ML20083K484

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Proposed Tech Specs Reflecting Minor Title & Responsibility Changes & Incorporating Containment high-range Radiation Monitors & Main Vent wide-range Noble Gas Effluent Monitors, Per Generic Ltr 83-37
ML20083K484
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 04/09/1984
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20083K466 List:
References
GL-83-37, NUDOCS 8404160193
Download: ML20083K484 (26)
v • d • e


Text

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ENGINEERING & $UPPLY ELECTRIC INTER-

e. GENER AL SER VICE5' 3 CONSTR UCTION s CONNECTION AND m OPER ATIONS

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  • Corporate Responuinhty MANAGER l ELECTRIC for Fare Pru:ection , TEST Program ,

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STAFF I I I I l I MANAGER MANAGER 8 MANAGER MANAGER MANAGER MANAGER PROJECT ELECTRIC 8 NUCLEAR QUALITY PRODUCTION REAL ESTATE &

MANAGEMENT ENGINEERING POWER ASSURANCE MAINTENANCE OFFICE SERVICE 5 I I L I I  !  ! GENERAL SUPERVISING PLANT SUPERINTENDENT SUPERVISOR DIRECTOR NUCLEAR l ENGINEER $UPERIN TENDENT STAFF STAFF MAINTENANCE PROJECTS &

SECURITY PROJECT $ g NUCLEAR CALVERT CLIFFS & MODIFICATIONS ENGINEE RING SERVICES g GENERATION s A ENGINEERING g  ?

L.-------- P05RC A55bTANT GENER AL PRINCIPAL SUPERVISOR NUCLEAR CALVERT CLIFFS GENERAL SUPERVISOR ENGINEER StCURITY COMPU TER

$YSTEMS MAINTENANCE MODIFICATIONS

& MODIFICATION 5 ENGINEERING NUCLEAR NUCLEAR FIRE PREVENTION UNIT N

  1. 3 j' PRINCIPAL ENGINEER PLANT ENGINEERING
, NUCLEAR FIGURE 6.2-1 P'

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& MODIFICATIONS NUCLEAR NilCLEAR PIntE PetEVENTION

, UNIT PRINC1 PAL ENGINEER PLANT ENGINEERING NUCLEAR PIGURE 6.2-I w.saassgf OttGANIZATION CitAR T

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CALVERT CLFP5 NUCLEAR POWER PLANT SALTananaE GAS & ELECTRIC COMPANY L- .

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SWuus 3 l W t.EGEND,: RO - Reactor Operator License as 4 **** SRO - Senior Reactor Operator n

a License

  • Onsite Responsibility for Fire

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Protection Prograss g a e

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b Fignsre 6.2.2 3rganization Chart (Two Unit Operation) - Calvert Clif fs Nuclear Power Plant Baltiaore Gas and Electric Coupany I W

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33 and particulat:0 vith half-11vcs gr00tcr than eight dcys r 1 cased frcm tha plant to 1/700 of the levels of 10 CFR Part 20, Appendix 3, for unrestricted areas. This reduction factor of 700 is arbitrarily applied to I-131 and to all radionuclides in particulate form with a half-life greater than 8 days to allow for the = ilk-exposure pathway. The release rate is deter =ined by:

Qi 4 M3/sce.'

(MFC)1 -

X/Q x 700 vbere 41 and !GC are defined in 2.3.3.1. The X/q value is derived from the annual average cetterological data.

Specification 2.3.B.3 establishes an upper li=it for the release of gaseous activity at 16% of instantaneous release li=it of gross activity and 8% of the release rate of I-131 and particulates vith half lives greater than 8 days averased over any calendar tuarter, and 8% and k%, respectively, when averaced over any 12 consecutive mor.ths. The intent of this specificatica is to per=it the licensee the flexibility of operation to assure that the public is provided a dependable source of pcver under unusual operating conditions which =ay te=porarily result in higher releases than the objectives. The licensee has shsvn that gaseous hiesses vill result in a small fraction of doces specified in 10 CyR Ps.rt 20.

Specification 2 3 3.h requires that suitable equip =ent to dilute and =ecitor the Is

. radioactive gaseous releases and operating during any period these releases are taking place.

Specification 2.3.B.6 limits the radioactivity that =ay be released to the environ-

. ment to as lov as rea.wnable achievable.  %

Specificatica 2.3 3 7 limits tho =v4== offsite does to vell belov the limits of 10 CyR Part 100, postulating that the rupture of a vaste gas decay tank holding the ==vN" activity releases all of centents to the atnesphere.

