ML20059G364

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Proposed TS Sections 3.3.7.2 & 4.3.7.2,relocating Seismic Monitoring Instrumentation Lco,Srs & Associated Bases to Updated FSAR
ML20059G364
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 01/10/1994
From:
AFFILIATION NOT ASSIGNED
To:
Shared Package
ML20059G352 List:
References
NUDOCS 9401240123
Download: ML20059G364 (19)
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Text

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ATTACHMENT 2 -

UMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 50-353 LICENSE NOS. NPF-39 NPF-85 ,

TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 93-16-0 AFFECTED PAGES UNIT 1 UNIT 2 i

ix ix xlx xix 3/4 3-68 3/4 3-68 3/4 3-69 (Deleted) 3/4 3-69 (Deleted) 3/4 3-70 (Deleted) 3/4 3-70 (Deleted)  ;

3/4 3-71 (Deleted) 3/4 3-71 (Deleted) .

3/4 3-72 (Deleted) 3/4 3-72 (Deleted)  ;

B 3/4 3-5 B 3/4 3-5 l

9401240123 940110 PDR ADOCK 05000352 P pop L

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2 s* l INDEX

-(IMITINGCONDITIONSFOROPERATIONANDSURVEILLtT_ IRE 0VIREMENTS SECTION . PAGE i e

INSTRUMENTATION (Continued) .

Table 4.3.7.1-1 Radiation Monitoring -

Instrumentation Surveillance .  ;

Requirements..................... 3/4 3-66  ;

i The information from pages 3/4 3-68 through 3/4 3-72 has been intentionally omitted. Refer to note on page 3/4 3-68.......... 3/4 3-68 ,

The information from pages 3/4 3-73 through 3/4 3-75 has been intentionally omitted. Refer to note on page 3/4 3-73......... 3/4.3-73 Remote Shutdown System Instrumentation and Controls.... 3/4 3-76 {

Table 3.3.7.4-1 Remote Shutdown System .

Instrumentation and Controls.. ... 3/4l3-77 ,

Table 4.3.7.4-1 Remote Shutdown System Instrumentation Surveillance  !

Requirements..................... 3/4 3 Accident Monitoring Instrumentation.................... 3/4 3-84 j ,

Table 3.3.7.5-1 Accident Monitoring Instrumen-

.tation........................... 3/4 3  !

Table 4.3.7.5-1 Accident Monitoring Instrumenta- j .

tion Surveillance Requirements... 3/4 3-87 Source Range Monitors.................................. 3/4 3-88  !

a Traversing In-Core Probe System........................ 3/4 3-89 Chlorine Detection System.............................. 3/4.3-90

-Toxic Gas Detection System....................... ..... 3/4 3-91 i

3/4 3-92 Fire Detection Instrumentation............... .........

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LIMERICK - UNIT 1 ix j

4* INDEX J

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BASES LSECTION PAGE i INSTRUMENTATION (Continued)

(Deleted).............................................. B 3/4 3-5 I"

( D e l e t e d ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . B.3/4 3-5 j Remote Shutdown System Instrumentation and Controls.... B 3/4 3-5  !

Accident Monitoring Instrumentation.................... B 3/4 3-5 Source' Range Monitors.................................. B 3/4-3-5 Traversing In-Core Probe System........................ B 3/4 3-5 j

.q Chlorine and-Toxic Gas Detection Systems............... B 3/4.3-6 l Fire Detection Instrumentation.................. ...... B 3/4 3 Loose-Part Detection System.... ... ................... .B 3/4 3-6 ,

(Deleted).............................................. B 3/4 3-6  !

Offgas Monitoring Instrumentation...................... B 3/4 3 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.................... B 3/4 3-7. j P

3/4.3.9 FEEDWATER/ MAIN TURBINE' TRIP SYSTEM ACTUATION INSTRUMENTATION........................................ B 3/4 3-7 i

/ 1 Bases Figure B 3/4.3-1 Reactor Vessel Water '

Level..................... B 3/4 3-8 .;

'3/4.4 REACTOR COOLANT SYSTEM s

3/4.4.1 - RECIRCULATION SYSTEM................................... B 3/4~4-1: l 3/4.4.2- SAFETY / RELIEF VALVES................................... .B-3/4:4 <;

-3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE {

Leakage Detection Systems.............................. B 3/44-3 Operational.

