Text

Proposed Tech Specs,Consisting of Change Request 96-02, Proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 & Relocation of Selected Requirements
	ML20129B836
Person / Time
Site:	Seabrook
Issue date:	10/17/1996
From:	; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	;
Shared Package
ML20129B818	List: ML20129B814; ML20129B821; ML20129B836;
References
	NUDOCS 9610230126
	Download: ML20129B836 (33)
	v • d • e

1!iDH LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PJff

^

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 zENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION . . . . . . .............. 3/4 3-16 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS . . . . . . . . . . . . . 3/43-24 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

' Yk ..._. 0..... r .n.,(76 7.*F.71t* 1H' apt)s,y W). ).

e-if:H hi:tr;;=t:t :MTwV Muf4fr'.d. aP45'l 'I d.*7.". .

3/4 3-40 3/43-41 l

V*.r43/43-42 TAB E TABLE 4.3-4 SEWIREMENM-ED(M W F.4pf.@~ebj......

~

3/4 3-43 D9E+ M:t::r:1:gic:1

- - -: _n I-hMW(tW40FJo*I48.M'Id.orjtfyt) m 3f4 3 44

'ABLE B'@ 3M7(3/43-45 Remote Shutdown System . . . . . . . . . . . . . . . . . 3/4 3-46 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM . . . . . . . . . . . . . . . 3/43-47 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 3-53 Radioactive Liquid Effluent Monitoring Instrumentation . 3/4 3-55 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3 56 9610230126 961017 PDR ADOCK 05000443 P PDR La76t SEABROOK - UNIT 1 iv Amendment No. 17-l

_INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS '

SECTION PAGE TABLE 4.3-5 RADIOACTIVE LIQUID EFFLUENT MONITORING 1

INSTRUMENTATION SURVEILLANCE REQUIREMENTS................ 3/4 3-58 Radioactive Gaseous Effluent Monitoring Instrumentation.. 3/4 3-60 l TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITO INSTRUMENTATION........................ RING

.................. 3/4 3-61 TABLE 4.3-6 RADIOACTIVE GASEOUS EFFLUENT MONITORING l

INSTRUMENTATION SURVEILLANCE REQUIREMENTS................ 3/4 3-64 l 3/4.3.4 T$1MW)W.9t$.W./.3.W.%!O).. 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.............................................

Cold Shutdown - Loops Fi11ed........................

.... 3/4 4-4 '

Cold Shutdown - Loops Not

.... 3/4 4-6 Filled......................... 3/4 4-7 1

3/4.4.2 SAFETY VALVES Shutdown..................... ........................... 3/4 4-8 0perating....................

........................... 3/4 4-9 1 3/4.4.3 PRESSURIZER............................ i 3/4.4.4 3/4 4-10 3/4.4.5 RELIEF VALVES............................................

.... ............. 3/4 4-11 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..................

Operational Leakage........................ ............. 3/4 4-20

............. 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

. 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 "

c;2//[p H

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION g

3/4.12.2 LAND USE CENSUS ..

.................. 3/4 12-3 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM . . . . . . . . . . . 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 M0VABLE 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 QUADRANT 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 .............. B 3/4 3-3 3/4.3.4 URJITORING INSTRUMENTAg(PfigyFHidite.1,tayMif,thq1rA)

J2R5FEEITTifd.m tya B 3/4 3-6

e <

3/4.4 REACTOR COOLANT SYSTEM 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 LEAXAGE . . . . . . . . . . . . . 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>lMeV) 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 l L.sWL SEABROOK - UNIT 1 x Amendment No. l

INDEX

-5.0 DESIGN FEATURES' SECTION PAGE 5.3 REACTOR CORE -

5.3.1 FUEL ASSEMBLIES.......................................... .. 5-9 5.3.2 CONTROL ROD ASSEMBLIES................................... .. 5-9 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE........... 5-9 5.4. 2 : V0LUME......................................................

.................. 5-9 E

5.5 (ME$

w__ EOR 0 LOGICAL TOWER LOCATIO . . 6.d.4 /#Wl4F.4.49.H.99 5.6 FUEL STORAGE ' '

5.6.1 CRITICALITY................................. 5-10 5.6.2 0RAINAGE....................................................