In addition to the limiting conditions for operation listed under 2.3.3.1,

%. 2.3.3.2, and 2.3 3.3, the reporting requirements of Specification f.6.2c. (2) de11neste that the licensee shall identify the cause whenever the radicactive osA b N0

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I.1 Rscpch::ibility The Plant Superintendent, Calvert Cliffs, has the direct responsibility to f:

assure compliance with the specific 2tions presented in Section 2.0. -l

- i Direnfw/Envi<comenfrd Prgrams, has The Ci.f ::cci------* ' Tr-irre , Electric Engineerir.g Department, th,e direce responsibility to assure compliance with the specifications presented in Sections 3.0 and 4.0.

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1 Calvert Cliffs Unit 1 5.1-1 Amendment No.

. Calvert Cliffs Unit 2 Amendment No.

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' 5'. 3 Ravicv and Audit g 4 33 l

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o Tho Off-Site Safety end-Review Ccamittee as described in Appendix A Technical Speci-A .

fic:tions, paragraph b.5, shall be responsible for: -!

1. Reviewing the results of the Envira-ental Monitoring Require =ents and the Environmental Surveillhee and Special Studies as required by the specifi- >

cations.

2. Reviewing and approving proposed changes to the Environ = ental Technical l

Specifications.

3. Reviewing results of the audits perfor=ed by the quality Assurance Depart =ent.
k. Review of occurrences whica exceed a limiting condition for operation.

The Plant Operations snd Safety Review Committee 'as described in Appendix A, Spesification o.5, shall be responsible for:

1. Review of the results of any any proposed changes to the specifications ir. Sectica 2.0 and preparation of a summary report of this reviev for presen-

.tation to the Off-Site Safety M Review Committee.

g 2. Review of proposed changes .or modifications to plant equipment or systems affecting specifications in Section 2.0.

3. :Baview of operating procedures and changes thereto, for the systems and com-ponents involved in fulfilling specifications in Section 2.0.

Ilievu.e Al Pres == Wif,

_ The 1 ' --^' M  :--' ; "; g , Electric Engineering Department shall be responsible for:

1. Review of the results of any any proposed changes to the specifications in 3ecticas 3.0 and h.0, and preparation of a summary report of this review for presentation to tne O'ff-Site Safety end. Review Co:mnittee.
2. Haview of operating procedures, and changes thefeto, for the systems and com-ponents involved in fulfilling specifications in Sections 3 0 and k.0.

The Auslity Assurance Department shall be responsible for audit of the operating procedures for the systema and components' involved in fulfilling the Environmental TeInnical Specifications. Significant findings of the audit shall be presented to e

and reviewed by the Off-Site Safety and. Review Committee. ,

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S.5- Operating Procadures y systa=s which,are directly involved vith the fulfill:.e:t of the environ = ental j

hsical specifications shall be operated in accordance vith approved operati::g j prDc3dures.

5.5 1 on-Site Invironmental Moniterlig Progrs=

l All vritten operating procedures, and changes thereto, which pertain to specifica-tieno in Section 2.0 shall be revieVed by a me=ber of the plant staff and approved by tho ?lant Superintendent ' prior to implementation, excepe as provided in the

fallowing paratraph:

Tc=porty changes to operating procedures which do =ot change the intent of the

'criginal procedure =ay be made provided such changes are app.-eved by tvo licensed

! senior reactor operators , one of whom shall be the Shift Superdsor. Such changes

shall be documented and subsequently reviewed by the Plast Operations and Safety

. R; view Co==ittee and approved by the Plant Superintendene.

(, .2 Off-Site Environmental Monitoring Progrs=s

! All written operating procedures and changes thereto, which pertain to specifica-Pro

ticas in Sections 3 0 and h.0, shall be reviewed by the I
viren= ental_r:i; i; yens DicteterdEnvironwatal %ra. ors UnN
Greer, Electric Engineering Depart =ent and approved by the N

, ang6aser prior to implementation, except as providad below:

, TemporsW changes to operating procedures which do not change the intent of the criginal procedure may be made provided such changes are a, proved by the project 1:sder as specified in the operating proceduy. Such changes shall be subsequently J Pre W+ Directb[nvironeofal reviewed by the . Environmental 1ysms____ '-- Or:q and approved by the S:f __4. x N ?. N a...

