80% of the total whole-body dose received from external , sources should be assigned to specific major work functions;
- b. The results of specific activity analyses in which the primary y coolant exceeded the limits of Specification 3.4.8. The following ;
information shall be included: (1) Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded
&[ (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiofodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean up flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration (pci/gm) and one other radio-iodine isotope concentration (pCi/ge) as a function of time for the
*A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
. **This tabulation supplements the requirements of S20.407 of 10 CFR Part 20.
iEABR00K - UNIT 1 6-15
ADMINISTRATIVE CONTROLS 6.8.1.2 (Continued) duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit. p p g c. Documentation of all challenges to the pressurizer power-operated relief valves (PORVs) and safety valves, p - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.8.1.3Moutine/nnual Rafiological Jfivironment,ai Operati Reports vering d.he op Yation f the sta 1on during,4.he previov's calenda year shal be submi prior o Ma of each ear. The nitial re rt shall e submitt prior to May of year fo owing ini al critic ity and all inclu mpies t t)e preop ational adiologi Environm tal Prog m of the it fo. a east
/2 years rior to riticalit heAnnu1Radiologj 1 Enviro ental Op ting Reppets shall jnclude s ' aries', erpretati ns, and a analysis diologica environm ntal surv llance a vities trends or the resuJts of the includin a compari fn with f / the repof ,f period, operation- studies with operational c rols, as app priate, with p tous envi nmental s rveillan e' reports, d an assejmentoft observe 1mpacts the plant operatio n the env) onment. ,
Thy reports shefll also in lude the sults of he Land e Census ( equired by l fpecificati 6 3.12.2.p/ j
/ The nnual Rad clogical vironmenta Operatip Reports j all include he result f analy ' of all r !
envir,a mental rp ationmers,a'diologica-'environmpntalsamp}esandofall urements aken dur)fg the pe 'od pursuant ,to the logations sp (fied in t,h6 table a figuresf tn the O te Oose Calrulation / fpmual, as 1 as summarized anp tabulatep results 9 these analys'es and f.easuremepsinthe frmat of pie table jo the Radiological Ass s'sment Branc Technicp Position Revisio , Novem f 1979. If(the event t some in I vidua)/resultsay not ava' ble fo clusionfiththereppt,therep ! sha}J be submipted notin nd expip ing the feasons for ttie missing r,e ults TI)e' missing Cata shall e submit 4d at soo /as possible n a suppleyhtary eport. p/ The/ reports shall also, nelude the following: a summary escription j the' Radiological /fnviron ntal Moni) ding Progra,m; at least legiblepaps** l covering a'l sam,pling tions keyed to a tattle giving dif ances and Alrections ! f 'm the cetttsrline one react,c'r; the resylts of licenfee participation in
/eInterl,Aliorato specified progra s not omparisor4rogram anj/the correc ve action taien if the be g performep as require Specifip(tion 3.12.3 reasoryfor not ductin {
e Radiological Environ ntal MoniA6 ring Progr s i reqyhed by ificatip 3.12.1, d discussion f all devM tions from U e i s ling sepfd11e; discussion of vironmental ample measurements tht, exceed l e repor)ing levels /but are n the result,o plant effluents, pursuant to Specj(tication achiev3.,1.1; ble. and disc'ussion of 11 ar,alyses j h which the / ACTIO LLD required of was/no
,\v'N ,b'. /p 5
/ l
/*A singM submitt)a may be made oramulffpleunitstation. ,/
the/
**0nytiIap Q4catio shall p6ver 11becovered'byoney location [near /more additiofial -
maps.SI 4 / - o SEABROOK - UNIT 1 6-16
&OS~
f/ Yg
l 1 s l a ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT e l' 6.8.1.3 The Annual Radiological Environmental Operating Report covering the operation of the h unit during the previous calendar year shall be submitted by May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reponing period. The material provided shall be coni,istent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10 CFR Pan 50. AS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted by May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR Pan 50. SEABROOK - UNIT 1 6- Amendment No.
1 ADMINISTRATIVE CONTROLS ( ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT
,p 6.8.1. JA rout e Annual adioactive Eff uent Release Re rt covering th ppera on of t statio during the pre ous calendar y r of operation hall i be s itted y May 1 each year. T The nual Ra onctive Efflu t Release Repor s shall includ a summary the q ntities f radioactive 'iquid and gaseo s effluents an solid waste-release from th station as ou ined in Regula ry Guide 1.21 Measuring, /
Evalu ing, and eporting Rad activity in So d Wastes and R eases of Radi active M erials in Li d and Gaseous ffluents from ght-Water-coole Nu ear Powe Plants," Rev ion 1, June lg with data s arized on a rterly sis followin the format of # pen, dix B there . For solid w er, he forma for Table 3 Appendix B slya'11 be suppleme ed with three additio 1 categories- class of solid wastes (as de ned by 10 CFR P t 61), type o container (e g., LSA, Type {TypeB,Larg uantity) and SOLI FICATION age or absorbent e.g., cement). The Annua Radioactive ( luent Release eport shall i ude an annual
, ummary of ho y meteorolog tal data colle ed over the p ous year. Thi l i
annual summa may be eith in the form an hour-by-ho isting on ma tic tape of wi speed, wind irection, atm heric stabilit , and precipit . on (if measu ed), or in th form of join requency distr utions of win peed, wind di ction, and a dospheric stab ty.* This sa report shall clude an l asses ent of the r g)iation doses d e to the radio tive liquid a gaseous eff1 nts release rom the unit station.duri the previous lendar year. T same repor hall also inc de an assessm t of the radi on doses fro ioactive li d and gaseou effluents to BERS OF THE P LIC due to thp4 ctivities i de the SITE NDARY Figur .1-3)during e report peri . ) All assumpt) ns used in ma ng these(ass sments, i.e., ecific activi , exposure time, and locat n, shall be i cluded in th reports. The meteoro}4gical conditi s concurrent th the time release of ra onctive materi41s in gaseous fluents, as termined by pling frequen and measgrement,shall used for de raining the seous pathway ses. The as s: ment of radj tion doses s 11 be perfo d in accordan with the thodology and parameters in he OFFSITE CALCULATION NUAL (ODCM) The An al Radioact e Effluent rease Report ska 1 also inel e an i' assessment f radiation ases to the ely most ex ed MEMBER OF HE PUBLIC ,{ j from reactor releases nd other nea yuraniumfuelpp cycle source , including , I doses f/om primary fluent pathw and direct diation, for he previous ' l calendar year / ! F V h S In lieu o submission wi h the Annual dioactive Effl ent Release Rena t, the
/ license as the optieji of retaining is summary o quired mete logical data provided to p NRC upon req, st.
site in a[le that shall SEABROOK - UNIT 1 6-17 AmendmentNo.JZ
I ADMINISTRATIi!E CONTROLS RADIO TIVE EFFLdENT RELEASE /EPORT j 6 .l.4 (f inued) fashow with 40 C ! Part 190, Environnen 1 Radiati Protecti Standaenforma s for ear Power ration." eptable dose from 11 alculati l tr h ti 1.1 , Rev. 1, and gas s affluents are giventhods for' Regulato Guide tober 19 The ual Radioactive Effluent 'Aelease port shall/ nelude a st and scriptios/of unplann9d releases ros the si to 12dtES AICTED- of padioacti (e material in gaseous ed 11guld fluents during reporti
/ period.
Annual ioactive ffluent Release Repo shall include any es made uring the rting riod to PROCESS Col (TROL PROGRAM and th pur ' ant to 'ification 5.12 and 5 3, res ively, asfell as or change to L1 d, Gaseou , or Solid dwaste taent Syptoms pursu t to ~ S A ficati 5.14. I shall also aclude a sting of locati s for dose alculatio and/or eevironmental nitori dentift by the La Use Censu
/ pursuantSpecification 3.12. .
