ML20073J810

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Proposed Tech Specs Re Removal of Seismic & Meterological Instrumentation
ML20073J810
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/29/1994
From:
Public Service Enterprise Group
To:
Shared Package
ML20073J809 List:
References
LCR-94-18, NLR-N94117, NUDOCS 9410070136
Download: ML20073J810 (12)
v • d • e


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i ATTACEMENT 2 i

TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION REMOVAL OF SEISMIC AND METEOROLOGICAL INSTRUMENTATION  :

FROM THE TECHNICAL SPECIFICATIONS

-FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION NLR-N94117 DOCKET NO. 50-354 LCR 94-18 r The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this License Amendment Request:  !

Technical Specification Paaes i t

3/4 3.7 viii and xviii 3/4.3.7.2 3/4 3-68, 3/4 3-69 and 3/4 3-70 3/4.3.7.3 -

3/4 3-71, 3/4 3-72 and 3/4 3-73 B 3/4 3.7.2 B 3/4 3-4 B 3/4 3.7.3 B 3/4 3-4 and B 3/4 3-5 ,

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l 9410070136 940929  ;

PDR ADOCK 05000354 l P PDR j

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION Table 3.3.5-1 Reactor Core Isolation Cooling System  !

Actuation Instrumentation................. 3/4 3-52 Table 3.3.5-2 Reactor Core Isolation Cooling System Actuation Instrumentation Sctpoints....... 3/4 3-54 Table 4.3.5.1-1 Reactor Core Isolation Cooling System Actuation Instrumentation Surveillance Requirements............................ 3/4 3-55 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION......................... 3/4 3-56 Table 3.3.6-1 Control Rod Block Instrumentation......... 3/4 3-57 Table 3.3.6-2 Control Rod Block Instrumentation Setpoints................................. 3/4 3-59 Table 4.3.6-1 Control Rod Block Instrumentation Surveillance Requirements................. 3/4 3-60 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...................... 3/4 3-62 Table 3.3.7.1-1 Radiation Monitoring Instrumentation... 3/4 3-63 Table 4.3.7.1-1 Radiation Monitoring Instrumentation Surveillance Requirements............... 3/4 3-66 3/4 3-68'

/ Se ismic/ Moni /t6 ring Instrumentati / onf. . . . . . ./. / ./. . . . . .

( /Table 3f 3.7.2-1 Seismic Monjtoring Inst'rumentatior)./. 3/4f3-69 ....

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Tab 1'e 4.3.7.21 Seismic Monitoring / Instrumentation

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/ ('. . . . . . . . . ./ 3/4 3 70

/ Surveijiance

, / Requi rementls.

. Meteorological Monitoring Instr 6'mentationg.........../.... 3/4 3-71

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,' / j' 7' Tab 1I3.3.7.3-1'Meteorolog,icalMonitoring /

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/ Instrumfntation.../........../.......<.. 3/4 '72

\'Table 4.3.'7.3-1 MeteorologicaVMonitoring

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{(. x Instrumentation Surveillance / /

/ Requi rements. . . . . . . . . '. . . . . .

....../ 3/4 ) 3 Remote Shutdown Monitoring Instrumentation and Controls... 3/4 3-74 HOPE CREEK viii

.n0EX BASES  :

SEC'!ON PAGE INSTRUMENTATICN (Continued)

'Se*ismicfMonjte'

/ / ring (Idstrumentat 'n . . . ./. . . -... $ 3/* 3-

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Meteorologic/al Men'1toring/ Inst umentation .,.. . . 6, /4 ' _

Remote Shutdown Monitoring 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 Loose-Part Detection System.. .. ?P B 3/4 3-6 ,

Radioactive Liouid Efficent Monitoring Instrumentation. .. ...... ... ... B 3/4 3-6 i

Radioactive Gaseous Effluent Monitoring l Instrumentation. .... ...... . ... . B 3/4 3-6 '

3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM. ... , .... B 3/4 3-7 i

}/4.3.9 FEEDWATER/MilN TURBINE TRIP SYSTEM ACTUAT.'ON INSTRUMENiATION.. .... . .... . .. . B 3/4 3-7  !

Figure B1/4 3-1 Reactor vessel Water Level. B 3/4 3-3 3/4.4 QEACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM. . . B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.. . .. . .. B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE I

Leakage Detection Systems. .. .. . ... B 3/4 4-3 '

Operational Leakage.... .. .......... . ....... ... . B 3/4 4-3 3/4.4.4 CHEMISTRY.... .... . ....... ... ..... .. . ....... B 3/4 4-3 i 3/4.4.5 SPECIFIC ACTIVITY. .. .. . . . ..... ..... .. . B 3/4 4-4 l 3/4.4.6 PRESSURE / TEMPERATURE LIMITS. . ..... .... .... B 3/4 4-5 Table B3/4.4.6-1 Reactor Vessel Toughness.. . . . B 3/4 4-7 Figure B3/4.4.6-1 Fast Neutron Fluence

- (E>1Mev) at (1/4)T as a Function of Service Life. . . .... B.3/4 4-8 ,

HOPE CREEK xviii Amendment No. 3 sen / 537 1

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' INSTRUMENTATION

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/ SEISMIC MONITORING INSTRUMENTO ION f

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LIMITING CONDIT10N FOR aPERATION

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'3.3.7.2/ihe seism.c monitopifig entation instrum,/

shown in Tab)( 3.3. 7.2 ale, l

shall b'e OPERABLE.