Leakage.................................... .B 3/4 4-3

=3/4.4.4. CHEMISTRY.............. ................................ B 3/4 4-3 ,

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LIMERICK - UNIT 1 xix  !

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~#5ection3.3.71 (Deleted) i E

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i THE INFORMATION FROM THIS TECHNICAL-SPECIFICATIONS SECTTON HAS BEEN RELOCATED '. ,

TO THE UFSAR. TECHNICAL SPECIFICATIONS -f t

PAGES 3/4 3-69 THROUGH 3/4 3-72 0F THIS SECTION HAVE BEEN INTENTIONALLY OMITTED. l

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LIMERICK - UNIT'I 3/4 3-68

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-BASES _

3/4.3I7.2 (Deleted) c INFORMATION FROM THIS SECTION RELOCATED TO THE OFSAR. l E l 3/4.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED.T0 THE' ODCM.

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3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS  !

The OPERABILITY of the remote shutdown system instrumentation and controls  ;

ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability ,

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

-3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION  !

The OPERABILITY of the accident monitoring instrumentation ensures.that

. sufficient information is available on selected plant parameters to monitor and  ;

assess important variables following an accident. This capability is' consistent with .

the recommendations of Regulatory Guide 1.97, " Instrumentation frr Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an' Accident," '

December 19'/5 and NUREG-0737, " Clarification of TMI. Action Plan Requirements,"

November 1980.

3/4.3'.7.6 SOURCE RANGE MONITORS  ;

1 The source range monitors provide the operator'with information of the status.of

.the neutron level in the core at very low power levels during startup.and shutdown. .

At these power levels, reactivity. additions shall not be made without this fiux level t information available to the operator. When the intermediate range monitors are;on-  !

scale, adequate information is available without the SRMs' and they can be retracted. .j 3/4.3'.7.7 TRAVERSING IN-CORf PROBE SYSTEM /

The OPERABILITY of the. traversing in-core probe system with the specified minimum J complement of equipment ensures that the measurements obtained from use.of this  ;

equipment accurately represent the spatial neutron flux distribution .of the reactor j core. j The.TIP system OPERABILITY is demonstrated by normalizing all probes 1(.i.e., i

-detectors) prior to performing an LPRM calibration function. Monitoring. core thermal'.

limitsLmay involve utilizing individual detectors to monitor selected areas of the reactor core, thus all detectors may not be required to be OPERABLE. -The OPERABILITY- it of individual detectors to be used for monitoring is' demonstrated by comparing the-  !

detector (s) output in the resultant heat balance calculation (P-1). with data obtained j during a previous heat' balance calculation (P-1). ,

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' LIMERICK - UNIT: 1 B 3/4.3-5

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'l INDEX- -1 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS l SECTION PAGE

-INSTRUMENTATION (Continued)

Table 4.3.7.1-1 Radiation Monitoring '

Instrumentation Surveillance Requirements.................... .3/4 3-66 -I The information from pages 3/4 3-68 through 3/4 3-72 has been . intentionally omitted. Refer to note on page 3/4 3-68.......... 3/4 3-68 .!

The information from pages 3/4 3-73 through 3/4 3-75 has been intentionally omitted. Refer to note on page 3/4 3-73.......... 3/4 3-73 i Remote Shutdown System Instrumentation and Controls..... _3/4 3-76 Table 3.3.7.4-1 Remote Shutdown System ,

Instrumentation and Controls... . 3/4 3-77 Table 4.3.7.4-1 Remote Shutdown System t Instrumentation Surveillance '

Requirements.................... 3/4 3-83 Accident Monitoring Instrumentation..................... 3/4 3-84 Table 3.3.7.5-1 Accident Monitoring Instrumen- -

tation.......................... 3/4_3-85 i

Table 4.3.7.5-1 Accident Monitoring Instrumenta- .

tion Surveillance Requirements.. 3/4 3-87  :

Source Range Monitors................................... 3/4 3-88; 3 r

Traversing.In-Core Probe System......................... 3/4 3 Chl ori ne Detec ti on System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-90 '!

i Toxic Gas Detection-System.............................. 3/4 3-91 Fire Detection Instrumentation.......................-.... 3/4 3-92 t

' LIMERICK - UNIT 2 ix .