... ............ 5-10 5.6.3 CAPACITY....................................... ............ 5-10 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT........................... 5-10 ;

TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.................. 5-11 1

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY.............................................. 6-1 6.2 ORGANIZATION................................................ 6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS.......................... 6-l' 6.2.2 STATION STAFF............................................. 6-2 FIGURE 6.2-1 (This figure number is not used)................... 6-3 FIGURE 6.2-2 (This figure number is not used)................... 6-3 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION...................... 6-4 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

Function...........................................

Composition............................................... 6-5

....... 6-5 Responsibilities.......................................... 6-5 Records................................................... 6-5 6.2.4 SHIFT TECHNICAL ADVIS0R................................... 6-5 6.3 TRAINING.................................................... 6-5 SEABROOK - UNIT 1 xiii i!

. ._ _ . __-. _ _ _ _ _ . _ . _ _ __ _ _ _ . _ _ _ _ _ _ _ . _ _ .. _ m-.__ _ _

1%"T

< 5.3.D. (rMsnuF1cand rhMBG!t- IS A OT dSuh) gINSTRUMENTATION MONITORINGANSTRUMENTATION INCORE D ECTOR SYSTEM t

LIMIT G CONDITION FOR OP, TION 3 .3.2 The Incore D ector System shall be ERABLE with:

a. At least 75% f the detector locatio s and, b.~A minimum f two detector locati s per core quad nt,

c. An OPE LE incore detector 1 fixed etector string with ation consist o a fuel assembly ontaining a mov e incore detector c able minimum of thres/0PERABLE of mapping fie location. detecto s or an OPERABLE f

APPLIC LITY: When the Inc e Detector Syste is used for:

' I a Recalibration of th ExcoreNeutronpxDetectionSy em, or

b. Monitoring the UADRANT POWER TILT TIO,.or

c. Measurement of FL and F,(Z), oh '

4

d. Input int he FIDS Alarm

, AfJJQg:

l With the 2ncore Detector Sys em inoperable o not use the sys y m for the above applica)rle monitoring or c,alibration func ons. The provisio ~s of Specificati 3.0. tre not applicable l

RVEILLANCE REQUIREMENTS -

(Plant procedur s are used to etermine that t re Detector Sy em is OPERABLE.)

/ '

4 l

Lar(A SEABROOK - UNIT 1 3/4 3-40 AmendmentNo.Jf

[

INSTRUMENTATIO MONITORING)f4STRUMENTATION SEISMIC STRUMENTATION L NG CONDITION F OPERATION

/ / / /

/

3.3.3.3 The se 4mic monitoring inst mentation shown /

n Table 3.3-7 shall b

OPERABLE.

3 APPLICABILI : At all times.

ACTION

a. With one or re of the above equired seismic monit ing instruments i

inoperable or more than 30 ays, prepare and subm' a Special Report t he Commission rsuant to Specificati 6.8.2 within the next 1 ays outlining e cause of the malfu ion and the plans for storing the ins ument(s) to OPERABLE atus. g b TAeprovisionsof pecification 3.0.3 a not applicable.

g h , ,

SL'aVEI LANCE RE0VIRE tE TS .

4[3.3.3.1 Each the above required smic monitoring ins uments shall be

/ emonstrated d QF TABLE by the perforrpa ce of the CHANNEL C K. CHANNEL CALI-BRATION, a NALOG CHANNEL OPERA 10NAL TEST at the fre encies shown in f

Table 4.3 .

4.3.3 .2' Each of the abovp required' seismic mon oring instruments ctuated dur' g a seismic event grpater- than or equal to .01 g shall be're ored to

O ABLE status within J4 hours and a CHANNEL ALIBRATION perfor d within 0 days following theA eismic event. Data all be retrieved om actuated instrumentsandan%zedtodeterminethe agnitude of the v ratory ground motion. A Speci 1 Report shall be pre ed and submitted the Commission y

pursuant to Sp ification 6.8.2 withi 4 days describin the magnitude, e-quency spect m, and resultant effep upon facility fe,a ures important safety.

i SEABROOK - UNIT 1 3/4 3-41 h

._ .. . _ _ __ .. . _ . . . . _ _ _ _ _ _ . _ _m _ .