The Annual 9 loactiveJffluent Release Repo shall a include felleying: an lanation pt to why thd inoperalpflity of 1 id or ga ous eff1 nt monit i inst ntation not ce ted wi a the time / ified i I ification/ .3 .9 or .3.3.10, spective ; and de iption of events ) 1 infl to 1) quid hold tanks or s storag tanks ex ing the) mits of if' cat)4n 3.11.1. - _ d - IpfTHLY CPERATING REPORTS 6.8.1.5 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Ilmelaar Regulatory Commission. Washington, D.C. 20555, Atta: Document Control Desk, with a copy to the NRC Re!Iional Administrator, no later than the 15th of each month following the ca endar month covered by the report. CORE OPERATING LIMITS REPORT 5.8.1.6,a Core operating limits shall be established and documented in the CORE OPERATilIE LDt!TY REPORT prior to each reload cycle, or prior to any remaining portion of a rf,.d cycle, for the following:
- 1. Cycle dependent Overpower AT and Overtemperature AT trip setpoint parameters and function modifiers for operation with skewed axial power profiles for Table 2.2-1 of Specification 2.2.1,
- 2. SHUTD0lNI MARGM limit for MODES 1, 2, 3, and 4 for Specification 3.1.1.1,
- 3. SHUTD0lAl FARGIN limit for MODE 5 for specification 3.1.1.2, !
1
- 4. Moderator Temperature Coefficient BOL and E0L limits, and 300 ppm surveillance limit for Specification 3.1.1.3, SEABROOK - UNIT 1 6-13 Amendment No.
ADMINISTRATIVE CONTROLS RECORD RETENTION 6.9.3 (Continued)
- f. Records of reactor tests and experiments; g.
Records of training and qualification for current members of the station staff; h. Records of inservice inspections performed pursuant to these Technical Specifications;
- i. Records of quality assurance activities required by the Operational Qualicy Assurance Manual;
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 1C CFR 50.59;
- k. Records of meetings of the 50RC and the NSARC;
- 1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.7 including the date at which the service life commences and associated installation and maintenance records; m.
Records of secondary water sampling and water quality; and
- n. Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures i
g4 effective at specified times and QA records showing that these y jtL procedures were followed.
- g# 9 y6.10O. RADIATION PROTECTION PROGRAM 6.10.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
6.11 HIGH RADIATION AREA 6.11.1 Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the -
" control device" or " alarm signal" required by paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface that the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a P.sdiation Work Permit (RWP). Individuals l
qualified in radiation protection trocedures (e.g. , Health Physics Technician) or personnel ct.ntinuously escorud by such individuals may be exempt from the RWP i'ssuance requirement during 1.nz performance of their assigned duties in high radia-tion areas with exposur':. rates equal to or less than 1000 mR/h,. provided they are otherwise following plant radiation protection procedures for entry into such high SEABROOK - UNIT 1 6-20
/(Cl3g/ 1
pf80' 6.9.3
- o. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
i i l SEAllROOK - UNIT l 6- Amendment No.
i AMINISTRATIVE CONTROLS HIGH RADIATION AREA 6.11.1 (Continued) radiation areas. Any individual or group of individuals permitted to enter such areas sh'11 be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device that continuously indicates the radiation dose rate in the area; or
- b. A radiation monitoring device that continuously integrates the l radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established srd personnel have been made knowledgeable of them; or
- c. An individual qualified in radiation protection procedures n a radiation dose rate monitoring device, who is responsible ar providing positive control over the activities within the csa and shall perfom periodic radiation surveillance at the frequency specified in the Radiation Work Pemit. ,
a 6.11.2 In addition to the requirements of Specification 6.11.1, areas
~
accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm ) (18 in.) from the radiation source or from any surface that the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, j and the keys shall be maintained under the administrative control of the Shift i Superintendent on duty and/or health physics supervision. Doors shall remain l locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) { continuous surveillance may be made by personnel qualified in radiation grotection procedures to provide positive exposure control over the activities aeing performed within the area. For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device. 6.12 PROCESS CONTROL PROGRAM (PCP) 2,1
. he P shall e appr ed by t Commi ion prio to impl w
ntatio . W 64 .2 L ensee- itiat changes o the P:
. all be submitte o the mission n the An al Rad active fflue Releas eport r the pe od in wh h the ange(s) s made This s mittal all co n:
SEABROOK - UNIT 1 6-21 AmendmentNo.g
[ 6.12 PROCESS CONTROL PROGRAM (PCP) Changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.3.o. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluationsjustifying the change (s) and
- 2) A determination that the change will maintain the overall conformance of the olidified waste product to existing requirements of Federal, State, or other applicable regulations.
- b. Shall become effective after review and acceptance by the SORC and the approval of the Station Director.
- ' 6.13 OFFSITE DOSE CALCULATION MANUA Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.3.o. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluationsjustifying the change (s) and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106,40 CFR Part 190,10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become efTective after review and acceptance by the SORC and the approval of the Station Director,
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and each affected page shall indicate the revision number the change was implemented. SEAllROOK - UNIT I 6- Amendment No.
AQtilNISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (PCP)
~
6.12.2 (Continued) f/1) Suffipidtlydeta [d informatJdfIto total 1[upport thM
/ ra 6nale for plementa change wi out benefit f additiona or formation-A dete ation tha he change,d d not reduc he overa con ance of t solidified aste produc oexisting'/
cteriaforjelidwastes; .d 3 DocumentatTon of the f ct that the ange has een revie and f nd acceptab e'by the SOR
. Shall effecyveuponrevip and accep ance by t 50RC.
6.13 ')FFSITE DOSE CALCULATION MANUAL (ODCM) 9 6.13.1 (e OCDM sh be appro d by the to ssion prior 'o implementation. I E icens -initiated anges to t ODCM:
- a. Changes t art A shall e submitte o and appr d by the NR 1 staff p or to impi ntation.
- b. Ch) ges to Part shall be s mitted to th ommission J the 6nual Radioa ve EffluenVRelease Re t for the lod in whi '
the chang wasmadejffective. T) submittalj 11 contai .
- 1) ficienti etailed info ationtototaIlysuppor he rationale the change ithout benefft of addi nal or supplempn al informa (n. Informat(on :ubmi should consi,t J of a pack of those pjges of the E to be chan d with'each page r3 ered,datedandcontaint'ngtherevis) 4 nimber,toget r with apprppriate anal is or evaluat ons justifying,A e change (sp
) W 11 not red the accuracy /
A detemination ory(11 ability othat d the change' ions or Se nt / determinationg'f/' and ose calculat
/
- 3) Documentationofthefdtthatthe ange has been eviewed
/ and foun'd acceptable'by the SOR
, Changes-to Par ance j yso"c Jt B s all / become effe tive - uplon
)
i SEABROOK - UNIT 1 6-22 Amendment No. ,
i ADMINISTRATIVE CONTROLS f~ 6.14 MAJOR CHANGES TO LIQUID. GASE0US. AND SOLID RADWASTE TREATMENT SYSTEMS
- 6.14.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid, gaseous, and solid):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the 50RC. The discussion of each change shall contain:
1)- A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2) sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- 3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; 1
An evaluation of the change, which shows the predicted 4) releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from f those previously predicted in the License application and amendments thereto;
- 5) An evaluation of the change, which shows the expected maximum exposures to a MEM8ER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those -
previously estimated in the License application and amendments thereto;
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the change is to be made;
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and 1
- 8) Documentation of the fact that the change was reviewed and found acceptable by the 50RC.
