ML20037D351

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Forwards marked-up Revision to Draft Tech Specs.Changes Pertain to Environ Aspects of Tech Specs & Are Necessary to Apply to Plant Design
ML20037D351
Person / Time
Site: Summer 
Issue date: 07/06/1981
From: Shealy L
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Weinkam E
Office of Nuclear Reactor Regulation
References
NUDOCS 8107100096
Download: ML20037D351 (59)
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Text

{{#Wiki_filter:_ SOUTH CAROLINA ELECTRIC & GAS COMPANY Post orrics mox 7e4 m /f Q b g[M'pf COLUMBI A, S. C. 29218 Nuclear Operations p/ fg Q o II Ei 9% g y rf gl 3" Y 6-a; - y_ Mr. Ed. Weinkam w, Office of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

V. C. Summer Nuclear Station Docket No. 50/395 Technical Specifications

Dear Ed:

Attached is our proposed revision to your latest draft (March 10, 1981) of the Technical Specifications for the V. C. Summer Nuclear Station. Most of the changes are to the environmental part of the Specificatiors and are necessary to apply to our plant design. Explanation for each change is as follows: h Explanation 3/4 3-10 The $2.0 second response is based on lead-lag circuit set at zero. The Surveillance Test will be performed with the lead / lag circuit functioning normally. The correct response time for normal lead / lag compensation is 14.0 seconds. 3/4 3-41 Notations for the plant radiation monitors were-incorrect. Range for RM-G7 is different from RM-G18 and there are no alarm / trip setpoints. 3/4 3-41a In this Table only the high range moniturs have p/ been listed. The condenser exhaust and auxiliary building exhaust both are exhausted through the main plant vent. We do not monitor steam safety / valves, relief valves or atmospheric steam dump r G valves but do monitor each steam line upstream of ADD'. these valves. g, 4,. 4 7 i y T. Chakas bwi 1 8107100096 810706 PDR ADOCK 05000395 A PDR

Mr. Ed Weiakam Page 2 July 6, 1981 3/4 3-43 & Items in this Table were changed to correspond 3-43a to the items in Table 3.3-6. 3/4 3-65 Typographical errors. 3/4 3-66 Adding additional information. Condensate demineralizer effluent was eliminated because this effluent will be batched and released in accordance with Specification 3.11.1.5. There are no flow rate measuring devices on the penstocks or the circulating water discharge canal. These flows will be conservatively estimated from head curves. 3/4 3-67 Clarification of reason for action. 3/4 3-68 These ACTIONS are no longer referred to by the Table. 3/4 3-69 Items were changed to correspond to the items in Table 3.3-12, 3/4 3-70 CHANNEL FUNCTIONAL TESTS were changed to describe installed instrumentation. 3/4 3-72 On each recombiner there is a H2 and 02 m nitor upstream and a H2 and 02 monitor downstream. The condenser air removal effluent has been omitted because this effluent goes out the plant vent. 3/4 3-73 The sampler flow rate for the plant vent is monitored. 3/4 3-74 ACTION 40 was changed for clarification. 3/4 2-75 Items of this Table were changed to correspond & 3-76 to the items in Table 3.3-13. 3/4 3-77 CHANNEL FUNCTIONAL TESTS were changed to describe installed instrumentation. Notes 4 and 5 were combined due to the way the monitors are described in the Table. 3/4 4-17 The radiation monitor notation was added for clarity.

