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Proposed Tech Specs Re Removal of Specification from TSs & Relocation of Bases to UFSAR & Surveillance Requirements to Applicable Surveillance Procedures
	ML20078C845
Person / Time
Site:	Hope Creek
Issue date:	01/20/1995
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML20078C838	List: ML20078C835; ML20078C845;
References
	NUDOCS 9501270127
	Download: ML20078C845 (11)
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

. j ATTACHMENT 2 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION REMOVAL OF EXPLOSIVE GAS MIXTURE FROM THE TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 NLR-N94209 DOCKET NO. 50-354 LCR 94-26 i

l The following Technical Specifications for Facility Operating l License No. NPF-57 are affected by this License Amendment Request:

Technical Soecification Paces 4 I I 3/4.11.2.6 xvi and xxi 3/4.11.2.6 3/4 3-97, 3/4 3-99, 3/4 3-100, 3/4 3-102, and 3/4 11-16 B 3/4.11.2.6 B 3/4 11-4 and B 3/4 11-5 i

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9501270127 950120 PDR ADOCK 05000354 P PDR

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE i

i (ExplosiveGasMixture..................................... 3/411-1_6) i Main Condenser............................................ 3/4 11-17 i Venting or Purging........................................ 3/4 11-18

3/4.11.3 SOLID RADI0 ACTIVE WASTE TREATMENT......................... ?/4 11-19 l 3/4.11.4 ' TOTAL D0SE................................................ 3/4 11-20 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 1

r 4

3/4.12.1 MONITORING PR0 GRAM........................................ 3/4 12-1 1

Table 3.12.1-1 Radiological Environmental i Monitoring Program................... 3/4 12-3

! Table 3.12.1-2 Reporting Levels For Radioactivity

Concentrations In Environmental

Samples.............................. 3/4 12-9 Table 4.12.1-1 Detection Capabilities For I i Environmental Sample Analysis........ 3/4 12-10 l

3/4.12.2 LAND USE CENSUS.............. ............................ 3/4 12-13 3/4.12.3 INTERLABORATORY COMPARIS0N PR0 GRAM........................ 3/4 12-14 1

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1 HOPE CREEK xvi

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. 4 INDEX BASES

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SECTION PAQI 3/4.10 SPECIAL TEST EXCEPTIONS l 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.................... B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM...................... B 3/4 10-1 ]

l 3/4.10.3 SHUTDOWN MARGIN Dh ASTRATIONS................... B 3/4 10-1 j l

3/4.10.4 RECIRCULATION LOOPS.............................. B 3/4 10-1 l I

l 3/4.10.5 OXYGEN CONCENTRATION............................. B 3/4 10-1 3/4.10.6 TRAINING STARTUPS................................ B 3/4 10-1 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING... B 3/4 10-1 l i

3/4.10.8 INSERVICE LEAK AND HYDFOSTATIC TESTING........... B 3/4 10-2 l l l

1 3/4.11 RADIOACTIVE EFFLUENTS l 3/4.11.1 LIQUID EFFLUENTS Concentration......................................... B 3/4 11-1 i

Dose.................................................. B 3/4 11-1 Liquid Radwaste Treatment System...................... B 3/4 11-2 Liquid Holdup Tanks................................... B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS Dose Rate............................................. B 3/4 11-2 l Dose - Noble Cases.................................... B 3/4 11-3 1

Dose - Iodine-131, Iodire-133, Tritium, and Radionuclides in Particulate Form................... B 3/4 11-3 Gaseous Radwaste Treatment System and Ventilation Exhaust Treatment Systems............... B 3/4 11-4 l

l l [ Explo s ive Gas Mixture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B3/411-f)

Main condenser........................................ B 3/4 11-5 Venting or Purging.................................... B 3/4 11-5 l 3/4.11.3 SOLID RADIOACTIVE WASTE TREATMENT..................... B 3/4 11-5 l

3/4.11.4 TOTAL DOSE............................................ B 3/4 11-5 HOPE CREEK xxi Amendment No. 69 l l

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D TA8LE 3.3.7.11-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION -