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APP (ICABILITd At all t'imes. p/

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ACTION:/ / / .

/5. With one or more of the above required seismic monitor mgj instroents

/ inoperable fop more than'30 days, prepare and.s'ubmit a Special Reporv ,

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to the Commission pursu' ant to Specification,6I9.2 within the next *

/10 days o6tlining the'cause i of,the malfunction and the plans for restor,in'g the ins,trument(s) to OPERABLE, status. ,/ j j

'b. The ovisions/ofSpecific$ tion 3.03'arenot,ap'hlicable.

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SURVEIt' LANCE REQUI'REMENTS / / '

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- 4.3.7.2.1/ Each of the above req'uired seisniic monitorin'g instrundnts shall'be demonstrated OPERABLE by the. performance of the CHANNEL CHECK / CHANNEL,FUNC- '

TIONAL' TEST and, CHANNEL CALIBRATION operations at,,the frequencies shpwn in Tabl6 4.3.7.2-1. '

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4.3.7.2.2 'Each of the above requ,. ired seismic monitor g instruments actu ted

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lduring a' seismic event greater than shall or equil to 0.01g,in/

be' restored'to l 0PERABLE 5 days following status the seismic withinevent. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Da'taand a CHANNEL shall, tie retrieved from CALIBRATION ac'tuated performed wi' th .

l i.nstruments and analyzed'to determine the magnitude of the vibrato'ry ground  :

, motion. A Special Report shall be' prepared,and submitfed to thi Commission 5 pursuant, to Specification 6.9.2,within 10, days describing the'inagnituds,

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gmrequency spectrum'and resultant effect dpon unitefeaturesj i'importapt' to spfety/  !

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HOPE CREEK 3/4 3-68 Amendment No. 19 _ _ . . _ ,

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TABLE 3.3.7.2-1 l 7

SEISMIC MONITORING INSTRUMES:t. TION [

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MINIMUM MEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE ' OPERABLE

1. Triaxial Time-History Accelerographs
a. 500' From Reactor Building i 1G 1 Free Field, 60' Below Grade ,
b. Primary Containment Foundation, i 1G / 1 Room 4101
c. Refueling Floor in Reactor i 1G 1 Building ,e
d. Core Spray Piping in Drywell if1G 1
e. Auxiliary Building Foundation i 1G 1
2. Triaxial Peak Accelerographs
a. Reactor Support Lateral Trusp/ i SG 1
b. Core Spray Piping in Drywelf i SG 1
c. Service Water Pump Piping i 5G 1
3. Triaxial Seismic Switches
a. Primary Containment F'oundation, NA 1*
b. Room Primary4101 (Triggep) Foundation,NA Containment 1(a)

Room 4101 (Switch)

4. Triaxial Response 7 5pectrum Recorders

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a. Primary Containment Foundation 1.0 -32.0 Hz** 1 (north-s,o'uth)
b. Primary /Contair. ment Foundation 1.0 -32.0 Hz** 1 (east-kest)
c. Primary Containment Foundation 1.0 -32.0 Hz** 1 (vertical)

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(a)Withr$actorcontrolroomannunciation.

  • Provi' des trigger mechanism to activate magnetic recording tapes for the time'-history accelerographs.
    • Eadh recorder has 16 reeds responsive to 16 discrete frequencies from 1(0-32.0 Hz. Each recorder also contains 16 switches integrally related

-to the 16 reeds which provide independent control room indication when predetermined acceleration levels and design limits have been exceeded.

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HOPE CREEK 3/4 3-69  ;

4 TABLE 4.3.7.2-1

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SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ,/

CHANNEL CHANNEL FUNCTIONAL

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CHANNEL INSTRUMENTS AND SENSOR LOCATIONS CHECK TEST CALIBRATION

1. Triaxial Time-History Accelerographs /

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a. 500' From Reactor Building M SA'

/ R Free Field, 60' Below Grade '

b. Primary Containment M SA R Foundation, Room 4101
c. Refueling Floor in Reactor M '

SA R Building

d. Core Spray Piping in Drywell M / SA R
e. Auxiliary Building Foundation M / SA R
2. Triaxial Peak Accelerographs ,
a. Reactor Support lateral NA' NA R Truss
b. Core Spray Piping in Drywell , ' NA

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NA R

c. Service Water Pump Piping NA NA R
3. Triaxial Seismic Switches
a. Primary Containment ,

NA SA R Foundation, Room 410)

(Trigger) /

b. Primary Containmept NA SA R Foundation Room 4'101 (Switch)

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4. Triaxial Response-Spectrum Recorders
a. Primary Containment M SA R Foundatio'n (north-south)
b. Primary /Containment M SA R Foundation (east-west)
c. Prima'ry Containment M SA R Foundation (vertical)

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J HOPE CREEK 3/4 3-70

l INSTRUMENTATION /

/ l METEOROLOGICAL MONITORING INSTRUMENTATION

/ l LIMITING CONDITION FOR CPERATION 3.3.7.3 The meteorological monitoring ninstrumentatio/ channels shown in T...~e 3.3.7.3-1 shall be OPERABLE. /

APPLICABILITY: At all times. ,

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ACTION:

a. With one or more of the required meteorological monitoring instrure -

tation channels incperable fo/ more than 7 days, in lieu of any ot e-report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pu'rsuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instru'mentacion to OPERABLE status.

b. The provisions of Spe/ cification 3.0.3 are not applicable.