1 ) Mr. Ed Weinkam Page 3 July 6, 1981 i 3/4 4-35 Error 3/4 11-2 The waste from our condensate dimineralizers will be batched and discharged in accordance with Specification 3.11.1.5 or shipped to a low tadwaste burial ground. 3/4 11-3 The note has been added for clarity. If no i radioactivity can be measured, it will be assumed that there is none present. 3/4 11-4 We will composite grab samples on the steam generator blowdown and turbine building sump rather than continuously sample. 3/4 11-7 This change is to better define the outside storage tanks that will be covered by this Specification. 3/4 11-8 The slurry volume to resin weight ratio cannot be^ assumed to be constant at 100 milliliters / gram i as stated in the bases. However, with these i changes to the Specification, the release will still be in accordance with Appendix I. 3/4 11-9 See Explanation for 3/4 11-8. 3/4 11-11 The main condenser air removal system has been deleted since this discharges through the m.in l plant vent. Item E of this Table has been elimi-nated because the nobic gas radiation monitors do not belong in this Table since they are listed in Table 3.3-13 and Surveillance 4.11.2.1.2 excludes nobel gases. 3/4 11-12 See explanation for change on Page 3/4 11-3. 3/4 11-13 These changes are to clarify the notation in the Table. 3/4 11-16 These limits were chenged to be consistent with 3.11.2.2. 3/4 11-18 During normal operation without failed fuel the amount of radioactive materials being added to the tank is not sufficient to justify analysis i every 24 hours. However, in the event of failed fuel the quality of radioactive material in a tank will be determined each day when radioactive materials have been added to the tank. . _... _,. _. _... _. _. _. -.. _ _.. _ - - _,, _ _ -. ~. _.. _ _, _. _ _ _, _ _. _ _. _ _ _ _. _ _ _

i i Mr. Ed Weinkam Page 4 July 6, 1981 1 4 3/4 12-3 These changes update this table to the current thru 12-12 environmental monitoring program. B 3/4 11-2 See. Explanation for 3/4 11-8. & 11-3 1 5-1 The reactor building is a prestressed-posttensioned reinforced concrete structure. Figure 5.1-4 Mispelled. l 6-3 New plant organization chart to reflect recent changes. The major changes are that now the 1 Health Physics Supervisor, QC Inspection Coordinator, and the Nuclear Training Coordinator report directly to plant management. 4 I Should you have questions concerning these changes, please call me at 803-748-3299. 4 l Sincerely, er%)# Leland Shealy Attachment CC: A. R. Koon 1 ] i i I 4 I l l i - -,... _ _ _ _..., -.. ~... _ _.... - -.,,., _... -,, _. _... -, _. -....

i s-c.m (, . t.).y c. ..e z a .j s i I TAntE 3.3-2 un 5 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 3 a F'UNCTIONAL UNIT RESPONSE TIME E Not Applicable q 1. Manual Reactor Trip 2. Power Range. Neutron Flux $ 0.5 seconds" 3. Power Range, Neutron Flux, il10h Positive Rate Not Applicable 4. Power Range, Neutron Flux, liigh Negative Rate. 1 0.5 seconds * 'i 1 5. Intermediate Range, Heutron Flux Not Applicable l D 6. Source Range, Heutron Flux Not Applicable M 4,cp 3:::= l 7. Overtemperature AT 1 A4'seco. ids" g T l m2 l

  • l I

~' 8. Overpower AT Not Applicable i m 1. O 9. Pressurizer Pressure--Low 1 2.0 seconds I j 10. Pressur'izer Pressure--liigh 1 2.0 seconds I 11. Pressurizer Water Level--liigh Not Applicable 4 i j i gi f* l

=

Q INeutrondetectorsareexemptfromresponsetimetesting. Response time of the neutron flux signal portion l l of the channel shall be measured from detector output or input of first electronic component in channel. g ao e is (n r

O O O v. IAulE 3.3-6 5 { RAOIATION MONITORING INSlRUMENT.'110N MINIMUM E CilANNELS APPLICABLE AtARM/ TRIP MEASUREMENT U INSIRUMLNI OPERABLE MODES SEIP0lNT RANGE ACTION 1. ARLA MON 110RS g,g a. Spent fuel Pool Area (RNG-&) _j 4 1 $ 15 mR/hr 10 - 10 mR/hr 23 b. Reactor fluilding Manioulator S Crane Area (HMG-17A (. 1 6 1 1 R/hr 1 - 10 mr/hr 26 gyg) E m-Gl7A 8 Igactor fluilding Area E -l&3-& - 4 5 -(-)-rad /hr -10 -rad /hc _ __28-c. 2-PROCLS MONI(URS ? b 8-