1 rgts TMutge&A is McT 4Sh TABLE 3.3-7 s

4 p/

SEISMICMOSdORINGINSTRUMENTATJdN MIN UM MEASUREMENT IN RUMENTS INSTRUME S AND SENSOR LO IONS RANGE PERABLE

1. Tr xial Time-Histo Accelerographs* -

. 1-SM-XT-6700 F ee Field Control lg 1**

Room East Ai Intake, elevation l' 6"

b. 1-SM-XT- 01 Containment Fo dation, 1 - 1*

elevat n -26' 0" c.1-5 -XT-6710 Containme .0perating lg 1**

F or, elevation 25' "

2. T iaxial Peak Accel ographs

a. 1-SM-XR-6702 cumulator Tank 5 K-9C, 0-20 1 elevation - 0"

/ b. 1-SM-XR- 03 Safety Injec 'on -20 Hz 1 Pipin elevation -24' 0'

c. 1- -XR-6704 PCCW Pi ing, Primary 0-20 Hz 1 xiliary Buildin elevation 47' 0"

3. riaxial Seismic itch #

1-SM-XS-6709 C tainment Founda on, 0.025g to 0 Sg 1**

elevation -2 0"

4. Triaxial esponse-Spectru Recorders

a. 1- -XR-6705 Contai ent Foundation, 1-30 Hz **

evation -26' 0" p

. 1-SM-XR-6706 f ntainment Foundati 1-30 Hz 1 next to SI K-9C, elevation -26' 0"

c. 1-SM-X 707 Primary Auxil 1-30 z Buil i g, elevation 25' 0'pfy 1

~

d. SM-XR-6708 Service ater Pump House, 1-30 Hz elevation 22'-0"

" Trigger mechapism in accelerograph nit activates recor ers in control r om whenitsejnfsagroundmotiono 0. 01g.

- With reactor control room in cation

Swit[setpointis0.13g/trhorizontalandv ical axis.

w a

SEABROOK - UNIT 1 3/4 3-42 .

l LAM (7dtS %dE t wBet /t Aof MSO)

TABLE 4.3-4

] SEISMICMONDORINGINSTRUMENTATIONSURVEILLANCEREQUIREMENTS/ '

ANALOG i CHANNEL l C NNEL CHANN INSTRUMENTS D SENSOR LOCA. ONS OPERATIONAL / l CHECK CALIB TION TEST / l

1. Triaxi Time-History Accelerographs*

i

a. SM-XT-6700 Fr Field Control M R SA oom East Air take,**

elevation 11' 6" i

b. 1-SM-XT-6 Containment Fou dation,** M R elevatio . A.

i 26' 0"

c. 1-SM-X 6710 Containment perating R N.A.

, Floor,

elevation 25' "

2. Tria al Peak Accelero aphs

a. -SM-XR-6702 Accu ulator Tank N.A.

SI-TK-9C, eleva on -6' 0" R N.A.

I

b. 1-SM-XR-6703 afety Injection N.A. R N. .

Piping, eley tion -24' 0" ,

1 c.1-SM-XR-6J04PCCWPiping, rimary N. R N.A.

Auxiliarf Building, ele ion 47' 0" -

3. Triaxia Seismic Switch 1-SM -6709 Containmp Foundation,** M N.A.

eley tion -26' 0"

4. iaxial Response / Spectrum Recorder

a. 1-SM-XR-6705 Containment Fou tion,**

)

N. .

M# R elevation 26' 0"

, b. 1-SM-XR 06 Containment undation N . R N.A.

next t SI-TK-9C, eleva on -26' 0"

c. 1-S R-6707 Primary A xiliary N.A. R N.A. ;

B/u ding, elevation 25' 0"

d. -SM-XR-6708ServfceWaterPump House, elevatio 22'-0" N. A. R N.A.

Each a /Ierographhasa. riaxial trigger activate the rec der.

- With actor control om indications.

CH NEL CHECK to con'sist of turning ) e test / reset switc and verify all mps illuminate /n 1-SM-XR-6705. / _

SEABROOK - UNIT 1 3/4 3-43

3.3.3.V (TAlf $fEc4FacArcA AtlMfER tr nor usM lh INSTRUMENTATION

/

MONITORING INsTRURERTKTION -

HETEOROLOGICAL I STRUMENTATION L ING CONDITION OPERATION 3.3.3.4 The meteorological monitoring instr entation channels hown in Table 3.3 8 shall be OPERABLE.

