ML070190214

Units, 1 and 2 - Tech Spec Pages for Amendments 192 and 193 Technical Specification 1.1 Definitions and Technical Specification 3.4.16 Reactor Coolant System Specific Activity

ML070190214
Person / Time
Site:	Diablo Canyon
Issue date:	01/19/2007
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Wang A, NRR/DORL/LPL4, 301-415-1445
Shared Package
ML063450364	List: ML063450372 ML070190214
References
TAC MC9671, TAC MC9672
Download: ML070190214 (6)

Text

(4) Pursuant to tle Act and 10 CFR P.a.is 3o, 40, and 70, to receive, possess, and use in aimoumnls as requ!rad ay byproduct, source or sqel6 nucl6et material without restriction to chenmica or'phy.sical form, for sample analysis or Instrument calibration or asaodaled with radoeffV6. apparatus or compdnents: and (5) pursuant to tho Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, Such byproduct and speol nucJaer matedals as may be producad by tlih- operation of thelaadlity.

C. This License sheal be deemed it contain and ubjept to the condtin *pc.ed Inthe Qomm~lalon.'p .ragulatlona set forth In lO CF:R chapteIr a.n.d Is subjetto pOapppl. ahe prvisions e th0 Acand 6o the rules, regula*l*os, ead.ordem of 1I comm!isson now or hereafter li/ effect; and to subjec to the addilional conditions specified or Incorporated below (1) Maximum Power Level The Pacflc Gas and Electrfc Companly Is authorized to operate the facility at

• o*"*,power) reactor in core pdWer I*i/.e.snot accordance 'Wththeincondijions emc.sofspeclfled herein." thermsl(1 00A rated 34J1. negswetts (2) Technicallee.facutlons The Techni.al SpeCl1ca12ons contained InAppendli A and the Environ.r'enlul

...... .. .... " ... ProtectiorL Plan .06rta.lned InAppendix 1, ts uvlsed ftugh Miendment No.

1 9 2 , are. h reby ircacrpo.a!.d Inthe li.criso. P ifcic Gi s .Es I' ldr ComPany -

Shall bariaideh faca.lty Inaccordanfa wlh"th. Technic*/ S, -pcbifcAtlons and the Envfroiou'iinti Pt0rotecon Plan except whereohenwise staled InsP'eOil license copdliachi.

(3) Inltl Test baram The Pacific dos apd Elect.ic Qomppny .l. conduct the p.st-fual oadlng .Inial

• . test pr* 1lo f~rtiiki 06-060 4 o~f P-4,I~04 p i ,~ 14904,00IG thfpI( q Mlyss ~ anehdd),w~l~uginaidi MrY. MgrjijinodlflcallDons of

~aray ~po4 thIs progrim ugiis moddllcad.n. have.bmnIdentiied nd have rIcieu pdor NICappo 'Major moi V~boh ir defhned i.

• a. eim!.naWlon of ny. teIt Idenflled in 6ecUn 14 of PG&E's Final Safely.

A salysis Report is amended a being essental; Amendment hg.-. 1 92

'p

(4) Pursuant to the.Aft and 10 CFR Parti 30, 403 and 70, to receive, possess, and use In am.unts as required any byproduct, soo.ce or special nuclear material with6ut restriction to chemical or physical form, for. stple analyss ar strnt 'ecaibration or associated with radioactive apparatus or companentsi and (6) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such b :prtd:Ft and speclal nuclear materials as may he produced by the operation of the faceili.t C. This. liceinse shall be deemed to c6ntain, ind is subject to the conditions specified In the Comitfpspa's refuletlaps.set forth in 10 CFR Chapter I.-

• Bd 1s stb$,idct to all aplpca.l.prov"isons of the At and. tO the ru~les, ragul~tons, and orders of the Comission now or hereafter in.

. effect; aid is subject to the additional ondiltions specifJed or Incor-porated below:

(1) Maximun, Power Level TOe Paefffc Gas and. Electri Company *s authoriz*d to operate thie fa¢.*.t.at reacto cor.er levels not in all Ss of

• L1I .g~p s JhU t""e " catal ion5 zpecgfied hereih. Al.(1Q09.rtet. power).n..accordance -with.

• (2) Teclihleal *Se*iftications (SSER'32, Section 8)* and EnViranmentml

• ~~ trtt-1bifl Plan -

• Tii* mT,-1-I.4-pecif cations-vont W-in A*A pndi A and the

• ~~ ~ tiFPH.

. p-fq 1 ppnix as revised

• Pa Ujfq . ctio~ldn~ micr~rtdin ff~ 1ýceIeX 4 ~'th TAha6n0 1bwi~ tftEv raownetal C1f .4ns Sac 1**

• (3). 1~i,

• l" ..... Pit-rooiram"l'cep "Ii 3i, aifiltkctfiog 4.4.1) hee"t oIgtise -"' ~t"bed intpeic

• seI

• . Any c g he I Tee PIOgrim -dscfhd ip Sect4pp 14 Of t~i a,~ in-4.ew th th 1 CFR isfr~sa

.9 h1. e V O'itd In iccordunce with 50,5h(b) within one a"onthof-such chaige.. * .. ** . * .

• 1 noato Me t*loj Iiesecni

" I 4 .* - ny dgeno.j the section of the Sa y EdvaluatORReport eandler Its supplemnts " ". ".

. . ". jn t:he 1icepsqg~aition is diucusssked."

. . Aiienhdme.n-t .io, 193

Definitions 1.1 1.1 Definitions (continued)

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133,1-134, and 1-135 actually present. The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or Table E-7 of Regulatory Guide 1.109, Revision 1, NRC, 1977, or International Commission on Radiological Protection (ICRP) Publication 30, 1979, Supplement to Part 13 pages 192-212, Table titled "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."

DOSE EQUIVALENT XE-1 33 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-1i33 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. Ifa specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-1 33 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil."

(continued)

DIABLO CANYON - UNITS I & 2 1.1-3 Unit 1 -Amendment No. 4!35,455,!4*, 1 92 3 Unit 2 - Amendment No. 435,455;546, 1 93

Definitions 1.1 1.1 Definitions (continued)

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as thait from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or (continued)

DIABLO CANYON - UNITS 1 & 2 1.1-3a Unit 1 - Amendment No. 435,455, 192 4 Unit 2- Amendment No. !, 55,!5, 193

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133-specific activity shall be within limits.

APPLICABILITY: MODES 1, 2,3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 .--------- NOTE-----

not within limit. LCO 3.0.4c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131 60 pCi/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 to within limit.

B. DOSE EQUIVALENT B.1 - NOTE---- 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> XE-1 33 not within limit. LCO 3.0.4c is applicable.

Restore DOSE EQUIVALENT XE-1 33 to within limit.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR DOSE EQUIVALENT 1-131

> 60 pCVgm. I DIABLO CANYON - UNITS I & 2 3.4-35 Unit 1 - Amendment No. 436,460,1 92 35 Unit 2 - Amendment No. 45,1470, 1 93

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 - -NOTE-------------O----- 7 days Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity < 600.0 pCi/gm.

SR 3.4.16.2 ---- NOTE Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 14 days specific activity _ 1.0 pCi/gm. AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of > 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

DIABLO CANYON - UNITS I & 2 3.4-36 Unit I - Amendment No. 435, 19 2 36 Unit 2 - Amendment No. 445, 19 3