2,3 4
  • 'MN 3

C u.. g64 by Re-6tP g i, 2, 3 4 g[4 g - s o'r R. /g p_ 26 y w a. Spent fuel Pool Exhaust - D Ventilation System (RMA-6) p -5 6 M if

i. Gaseous Activity R" AT

^^ $ 1 x 10 pCi/cc 10 - 10 cpm 25 q ( Kr-85) u 6 ii. Particulate Activity 1 ^^ c 2 v -l grottnd 10 - 10 cm 25 ~ __. g 2-h. Containment Ts:= i. Gaseous Activity b - Purge & Exhaust 6 Isolation (HMA-4) 1 6 < 2 x background *** 10 - 10 cpm 26 L ra Ra-M ii. P rii ulate Activity i  ; ( t - RCS Leakage 6 Oetection 1 1, 2, 3 & 4 N/A 10 - 10 cpm 24 6 '~ c. Contr RoonNisola tion i ALL MODES -< 2 x background 10 - 10 cpm 27 ua m-A1) '._ s g mU 3:

  • With fuel in the storage pool or building yy M
    • With irradiated fuel in the storage pool

-r) ^^^ Alarm / trip setpoint will be per the Operational Dose Calculation Manual when x,s purge exhaust operations are in progress %m o rg To$ c> rv1 >5 2 --i --t O 31

O O O g IABLE 3.3-6 (Continued) x r} RADIAL 10N MONIl0 RING INSTRtJMLNTAll0N MINIMtJM E CilANNLtS APPLICABLE ALARM /IRIP MEAStlREMENT U If SIHilMI N1 OPERAlli E MODES SLIPOINT RANGE ACIION N ~ PROCISS MONITORS (Continued) NobleGasLitluentMonitorshl:3h Oqe d. -i. W.t ate-lhtiltiinti 2 ._f,xt e r__ System 1 2M-& 4 ( -) rad /hr 10-uCi/cc -28 'J /ht ahtti-ittimj /A 3 t 'I 1 mR/Ar2_ t tratrst-$ystar 1 1, 2, 3 & 4 -( -rad /hr 4-10-teC-i/w 28 (km-Al3 ,d R is iW. T Wne--Lefety Llve od-1 '*"lkR-(-)s/A -1:JO.i -Histturry 1/ valve 1, 2, 3 & 4 -rod /hr. uCi/ m 28 TI y tram acog L,m(Re-Gi9 A,g,c). g H l' -i. AtmospheriMteam-Dtm p- . Live Ili,sd artje velv w l, 2, 3-&-4 (- ) rad /hr 1= 10bret/cc-G &- E 7.! i b.v-Reactor fluilding Purge o: ib Q _{ f Supply & Exhainst Ng o.l S - 28 [ Sys tem ( C.M-A M) j 1 1, 2, 3 & 4 -(-)- ra d/lis' FR L-f.) vi. t'orittense r-fThatis t--- __.hyst a = 1 1, 2, 3-&'t ( ) rad /hr-lo$-stC i/cc -28 {_*j ._.i 'o'~ _t..> .3 L,5-8 ~~.-. 7~ t.,. ~- 7> N ) Z v C. r 1 E5 (.7 2: am 2 iEi >^ .g ---e O 71, s-

O O O g IAllLE 4.3-3 1g RADIATION MONITORING INS'IRUMENIATION SURVEILLANCE REQUIREMENTS I CilANNEL MODES FOR WillCil E CllANNEl CilANNEL FUNCTIONAL SURVEILLANCE El INSiltilHiNi CllECK CALIBRATION TEST IS REQUIRED .a 1. AREA MONIIORS Em-66 a. Spent fuel Pool Area (RMG-e) S R H ^ 13 Reactor fluildtog,M,anipulator S R H 6 Crane Ased ( M 1/A or 178) c. Reactor llisildina -5 -R M-1 Pit 0 CESS MON!10H5M gt;l Area 2 7 ;-3-84 ~ l N a-61 %f. M g h,gt 3 q n 3 7 e, g 4 R4 IE 5 m g i,,8 3gi 2. Spent fuel Pool Exhat3 a. rea - VentilationSystem(HMA'-4) N'D i. Gaseous Activity S R H ^^ ii. Particulate Activ.t*u 5 R M T s 4 w in. Containment A 1. Gaseous Activity - Purge & Exlu g Isolation ( S R H 6 ii. Particulate Activity - HCS leakage Detection S R H 1, 2, 3 & 4 M.N Control Room Isolation (Re-Ah S R H All MODES c.