APPLICABILI -

At all times. g ACTION:

a. With one r more required teorological moni ring channels inop able for more n 7 days, prepar and submit a Spec al Report to the Commissionp'ursuanttoSpecifktation6.8.2withi the next 10 days

< outlining the ause of the malfhqction and the pla for restoring the channel (s) OPERABLE status,

b. .he provisions of cification 3.0.1 are not applicabl .

SURVEILLANCE R UIREMENTS

.3.3.4 Each of meteorological nitoring instru e ation cha'nnels sh wn i Table 3.3-8 shalt be demonstrated 0 RABLE by the perfb mance of:

A Daily CHAN L CHECK, and b.

ASemiannualCHAyELCALIBRATION k

SEABROOK - UNIT 1 3/4 3-44

(58ts Taetc S4m89t IP 9#M g TABLE 3.3-8 METEOROLOGICAL MOM TORING INSTRUNENTATION {

1 INIMUM !

I STRUMENT LOCATION OPERABLE

1. Wind S eed J '

a. Lower Level Nomi 1 Elev. 43 ft 1

. Upper Level N inal Elev. 209 f 1 '

2. Wind Directio !

i i

a. Lower Level Nominal Elev. 3 ft 1 l

b. U er Level Nominal E1 . 209 ft 1

3. Air emperature - AT 1

. Lower Level Betw n Elev. 43 ft a d 150 ft 1 l

b. Upper Lev l B ween Elev. 43 f and 209 ft 1 1 I

l I

e O

e SEABROOK - UNIT 1 3/4 3-45

4 g 3M.3.fLTms IOc& "D" " **'Y i INSTRUMENTAT10 j 7/4.s.9 iviQiaL vvLrd?LLU F5GTsGTIGH ,

LIMITING / CONDITION FOR OPERATION l /

3.3. At least one urbine overspeed rotection System hall be OPERABL

! . PICABILITY: ES 1, 2, and 3,

/ ACTION:

l

a. With one step val e or one control valve per high pr sure turbine 4

steam line inop able and/or with,6ne intermediate top valve or one l intercept valy per low pressur urbine steam lipe inoperable. 1 restore the inoperable valve ( to OPERABLE statfis within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months l or close atjleast one valve .

l the affected s am line(s) or isol e l the turb)n's from the steam 7 upply within thp ext 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . '

i b. With Aho above require M urbine Overspeed Protection System therwise i inoperable,within6 'urs isolace the turbine from the s am supply.

j

/

SURVEILLANCE REQUIREMENTS __

/

4.3.4d.TheprovisionsofSpecificatic 4.0.4 are not a licable.

\ /

i 4(3.4,2 Theabove,r/ equired Turbine vers;iend Protecti System shall be

! ' demonstrated OPERABLE:

AtJanstonceper7 ys by cycling e i a. of the followin Ives f,

t rough at least o complete cycle m the running pos ion: g~

1) Four high ressure turbine p valves, and l 2) Six lo pressure combin intermediate valv .

' b. At less once per 31 days ) direct observati of the moveme of -

each of the above valves /an the four high essure turbine ntrol /

/ valvpf through one complete cycle from th running positi ,

! c. t least once per 18 months b perfo nce of a CHANNE ALIBRATION i on the Turbine 0,vdrspeed Prot c ion stems, and

. At least onevpar 40 months b assembling at 1Aast one of eac of the above yt1ves and performi valve seats, disks, and sta d)avisualandsuyfaceinsgectio nd verifying n unaccepta le f ws or f

If unacceptable flaws r excessive to osion are excess)v's corrosion.

founf, all other valves pf'that type shal e inspected. _

i i SEABROOK - UNIT 1 3/4 3-67 AmendmentNo.A]g

fNSTRUMENTAT[0N BASES

~ ^

MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS (Continued) and abnormal conditions. Once the required logic combination is completed, the

system sends actuation signals to initiate alarus or automatic isolation actio and actuation of Emergency Exhaust g entilation Systems. g i .h 3/4.3.3.2 CTd8C terc,wneA wnsa a aor %

ThjVIncore Delept'or System c ists of either'a) fixed ector st

~

gs and t fr associated' signal pro ing, or b) sp(able incor detector the associated gnal proce ng. OPERABI by eith, fixed ectors or able detec ut not by a'IATY may be p combinati ofboth./

Th PERABILITY p the Incore Detector Sys)e's ensure measur nts obtained'from use of tfi'is system ccurately present [s th'atthe the atial neu on flux dis ution of t j core. .