- b. Shall become effective upon review and acceptance by the SORC.
e
- Licensees may choose to submit the nformation called for in this Specification as part of theb SAR update j PureWT To /o CFA.fo.7I. I SEABROOK - UNIT 1 6-23 AmendmentNo.[
i SECTION III Retype of Proposed Changes The attached retype reflects the currently issued version of the Technical Specifications. Pending Technical Specification changes or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with Technical Specifications prior to issuance. Page 2 I l l l l
INDEX 1.0 DEFINITIONS SECTION g 1.1 ACTION ...... . . . . . . 1-1 1.2 ACTUATION LOGIC TEST ..... .. . .. . . 1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST . . . . 1-1 1.4 AXIAL FLUX DIFFERENCE . . . 1-1 1.5 CHANNEL CALIBRATION . ... . . . 1-1 1.6 CHANNEL CHECK . .. . . . 1-1 j 1.7 CONTAINMENT INTEGRITY . ... .
. 1-2 1.8 CONTROLLED LEAKAGE . .. . . . ... . 1-2 1.9 CORE ALTERATION ....... .
1-2 1.10 CORE OPERATING LIMITS REPORT .. . . . 1-2 1.11 DIGITAL CHANNEL OPERATIONAL TEST .. . . . 1-2 1.12 DOSE EQUIVALENT I-131 . . . . . . . . . ... 1-3 1.13 E - AVERAGE DISINTEGRATION ENERGY . . . 1-3 1.14 ENGINEERED SAFETY FEATURES RESPONSE TIME.. ... 1-3 1.15 FREQUENCY NOTATION ....... .. 1-3 1.16 GASEOUS RADWASTE TREATMENT SYSTEM . 1-3 1.17 IDENTIFIED LEAKAGE . . 1-3 1.18 MASTER RELAY TEST . . . ... . . 1-4 ' 1.19 MEMBER (S) 0F THE PUBLIC . . . . . 1-4 1.20 0FFSITE DOSE CALCULATION MANUAL . . .
. 1-4 1.21 OPERABLE - OPERABILITY . .... . . . 1-4 1.22 OPERATIONAL MODE - MODE . ..
1-4 1.23 PHYSICS TESTS . . . . . . . ... . . .. 1-4 1.24 PRESSURE BOUNDARY LEAKAGE . . . . 1-4 1.25 PROCESS CONTROL PROGRAM . .. . . 1-5 1.26 PURGE - PURGING . . . . . . . . . . .. 1-5 1.27 OUADRANT POWER TILT RATIO . . .. . ... .. 1-5 1.28 RATED THERMAL POWER . . . . . . . . . ... . 1-5 1.29 REACTOR TRIP SYSTEM RESPONSE TIME , . . .. . . 1-5 1.30 REPORTABLE EVENT .. .......... . .. 1-5 1.31 CONTAINMENT ENCLOSURE BUILDING INTEGRITY .. ... 1-5 1.32 SHUTDOWN MARGIN . .. . .. ... . 1-6 1.33 SITE BOUNDARY . . ..... ,. .. . . 1-6 1.34 SLAVE RELAY TEST .. ... . 1-6 1.35 (NOT USED) . . . . . 1-6 1 1.36 !.'URCE CHECK . . . . 1-6 1.37 S,AGGERED TEST BASIS.... . . . . 1-6 1.38 THERMAL POWER . . . . . . . . . . . . 1-6 1.39 TRIP ACTUATING DEVICE OPERATIONAL TEST .. . . 1-6 1.40 UNIDENTIFIED LEAKAGE . . 1-7 1.41 UNRESTRICTED AREA . . . . .. . 1-7 1,42 (NOT USED) . . . .... . .. 1-7
]
1.43 VENTING . ... . . . . .. 1-7 TABLE 1.1 FREQUENCY NOTATION . . . . 1-8 TABLE 1.2 OPERATIONAL MODES . . . . 1-8 l f l SEABROOK - UNIT 1 i Amendment No. 9
INDEX 1.0 DEFINITIONS l 1 SECTION PAGE i 1.1 ACTION ....... .. .. . 1-1 1.2 ACTUATION LOGIC TEST ..... .. . ... . 1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST .. . .. . 1-1 1.4 AXIAL FLUX DIFFERENCE . ... . .. . . 1-1 1.5 CHANNEL CALIBRATION .... ... .. . 1-1 1.6 CHANNEL CHECK ............. . . . 1-1 1.7 CONTAINMENT INTEGRITY . . . . .... .. 1-2 ' 1.8 CONTROLLED LEAKAGE . ... ... . .. .. 1-2 1.9 CORE ALTERATION ..... .. . .... . . 1-2 1.10 CORE OPERATING LIMITS REPORT ... . . 1-2 1.11 DIGITAL CHANNEL OPERATIONAL TEST ... .. . . 1-2 1.12 DOSE EQUIVALENT I-131 . . . . . . .. . ... . 1-3 1.13 E - AVERAGE DISINTEGRATION ENERGY ... . 1-3 1.14 ENGINEERED SAFETY FEATURES RESPONSE TIME . . 1-3 1.15 FREQUENCY NOTATION ........ . .. .. . 1-3 1.16 GASEOUS RADWASTE TREATMENT SYSTEM , ... . . 1-3 1.17 IDENTIFIED LEAKAGE . . .. ... 1-3 i 1.18 MASTER RELAY TEST . . . .. . ... .,. . 1-4 ; , 1.19 MEMBER (S) 0F THE PUBLIC . . . . . 1-4 ! l 1.20 0FFSITE DOSE CALCULATION MANUAL . . . . 1-4 1 l 1.21 OPERABLE - OPERABILITY .. . . . 1-4 1 1.22 OPERATIONAL MODE - MODE . ...... ... . 1-4 1.23 PHYSICS TESTS . . . . . . .. . .. . 1-4 1.24- PRESSURE BOUNDARY LEAKAGE . . ... . 1-4 1.25 PROCESS CONTROL PROGRAM ..... . . .. 1-5 ' 1.26 PURGE - PURGING . . . . . . . ..... . 1-5 1.27 OUADRANT POWER TILT RATIO . . .. .. .. 1-5 1.28 RATED THERMAL POWER . . . . . . . . ... .. .. 1-5 1.29 REACTOR TRIP SYSTEM RESPONSE TIME . . .... .. 1-5 1.30 REPORTABLE EVENT ................... . 1-5 1.31 CONTAINMENT ENCLOSURE BUILDING INTEGRITY
..... 1-5 1.32 SHUTDOWN MARGIN . . . . .... . . . .. 1-6 1.33 SITE BOUNDARY . . ...... ... . .. 1-6 1.34 SLAVE RELAY TEST . ... . ... .. 1-6 1.35 (NOT USED) .. . .. . . 1-6 1 1.36 SOURCE CHECK ...... 1-6 1.37 STAGGERED TEST BASIS . . ... ... 1-6 1.38 THERMAL POWER . . . . . . . . . . . . . 1-6 1.39 TRIP ACTUATING DEVICE OPERATIONAL TEST . . 1-6 1.40 UNIDENTIFIED LEAKAGE .. . .. . . 1-7 i 1.41 UNRESTRICTED AREA .. . . . 1-7 l 1.42 (NOT USED) .. ... . .. . . 1-7 1.43 VENTING . . . ... .. .. 1-7 ]
l TABLE 1.1 FREQUENCY NOTATION . .... . . 1-8 TABLE 1.2 OPERATIONAL MODES . . . . . . 1-8 l' SEABROOK - UNIT 1 i Amendment No. 9 \
I L lEEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l SECTION PAGE
- j. -TABLE-3.3-2 (This table number is not used)
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . .. ... ..... .. 3/4 3-9 l 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION . . . . . . . . . . . . . . . . 3/4 3-14 p l TABLE 3.3-3' ENGINEERED SAFETY FEATURES ACTUATION SYSTEM i INSTRUMENTATION . . . . . . ..... .... .. 3/4 3-16 I TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM l INSTRUMENTATION TRIP SETPOINTS . . . . .. . . . . . . 3/4 3-24 L TABLE 3.3-5 (This table number is not used)
~ TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS ....... 3/4 3-31 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations ... ... 3/4 3-36 l TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS . . . . . . . . . . . . . . . . . . 3/4 3-37 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS . . . . . . . . . . 3/4 3-39 (THIS SPECIFICATION NUMBER IS NOT USED) ..... .. 3/4 3-40 l (THIS SPECIFICATION NUMBER IS NOT USED) ........ 3/4 3-41 ; TABLE 3.3-7 (THIS TABLE NUMBER IS NOT USED). ......... 3/4 3-42 TABLE 4.3-4 (THIS TABLE NUMBER IS NOT USED). . . ... .... 3/4 3-43 (THIS SPECIFICATION NUMBER IS NOT USED) ........ 3/4 3-44 L TABLE 3.3-8 (THIS TABLE NUMBER IS NOT USED). .... ..... 3/4 3-45 l Remote Shutdown System . . . . . . . . . . . . . . . . . 3/4 3-46 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM . . . . . . . . ...... 3/4 3-47 Accident Monitoring Instrumentation .......... 3/4 3-49