c S

~^With fuel in the storage pool or building

  • ]

^^With irradiated rasel in the storage pool Gi a 4

O O O l IAlll E 4.3-3 (Continued) o. S$ RADI ATION HONIl0 RING INSTRUMENTATION SURVEILl ANCE REQUIRfhENIS

u CilANNEL H0 DES FOR WHICll E

CllANNEL CllANNEL FUNCIIONAL SURVEILLANCE G INSIRilHINI Clll CK CALIBRATION IEST IS REQUIRLI) e l'ROCLSS HONil0RS (Cont.inued) NolaleGasEttluentMonitors(NhNtag 6 c. -i-Ra t twas tritII t-t it i n g-Ex tra tis t-Sys t em 5 - R --- H 172p _&_4 . % Plant vex (Rm-Atb ( _ lie hHinry-ttttt-triing-txtTatistDtem-S R H 1, 2, 3 & 4 d lii: N$ b dth hh ve Ytsdds,Je S R H 1, 2, 3 & 4 t -iv--Atmost *eric-Steam-Dump-Valve-4 -Iliwhange S R -H-1,-.2 r3-&-4~ f; tU x Reactor Building Purge Sup ly 5 "I & Exhaust System (,RM-A S R H 1, 2, 3 & 4 abComienset"L xhatts t-Sys tem 5 R -M- ~172; &-4 % d x 6-

  • v kk a

T45TRd MSTAT804 fMSHLHENIAIIC?t~ hDI0ACEVELIOUIDEbUENfMONIbflNGINSIkMENhfION N. / LIMI[INGCONDIbONIOY0kEfA) ION 3.3.3.8 lhI radioactive liquid M ueiit> monitoring instrumentation channels shown i(Iabfe>3.3-12 shall be(OPEEABGDwith their alarm / trip setpoints set to ensure that the limits ofcSpecificaucr> 3.11.1.1 are not exceeded. CIbe' alarm / trip _setpoints of these chaniG s'shall be determined in accordance with the d)EESII{DOSECCALCOL IIO!CEANUAL (ODCM). ~ APPLICABILIIY: At all times. ACIION: a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels 02E2ABLE, take the ACIION shown in Iable 3.3-12. c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE '2EQUIREMENIS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPEEABLE by performance of..ie CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBEAIION and CHANNEL EUNCIIONAt. IESI operations at the frequencies shown in Ia' ale 4.3-8. t ] ' M4 fG (L b '43 NY ske Ode SUMME2 - UNII 1 3/4 3-65 NOV 191580 Q :'

o (v (.os-g s g' s s. E o .a >o ) ~ ses TABLE 3.3-12

c. C) sn
-a 9

eo RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION 'g a y L) u U rri g HINIHUM ._., j ['?-- q CilANNELS ~A i INSTRUMENT OPERABLE ACTION ] x D.' 1. GROSS RADI0 ACTIVITY HONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE E_. rO 2($ E C2 a. Liquid Radwaste Ef fluent Line - RM-LSec. c.m-L9 1 337 $Z --i l g j b. Steam Generator Blowdown Effluent Line j .n 1. Unprocessed-during-Power Dperation - RM-LIO oc Rm-L3 1 29, t j -2. Unprocessed-during-Startup .RM't3-9 26 g

2. 3: Processed

'RM-L7 os:. Rm-L9 1 . 34lT) l <a c. Turbine Room Sump Effluent Line - RM-L8 1 30i i ~ h A __ Condensate-Demineralizer-Ef fluent--tine- -RM-L(?)- 1-- --28 p 2. FLOW RATE HEASUREMENT DEVICES a. Liquid Radwaste Effluent Line 1 31 i --b _ Discharge-Canal-(Penstocks-) 1-31- _c.- _ Circulating-Water-Discharge-Canal- --I 31- ~~ .b. d.- 6 team Generator Blowdown Ef fluent Line 1. Unp roc e s s e d -du ri ng - Power-Op e ra t i on 1 31 -2 Unprocessed-during-Startup 1- -31~ 3. Processea 1 31 -e.-- Condensate _Demineralizer-Ef fluent-Line-1 ~31 -- g 3. TANK LEVEL INDICATING DEVICES a, Condensate Storage Tank (1} 32 l ~ u2 U$ i 8