For t purpose of tsuring F (Z or .d a 1 incore fl map is used -

Quarter- a flux map defined June 1976, be used in WCAP-86T recal tion of the core Neutye)n Flux De action nd System,$

full inco flux map r symetric) ore detect 6rs may ed for monit in T

P,0lfER TILT RATIVwhen one Po(er Range nel is inop able.g the QU 3/4.3.3.3 Y _ ITI;ibi5h?N Tr*us sweoftcAnA numsel at aor uNth &C*T -

e OPERAB}MTY of thafeismic ins ntation enfures that s icient capa lity is a11able to romptly det ine the mp.gfiitude of a smic even an evaluate e respons of those f ures impor nt to safety This cap iglityis quired to rait compar) on of the asured resp a to that d

/inthe ity to date ne if plant utdown is quire pursu toignbasis,forthefaci}Part100./Theinstrume Appe fx A of 10 A ation is istent wi he reco ations of ulatory Gyfde 1.12 "I rumentatiop or Earth

' qu es," Apr 1974. / /

3/4.3.3.4 Q M INSTR " Erd SPRtFlcerkwam or ner uscW ,

The ERAERITY,af the meteor Togical inst entation e es that suffici meteorol 1 cal data ar available f estimatin ential radiation /

doses the publ as a resul f routine o accidental ease of radio t'ive ma als to t atmosphere. hiscapabi}ifyisrequi to evaluate t need initiati protective asures to pydtect the heal h and safety he blic andAs consisten Guide 1.23, f"Onsite)t6teorologicaPPrograms," february 1972/iththerecsessendations,efReg 3/4.3.3.5 REMOTE SHUTDOWN SYSTEM The OPERABILITY of the Remote Shutdown System ensures that sufficient capability is available to permit safe shutdown of the facility from locations

{

outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of Appendix A to 10 CFR Part 50.

~

" ud}

E. .

. _ . NI " **"

INSTRUMENTAT10N BASES MONITORING INSTRUMENTATION 3/4.3.3.10 RADIDACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION (Continued) of General Design Criteria 60, 63, and 64 of Appe.1 dix'A to 10 CFR Part 50. The sensitivity of any noble gas activity monitors used to show compiiance with the gaseous effluent release requirements of Specification 3.11.2.2 shall be such that concentrations as low as 1 x 10 5 pCi/cc are measurable.

3/4.3.4 D ms SmsHcanoA tJQMGEYL I[ M OT L4560 j

~ _ _-_ _

s

=

l T s specif~ cation is ovided to JH'isure that e turbine verspeed/ l prote ion ins umentatio and the tv 5ine speed ntrol val s are OP TABLE s i

and ill pro ct the tur ine from e essive ove peed. Pr ection fr turbin !

e essive erspeed is required s' ce excessi overspee of the t ine coul ;

enerate otentially amaging m siles whic could imp and da ge safety-related components equipment or structu s, i

SEABROOK - UNIT 1 B 3/4 3-6

/]

4

DESIGN FEATURES l

DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 52.0 psig and a temperature of 296*F.

5.3 REACTOR CORE

' FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with a zirconium alley. Each fuel. rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-1ength control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80% silver,15%

indium, and 5% cadmium. All control rods shall be clad with stainless steelt.

tubing. -

5.4 REACTOR COOLANT SYSTEM -

DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 650*F, except for the pressurizer which is 680*F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,255 l cubic feet at a nominal T" of 588.5'F. DELETE ST5 METE 0lt0 LOGICAL TOWER LOCAt1ON 5.5 The me rologic tower s 11 be loc (ed as sh onFigyre5.1-(

WN g J.C (TM ffEctFic4ned A4+tFER If NOT (4 FED)

Le7 R SEABROOK - UNIT 1 5-9 Amendment No. -34~

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SECTION III HelyPe of Proposed Changes 11