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Calvert Cliffs Unit 1 5.5-1 Amendment No. /7

_ Calvert Cliffs Unit 2 AmendmentNo.Jf:

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Ate 0 OPERAt40N5 CO#45IatscIIGN I

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MAteAGEA M A8( AGE A MAf4AGEH MANAGER OUALITY ASSURANCE Nuct.EAM POWEN 3 ElECIAlc1(Si EEEC1 Hic (NGeteEE A6HG i

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h MANAGCMENT COGANil ATION C40A84T HEL AllNG 10 ENWlHOf4 MENTAL MATIEH1 4M CAs.vCNT CLif f S HUCLEAN POWER PL ANI HA4.flMOHE GAS a ELECiftlC COMPANT 3 6

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1 TABLE 3.3-6

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RADIATION MONITORING INSTRUMENTATION 2 MINIMJM

[. CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT q~ INSTRUMENT' OPERABLE MODES SETPOINT RANGE ACTION

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  • 1. AREA' MONITORS E'

q a.. Containment

, ._, i. Purge & Exhaust

+- Isolation 3 6 < 220 mr/hr 10-I - 104 mr/hr 16 I 2'. ES OR 4 I 8,e I , + so %e 1 - Io' Jt/Ar 30

a. Containment
i. Gaseous Activity R a) RCS Leakage
  • Detection 1, 2, 3 & 4 6
1 Not Applicable 1 - 10 cp, j4

,  ? it. Particulate Activity i g a) RCS Leakage Detection 1 1, 2,:3 A 4 Not Applicable 1 - 106cpm 14 4-

b. Nebk. 6 5' EHim+ Menilwr i Man w wa %p i . i, t, 544
  • lo" fa 10* D % 30
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TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE require-ment, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 16 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

t ACTicM 30- Win ne Awaher at OPERA 6LE cA nds less f4 equires(

y an. Minim t$ sands ofEt.AGLE reytrennb, iniHede At.

pesplasud aHernds me. sed. *F e,*.iten'y du appropeMe.

permuhet.sh wisin 72 houn, and -

l) tinse (cfort. 60 inopt@Idt CAanad(s) to OtF08L5I dsk wi%in 30 day of % sven+, or

2) p< spare. ad 54=1+ a Spetal Repect fo Mt f.eaatssim rwswad h Specificditm (. 4.2. w(Min Johs fol/evig i
k. asken Valu, St CW$L eh Yu, the u@ auklinM3 smi. thi plans and seAduk for fasieriq
opernIi)to tiu, sykm QPERA6LE statur.

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.g TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS p CHANNEL MODES IN WHICH

-Q- CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 3 INSTRUENT . CHECK CALIBRATION TEST REQUIRED h 1. AREA MONITORS' 5

_. a. Containment

,- 1. Purge & Exhaust F - . . C +a3=MhENsf Anap "

2. ROCESS MONITORS N.A. R 6 i, t, 3p g
a. Containment t*
1. Gaseous Activity a) RCS Leakage Y. Detection S R H 1, 2, 3, & 4 Es 11. Particulate Activity a) RCS Leakage Detection S R H 1, 2, 3, & 4
b. t4aMe Gu Efflunt t%iles i
i. M.I., Ve.4 Wida Reage. W. A. g g g, t,is, t t I

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FROM F195 '94.03.12 1Ie32 FCJt B S-lo41.

, PLANT SYSTEMS -

AUXILIARY FEE 0 WATER SYSTEM l .

.. LIMITING COM0! TION FOR OPERATION

-. 3.7.1. 2 Two auxiliary feedwater trsins consisting of one steam driven and.one motor driven pump and associated flow paths capable of automatically initiating flow shall be OPERABLE.* (An OPERABLE steam driven train shall consist of one pump aligned for automatic flew initiation and one pump aligned in standby.)*X

. 4

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APPLICA81L!TY: fiODES 1. 2 and 3.

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ACTION: . . . .

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1. e::t: : th: in:;;r:L1: =t:r er :: ;=; :: cers.aelt : ::: a t m .

72 5:;.;r;.^,7 5: i n MOT S'i"T0*.'." wi th! th: ::t 12 5:e- . -

. 2M onf._fie!t.pwp_ N'opmeb!e;-ppform_de.Afocq. :

1. WM4 Wo. 25 mofor- &iven pomp inoormde :

th) A/y ,t4* dealAf s/eam &ma paap_.Je.pfoeslic .M4ofy --

3 5 t a lk m 7 2 k ur s ev~ Q,jj he7 .ssw2:ewn p#/pg_ ..

_ /fg. iw/ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ..a..n.d.

3 .. _ . . _ . . . . - . . . . . . . . . . . _ .

= ._ . . . . _ . . _ - .

(4) hindms do. 25 paolor-drien ?!.".!$ /o C.P..E. ?. FABLE.~.. s.h... hd . .