% [f b O] INSTRUMENTATION .Mb Q TABLE 1.3-12 (Continued) TABLE NOTATION ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may - continue for up to 14 days provided that prior to initiating a release: a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, anc b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway. ACTION 29 - With the number of channels OPERABLE less than required by the' Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radica'ctTvity (beta or gamma) at a limit of detection of at least 10 7 microcuries/ gram: a. At leas't once per 8 hours when the specific activity or the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131. b. At least once per 24 hours when the specific activity of = the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131. ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Char ~1s OPERABLE requirement, effluent releases via this pat.% y a ay continue for up to 30 days provided that, at least once per 8 hours, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 aferecuries/ml. ACTION '41 - With the number of channels OPERABLE less than' required by the ~ Minimum Channels OPERABLE requirement, effluent releases via ~ l this pathway may continue for up to 30 days provided the ficw l rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate ficw. ACTION 32 - With the numcer of channels OPERABLE less than required by the i Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid j level is estimated during all liquid additions to the tank,-to na n ,c. rs i b; I SUMMER - UNIT 1 3/4 3-57 NOV 191980 u,_... l

( INSTRUMENTATION () TABLE 3.3-12 (Continued) TABLE NOTATION' " \\ ~ -ACTION-33 With-the number-of-channels-OPERABLE-tess-than_ required.by_the 4 Minimum Channels CPERABLE requirement, effluent releases may j continee for up to 14 days provided Liquid Waste Effluent s 's Monitor RM-L9 is CPERABLE or prior to initiating a release:,/ / / \\, N 'N a. At least two independent samples are analyzed'in accordance with Specification 4.11.1.1.3, and O b. At least two technically qualified me bers of the facility =taff independently verify the release rate calculati. and discharge line valving. Otherwise, suspend release of radioactive effluents via this ~ ,g pathway. ACTION-34-- Witti-the-number-of-channels-OPERABLE-less-than required _by_the Minimum Channels CPERABLE requirement, effluent releases via' x this pathway may continue'for up to 30 days provided Liquid Waste Effluent Monitor RM-L9..is OPERABLE or grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 1.0 7 microcuries/gm: hg , / a. At least once per 8 hours when the specific activity v ,/ of tha secondary coolant is greater than 0.01 ,/ ' microcuries/gm DOSE EQUIVALEN I-131. b. At least once per 24 hours when the specific gravity of the secondary coolant is less than or equal to 0.01 microcuries/gm DOSE EQUIVALENTxI-131. N l i .pdj' SUMMER - UNIT 1 3/4 3-68 j NOV 191980 = ~e = m

( \\,,, ' e.

  • A 4

=; -t TABLE 4.3-8 N1 o en RADI0 ACTIVE iIQUID EFFtUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIRE;1ENTS h$ @ Ei 2: S __. O CilANNEI C CilANNEL SOURCE CllANNEL FUNCTIOML,=, i7 INSTRUMENT CllECK CilECK CALIllRATION TEST ;*j u L>'O 1. GROSS DETA OR GAMMA RADIDACTIVITY HONITORS

--. I ' ~!

PROVIDING ALARM AND AUTOMATIC TERMINATION

.]