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS I

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 1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION . . . . . . . 3/4 3-14 j TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM I INSTRUMENTATION . . . . . . .......... . 3/4 3-16 l TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPCINTS . . . . . . . 3/4 3-24 TABLE 3.3-5 (This table number is not used)

TABLE 4.3-2 ENGINEERED SAFETY FlATURES 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 TABLE 4.3-4 (THIS TABLE NUMBER IS NOT USED). . ... 3/4 3-43 (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 i.able number is not used) . ... 3/4 3-53 i Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-55 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-56 SEABROOK - UNIT 1 iv Amendment No N

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 4.3-5 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . 3/4 3-58 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-60 TABLE 3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION .............. . 3/4 3-61 TABLE 4.3-6 RADI0 ACTIVE GASEOUS EFFLUENT 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 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 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 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.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.12.2 LAND USE CENSUS . .. . . . .... .. 3/4 12-3 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM . .. . , . 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 BORATION 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 LIMIIS . . . .. .. 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 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 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) . . B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM 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. -le

_y INDEX 5.0 DESIGN FEATURES SECTION PAGE 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES . . . . ... ..... . 5-9 5.3.2 CONTROL ROD ASSEMBLIES . . ... .. . .... 5-9 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE ..... . .. 5-9 5.4.2 VOLUME . . . . . . . .. . .. ... 5-9 5.5 (THIS SPECIFICATION NUMBER IS NOT USED) .. ........ 5-9 )

5.6 FUEL STORAGE !

5.6.1 CRITICALITY . . .. . . .. .. .. .. 5-10 5.6 2 DRAINAGE . . . . . .. . ... 5-10 5.6.3 CAPACITY . . . . . . . 5-10 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT .... . .. . . . 5-10 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS . . . . 5-11 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY , . . . . ... .. .. 6-1 6.2 ORGANIZATION . . . . . . . .. ... ... 6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS .... . .. 6-1 6.2.2 STATION STAFF . . . . .. . .. .. 6-2 FIGURE 6.2-1 (This figure number is not used) .. .. . 6-3 FIGURE 6.2-2 (This figure number is not used) . . .. 6-3 TABLL 6.2-1 MINIMUM SHIFT CREW COMPOSITION . . . . . . . 6-4 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) l Function . . . .. . ... ... . 6-5 Composition . . . . .. . .. 6-5 Responsibilities . . . .. . .. . ... 6-5 Records . . . . .. . . . . . .. . . 6-5 6.2.4 SHIFT TECHNICAL ADVISOR . .. . . . 6-5 ,

6.3 TRAINING . . . . . . . .. . .. . 6-5 SEABROOK - UNIT 1 xiii Amendment No.

INSTRUMENTATION 3.3.3.2 (THIS SPECIFICATION NUMBER IS NOT USED) l 1

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SEABROOK - UNIT 1 3/4 3-40 Amendment No. 27. 33

INSTRUMENTATION 3.3.3.3 (THIS SPECIFICATION NUMBER IS NOT USED l

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SEABROOK - UNIT 1 3/4 3-41 Amendment No.

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SEABROOK - UNIT 1 3/4 3-42 Amendment No.

TABLE 4.3-4 (THIS TABLE NUMBER IS NOT USED)

I SEABROOK - UNIT 1 3/4 3-43 Amendment No.

INSTRUMENTATION 3.3.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) l SEABROOK - UNIT 1 3/4 3-44 Amendment No.

TABLE 3.3-8 (THIS TABLE NUMBER IS NOT USED)

SEABROOK - UNIT 1 3/4 3-45 Amendment No.

INSTRUMENTATION 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) a SEABROOK - UNIT 1 3/4 3-67 Amendment No. 4

4 i INSTRUMENTATION

! BASES i MONITORING INSTRUMENTATION j 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS (Continued) )

i' and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.

1 3/4.3.3.2 (THIS SPECIFICATION NUMBER IS NOT USED)

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3/4.3.3.3 (THIS SPECIFICATION NUMBER IS NOT USED)

} 3/4.3.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.3.3.5 REMOTE SHUTDOWN SYSTEM i

The OPERABILITY of the Remote Shutdown System ensures that sufficient l i capability is available to permit safe shutdown of the facility from locations '

, outside of the control room. This capability is rrquired in the event control room habitability is lost and is consistent with General Design Criterion 19 of l Appendix A to 10 CFR Part 50.