__.__tW/dtn Ae. i>ed /4fob.s or le In M__sytirtowd AM ~ -

,gd sed a kaes. . . . . - _ . - ..

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K W1th one steam-driven pump inoperable:

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Align the OPERABL

.within72hoursor[beinHOTSHUTOOWNWithinthenext12 hours,and ..

, (Q

--- A Restore the inoperable steam driven pump to standby status (or auto- - .l.

metic initiating status if the other steam driven pump is to be' _. c.

. placed in standby) within the next 30 days or be in NOT SHUTDOWN .

.within the neat 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, t . . _ - _ _ . .

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  • X A standby. pump.shall be available for operation but aligned so that auto- t

. matic flow initiation is defeated upon AFAS actuation.- ,

. '.CALVERT CLIFF $ - UNIT 2-3/4.7 5 . .. _ . _Amendment _ _ _-- _No. M . (f. M . M- _ - - - - _ _ _ _ _ _

f F m 03-10 %-

b. Ukib ory k>o pwim inepmL/e :
1. Ver/7 hi /Je reinening pump is algoal A sak,a/a. todialty slohs .wt/4tn. oss k>ae, .aa/ l

.2. Verdh ud/4to one hour /Aa/ //o. /3 make-driven pump is OPERABLE Q?d vake 1 ~l'V~ 4550 he.s been erevoiked

^

l w/4tn Jhe /oM 30 days, .gZd

.9. /Fr.sJare a secondpump A suksehr is/dohy s/s/a.s wi/hn 72 haxu cv La h //07~ s/M7D%/d ud/Wo ./de

.. /!Wk. /I b0*"'f

c. shenever controls inathe subsystem direct flow (consisting)of path required forone pump piping, operability is inoperable valves and for the performance of periodic testing (e.g. manual discharge valve -

closed for pump Total Dynamic Head test) a dedicated operator will be stationed at the local station with direct communication to the Control Acom. Upon completion of any testing, the subsystem required for operability will be returned to its proper status and verified in its proper status by an independent operator check.

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d. The requirements of Specification 3.0.4 are not applicable whenever r; eMt . tf:: :" t:: ' :t:r r ;t::- f S: ) m;; r: 01?; :f ' ?

. :t-- t4 : *1= '24 t4:t!=. one, i,,ok, ed essa shoa,. 4.i.or p

. for Aso a Anon- a'etron psn>ps) .aee. o/dnea' .4,- sokmo*c-

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AUXILIARY FttDWATER SYSTEM SURVt1LLANCE REQUIREMENTS ,

4. 7.1. 2 dach auxiliary fee' water d flowpath shall .b,e demonstrated CPERA8tt:
4. At least once per 31 days by:
1. Verifying that each steam driven pump develops a Total 0ynamic Head of > 2800 ft. on rectreulation flow. (!f verification must be Tenonstrated during startup, surveillance testing shall be performed upon achieving an RCS temperature > 300*F and ,

prior to Entering M0011).

CALVERT CLIFFS - UNIT 2 3/4 7-54 AmendmentNo.$f,g

FP0ft 7895 *s4.03.12 11:36 1

FCA. 93 -104--

.-- 2. Verifying that the motor driven pump develops a Total Dynamic Head of .>. 3100 f t. on recirculation flow.

3. Cycling each testable, remote operated valve that is not in-Its operating positian through at least one complete cycle.

- _. 4. Verifying that each valve (panua1, power operated or automat'ic) i,n, ..the direct . flow path is in.. . it,s.

, .; correct position.,,a'h.,r .'."/

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-::t; 'nt ;n th; : 'ndt::t:; ::nt.:'!:r ?- CO..te:1 8 ee.

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.b. Before enteeing H00E 3 after a COL.Q SHUTC3WN of at least 14 dax$ by completing a flow . test that verifies the flow path from the condon-sets storage tank to the steam generators. ,

. . . _ v:le;

c. A,_t.m_least,once per 18 months by:'.:__'_'y'_ng _ _. ___ th:t,,:::t

,.. .2  ::t:--tt: _.....i._._.

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1. Ven$'n3 Hn/ am/* dew'e m/.'* .. .

u..s.. ./.4e._./,4u) pd/.4._.-. _. _ _ . _

oessaAr.s /* 14 comre/ pan /Au GenAcoke .,e ,& - ~ ~

inadatahf> cAc w sfe m fre i 4 9 isfa' Zed.T~os,d' s k ~'~'"

wl/+y Mar /s pump aasoaches/f .sk,,4 opm-- -

1 recee/ of eded AMs /e.s/ s)i od/> e.ne' . .. ._ . - - . . ..

f 9 Yek, l&, N)*/ 5 e d 49 9 _ A ra_<'M. ./.*c.. 9 A k_n .if ._ . -.

l es,aa(/c e/ &&, s ,.w, o_ww,.1_of_ _.2%,,fP"....isomow . . . . . . .. . .. . . . _ . . _ _ .