2 N

MINIMUM CHANNELS INSTRtNENT OPERA 8LE APPLICA8ILITY ACTION

1. CONDE OFFGAS TREnTMENT SYS M -.

LOSIVE S MONITORI SYSTEM ~

( a. rogen Moni r 1 **

124

2. FILTRATION, RECIRtULATION AND VENTILATION MONITORING SYSTEM ITe Ace ai[A In58 1

a. Noble Gas Activity Monitor 1

123

b. Iodine Sampler 1 a M 125

c. Particulate Sampler 1

Y 125

$ d. Flow Rate Monitor 1

122 i e. Sampler Flow Rate Monitor 1

122

3. SOUTH PLANT VENT MDNITORING SYSTEM

3 a. Noble Gas Activity Monitor

a 1 123

b. Iodine Sampler 1

125 g c. Particulate Sampler 1

125 g, d. Flow Rate Monitor 1

i 122 ,

e. Sampler Flow Rate Monitor 1 *

~ 122 W

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4 L_._. - - - _ - _ - - _ _ _ . _ _ _ . - . _ _ _ - _ . _ _ . _ _ _ _ _ - - _ _ _ - _ _ _ _ _ - - - - _ . _ _ _ _ _ - _ _ _ , _ . . . , - , . - ,. . - - - , .,, . --

l TABLE 3.3.7.11-1 (Continued)

TABLE NOTATION At all times.

("" During operation of the main condenser air ejectop ACTION 122 - With the number of channels OPERABLE less than required by the '""

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Otherwise, ruspend release of radio-active effluents via this pathway.

ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effiuent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, suspend release of radio- ,

active effluents via this pathway.

ACTION 124 - Mit the n er of cha nels OPER LE less t n require by the Mi imum C annels OPE BLE requi ment, ope ation of a n condens r

, fgas eatment sy em may co tinue pro ded grab spies are collec d at leas once per hours and analyzed w hin the f -

lowin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . therwise, suspend r ease of r ioactive f

flu ts via thi pathway.

a

. ACTION 125 - With the number of channels OPERABLE less than required by the agha l

Minimum Channels OPERABLE requirement, effluent releases via "' g .

i this pathway may continue provided that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples inFI are continuously collected with auxiliary sampling equipment as

! required in Table 4.11.2.1.2-1. ;

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j HOPE CREEK 3/4 3-99 Amendment No.18 I

TA8tE 4.3.7.11-1 i .

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTAT .

CHANNEL MODES IN WHICH

= SOURCE CHANNEL FUN '30NAL SURVEILLANCE A

3 CHA WEL CHECK __ CALIBRATION TEST REQUIRED CHICK _

I INSTRWENT T SYSTEN

[ Ifer/4ce u/M 1"u

1. " MAIN CC NSER OFF S TREAT ORING S TEM EXPLO VE GAS M D .A. )

ia. drogen itor

2. FILTRATION, RECIRCULATION AND VENTILATION MONITORING SYSTEM

M lt(2) Q(1)

D

a. Noble Gas Activity Monitor

N.A. N.A. N.A.

W

b. Iodine Sampler

N.A. N.A.

W N.A.

p

c. Particulate Sampler

M.A. R Q D

d. Flow Rate Monitor *

'N.A. R Q 0

e. Sampler Flow Rate Monitor

3. SOUTH PLANT VENT MONITORING SYSTEM

g 0 M R(2) Q(1)

E a. Noble Gas Activity Monitor

N.A. M.A.

N W N.A.

l b. Iodine Sampler

E N.A. M.A.

W N.A.

c. Particulate Sampler

N.A. R Q D

' O d. Flow Rate Monitor Q N.A. R D

e. Sampler Flow Rate Monitor e

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- _ . - - _ - . _ _ _ _ _ _ - x -_ -_ _ . _ _ _ _ _ _ - _ . . .- - _ . _ _ _ _ _ _ _ _ . - _ . - _ _ - - _ _ - - _ _ . _ _ _ _ _ _ _ . _ - - _ _ - . _ _ _ _ _ _ _ - - . . _ _ _ - - _ _ - . _ . _ - _ _ _ _ - . _

t TABLE 4.3.7.11-1 (Continued)

TABLE NOTATION .

4 At all ti.nes.

h Durina operation of the main condenser air ejectory (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditi'ons exists:

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1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

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3. Instrument indicates a downscale failure.

4 (2) The initial CHANNEL CALIBRATION shall.be performed using one or more of 4

the reference standards certified by the National Bureau of Standards (N65) or using standards that havt been obtained from suppliers that participate '

These standards shall in measurement assurance activities with NBS.

permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are NBS traceable shall be used.

i the use f standard gas sampi 4 -

3) he CHANNEL ALIBRATION hall inclu i containin a nominal: .

1. Zer volume per nt hydroge , balance itrogen,' d

2. 1 volume ce ent hydrog , balanc nitrocen.