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i SEABROOK - UNIT 1 B 3/4 3-4 Amendment No. 24, 33

INSTRUMENTATION BASES MONITORING INSTRUMENTATION 3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Continued) of General Design Criteria 60. 63 and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release reouirements of Specification 3.11.2.2 shall be such that concentrations as low as 1'X 10-6 gci/cc are measurable.

3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED)

SEABROOK - UNIT 1 B 3/4 3-6 Amendment No.

DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building i< designed and shall be maintained for a maximum internal pressure of 52.0 psig and a temperature of 296 F.

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, 5.3 REACTOR CORE l

FUEL ASSEMBLIES l ;

5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.

CONTROL R0D ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80% silver.15% i indium, and 5% cadmium. All control rods shall be clad with stainless steel l tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR. with allowance for normal degradation pursuant to the applicable Surveillance Requirements. ;

b. For a pressure of 2485 psig, and

c. For a temperature of 650 F. except for the pressurizer which is 680 F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12.255 cubic feet at a nominal T m of 588.5 F.

5.5 (THIS SPECIFICATION NUMBER IS NOT USED)

SEABROOK - UNIT 1 5-9 Amendment No. 6. 34

Section IV Determination of Significant Ilazards for Proposed Changes 12

IV. DETERMINATION OF SIGNIFICANT IIAZARDS FOR PROPOSED CHANGES License Amendment Request (LAR) 96-02 proposes changes to the Seabrook Station Technical Specifications to relocate four instrumentation-related Limiting Conditions for Operation (LCOs) contained in Technical Specification (TS) Section 3/4.3, " Instrumentation", to the Seabrook Station Technical Requirements Manual (SSTR). They are:

LCO 3.3.3.2 - Incore Detector System LCO 3.3.3.3 - Seismic Instrumentation LCO 3.3.3.4 - Meteorological Instrumentation LCO 3.3.4 - Turbine Overspeed Protection in accordance with 10CFR50.92, North Atlantic has concluded that the proposed changes 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:

l. The proposed changes do not involve a sigmficant increase in the probability or consequences of an accidentpreviously evaluated.

The incore detector system, seismic monitoring instrumentation, meteorological monitoring instrumentation and turbine overspeed protection system are neither part of an initial condition of a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier, nor are they relied upon as a primary success path to mitigate such events. None of these instrumentation-related systems are related to events that are considered frequent or dominant contributors to plant risk. These instrumentation-related systems are not considered a design feature or an operating restriction that is an initial condition of a design basis accident or transient analysis, nor do they provide a function or actuate any accident mitigation feature in order to mitigate the consequences of a design basis accident or transient. Therefore, malfunction of anyone of these systems will not result in an increase in the probability or consequences of an accident previously evaluated.

The proposed changes do not involve any physical changes to the plant, do not alter the way any structure, system or component functions, do not modify the manner in which the plant is operated, and do not impact the physical protective boundaries of the plant. The proposed changes do not decrease the efTectiveness of administrative controls of assuring operation of the facility in a safe manner.

Relocation of the aforementioned instrumentation-related LCOs and associated SRs to the Technical Requirements Manual will continue to be administratively controlled in accordance with TS Section 6.0," Administrative Controls". The Seabrook Station Technical Requirements Manual is a licensee-controlled document which contain certain technical requirements and is the implementing manual for the Technical Specification Improvement Program. Changes to these requirements are reviewed and approved in accordance with Seabrook Station Technical Specifications, Section 6.7, and as outlined in the Technical Requirements Manual. Specifically, all changes to the Technical Requirements Manual require a 10 CFR 50.59 safety evaluation and be reviewed and approved by the Station Operations Review Committee (SORC) and the Nuclear Safety Audit Review Committee (NSARC) prior to implementation.

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The proposed changes will not degrade the ability of systems, structures and componems important to safety to perform their safety function. The proposed changes will not change the response of any system, structure or component important to safety as described in the Seabrook Station Updated Final Safety Analysis Report (UFSAR). Since the plant response to an accident will not change, there is no change in the potential for an increase in the consequences of an ;

accident previously analyzed. As such, the proposed changes do not involve a significant !

increase in the probability or consequences of an accident previously evaluated.