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' BASES i

- SECTION PAGE INSTRUMENTATION ~(Continued)

(Deleted)..................................................... _ B 3/4 3-5 l (Deleted)..................................................... B 3/4 3-5  !

Remote Shutdown System Instrumentation and Controls. . . .. . . . . . . ' B 3/4 3-5 ,

Accident Monitoring Instrumentation........................... B 3/4 3-5' Source Range Monitors......................................... B 3/4 3-5  ;

Traversing In-Core Probe System............................... B 3/4 3-5 Chlorine and Toxic Gas Detection Systems...................... B 3/4 3-6 Fire Detection Instrumentation................................ B 3/4 3-6' Loose-Part Detection System.................................. B 3/4 3-6 ,

(Deleted)................................ .................... B 3/4 3-6 Offgas Monitoring Instrumentation............................. B 3/4 3-7 -

3/4.3.B TURBINE OVERSPEED PROTECTION SYSTEM........................... B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION l B 3/4 3-7 INSTRUMENTATION...............................................  ;

Bases Figure B 3/4.3-1 Reactor Vessel Water 4 Level........................... B 3/4 3-8 3/4.4 REACTOR COOLANT SYSTEM RECIRCULATION SYSTEM.......................................... ~!

- 3/4.4.1 B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.......................................... B 3/4 4-2 -

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE l Leakage Detection Systems..................................... B 3/4 4-3

. Operational Leakage........................................... B 3/4 4-3 3/4.4.4~ CHEMISTRY..................................................... B 3/4 4-3a LIMERICK - UNIT 2_ xix 4

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'Section'3.3.7.2 (Deleted) ,

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THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED .

TO THE UFSAR. - TECHNICAL SPECIFICATIONS PAGES 3/4 3-69 THROUGH 3/4 3-72 0F THIS SECTION HAVE BEEN INTENTIONALLY OMITTED.

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.LlHERICK - UNIT 2 3/4 3-68

. i i INSTRUMENTATION i BASES 3/4.3.7.2 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR. [ i 3/4.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.  ;

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3/4.3.7.4 REMOTE SHUTOOWN SYSTEM INSTRUMENTATION AND CONTROLS ]

The OPERABILITY of the remote shutdown system instrumentation and controlsL  :

ensures that sufficient capability is available. to permit shutdown and .!'

maintenance of liOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event. control room habitability is j

' lost and is consistent with General Design Criterion 19 of 10 CFR Part 50,  ;

~ Appendix A. The Unit 1 RHR transfer switches are included only due to their  ;

f potential impact on the RHRSW system, which is common to both units. ,

3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION q

The OPERABILITY of the accident monitoring instrumentation ensures-that .

sufficient.-information is available on selected plant parameters to monitor and

. assess 'important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for. Light '

Water Cooled Nuclear Power Plants to Assess Plant Conditions During and e

-Following an Accident," December 1975 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980. ,

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3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the '

status of the neutron level in the core at very low power levels during startup 1 and shutdown. At these power levels, reactivity additions shall not be made 1 without this flux level information available to the operator. When the l intermediate range monitors are on scale, adequate information is available >

without the SRMs and they can be retracted. j 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the speci.fied '!

minimum complement of equipment ensures that the measurements obtained from use

-~o f this equipment accurately represent the spatial neutron flux distribution of. :i

~t he reactor core. j The TIP system OPERABILITY is demonstrated by normalizing.all probes (iie,,

-de.tectors) prior to performing an LPRM calibration function. Monitoring' core <

ther.aal . limits may involve utilizing individeal detectors to monitor selected areas of the reactor core, thus-all detectors may not be required to be

. OPERABLE. lThe OPERABILITY of individual detectors to be used for monitoring is

' demonstrated by comparing the detecto'r(s) output in-the resultant heat balance .

calculation (P-1) with data obtained during a previous heat balance calculation j' (P-1).