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& hr etel1 s0$40 klf. . . _ . __._ _... - . ... .

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t PAseer dom . wir 2 _ 44 7-64 . f,pg%v( gb; L

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non is,s no es.t ~ iiisi

_ m x ~ FC.ft Y3-le d plus 25 gym end' mim/s 24.9pm At ha mofoe d ;ve,p p ,,,,,,p frein. 7~he dottespondtnj valve.t Ae ./he stoom -

desven pua,Qs Mo'n era plus 57 gym and minus gogym.

Pt._ ANT SYSTh A N ^

SAsts U = maximum number of inoperable safety valves per .

l opprating steam itne 106.5 = Power Level-High Trip Setpoint for two loop operation

. . .s 46.8 = power Level-High Trip Setpoint for single loop .

operation sith two reactor coolant pumps operating q

in the same loop X = Total relieving capacity of all safety valves per -

steam line in 1bs/ hour i Y = Maximum relieving capacity of any one safety valve in Ibs/ hour ,

3/a.7.1.2 AUX!LIARY FEECWATER SYSTEM The OPERABILITY of the, auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 3000 F from normal operating ccnditions in the event of a total loss of offsite power. A capacity of 400 gom is sufficient to ensure that adequate feedwater flow is available to remove decay heat snd reduce the Reactor Ccolant System temperature to less than 3000F when the shutdcwn cooling system may be placed into operation.

> r=200 F1:w coatrol valves, installed in each g leg polying the steam generators, are . set 6  ;

maintain a nominal flow setpoint of 4M gpm lus or minus 10 gpm for operator -

(settine band. The nomina 3 1ow setpoint of M & gem incorporates a total instru.

ment.. loop error band _o gp'us* q g . G17 vr. ;e..! Tb r.. *. i} .2 u..

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e ; ;;= e = e = = = := .,a : e _e = :. u = t a uie .e u e .. :n.c, e=zer :==: te =;inisaeas c := # .n..;;;ue.; e = ;e.tu 1 be....a.ca= aua aru,. ire. n =;c..u;.nu mae eaae=

en a'_t; = ue; n nrdr

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CALVERT CLIFF 5 . UNIT 2 S 3/4 7-2 ,

AmendmentNo.M.ff.M' e , - - - --

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(alliiLih We k Me F3bnf 5.6.2.b Nancou':1aa Radiological Enviro'emental Opera:ing Reports

, if a confirmed sessured level of radioactivity,at any offai:e loca:1on in a environmental medit:a exceeds :an :ines :he " background" value, QA eydk/dl/00

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, a i, a, e,.,r AfRC R shall be subsi::ed := the ir:::::qftens/ AoCwisoihahrt-AkskyM. D. C.. '- a 5:;in:1 Offic: M.:h a espy :o :he

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  • .; 2
    ;;i & ) withis II. days' af ter confir=ation.

The r'eport shall include an evaluation of any release conditiscs, environ =en:a1 factors, or a: hor aspects necessary to explain the resules.

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^^1  ! 7..... ....; ;

    • AM T.~ u .f* 4- 3 ;__ . . :; . . ; v: .n,;_

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a. FCR.14-35i

. PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.1T.1.1 The fire suppression water system shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the contained water supply volume. -

~

b. At least once per 31 days on a STAGGERED TEST BASIS by starting the electric motor driven pump and operating .it for at least 15 minutes x ::f r:Oti:r '!:r. This test shall be performed on l a STAGGERED TEST BASIS with the test required by 4. 7.11.1. 2.a . 2.
c. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, ,

sealed, or otherwise secured in position, is in its correct position.

d. At least once per 12 conths by performance of a system fluch of the filled portions of the system. .
e. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
f. At least or.ce per 18 months by performing a system functional test .