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SURVEILLANCEREQUIREMESTS i

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4.3.7.3 Each off ihe above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CA(IBRATION operations at the frequencies shown in Table 4.3.7.3-1.

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HOPE CREEK 3/4 3-71 Amendment No. 19

TABLE 3.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION f

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MINIMUM ,'

INSTRUMENTS fNSTRUMENT OPERABLE

a. Wind Speed
1. Elev. 33 ft. 1
2. Elev. 150 ft. ,

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b. Wind Direction
1. Elev. 30 ft. 1 l
2. Elev. 150 ft. p 1

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c. Air Temperature Difference

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1. Elev. 150-33 ft. 1 I

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i HOPE CREEK 3/4 3-72 - - -

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/ TAB LE ,4'.' 3. 7. 3-1 /

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' METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREliENTS 7

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'/ / / / ['/ CHANNEL CHANNEL ,

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-INSTRUMENT / / CHECK CALIBRAT' ION  ;

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a. ' Wind Speed' / /,/ / /' SA,/' ,f

,!- 1. j E v. 33 ft./ / ./ 0 ,/  ;

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f 2; Elev.,150 ft. j

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1._ Elev. 33'ft. ,/

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2. Elev. 150 ft.

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c. Air. Temperature' Difference'/ j g

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, ~. Q l ace us hh .$*15k b HOPE CREEA 3/4 3-73

LNSTRUMENTATION BASES 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30936P-A, "BWR Owners' Group Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)," Parts 1 and 2 and GENE-770-06-2-A, " Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." The safety evaluation reports documenting NRC approval of NEDC-30936P-A and GENE-770-06-2-A are contained in letters to D. N. Grace from A. C. Thadani dated December 9, 1988 (Part 1), D. N. Grace to C. E. Rossi dated December 9, lo88 (Part 2), and G. J.

Beck from C. E. Rossi dated September 13, 1991.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the diff erence between each Trip Setpoint and the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analyses.

3/4.3.6 CONTROL R00 BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4, Control Rod Program Controls and Section 3/4.2 Power Distribution Limits and Section 3/4.3 Instrumentation. The trip logic is arranged so that a* trip in any one of the inputs will result in a control rod block.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analyses.

3/4.3.7 MONITORING INSTRUMENTATION 3/4,3.7.1 RADIATION MONITORING INSTP;riENTATION The OPERABILITY of the radiatio;; ..;nitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63 and 64.

3.4.3.7.2'SEISMICMdNITORINGINSTRUMENTATION The'.0PERABILITY of the seismic monitoring instrumentation ensures that

f. sufficient capability is available to promptly determine the magnitude of aj/ .

seismic event and evaluate the response of those' features imp'ortant to safety. '

This capability is required to permit comparison of the meisured response to that -

used in the design basis for the unit. This' instrumentation is consistent with , i l the recommendations of Regulatory Guide 1.12 " Instrumentation forAarthquakes/ ,

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J/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION / / fj The OPERABILITY of the meteorological monitoring instrumentation' ensures / /

< that sufficient meteorological data is available for estimating pot'ential radia ' ,

ution doses to_ the public as a result of routine or accidental release of, ij g qka & Inur b N HOPE CREEK B 3/4 3-4 Amendment No. 62 l l

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INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) k fadioactivejEater5alst the/tmospher fhls apacil ty is r uIred ~

eva)6atetpeneedf initia, ting prote tive my ures o prote the hp th an safety of/the publitf. Thip'instrume/tation s cons tent wi h the rfcommend ns of/Regulatog Guide /1.23 "Onpite Meteo)rologig}i Prog ms, 3/4.3.7.4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown monitoring instrumentation and con-trols ensures that sufficient capability is available to permit shutdown and maintenance room. of HOT SHUTDOWN of the unit from locations outside of the control This capability is required in the event control room habitability is lost .and is consistent with General Design Criteria 19 of 10 CFR 50.

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 r.n accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.

3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. For a discussion of SPIRAL RELOAD and SPIRAL UNLOAD and the associated flux monitoring require-ments, see Technical Specification Bases Section 3/4.9.2. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.

3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.

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HOPE CREEK B 3/4 3-5 Amendment No. 14 l

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INSERT 1 3.3.7.2 DELETED 3.3.7.3 DELETED INSERT 2 PAGES 3/4 3-69 THRU 3/4 3-73 ARE DELETED INSERT 3 3/4 3-69 thru 3/4 3-73 INSERT 4 3/4.3.7.2 DELETED 3/4.3.7.3 DELETED

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