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LIMERICK f 0 NIT.2 B 3/4 3-5

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. i ATTACHMENT 3 LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 50-353 LICENSE NOS. NPF-39 NPF-85 UPDATED FINAL SAFETY ANALYSIS REPORT PROPOSED CHANGES ASSOCIATED WITH .l TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 93-16-0 l

i FOR INFORMATION ONLY i l

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LGS UFSAR 3.7.3.14 Seismic Analysis for Reactor Internals (NSSS)

The modeling of RPV internals is discussed in Section 3.7.2.3.1.2.

The damping values are given in Table 3.7-1, 3.7.3.15 Analysis Procedures for Dampinct 3.7.3.15.1 Analysis Procedures for Damping (NSSS)

Analysis procedures for damping are discussed in Section 3.7.2.15.1.

3.7.3.15.2 Analysis Procedure for Damping (Non-NSSS)

If the equipment damping is unknown, the response spectrum curve  :

for 0.5% damping is used to arrive at a conservative seismic loading. The damping values used for the OBE are increased for the SSE, where sufficient justification is established.

3.7.4 SEISHIC INSTRUMENTATION

,- 3.7.4.1 Comparison with Recrulatory Guide 1.12 (Rev 1) ,

The seismic instrumentation progr complies with Regulatory Guide 1.12 (Rev 1), except for the ite 5 isted below:

Abb supplied as discrete '

Response spectrum recorders are not instruments. A response spectrum-analyzer, permanently installed-in the control room, presents more complete information than that pre'sented'by response spectrum recorders.

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Recorded data from the tilaxial" time history .accelerographs are fed into the response

";2Bfedtrum analyzer to produce earthquake spectra immediately

. Tfcil16 wing an eadhquake.

  • All locations where response - spectrum

~ recorders' are required ~by the regulatory guide are monitored by time history accelerographs. This system achieves the intent of Regulatory Guide 1.12 (Rev 1).

3~N S ERT 4 3.7.4.2 Location and Description of Instrumentation The following instrumentation . is provided for Unit 1 only, as essentially the same response is ' expected at Unit 2.

a. Six triaxial time history accelerographs
b. Thr e tri xial eak r cordi g a ele gra ne -iaxi 1 sei . ic s- tch
s. ~

btLCTE 3.7-38

LGS UFBAR C H A N(, E (d5 \ne h iakial heiskic thigge O

'o one response spectrum analyzer c f. A system control panel which includes seismic event visual and audible annunciators.

d . N P a' a mit Orh unidgial kismh trikge[ ,

All instrument characteristics meet the requirements of section 5 of ANSI N18.5 (1974).

T b History Accelerographs 3.7.4.2.3rN Triax 6Eu,ial Time 6 Triaxial time history accelerographs (T/A) produce a record of the time-varying acceleration at the sensor location. These data are  !

.used directly for analysis and comparison with reference information, and may be converted to response spectra form for spectral comparisons with design parameters.

' Each T/A contains three accelerometers mounted in a mutually orthogonal array. All T/As have their principal axes oriented identically, with one horizontal axis parallel to the major horizontal axiy assumegri the seismic analysis. T/As are located '

as @ SETS) (.s ho Gn i n T d le 3.7- zB,)

C.H4 N(qE [ ~ Prima cdntainmen founda ion

. ntait ent s ctur (diap agm ab) bELETE

. c. Re tor e closu e foun ation fd. Reac r pip ng su ort 'n cont innen ')

. utsid conta nment on sei mic Ca gory e ipme t I h at ex anger in re ctor closu ) .