- TABLE'3.3-10 ACCIDENT MONITORING INSTRUMENTATION , . . . .. 3/4 3-50 l TABLE 3.3-11 (This table number is not used) . . . .... 3/4 3-53 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-55 TABLE 3.3-12 (THIS TABLE NUMBER IS NOT USED) .......... 3/4 3-56 l
l SEABROOK - UNIT 1 iv Amendment No. 60
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION f1GE TABLE 4.3-5 (THIS TABLE NUMBER IS NOT USED) .... . 3/4 3-58 Explosive Gas Monitoring Instrumentation . . . . 3/4 3-60 lABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION .. .. 3/4 3-61 TABLE 4.3-6 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . .. 3/4 3-64 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) .. . 3/4 3-67 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation . .. . 3/4 4-1 Hot Standby . . ... . ....... . 3/4 4-2 Hot Shutdown . . . .... .. . . 3/4 4-4 Cold Shutdown - Loops Filled . . . . . 3/4 4-6 Cold Shutdown - Loops Not Filled 3/4 4-7 3/4.4.2 SAFETY VALVES Shutdown .... . ... .. . 3/4 4-8 Operating . .. ... .. ..... . 3/4 4-9 3/4.4.3 PRESSURIZER . ...... ... . 3/4 4-10 3/4.4.4 RELIEF VALVES ... . ..... .. . 3/4 4-11 3/4.4.5 STEAM GENERATORS . . . . . . . ....... . 3/4 4-13 TABLE 4.4-1 MININM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION .. .. .. 3/4 4-18 TABLE 4.4-2 STE/M GENERATOR TUBE INSPECTION.... .. 3/4 4-19 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems ... .. 3/4 4-20 Operational Leakage . . .. . 3/4 4-21 TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES 3/4 4-24 3/4.4 7 CHEMISTRY .. . . . . 3/4 4-25 TABLF. 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS . . 3/4 4-26 3/4.4.8 SPECIFIC ACTIVITY . .. . . 3/4 4-27 l l SEABROOK - UNIT 1 v Amendment No. 60 l
INDE1 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i SECTION PAiE ' 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . .... . 3/4 9-4 3/4.9.5 COMMUNICATIONS . . .... .. 3/4 9-5 3/4.9.6 REFUELING MACHINE ............ . 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS ... . 3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level . . . . ... .. 3/4 9-8 Low Water Level . .. .. . . . 3/4 9-9 I 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM . 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL , . .. . 3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE POOL . . . . . . . . . . . 3/4 9-12 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM . 3/4 9-13 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE ........... . 3/4 9-16 FIGURE 3.9-1 FUEL ASSEMBLY BURNUP VS. INITIAL ENRICHMENT FOR SPENT FUEL ASSEMBLY STORAGE ,. .. . 3/4 9-17 3/4.9.14 NEW FUEL ASSEMBLY STORAGE . . . . . 3/4 9-18 l 314.10 SPECIAL TEST EXCEPTIONS ! 3 1 2 IG NS$RilN.dNbPOWERbl5TRIBUilN' LIMIT 5. 3 2 l ! 3/4.10.3 PHYSICS TESTS ........ . . . 3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS ......... . 3/4 10-4 l 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN . . 3/4 10-5 J 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS l (THIS SPECIFICATION NUMBER IS NOT USED) ... . 3/4 11-1 (THIS SPECIFICATION NUMBER IS NOT USED) . . 3/4 11-2 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 11-3 Liquid Holdup Tanks . .. . . . 3/4 11-4 3/4.11.2 GASEOUS EFFLUENTS (THIS SPECIFICATION NUMBER IS NOT USED) . . 3/4 11-5 (THIS SPECIFICATION NUMBER IS NOT USED) . 3/4 11-6 (THIS SPECIFICATION NUMBER IS NOT USED) . 3/4 11-7 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 11-8 Explosive Gas Mixture - System . .. 3/4 11-9 3/4.11.3 (THIS SPECIFICATION NUMBER IS NOT USED) . 3/4 11-10 3/4.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) . 3/4 11-12 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 (THIS SPECIFICATION NUMBER IS NOT USED) . 3/4 12-1 l SEABROOK - UNIT 1 1x Amendment No. 6. 9 P
BDf.1 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION f%CiE 3/4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) .. . 3/4 12-3 3/4.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) .... . 3/4 12-5 3.0/4.0 BASES 3/4.0 APPLICABILITY . . . . . . .. . B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL . . . . . ....... .. B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS . . . . . . . . .. . B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES . . .. .. B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS . . . B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE . . . ............. B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR j ENTHALPY RISE HOT CHANNEL FACTOR . .... B 3/4 2-2 3/4.2.4 OUADRANT POWER TILT RATIO .... .. . . B 3/4 2-3 3/4.2.5 DNB PARAMETERS . . . . .... . B 3/4 2-4 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION . . . . . . . B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION , . . . . . . .. . . B 3/4 3-3 i 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) .. .. . B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM l
~
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION .. . B 3/4 4-1 3/4.4.2 SAFETY VALVES . . ... . . . B 3/4 4-1 3/4.4.3 PRESSURIZER . . . ... B 3/4 4-2 ! 3/4.4.4 RELIEF VALVES . . . . . . . . B 3/4 4-2 3/4.4.5 STEAM GENERATORS . . . . . . . . . . B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE .. .. B 3/4 4-3 3/4.4.7 CHEMISTRY . . .. . .. . . . B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY . . . . . . . .. . B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS . B 3/4 4-7 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE . . B 3/4 4-9 FIGURE B 3/4.4-2 (This figure number not used) B 3/4 4-10 SEABROOK - UNIT 1 x Amendment No. 50 l
]