2 The proposed changes do not create the possibility of a new or different kind of accidentfrom anypreviously analy:ed.

The proposed changes do not involve any physical changes to the plant, do not alter the way any l structure, system or component functions, do not modify the manner in which the plant is operated, and do not impact the physical protective boundaries of the plant. The proposed ,

changes do not decrease the effectiveness of administrative controls of assuring operation of the I facility in a safe manner. l Future changes to these instrumentation-related requirements will be reviewed and approved in l accordance with Seabrook Station Technical Specifications, Section 6.7, and as outlined in the i Technical Requirements Manual. Specifically, all changes to the Technical Requirements Manual require a 10 CFR 50.59 safety evaluation and be reviewed and approved by the Station Operations Review Committee (SORC) and the Nuclear Safety Audit Review Committee l (NSARC) prior to implementation. j l

Furthennore, the proposed changes will not degrade the ability of systems, structures and components important to safety to perform their safety function. The proposed changes will not change the response of any system, structure or component important to safety as described in the Seabrook Station Updated Final Safety Analysis Report (UFSAR). Since the plant response to an accident will not change, there is no change in the potential for an increase in the consequences of an accident previously analyzed, nor can it create the possibility of a new or )

different kind of accident from any previously evaluated. l Relocation of the aforementioned instrumentation-related LCOs and associated SRs to the Technical Requirements Manual will not create the possibility of a new or different kind of accident from any previously analyzed.

3 The proposed changes do not involve a significant reduction in the margin ofsafety.

There are no changes being made to any safety limits or safety system settings that would adversely impact plant safety. The proposed changes do not r.tfect the ability of systems, structures or components important to safety to ensure: 1) the safe shutdown of the facility, and

2) the mitigation and control of accident conditions within the fa.:ility. In addition, the proposed changes do not affect the ability of safety systems to ensme that: 1) the facility can be maintained in a shutdown or refueling condition for extended periods of time, and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.

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I The Technical Specifications recognize that the inoperability of the incore detection, seismic monitoring and meteorological monitoring systems do not require a change to the plant operating conditions, thus, the provisions of TS 3.0.3 are stated as not being applicable. As such, the proposed changes do not involve a significant reduction in the margin of safety.

The measurements from the incore detectors are used in a confirmatory manner. Core power distribution limits are addressed, and will continue to be addressed, in TS Section 3/4.2, " Power Distribution Limits". The present TS 3.3.3.2 ACTION for Incore Detector System inoperability is not to use the system for monitoring or calibration functions. This will continue to be the case when TS 3.3.3.2 is relocated to the Technical Requirements Manual. Where operation is dependent on the FIDS Alarm being OPERABLE and should FIDS Alarm inoperability occur, again other TS 3/4.2 Section LCOs and corresponding ACTIONS provide instruction for FIDS Alarm inoperability. As such, the proposed change does not involve a significant reduction in the margin of safety.

Turbine overspeed protection is neither part of an initial condition of a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier, nor is it relied upon as a primary success path to mitigate such events. In view of the orientation of the main turbine relative to plant structures and equipment, the low probability of unacceptable missile damage to structures and equipment important to safety, the on-going and augmented surveillance and maintenance programs, and industry operating experience of low failure rates of main turbines due to overspeed events; the consequences of a turbine overspeed event which generates missiles that directly leads to failure of plant structures and equipment important to safety is very low. There is low likelihood of significant risk to public health and safety because of turbine overspeed events. Failure of plant structures and equipment due to missiles strikes are much more likely to be caused by events other than turbine failures. As such, the proposed change does not involve a significant reduction in the margin of safety.

Future changes to these instrumentation-related requirements will be reviewed and approved in accordance with Seabrook Station Technical Specifications, Section 6.7, and as (utlined in the Technical Requirements Manual. Specifically, all changes to the Technical Requirements Manual require a 10 CFR 50.59 safety evaluation and be reviewed and approved by the Station Operations Review Committee (SORC) and the Nuclear Safety Audit Review Committee (NSARC) prior to implementation.

Relocation of the aforementioned instrumentation-related LCOs and associated SRs to the Technical Requirements Manual does not involve a significant reduction in the margin of safety.

Based on the above evaluation, North Atlantic concludes that the proposed changes do not constitute a significant hazard.

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