DELETE f. Fou datio of an ndep dent ismic ateg _I tru tu 5 (spr y pon pump truc re) tri ger S/T), sensStive in noyth,

~-

outh, and' ver iaxi l skisisi , is

\ A ical(cirection rovi ed to start the A segsors ecor ing yst m._ The SAT is har by_*tems . through f. above. _agne ic4 4 thee ecording system _ located in the control room Is provided for mu tiple channel recording of the signals from the T/As mounted on hbb 3.7-39

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C HA M Q E , LGS SAR b E~t. ETE

'h cw_ in TANc S 'I ~ 2 f items a, t5r kA huirh A u iaxia seism] c tr ger S/TV) sen rin que veti iv ction only, sproKided o sta the T/A s sor

' ecordin sys m lo sted the umpho se. his TV i prov,ded ly m unte re rder is 4

o r \* t e m g. ly. A s -aratt (loc provid s d f r th T/A mgunte on i pm g. A sin le pl ybac unit 's j _

lohate in he e trol \ room or pihyback of th tape fro all I/

i g\ rec der .

IN 6 E AT 6 *-'

ial P ak Recording cceles ogra s (P AB) OGCQ 3.7.4.2.

Tria ial p >ak re ordin accel ograp (P/A) are p ovid to re ord e tual peak espon c. ch se sing evice cont ins th ee l a cele ogra s mougted i a nu ally og al a ay. Dat f m ,

th pea reev ding nccele ograp are m nuall retr eved 011 wi an a ake P/A- are 1 ted as foi ows: /

f CHA Nq6

a. Prima con ainme t - o react ves el e pmen I To b ima cont nment - on eactor ipin g
c. Ou side f con innen - on seismi Cate cry I . qui ont (to of hea exch nger iping 1i rea tor e clos e)

'- F_

3.74.2.3[Triaxialseis o 89 teh h g y g4qg y One riaxikiseemic witch is i stal ed on he prim ry conta ~ nment' -

.oun tion. It ctiv tes 'sua and audib e annun lators i the ntr roo- if a OBE nput cce rat on le pl has en exce ded.

),, 3.7.4.2.4 Response Spectrum Analyzer V:. . x

. ., f.The . response spectrum analyzer is an electronic device which

~Q~'ZgenerateQa ; peak acceleration ver:;us frequency curve from a

" time-based complex waveform. 'The analyzer receives data from the T/A playback unit and computes the spectra. These can be compared with the spectra generated from the mathematical model and used to make timely operating dec.isions.

3.7.4.2.5 System Control Panel A panel' located in the control room houses the recording, playback,

~s and spectrum analysis units which are used in conjunction with the T/A" sensors to produce a time history and frequency-amplitude

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record of the seismic event. The panel also contains signal conditioning and display equipment associated with the response .

spectrum _ analyze M udib1 and isuel annunciatchs asdociatkd with)

{cgivatig of the se1\mic s itch anct the system power supply unit, l i bELETE l l

i 3.7-40 l l

' LGS, tiFSAR h rov ed M oO o n g re.dce- & a.n o, co g- c y 4 y q q.

3.7.4.3 Control Room Ope *ator Notification '/ o causes an audible and Activat\ ion oY the\S/T (Sectibn 3.}.4.h.1)lert the plant operator Visual annunciation in tne controA fudre to a set in M t at the TfA recording system has been activated.fTh r vert cal a - eler tion ev ls the ~rigg r wil be at horizgntal kligtly igher than he cA ecte back ound evel, inc , pe udi g le ibduc d vib atio from o urces such s traf ic, el vato ay b cha ged nce arki a chine y. These initi set oints een ob ained hich ndic te sihJ nifiy: ant glant perati g dat have bette syst_ . ope ation tha a diffe&nt -- smtpoint would rovi bElm h

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t he -eDr ic sw tch i conngcte to a dib1 and\v5sua lerhtio hzfe anr(unc i th co trol com~

d wiAl in icat ~

if e 0$E ac ~

"be n e cee ed. y The A AbD Activation of(the )/TV Vill \init.Kate \thj/ pump ouse timeHowever, history accelerographgg operatj;e and latch its' event indicator.

it does not ca se any audible or visual annunciation in the control room. The se ointdthhMwill be at a vertical acceleration level slightl hicherithan the eXDected har-kcround level.

DIWoPerate Ind c> indent Anb -

The peak acceleratron leal exper on ontainment base slab is available immediately following a seismic event. The level is obtained by playing back the recorded T/A data from the base slab location and reading the peak value from a chart recorder or the spectrum analyzer.