IEEX i BASES { SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL-AND COOLANT CIRCULATION . .. B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM , . . . B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL . . . . . . . . . . . .. . . . . . . . B 3/4 9-2 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM B 3/4 9-2 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE , .... . B 3/4 9-3 3/4.9 14 NEW FUEL ASSEMBLY STORAGE ... . . . B 3/4 9-3 l 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN .................... B 3/4 10-1 3/4.10.2 GROUP HEIGHT. INSERTION AND POWER DISTRIBUTION LIMITS . B 3/4 10-1 3/4.10.3 PHYSICS TESTS ..... . . ..... . B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS .. ...... .. . B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN . . .... B 3/4 10-1 3/4.10.6 REACTOR COOLANT LOOPS .... .. . ... B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFtOLNIS 3/4.11.1 (THIS SPECIFICATION NUMBER IS NOT USED) ... ... B 3/4 11-1 l l 3/4.11.2 GASEOUS EFFLUENTS . ......... . B 3/4 11-2 3/4.11.3 (THIS SPECIFICATION NUMBER IS NOT USED) . . B 3/4 11-5 l '3/4.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) . . . B 3/4 11-5 l 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 (THIS SPECIFICATION NUMBER IS NOT USED) .. . . B 3/4 12-1 3/4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) .. . . . B 3/4 12-1 l 3/4.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) .. B 3/4 12-2 l 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA . . . . . . . . . . 5-1 5.1 2 LOW POPULATION ZONE ............ .... 5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS .. . . 5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA BOUNDARY . . 5-3 FIGURE 5.1-2 LOW POPULATION ZONE . . . . . . . . . . . 5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION 5-7 5.2 CONTAINMENT 5.2.1 CONFIGURATION ......... . 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE . 5-9 SEABROOK - UNIT 1 xii Amendment No. 6 l
DEFINITIONS MASTER RELAY TEST 1.18 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include, a continuity check of each associated slave relay. MEMBER (S) 0F THE PUBLIC 1.19 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant. OFFSITE DOSE CALCULATION MANUAL 1.20 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.7.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.8.1.3 and 6.8.1.4. 4 OPERABLE - OPERABILITY 1.21 A system, subsystem, train, component or device shall be OPERABLE or have 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 system, subsystem train, component, or device to perform its function (s) are also capable of performing their related support function (s). OPERATIONAL MODE - MODE 1.22 An OPERATIONAL MODE (i.e. , MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2. PHYSICS TESTS l 1.23 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission. PRESSURE BOUNDARY LEAKAGE 1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. l SEABROOK - UNIT 1 1-4 Amendment No. 7, 9
DEFINITIONS , PROCESS CONTROL PROGRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20. 61, and 71. State 1 Regulations, burial ground requirements, and other requirements gcVerning the disposal of solid radioactive waste. l PE GE.- PURGING 1.26 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. QUADRANT POWER TILT RATIO 1.27 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector ino detectors shall be used for computing the average. perable, the remaining three RATED THERMAL POWER 1.28 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 Mwt. !- REACTOR TRIP SYSTEM RESPONSE TIME 1.29 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage. REPORTABLE EVENT l 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section d0.73 of 10 CFR Part 50. CONTAINMENT ENCLOSURE BUILDING INTEGRITY 1.31 CONTAINMENT ENCLOSURE BUILDING INTEGRITY shall exist when:
- a. Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit,
- b. The Containment Enclosure Emergency Air Cleanup System is OPERABLE.
and >
- c. The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.
SEABROOK - UNIT 1 1-5 Amendment No. 7, 9. 34 i i
DEFINITIONS SHUTDOWN MARGIN 1.32 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE BOUNDARY 1.33 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor lea ?d. nor otherwise controlled by the licensee. SLAVE RELAY TEST 1.34 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check. as a minimum, of associated testable actuation devices. 1.35 (NOT USED) SOURCE CHECK 1.36 A SOURCE CHECK shall be the qualitative assessement of channel response when the channel sensor is exposed to a source of increased radioactivity. STAGGERED TEST BASIS 1.37 A STAGGERED TEST BASIS shall consist of:
- a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and
- b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
THERMAL POWEB 1,38 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. TRIP ACTUATING DEVICE OPERATIONAL TEST 1.39 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of opcrating the Trip Actuating Device and verifving OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy. SEABROOK - UNIT 1 1-6 Amendment No. J.-9
DEFINITIONS UNIDENTIFIED LEAKAGE 1.40 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE. UNRESTRICTED AREA 1.41 An UNRESTRICTED AREA shall be eny area at or beyond the SITE BOUNDARY > access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. 1.42 (NOT USED) VENTING 1.43 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. 1 l SEABROOK - UNIT 1 1-7 Amendment No. 7.-9
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INSTRUMENTATION
. MONITORING INSTRUMENTATION RADIDACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 (THIS SPECIFICATION NUMBER IS NOT USED) i l
l i l l L- ! ( J l l i SEABROOK - UNIT 1 3/4 3-55 Amendment No. 22 1
)
D E S U T O N 2 S 1 I 3 . R E 3 B E M L U B N A E T L B A T S I H T ( m9sg8n 4 A- U YE R N9a8-
TABLE 3.3-12 (Continued) l ACTION STATEMENTS (THIS TABLE NUMBER IS NOT USED) l l l t L 1 SEABROOK - UNIT 1 3/4 3-57 Amendment
llll<ii 1l IjIll!llil
\1' i!l il D
E S U T - O . N _ 5 S - I 3 . R - 4 E B E M - L U . B N A E T L - B A _ T S I H T ( Ii Il n mr>mn 8 ,, 4 e CZw
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TABLE 4.3-5 (Contint M TABLE NOTATIONS (THIS TABLE NUMBER IS NOT USED) l l l
' ~ ~ -
SEABROOK - UNIT 1 3/4 3-59 Amendment No. 7 l
)
INSTRUMENTATION MONITORING INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The explosive gas monitoring instrumentation channels shown in Table l 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded. APPLICABILITY: As shown in Table 3.3-13. ACTION:
- a. With an explosive gas monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification declare the channel inoperable and take the ACTION shown in Table 3.3-13.
I
- b. With the number of OPERABLE explosive gas monitoring instrumentation channels less than the Minimum Channels OPERABLE.
take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.8.2 to explain why this inoperability was not corrected in a timely manner.