J which includes simulated automatic actuation of the system through-out its operating sequence, and:

1. Verifying that each automatic valve in the flow path actuates to its correct position, .
2. Verifying that each pump develops at least 2500 gpm at a dis- '

charge pressure of 125 psig,

3. Cycling each valve in the flow path tnat 'is not testable during plant operation through at least one complete cycle of full

. travel, and

4. Verifying that each high pressure pump starts (sequentially) '

to maintain the fire suppression water system pressure > 80 psig.

g. At least once per.3 years by perfonning a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook,14th Edition, published by the National Fire Protection Association. .

m '

U CALVERT CLIFFS - UNIT 1 3/4 7-67 Amendment'No. 25, 61'

}

FCR 84-35 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.11.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:
1. The diesel fuel oil day storage tank contains at least 174 gallons of fuel, and
2. The diesel starts from ambient 'conditions and operates for at least 30 minutes ._ .;: ;.._d

_:. This test shall be performed on a STAGGERED TEST BASIS with the test required by Specification 4.7.11.1.1.b.

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-0270-65, is within the acceptable limits specified in Table 1 of ASTM 0975-74

~

when checked for viscosity, water and sediment.

c. At least once per 18 months, during shutdown, by:
1. Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service, and
2. Verifying the diesel starts from ambient conditions on the auto-start signal and operates for 3,20 minutes while loaded with the fire pump.
l 4.7.11.1.3. The fire pump diesel starting 24-volt battery bank and charger l shall be demonstrated OPERABLE:
a. At least once per 7 days by verifying that:

! 1. The electrolyte level of each battery is above the plates, and

2. The overall battery voltage is 3,24 volts,
b. At least once par 92 days by verifying that the specific gravity-E is appropriate for continued service of the battery.
c. At least once per 18 months by verifying that:

, 1. The batteries, cell plates and battery racks show no visual l indication of physical damage or abnormal deterioriation, and i

2. The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material .

CALVERT CLIFFS - UNIT 1 3/4 7-68 Amendment No. 25, 61 3

L

.. 11 ptANT SYSTEMS ICR 811-35 SURVEILLANCE REQUIREMENTS 4.7.11.1.1

, The fire suppression water system shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the contained water supply

', volume.

b. At least once per 31 days on a STAGGERED TEST BASIS by starting the electric motor driven pump and operating it for at least 15

. minutes on ::' : ': 9 - ' M . This test shall be performed on a STAGGERED TEST SASIS with the test required by 4.7.11.1.2.a.2.

c. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed.. or otherwise secured in position, i:: in its correct position.
d. At least once per 12 months by performance of a system flush of the filled portions of the systam.
e. At least once per 12 mor.ths by cycling each testable valve in the flow path through at least one complete cycle of full travel.

l - f. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the systen through- -

out its operating sequence, and:

1. Verifying that each automatic valve in the flow path actuates

) -

to its correct position, t

2. Verifying that each pump develops at least 2500 gpm at a dis-charge pressure of 125 psig,
3. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and
4. Ver_ifying that each high pressure pump starts (sequentially) to maintain the fire suppression water. system pressure 180 psig.

l g.. At least once per 3 years by performing a flow test of the system i

l' in accordance with Chapter 5. Section 11 of the Fire protection Handbook.-14th Edition, published by the National Fire Protection

. Association.

l

?  :

CALVERTCOFFS-UNIT.2 3/4 7 Amendment No. U, 43 L

PL4NT SYSTEMS m 8b35 SURVEILLANCE REOUIREMENTS (Continued) 4.7.11.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:
1. The diesel fuel oil day storage tank contains at least 174 gallons of fuel, and
2. The diesel starts from ambient conditions and operates for at least 30 minutes ::  ::i :f :ti: n . This test shall be performed on a STAGGERED TEST BASIS with the test required by Specification 4.7.ll .l .l .b. .
b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-0270-65, is within the acceptable limits specified f a Table 1 of ASTM 0975-74 when checked for viscosity, water and sediment,
c. At least once per 18 months, during shutdown, by:
1. Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's

> recommendations for the class of service, and

2. Verifying the diesel starts from ambient conditions on the auto-start signal and operates for 1 20 minutes while loaded

.with the fire, pump.

4.7.11.l.3 The fire pump diesel starting 24-volt battary bank and charger shall be demonstrated OPERABLE:

.a. At least once per 7 days 'by verifyino that: .

l I

1. The electrolyte level of each battery is above the plates, and
2. ,The overall battery voitage is 'l 24 'vol ts .

b b'. ' At least once per 92 days by verifying that the specific gravity l- .is appropriate for continued service of the battery. ,

I c.. At least once per 18 months lby verifying that:

.l . The batteries, cel1 ~ plates and battery racks show no visual indication of pnysical damage or abnormal deterioriation, 'and i' 2. ~ The battery-to-battery and terminal connections: are clean, L

tight, free of corrosion and coated with anti-corrosion material .