I Significant response spectra from the containment base slab are in the control room immediately following a seismic e

availableThese'will be on readout equipment suitable for comparing

event.

the measured' response spectra with the OBE an6. SSE response f 'P?.*t* ' --> . .

comparison of Measured and Predicted Responses 3.7.4.4 Initial determination of the seismic event. level is performed immediately after the event by comparing the measured response spectra from the containment base slab wich the calculatedAnOBE and outline-SSE ' response' spectra for the corresponding location.

of the order.of actions to be taken after a seismic event is provided in Figure 3.7-44.

.T~N S EK T C 3.

7.5 REFERENCES

3.7-1 N.C. Tsai, " Spectrum Compatible Motions for Design Purposes", Journal of Engineering Mechanics Division, ASCE, Vol. 98, No. EM?,, Proc. Paper 8807, pp. 345-356 (Apri1 1972). __

cenidn%ent foundatj q,ound mcEfoo af %e W y4g TO bc e -de r;n a ck;v an

+, h e.

66 a.n Conkrol rooy3,7,41 atec./sj a hoM aon ud/6/ea nd v;.5/6Ie La /a r /m o

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INSERT A Triaxial peak recording accelerographs are not supplied as discrete instruments. The purpose of these accelerographs is to give an indication of seismic accelerations experienced by the plant in the event of power failure in the recording system. The availability of uninterruptible power ,

supplies (UPS), the limited information available from the peak accelerographs and the difficulty of retrieving data from the peak accelerog~aphs (two were located in the primary containment) made the peak accelerographs unnecessary. The system with UPS will perform the same  ;

functions as the triaxial peak recording accelerographs.

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INSERT B A self contained T/A sensor recording system is located in the Spray Pond Pumphouse. This T/A '

is not connected to the Control Room equipment. A separate portable computer is available to '

retrieve recorded data and transport to the Control Room. A single playback unit is located in the Control Room for playback of any of the recorder data. <

. INSERT C 3.7.4.5 Controls ,

Applicability: The seismic monitoring instrumentation shall be operable at all times. This ,

instrumentation is considered operable when it is capable of performing its specified functions  ;

and when all necessary attendant instrumentation, controls, electrical power, cooling 'or seal watEi, lubrication or other auxiliary equipment that are required for the system, subsystem, train, .

- component, or device to perform its functions are also capable of performing their related support ,

functions.

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'Actichs With one or more of the seismic monitoring instruments inoperable for more than 30 days, a.

Special Report shall be prepared and submitted to the Nuclear Regulatory Commission pursuant to Specification 6.9.2 of the Technical Specifications within the next ten days outlining the cause of the malfunction and the plans for restoring the instrument (s) to operable status.

'Ihe provisions of Specification 3.0.3 of Technical Specifications are not applicabic.

3.7.4.6 Surveillance Reauirements Each of the seismic monitoring instruments shall be demonstrated operable by the performance of the channel check, channel functional test and channel calibration at the frequencies shown and defined in Table 3.7-29.

Each of the seismic monitoring instruments which is accessible during power operation and which is actuated during a seismic event greater than or equal to 0.0lg, and which does not self-reset, shall be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a channel calibration performed

+ ,- ----y

t reset, shall be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a channel calibration perfonned l

within 5 days following the seismic event. Data shall be retrieved from the actuated instruments i

and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Nuclear Regulatory Commission pursuant to Specification 6.9.2 of the Technical Specifications within ten days describing the magnitude, frequency spectrum i and rmlant effect upon unit features important to safety, j INSERT D i

l The operability of the seismic monitoring instrumenation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the l

measured response to that used in the design basis for the unit.

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TABLE _ 3,7-26 .

SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE - OPERABLE - .