- c. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. l SURVElliANCE REQUIREMENTS 4.3.3.10 Each explosive gas monitoring instrumentation channel shall be i
demonstrated OPERABLE by performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6. SEABROOK - UNIT 1 3/4 3-60 Amendment No. 22
N O 4 I 3 T C A Y T I L I B
- A
- N C I
O L I T P A P T A N E M U R - T S N 3 I S 1 L
- G E 3 N N I NE 3 R AL O HB E T CA L I R B N ME 1 A O UP T M MO I
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TABLE 3.3-13 (Continued) i TABLE NOTATIONS (NOT USED) l During GASEOUS RADWASTE TREATMENT SYSTEM operation. 5
*** (NOT USED) # (NOT USED)
ACTION STATEMENTS ACTION 32 - (NOT USED)
. ACTION 33 - (NOT USED) 1 ACTION 34 - With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement, operation of this RADI0 ACTIVE GAS WASTE SYSTEM may continue provided grab samples are collected at least once per 4 hours and analyzed within the following 4 hours. 1
)
ACTION 35 - (NOT USED)
)
l l 4 l l SEABROOK - UNIT 1 3/4 3-63 Amendment i l
l H C IED HCE WNR RLU OLQ FIE AI ER
- SV ERS DUI OS S M T
N E M L E R A I LN U EOT Q NIS E NTE R AAT HR M E CE C P N O A L L N I E O V LI R ET U NA S NR ) AB 4 N HI ( O CL 0 6 I A T C . 3 A 4 T _ N E E M EK _ L U CC B R RE A. A T UH . T S OC N N S . I _ G . N I R L O EK T NC _ I NE _ N A :l D O HC E _ M C V I S S A O G L P E X V E I S M O E L T P S X Y E S EM TE ST AS WY S S AG r GN o I t ER i ) VO ns IT os TI Me T CN c N AO no E 0M er M I gP U DS y( R AA x T RG 0 S N . I 1 mh - g"" a c YT $ie
l S - T N E M E R I U Q E R E C N A L ) L K I E N
) V A R L d U B e S u Y n N L i
O L t I A n T N o A O C T I ( N T E N 6 M E U T 3 R N I 4 T S E _ E N G _ I L A B G P A N T I S I R H O T T ( I . N O M S _ A _ G E V I S O L P X E g m9s 8m t Z- m 8 r 28e~
TABLE 4.3-6 (Continued) TABLE NOTATIONS : During RADI0 ACTIVE WASTE GAS SYSTEM operation. (NOT USED) (NOT USED) ;
# (NOT USED)
(1) (NOT USED) (2) (NOT USED) (3) (NOT USED) ! (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
- a. One volume percent oxygen, balance nitrogen, and
- b. Four volume percent oxygen, balance nitrogen. ;
(5) (NOT USED) l J r l l l l l l 1 l l 1 l l SEABROOK - UNIl 1 3/4 3-66 Amendment No. 7 (
( 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 (THIS SPECIFICATION NUMBER IS NOT USED) l l SEABROOK - UNIT 1 3/4 11-1 Amendment f
Bal10 ACTIVE EFFLUENTS l10UID EFFLUENTS DOS.E LIMITING CONDITION FOR OPERATION I l 3.11.1.2 (THIS SPECIFICATION NUMBER IS NOT USED) l l l l l 1 l i l l l-l l l SEABROOK - UNIT 1 3/4 11-2 Amendment
1 f@ I0ACT.IVE EFFLUENTS LIOUID EFFLUENTS LIOUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 (THIS SPECIFICATION NUMBER IS NOT USED) l I I i i SEABROOK - UNIT 1 3/4 11-3 Amendment
1 RADIDACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE ( LIMITING CONDITION FOR OPERATION I ! 3 11.2.1 (THIS SPECIFICATION IS NOT USED) I i
)
l t SEABROOK - UNIT 1 3/4 11-5 Amendment
I
-RADI0 ACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE - NOBLE GASES l-l LIMITING CONDITION FOR OPERATION 3.11.2.2 -(THIS SPECIFICATION NUMBER IS NOT USED) l 1 l
l l l 1 l SEABROOK - UNIT 1 3/4 11-6 Amendment f l
f l l RADI0 ACTIVE EFFLUENTS l GASE0US EFFLUENTS l
- 1. I DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN
. IbU _ FbR l LIMITING CONDITION FOR OPERATION l
3.11.2.3 (THIS SPECIFICATION NUMBER IS NOT USED) 1. i I l t (
)
SEABROOK - UNIT 1 3/4 11-7 Amendment l
RADIDACTIVE EFFLUENTS l GASE0US EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION i l 3.11.2.4 (THIS SPECIFICATION NUMBER IS NOT USED) i l l l l 1 l l SEABROOK - UNIT 1 -3/4 11-8 Amendment l
RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADIDACTIVE WASTES LIMITING CONDITION FOR OPERATION 3.11.3 (THIS SPECIFICATION NUMBER IS NOT USED) i i l l i SEABROOK - UNIT 1 3/4 11-10 Amendment
RADI0 ACTIVE EFFLUENTS SOLID RADI0 ACTIVE WASTES ( SURVEILLANCE REOUIREMENTS 4.11.3 (Continued) (THIS SPECIFICATION NUMBER IS NOT USED) l l l l l { i l t l I l l l SEABROOK - UNIT 1 3/4 11-11 Amendment
RADI0 ACTIVE EFFIUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION I 3.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) l I I i l l l l SEABROOK - UNIT 1 3/4 11-12 Amendment i 1 l l
l 3/4 12 RADIOLOGICAL ENVIRONMENTAL MONITORING l 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 (THIS SPECIFICATION NUMBER IS NOT USED) 1 1 1 l i l l l l l SEABROOK - UNIT 1 3/4 12-1 Amendment
RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM
)
LIMITING CONDITION FOR OPERATION 3.12.1 (Contir>ued) (THIS SPECIFICATION NUMBER IS NOT USED) l l l l l SEABROOK - UNIT 1 3/4 12-2 Amendment No. 22
VI RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS l LIMITING CONDITION FOR OPERATION 3.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) l i i l l l l l I I i I l l l SEABROOK - UNIT 1 3/4 12-3 Amendment No. 23
RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS SURVEILLANCE REOUIREMENTS 4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) 6 e SEABROOK - UNIT 1 3/4 12-4 Amendment
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12 3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) i SEABROOK - UNIT 1 3/4 12-5 Amendment
3/4 11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11 1.1 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.11.1.2 (THIS SPECIFICATION NUMBER IS NOT USED) i 1 l l l l SEABROOK - UNIT 1 B 3/4 11-1 Amendment
L l RADI0 ACTIVE EFFLUENTS !- BASES l LIOUID EFFLUENTS 3/4.11.1.2 (THIS SPECIFICATION NUMBER IS NOT USED 3/4.11.1.3 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.11.1.4 LIOUID HOLDUP TANKS The temporary tanks include all those outdoor radwaste tanks that are not surrounded by liners. dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System. Restricting the quantity of radioactive material contained in the speci-fied tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20. Appendix B. Table II Column 2 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA. 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 (THIS SPECIFICATION NUMBER IS NOT USED) i l l SEABROOK - UNIT 1 B 3/4 11-2 Amendment I j
RADIDACTIVE EFFLUENTS BASES GASE0US EFFLUENTS 3/4 11.2.1 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 11.2.2 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.11.2.3 (THIS SPECIFICATION NUMBER IS NOT llSED) 1 l
)
l I 1 l l i i SEABROOK - UNIT 1 B 3/4 11-3 Amerdment
RADI0 ACTIVE EFFLUENTS BASES GASEOUS EFFLUENTS 3/4 11.2.3 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.11 2.4 (THIS SPECIFICATION NUMBER IS NOT USED) i t 1 1 SEABROOK - UNIT 1 B 3/4 11-4 Amendment
'RADIDACTIVE EFFLUENTS BASES GASEOUS FFFLUENTS 3/4.11.2.5 EXPLOSIVE GAS MIXTURE FOR THE GASE0US RADWASTE SYSTEM This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the GASE0US RADWASTE SYSTEM is main-tained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits.provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. 3/4.11.3 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) l i 1 i SEABROOK - UNIT 1 B 3/4 11-5 Amendment
31012 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) l I i SEABROOK - UNIT 1 B 3/4 12-1 Amendment
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) s i l l SEABROOK'- UNIT 1 B 3/4 12-2 Amendment
ADMINISTRAThE CONTROLS PROCEDURES AND PROGRAMS 6.7.6 (Continued)
- d. Backun Method for Determinina Subcoolina Marain A program that vill ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall l include the following:
- 1) Training of personnel, and
- 2) Procedures for mor,itoring.
- e. Post-Accident Samoling A program that will ensure the capability to obtain and analyze reactor coolant. radioactive iodines and 3 articulates in plant gaseous effluents, and containment atmosplere sam)1es under accident conditions. The program shall include t1e following:
- 1) Training of personnel.
- 2) Procedures for sampling and analysis, and
- 3) Provisions for maintenance of sampling and analysis i equipment. I
- f. accident Monitorina Instrumentation A program which will ensure the capability to monitor plant variables and systems operating status during and following an accident. This program shall include those instruments provided to indicate system operating status and furnish information regarding the release of radioactive materials (Category 2 and 3 instrumentation as defined in Regulatory Guide 1.97. Revision 3)*
and provide the following:
- 1) Preventive maintecance and periodic surveillance of instrumentation.