.3/4 7-60 leenement No. 77,43 IcALVERT CLIFFS - UNIT 2 s

-. =.. -. , , ... - - -

TABLE 3.3-11

~

FIRE DETECTIC!l INSTRUMEilTS KR 8b34 U? IT 1 INSTRUiENT LOCATION MINIMUM INSTRUME:lTS OPERAELE HEAT FLAME SMOKE 5 pent Fuel Pool nger Room 320 3 1-tain Control Ro 6 f Control Room Vent

  • a 2 Main Plant Exhaust Equip Room 524' 8 Control Room HVAC. Equip Rocm 512 4 Passage and-Filter Room 323 3 Unit i Cont SW Elec Pen Area
  • 4 -

Unit 1 Cont NE Elec Pen Area

  • 4

Unit 1 Cent East RCPS* 15 Urtit 1 Cont Ifest RCPS* 16

  • Control Rocm Vent Duct "B" 11 09 - .. 1 (0 # 8

-0"

'les: Passage 319 Elev 6

5

_ E/W Corridor 104 L ev (-) l_0'-0" intake Structure ,

~

48 Unit 1 Waste Proc Control Room 111 l Coolant Waste P.ec/ Mon. T.K Pp Room 110 -

2 11 Diesel Generator ** .. . . .

2 12 Diesel Generator ** 2 .

4 Unit 1 Cable Tunnel Elev B3'-0" 1

Cable Chase 1A - -

.- 1 Cable Chase 13 -

Unit 1 C.S.R. '& Cable Chase 1C" 2 10 Unit 1 Personnel Access Area Room 525 3

= Unit 1 Switchgear Elev 27'-0" Rocm 317'* 5 Unit 1 Switchgear Elev 45'-0" Room 430" 8 Unit i Elec Equip Room 529 3 Unit 1 East Ele: Pen. Room 429 3 Unit 1 West Elec Pen Roca 423 3 Unit i Refueling Watar TK Pump Room 439 -2

. Unit 1 East Piping Pen Rooms 227 and 316 3 5 Unit 1. Purge Air Su; ply Rocm 318 2

. Unit 1 West Piping Pen Rcoms 221 and 326 7 Unit 1 Latdown Heat Exchanger Room 324 1 Unit 1 'tolum.e Control TX Room 218. 1 Unit.l ECCS Pump Rooms 113 and 13 - - 7 w - Unit 1 Coolant Waste Rec TK Room ('14 flf f f 4.

l Unit 1 ECCS Pump Rocms 119 and 1;. -

7

'init 1 Elev 27'-0" Swgr Rcom Vent _0uct 1

Uni: 1 - Elev 45'-0" swgr Rccm Vent Duct . 1-

--Cetection ins:rument:~ ccated witnin -he con:nn ent are not r :uirac ~ to .:

0PERAELE during :ne erformanca of Ty e A Containment Leakage Rate Test:.

" Detectors lwni:n .au::ma:icallj ::ctua:e ' fire superassion systuns.

T f.

..mn .

TABLE 3.3-11 _

FIRE DETECTION INSTRUMENT UNIT 1 INSTRUMENT LOCATION MINIMUM INSTRUMENT CPERABLE HEAT FLAME SMOKE Main Steam Piping Room 315A 6 Hot Machine Shop 223 4 Battery Room 304 & 301 3 Misc. Waste Monitor Tank Room 113 1

-Charging Pump Room 115 3 East Piping Room 428 7 North South Corridor 410 4 Spent Fuel Pool 530 5 17 Radiation Chem., Lab Office, Rm. 513,518 & 519 1 16 Corridor 521,522, & 534 Cask & Equip. Loading Area Rm. 419,420,425 & 426 3 22 Spent Fuel Vent Equip. Room 520 2

' Component Cool Room 228 8 Radiation Exchange Vent Equip. Room 225 4 Boric Hold Tank & Pump Room 217 2 Reactor Cooling Pump Room 216 1 Hot Instrument Shop Room 222 2 Service Water Room 226 3 6 East Piping Room 224 10 Corridor 200,209, & 210 13 Solid Waste Room 418 & 417 2 3 Spent Resin Metering Tank Room 441 1 Waste Gas Equipment Room' 207. 1 Auxiliary Feed Tank Room 603 2 Misc. Waste Equipment Room 536 3 Corridor 308 6 N/S Corridor Room 410 4 N/S Corridor Room 308 6 Degasifier Pump Room 220 1 .

Waste Cas Compressor Room 208 2 CALVERT CLIFFS - UNIT 1 3/4 3-46 .

b f.