1. Triaxial Time-History Accelerographs (T/A's) r

.. a. Sensors

1) XE-VA-102 Primary Contairdent. 0 to 1 g 1 Foundation (Loc. 109-R15-177)
2) XE-VA-103 Containment Structure O to 1 g 1 (Diaphragm Slab) ,
3) XE-VA-104 Reactor Enclosure 0 to 1 g 1 Foundation (Loc.111-R11-177)
4) XE-VA-105 Reactor. Piping Support 0 to 1 g 1 '

(Mn. Sta. Line 'D', El 313',

m in containtsent)

5) XE-VA-106 Outside Contatriment 0 to 1 g 1 on Seismic Category I Equipment (RHR Heat Exchanger, Loc.102-R15-177) ,

(oJg ,

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6) XRSH.VA-107' Foundation of an 0 to 1 g . 1 Independent Seismic Category I Structure (Spray Pond Pump House, El 237')

' b. Recorders (Panel 00C693)

1) XR-VA-102 for XE-VA-102 N.A. 1 XR-VA-103 for XE-VA-103 N.A. I 1 2)
3) XR-VA-104 for XE-VA-104 N.A. 1
4) . XR-VA-105 for XE-VA-105 N. A. 1 ,
5) XR-VA-106 for XE-VA-106 N. A. 1 Triaxial Response Spectrum Analyzer 1-33.5 Hz 1 . **

_ f, - ~

(RSA); (Loc. Control Room) l

  • Includes sensor, trigger, recorder, and backup power supply.
    • Wit'h reactor coiltrol rooli indication and annunciation.

from the Triaxial s.. Receives signal from playb,ack unit fed with data Accelerographs i

TA 6u 3.7 - 29 SEISHIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNElx w CHANHE FUNCTIONAL CHANNEL A M CHECX . TEST . CALIBRATION ,,

INSTRUMENTS AND SENSOR LOCATIONS _ '

1. Triaxial Time-History Accelerographs (T/A's)'
a. Sensors '
1) .XE-VA-102 Primar'y Contain- H.A. SA R
  • ment Foundation .

(Loc. 109-R15-177)

N. A. SA R

2) XE-VA-103 Containment-Slab)

Structure-(Diaphragm H.A. SA R

3) XE-VA-104 Reactor Enclosure -

Foundation (Loc. 111-R11-177)

4) XE-VA-105 Reactor Piping H.A. SA R Support (Hn. Sts. Line 'D,' . ,

,' El 313', in containment)

Outside Contain- s.A. SA R ,

5) XE-VA-106 ment on " Seismic Category I

(;, Equipme'nt, (RHR Heat .

Exchanger, Loc. 102-R15-177)

H.A. SA R

6) XRSH-VA-107* Foundation of an Independent Seismic
  • Category I Structure (Spray -

Pond Pump House, El 237')

b. Recorders (Panel 00C693)

H.A. SA R

1) XR-VA-102 for XE-VA-102 H.A. SA R f
2) XR-VA-103 for XE-VA-103 H.A. SA R
3) XR-VA-104 for XE-VA-104 N.A. SA R 4), XR-VA-105 for XE-VA-105 N.A. SA R l
5) XR-VA-105 for XE-VA-106 Triaxial Response Spectrum Analyzer H.A. SA R 4.

(RSA)

" Includes sensor, trigger, recor er,d and backup power supply.

i IAUERT E o' w

F '. . .

J' rnSERT E P

    • channel check - the qualitative assessment of channel behavior during operation by i observation. This d termination shall include, where possible, comparison of the channel  !

indication and/or status with other indications and/or status derived from independent instrument  ;

channels measuring the same parameter.

      • channel functional test - shall be:

a) analog channels - the injection of a simulated signal into the channel as close to the sensor as practical to verify operability including alarm and/or trip functions and channel l failure trips.

~

^

b) bistable channels - the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions. .

k The channel functional test may be performed by any series of sequential, overlapping or total  !

channel steps such that the entire channel is tested.

i

' **** channel calibration - the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the ,

channel monitors. The channel calibration shall encompass the entire channel including the .j sensor and alarm and/or trip functions, and shall include the channel functional test. The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. .

t Surveillance Freauency Notation  !

Notation Freauencv  ;

N.A. Not applicable  ;

4 l

SA At least once per 184 days )

\

R At least once per 18 months (550 days) -

1

--, , . , - .

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