- 2) Preplanned operating procedures and backup instrumentation to be used if one or more monitoring instruments become inoperable, and
- 3) Administrative procedures for returning inoperable instruments to OPERABLE status as soon as practicable.
f *Seabrook has taken exce tion to the categorization of instrumentation provided in Regulatory Guide 1.9 . Revision 3. The Seabrook exceptions are provided in FSAR Table 7.5-1. which has been reviewed by the NRC staff in SER Supplement No. 5. SEABROOK - UNIT 1 6-14 Amendment No.
1 i I ! ADMINISTRATIVE CONTROLS j. PROCEDURES AND PROGRAMS r l 6.7.6 (Continued) ( g. Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM. (2) shall be implemented by operating 3rocedures, and (3) shall include remedial actions to be taken w1enever the program 1
-limits are exceeded. The program shall include the following elements:
- 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
- 2) Limitations on the instantaneous concentrations of l radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B.
Table 11. 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.
- 4) Limitations on the annual and quarterly doses or dose ,
commitment to a MEMBER OF THE PUBLIC from radioactive i materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50. l
- 5) Determination of cumulative and 3rojected dose contributions from radioactive effluents for ;1e current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,
- 6) Limitations on the operability and use of the liquid and 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 period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50.
l l SEABROOK - UNIT 1 6-14A Amendment No.
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS 6.7.6 (Continued)
- 7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY shall be limited to the following:
a) For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin. and b) For Iodine-1?l. for Iodine-133 for tritium, and for all radionucMdes in particulate form with half-lives greater than 8 days: less than or equal to 1500 mrems/yr to any organ.
- 8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50.
- 9) Limitations on the annual and cuarterly doses to a MEMBER OF THE PUBLIC from Iodine-131. Iocine-133. tritium, and all radionuclides in particulate form with half-lives greater l
than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50. l
- 10) (Not Used), and L 11) Limitations on the annual dose or dose commitment to any l MEMBER OF THE PUBLIC due to releases of radioactivity and to l radiation from urant.n fuel cycle sources ' ' forming to 40 CFR Part 190.
- h. Radioloaical Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall 3rovide (1) representative measurements of radioactivity in the lighest potential exposure pathways, and (2) verification of the 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, sampling, a elysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.
l l SEABROOK - UNIT 1 6-14B Amendment No.
ADMINISTRATIVE CONTROLS PROCEDURES AND PR0 mr 6.7.6 (Continued)
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and I
- 3) Participation in a Interlaboratory Comparison Program to ensure 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.
s i i l SEABROOK - UNIT 1 6-14C Amendment No. ) i
ADMINISTRATIVE CONTROLS i 6.8 REPORTING REQUIREMENTS ROUTINE REPORTS 6.8.1 In addition to the applicable reporting requirements of Title 10. Code I of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted. STARTUP REPORT 6.8.1.1 A summary report of station startup and power escalation testing shall be submitted following: (1) receipt of an Operating License. (2) amendment to the license involving a planned increase in power level. (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 nuclear, thermal, or hydraulic performance of the station. i i i i i l SEABROOK - UNIT 1 6-14 Amendment No. 34 1
7 ADMINISTRATIVE CONTROLS 1 l l 1 The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a descri) tion of the measured values of the operating conditions or characteristics o)tained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any 6dditional specific details required in license conditions based on other commitments shall be l included in this report. Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program. (2) 90 days following resumption or commencement of commercial power operation. or (3) 9 months following initial l criticality, whichever is earliest. If the Startup Report does not cover all l three events (i .e. , initial criticality completion of Startup Test Program. l 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
- 6.8.1.2 Annual Reports covering the activities of the station as described l
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. i Reports required on an annual basis shall include:
- a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures ;
greater than 100 mrem /yr and their associated man-rem exposure
- according to work and job functions ** (e.g., reactor operations and surveillance. inservice inspection, routine maintenance, special maintenance [ describe maintenance] waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD). or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions:
- b. The results of specific activity analyses in which the primary The following coolant exceeded information shall betheincluded:
limits of Sp(ecification 3.4.8. history starting
- 1) Reactor power 48 hours prior to the first sample in which the 19,it was exceeded (in graphic and tab _lar format): (2) Results of the last isotopic analysis for radiciodine ptrformed prior to exceeding the limit, results of analysir while limit was exceeded an6 results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations: (3) Clean-up flow history starting 48 hours prior to the first sample in which the limit was exceeded:
(4) Graph of the I-131 concentration ( iodine isotope concentration (pCi/gm) pCi/gm) and one as a function of other radio-time for the l l-l *A single submittal may be made for a multiple unit station. The submittal l should combine those sections that are common to all units at the station.
**This tabulation supplements the requirements of S20.407 of 10 CFR Part 20.
SEABROOK - UNIT 1 6-15
ADMINISTRATIVE CONTROLS 6.8.1,2 (Continued) duration of the specific activity above the steady-state level: and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit. c. Documentationofallchallengetyvalveses relief valves (PORVs) and sa to the pressurizer power-operated ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.8.1.3 The annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological 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. i
)
4 l SEABROOK - UNIT 1 6-16 Amendment
V 1 i ADMINISTRATIVE CONTROLS l l ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the by May 1 of each year. previous calendar year of operation shall be submittedThe r radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives l outlined in the ODCM ad PCP and (2) in conformance with 10 CFR 50.36a and l Section IV.8.1 of Appendix I to 10 CFR Part 50. l t l l l l l l l l 4 SEABROOK - UNIT 1 6-17 Amendment No. 22 f l
ADMINISTPATIVE CONTROLS l MONTHLY OPERATING REPORTS [ 6.8.1.5 Routine reports of-operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission. Washington, D.C. 20555. Attn: Document Control Desk, with a copy to the NRC Regional Administrator, no later than the 15th of each month following the calendar month covered by the report. CORE OPERATING LIMITS REPORT j 6.8.1.6.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
- 1. Cycle dependent Overpower AT and Overtemperature AT trip setpoint parameters and function modifiers for operation with skewed axial power profiles for Table 2.2-1 of Specification 2.2.1,
- 2. SHUTDOWN MARGIN limit for MODES 1. 2. 3. and 4 for Specification 3.1.1.1,
- 3. SHUTDOWN MARGIN limit for MODE 5 for Specification 3.1.1.2.
l 4 Moderator Temperature Coefficient BOL and EOL limits. and 300 ppm surveillance limit for Specification 3.1.1.3. l i i l SEABROOK - UNIT 1 6-18 Amendment No. 9. 33, 34
ADMINISTRATIVE CONTROLS RECORD RETENTION 6.9.3 (Continued)
- f. Records of reactor tests and experiments:
- g. Records of training and qualification for current members of the
-station staff:
- h. Records of inservice inspections performed pursuant to these Technical Specifications;
- i. Records of quality assurance activities required by the Operational Quality Assurance Manual;
- j. Records of reviews performed for changes made to procedures or gugmentorreviewsoftestsandexperimentspursuantto10CFR
- k. Records of meetings of the SORC and the NSARC:
- 1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.7 including the date at which the service life commences and associated installation and maintenance records;
- m. Records of secondary water sampling and-water quality: and l
- n. Records c. analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy l
of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
- o. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
'6.10 RADIATION PROTECTION PROGRAM l l
6.10.1 Procedures for personnel radiation 3rotection shall be prepared { consistent with the recuirements of 10 CFR 3 art 20 and shall be approved. i maintained, and adherec to for all operations involving personnel radiation exposure. E 11 HIGH RADIATION AREA 6.11.1 Pursuant to paragraph 20 203(c)(5) of 10 CFR Part 20. in lieu of the
" control device" or ' alarm signal" required by paragraph 20.203(c) each high 4 radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less-than 1000 mR/h at 45 cm (18 in.) from the i radiation source or from any surface that the radiation penetrates 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). Individuals qualified in radiation protection procedures (e.g. ,
Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h. provided they are otherwise following plant radiation protection procedures for entry into such high SEABROOK - UNIT 1 6-20 Amendment
p l ADMINISTRATIVE CONTROLS i: HIGH RADIATION AREA
.6.11.1 (Continued)
! radiation areas. 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 radiation monitoring device that continuously indicates the radiation dose rate in the area: or
- b. A radiation monitoring device that continuously integrates the l radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable.of them; or
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform aeriodic radiation surveillance at the frequency t .specified in t1e Radiation Work Permit.