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HOPE CREEK 3/4 3-102 Amendment No.10

i RADI0 ACTIVE EFFLUENTS fXPLOSIV7GASMIXTU[ ]

LIMITING CONDl?10N FOR OPE/ ION / ,

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' l 3.11.2.' The conce ration of hydan gen in the mai condenser off s treatment i

syst shall be l' ited to less or equal to % by volume.

l LICABILITY- At all times

! ACTION: l With the c centration of ydregen in th main condenser ffgas treatmen system excee store the con ntration to 1 wi thin he limit wit 'p g the n 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . limit, 1

b. Wi continuous nitors inoper e, take the a ions required j ecification .3.7.11, ACTIO .

c The provis' ns of Specifi tion 3.0.3 ar not applicable.

! RVEILLANCE UIREMENTS / /

/

/ /

! < /

4.11. The concent tion of hydro n in the main denser offg treatment j sys shall be det ined to be w' hin the above 'mits by conti ously moni ,

s treatment stem whenev j 4

t ing the waste ses in the m ' condenser o.*f stem is in ope tion with th e main conde r evacuation ydrogen m tors required OPE LE by Table .

.7.11-1 of Spe fication 3.3 .11.

Ref lace- ulhh in5,ed [

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'M HOPE CREEK 3/4 11-16 Amendment No. 49

i RADI0 ACTIVE EFFLUENTS BASES DOSE -' IODINE-131, 10 DINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM.

(Continued) j 'therequirementsinSectionIII.AofAppendixIthatconformanceMththeguides of Appendix I be shown by calculational procedures based on models.ad data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual' release-ratas of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effl.uents for the Purpose of Evaluating Compliance with 10 CFR Part' 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1,- July 1977. These equations also provide-for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual'inhala-tion of airborne radionuclides, (i) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the l milk and meat by man, and (4) deposition on the ground with subsequent exposure

! of man.

l 3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RADWASTE TREATMENT AND VENTILATION' EXHAUST TREATMENT The OPERABILITY of the GASEOUS RADWASTE-TREATMENT' SYSTEM and the VENTILA-TION EXHAUST TREATMENT SYSTEM ensures thht the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive mate- .

rials in gaseous effluents will be kept "as low as is reasonably achievable." l This specification implements the requirements of General Design Criterion 60 l of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D l of Appendix I to 10 CFR Part 50. The specified limits governing the use of i appropriate portions of the systems were specified as a suitable fraction of ;

the dose design objectives set forth in Sections 11.8 and II.C of Appendix I,

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10 CFR Part 50, for gaseous effluents. g j3

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f3/4.lf2.6 EXPLQ2IVE GAS MIXTURE /

! j This sp ification is p vided to e re that the ncentratio f poten- ,

tially exp sive gas mixtu .s containe n the GASE0 RADWASTE T TMENT SYSTE main co nser offgas sy em is main ined below t flammabili limits of hydro and oxygen. tomatic co rol features re include n the syste o pre nt the hydroge and oxygen oncentration om reachin hese flamma ity HOPE CREEK B 3/4 11-t i

. , , - , ,. - - . - = , - _r . . , , , . , - . - , , -m,_ _ _ . . ... .._-,,... , m , , , , - . ,

4

~RADI0 ACTIVE EFFLUENTS BASES i

VLOSYMAS MIXTUK (Continued) -

imit . These au d c cont 1 features i lude isola on of the ource o hyd gen and/or xyc on 1 s of dilutio steam. Ma* taining t concentra-t n of hydro n belc. .h flammability imit provi s assuran that the -

eases of r ioactive c erials will contro11e# in confor nce with t 50 hequireme s of Generpf Design Crit fon 60 of Mpendix A 10 CFR Pa.

4 3/4.11.2.7 MAIN CONDENSER !

Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance tnct the total body exposure to an !

individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A l to 10 CFR Part 50.

3/4.11.2.8 VENTING OR PURGING This specification provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. l 3/4.11.3 SOLID RADI0 ACTIVE WASTE TREATMENT l This specification implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times. The purpose of t.he PROCESS CONTROL PROGRAM is to provide quality assurance that the solidified ,

waste meets 10 CFR Part 61 requirements.

3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.

The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units including outside storage tanks,etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual For the dose purposes to a of MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

the Special Report, it may be assumed that the dose commitment to the MEMBER OF HOPE CREEK B 3/411-5

a INSERT 1 DELETED INSERT 2 3.11.2.6 DELETED INSERT 3 3/4.11.2.6 DELETED

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ML20078C845

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