~ ~

TABLE 3.3-11 F~RE DETECTIOff INSTRUtiEilTS FCR 814-34 Utili 2
  • R .};~'N W I?tSTRUMENT LOCATICit MIrlIMUM Iri3TRUMErlT5 GPERAE!_E*

HEAT FLAME St.!O):E Unit 2 East Elec Pen Rocm 409 ~ 3 Unit 2 West Elec Pen Rocm 214 3 Unit 2 Switchgear Elev 27'-0" Room 311** 5 Unit 2 Switchgear Elev 45'-0" Room 407** ' S

' Unit 2 Elec Equip Room 532 3 Unit 2 Cont SE Elec Pen Area

  • 4 Unit 2 Cont tiW Elec Pen Area *'

4

-Unit 2 Cont East RCPS* 16 Unit 2 Cont West RCPS* 16 Unit 2 Main ~ Plant Exh' Equip Room 525 .

i 8

' Unit 2 Personnel . Access Area Room 527 . 3 Cable Tunnel U-2 Elev 83'-0" - -

4

' ' Cable Chase ZA

1 Cable Chase 23 -

1

'Unie 2 C.S.R. & Cable Chase 2C** 2 .

10 Unit 2 Letdown Heat Exchanger Rocm.322 -

1 Unit 2 Volume Control Tank Roo.m 1R 6, -

. 1

___ -- Unit 2 Cool' Waste ' Rec TX. Room 07410 4 l

. Unit 2 ECCS Fwnp Rooms 101 and 7 Uni t 2 Pump Room .108 Elev .(-) 10'-0" l

.. Unit 2 Intake Structure 4a Unit 2 Elev 27'-0" Swgr Room . Vent Duct 1 Unit 2 'Elev 45'-0" Swgr Room Vent Duct 1 .

Unit 2 ECCS Pp Room d 120 7

-->-21 Diesel Generato 2- l Unit 2 Refueling W Pp_ Room 440 2 Unit 2 East Pp Pen Rocms 206 and 310 3 5-Unit 2-Purge Air Supply Rocm 312 2 Unit 2 ',{est Piping Pen Roems 211 and 321 2 3

  • 0stection instruments located withinL the cantainment are not required :s de OPERABLE during the ?arformanca of Type A Containmenc Leakage Rata Tests.

'"Cetectors whien aut:matically actuate fire su:pression systems. I p -

L! C.vtRT Cur 75 .

utur 2 -3n 3 es. A. .ene...,o:c . ::, t3 5

' t.

. . . - , . . - ~ ..

TABLE 3.3-11 ADDITIONAL DETECTION FIRE DETECTION INSTRUMENT UNIT 2 INSTR 1RIENT LOCATION MINIMUM INSTRUMENT OPERABLE NEAT FLAME SMOKE Main Steam Piping Room 309 6 East Piping Area Room 203 10 Charging Pump Room 105 3 -

Battery Room 307 & 305 3 Misc. Waste Monitor Tank Room i 7

East Piping Area Room 408 Componeat Cooling Room 201 9 Raditation Exchange Equip. Room 204 4 Boric Acid Tank & Pump Room 215 2 Reactor Cooling Pump Room 216A 2 Service Water Room 205 3 6 Auxiliary Feed Pu.np Room 605 2 1

Degasifier Pump Room

=

4 CALVERT CLIFFS - UNIT 2 3/4 3-46 3

f.

V

FCR 82-169 l ADMINISTRATIVE CONTROLS

b. A high raqiation, area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.12.1.a. above, and in addition locked barricades shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained underiggf". administrative control.,yf/ypp SM#N/WpW#idt/4NAty by he Supervisor-RaduJa.on Conttot and he 6.13 ENVIRONMENTAL QUALIFICATION 6.13.1 By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:

Division o.f Operating Reactors " Guidelines for Evaluating Environmental Qualiff. cation of Class IE Electrical Equipment in Operating Reactors" (00R Guidelines); or NUREG-0588 " Interim Staff Position on Environmental -

Quali fication of Safety-Related Electrical Equipment", December 1979.

~

Copies of these documents are attached to Order for Modification of Licenses OPR-53 and OPR-69 dated October 24 ,1980.

S.13.2 By no later than December 1,1980, complete and auditable records must be available and mai.ntained at a central location whi~c h describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the 00R Guidelines or NUREG-0588. Thereaftar, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

6.14 SYSTEM INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the folicwing:

1. Provisions establishing preventive maintenance and periodic visual inspection requirements, and .

2 ~. Leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

e I

CALVERT CLIFFS - UNIT,1 6-21 OfAdf ddidd 2didBdf 44L 1980 Amendment No. 53-

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