6.11.2 In addition to the requirements of Specification 6.11.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18.in.) from.the radiation source or from any surface that the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time , specification of the RWP, direct or remote (such as closed circuit TV cameras) i continuous surveillance may be made by, personnel qualified in radiation 3rotection procedures to provide positive exposure control over the activities 3eing performed within the area. For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for. purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device. 6.12 PROCESS CONTROL PROGRAM (PCP) Changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as re shall contain: quired by Specification 6.9.3.o. This documentation
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and SEABROOK - UNIT 1 6-21 Amendment No. 22
~
l
&QlilNISTRATIVE CONTROLS !
PROCESS CONTROL PROGRAM (PCP) l 6.12.2 (Continued) 1
- 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal. State, or other applicable regulations.
b.) S'nall become effective after review and acceptance by the SORC and approval of the Station Director. 6.13 0FFSITE DOSE CALCULATION MANUAL (0DCM) I Changes to the ODCM: {
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.3.o. This documentation 1 shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the ;
change (s) and
)
- 2) A determination that the change will maintain the level of radioactive effluent control recuired by 10 CFR 20.106. 40 CFR Part 190.10 CFR 50.36a. anc Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,
- b. Shall become effective after review and acceptance by the SORC and the approval of the Station Director
- c. Shall be submitted to the Commission in the form of a complete. .
legible copy of the entire ODCM as part of or concurrent with the ! Annual Radioactive Effluent Release Report for the period of the I report in which any change to the ODCM was made. Each change ; shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and each affected page shall indicate the revision number the change was implemented. 4 l l SEABROOK - UNIT 1 6-22 Amendment No. 22 l
ADMINISTRATIVE CONTROLS 6.14 MAJOR CHANGES TO LIOUID GASEOUS AND SOLID RADWASTE TREATMENT SYSTEMS
- 6.14.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid. gaseous, and solid):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Re3 ort for the period in which the evaluation was reviewed by the SOR:. The discussion of each change shall contain:
- 1) A summary of the evaluation that le' to the determination that the change could be made in acmardance with 10 CFR 50.59:
- 2) Sufficient detailed information to totally support the reason i for the change without benefit of additional or supplemental information:
- 3) A detailed description of the equipment, components. and processes involved and the interfaces with other plant systems:
- 4) An evaluati.on of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from I those previously predicted in the License application and i amendments thereto:
l l 5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto:
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste. to the actual releases for the period prior to when the change is to be made:
1
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed and found acceptable by the 50RC.
- b. Shall become effective upon review and acceptance by the SORC.
- Licensees may choose to submit the information called for in this Specification as part of the FSAR update. pursuant to 10 CFR 50.71.
SEABROOK - UNIT 1 6-23 Amendment No. 22
Section IV Determination of Significant Hazards for Proposed Change I r I l Page 3 L
1 IV. DETERMINATION OF SIGNIFICANT HAZARDS FOR PROPOSED CHANGES , License Amendment Request (LAR) 97-08 proposes changes to Seabrook Station's Radiological l Ef0uent Technical Specifications and Administrative Controls section of the Technical Specifications, as authorized by NRC Generic Letter (GL) 89-01, " Implementation Of Programmatic Controls For Radiological Effluent Technical Specifications (RETS) In The Administrative Controls Section Of The Technical Specifications And The Relocation Of Procedural Details of RETS To The Offsite Dose Calculation Manual Or To The Process Control Program." The proposed amendment has been prepared in accordance with the guidance specified in GL 89-01. The proposed amendment incorporates the l programmatic controls in the Technical Specifications (TS) for radioactive effluents and for environmental monitoring conforming to the applicable regulatory requirements. This will allow relocation of existing procedural details of the current RETS to the Offsite Dose Calculation Manual (ODCM). Procedural details associated with solid radioactive wastes will be relocated to the Process Control Program (PCP). l In accordance with e CFR 50.92, North Atlantic has reviewed the attached proposed changes and has l concluded that they do not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed changes do not involve a SHC is as follows:
- 1. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes do not affect accident initiators or precursors and do not alter the design assumptions, conditions, configuration of the facility or the manner in which the plant is l operated. The proposed changes do not alter or prevent the ability of structures, systems, or l components (SSCs) to perform their intended function to mitigate the consequences of an l initiating event within the acceptance limits assumed in the Updated Final Safety Analysis l Report (UFSAR). The proposed changes are administrative in nature and do not change the level of programmatic controls and procedural htails relative to radiological efuuents. Incorporation of programmatic controls for RETS in TSs will assure that the applicable regulatory requirements pertaining to the control of radioactive effluents will continue to be maintained. Since there are no changes to previous accident analyses, the radiological l consequences associated with these analyses remain unchanged, therefore, the proposed changes i do not involve a significant increase in the probability or consequences of an accident previously evaluated. l l
- 2. The proposed changes do not create the possibility of a new or different kind of accident from any previously analyzed.
The proposed changes do not alter the design assumptions, conditions, configuration of the f facility or the manner in which the plant is operated. The proposed changes have no impact on component or system interactions. The proposed changes are administrative in nature and do not change the level of programmatic controls and procedural details relative to radiological effluents. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously analyzed. f l Page 4
i
- 3. The proposed changes do not involve a significant reduction in a margin of safety.
There is no impact on equipment design or operation and there are no changes being made to the Technical Specification required safety limits or safety system settings that would adversely affect plant safety. The proposed changes are administrative in nature and do not change the level of programmatic controls and procedural details relative to radiological effluents. A comparable level of administrative control will continue to be applied to those design conditions and associated surveillances being relocated to the ODCM or PCP. Therefore, the proposed changes do not involve a significant reduction in any margin of safety. Based on the above evaluation, North Atlantic concludes that the proposed changes do not constitute a significant hazard. l Page5 ! L
Sections V & VI Proposed Schedule for License Amendment Issuance and Effectiveness and EnvironmentalImpact Assessment Page 6
V, PROPOSED SCHEDULE FOR LICENSE AMENDMENT ISSUANCE AND EFFECTIVENESS North Atlantic requests NRC review of1.icense Amendment Request 97-08 and issuance of a license amendment by September 30,1998, having immediate effectiveness and impleme..tation required within 90 days. VI. ENVIRONMENTAL IMPACT ASSESSMENT North Atlantic has reviewed the proposed license amendment against she criteria of 10 CFR 51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluent that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, North Atlantic concludes that the proposed change meets the criteria delineated in 10 CFR St.22(c)(9) and 10 CFR 51.22(c)(10) for a categorical exclusion from the requirements for an Environmental Impact Statement. l l Page 7
INFORMATIONAL NOTE Please note that this version of the ODCM, revised in accordance with 3 GL 89-01, Supplement 1, has been SORC approved as Revision 18 and is currently designated as Appendices X and Y. Appendices X and Y will not become effective until after issuance of the License Amendment. .}}