0F RELEASE s.. -..; p>

d. Liquid PadWaSte Effluenl5 Line - RM-LS, RM-L9 D P

R(3) Q(1) zu y " fel l

b. Steam Generator Blowdown Effluent Line -

D H R(3) Q(1) p,>, RM-L3, RM-L7, RH-L10 g ..g-- aa l

c. Turbine Room (Floor Dralr.s) Sump H

a Ef fluent tir,e - R>l-L8 0 H R/3) Q(1) -o w h d Condensate gemineralizer #- D -- - -P - R(3) -~~ Q (1). Effluant Line ~R54-L(7) ^ 2. FLCd RATE HE/.SURO1ENT DEVICES i CU

a. Liquid Ratkaste Ef fluent I.ine -

D(4) N./. R Q

  • j g

M,-RHat9 ~ y

b. Steam Generator alcwdcwn D(4)

N.A. R Q Ef fluent Line 5--AH-t3r;;;-; L7, R;; Lle- 'q ---cr-O i scharge-Cans t -(Pens toc ks ) _ _D(4) _. N.A.~__R- --Q-I -d.-CirculatinD-Water-DischarDe-Canal-- -- 0(4) --- N. A_.._ R- 'Q- .s,-Condensate-Demineralizer-Ef fluent-Line--- - D(4) _ _ N. A.__ IL ~ ~~Q~ 2 O p 3. IANK LEVEL INDICATING DEVICES l .o <d

a. Condensate Storaue Tanks D*

N.A. R Q E$

3q w. (O p ) INSTRUMENTATION J TABLE 4.3-8 (Continued) TABLE NOTATION. During liquid additions to the tank. (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates measured levels above the alarm / trip setpoint. 2. C f. w ? t.- failurer-in5YWE Po"Er-2 A' Instrument indicates aMownscale failure. J A. Instrumentcontrolsnotsetinoperatemode.h.c. pg,p (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates measured levels above the alarm setpoint. -2. Circuit-failure. v,dWd f6*"

2.,,3:

Instrument indicates a/sdewnseale failure. l ) r l .3 A: Instrument controls not set in operate mode, b.e-FNey-on (3) The initial CHANNEL CALIBRATICN shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall 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 shall be used. (4) CHANNEL CHECK shall consists of verifying indication of flow during periods of release. CHANNEL CHECX shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. ? i I i rf 1 b SUMMER - UNIT 1 3/4 3-70 NOV 191980 0

L DMFT f*^Nh) 8 (, i N )J t >== Lf1 O O N H CD e4 V: e V H M ar =7 M v v m M M v u i i

  • C l

6 i l i i r . \\ \\ t ~. _ _. - -_ I -J l m CD <C a w l I U W u a a Z >= M W W 4 4C W W O 4 l \\ >== A t. l

  • l

== A dC

  • C

} W Z l W l E 4 3m >= b b M C C Z C C 1 m .e .e M D 4 C.3 J E E Z W o o = Z u u CC ZW QJ c et -J b b Wk -- k % k m

  • =.,-

ne-Z = i 8 C ZW i M Z DA EC SJ m. e Z Z 9 W W = 0 J Q Z C1 - D Ci c w C & 1 { C <C w -m u ) H 6 V

  • S V

W q C", <C, > o > o o L e o m o .m h o .s E. L C = b c C o so a 4 e l s.o W n o m 4 +J W Db C I I I I

  • J

<C m ca o I e m l 6 C c E b c .c e Z L -.u = b c~ W C-L .oJ 0 2

  • a E W

>= +J E O CA W

== b a ( cJ L E b W - b = c 4J A sV C? as W C o C e t b= m E C W oH e oC )== Q m >= A C >= x q) O o Z u E W x-(' U -* 3 74 b tn E, x.J m u cc C.3 x w.J xE o x e C ..c. Z w +J.J W Tv 9= cj l 4.J

  • =

.c W J m{ 7<%^ 0 L ' QJ i c. L >= rc u J 4 c = m cm m - E m h

  • C 1

E 3 9 cc > E *s" <C W > O Cf yb b - D. -c= b c e CK O -e o aC b cc W .o b .o A9 .J c m e 4 .J *a e o u

  • J +*

m o uod z v 2 u=x. J aJ Ju, u ce, W aC a. O Z o C <C *C CC o CC aC aC O

c. W w C

>= A 3 >== C-C ^o cr. i E a 4 Z s Z mVO cW o4 oE i ut 1 e 6 = m7 1 m W W m C ed J> EE Z @4 2 4 W .J f C 9 C W Z >= C 4 aC CW Q >= c 3 b J C "J GJ C.b l< = W e Z CU i G u CK c = m@ CE aC C EE t.3 O C 0 J Cl C a-3 @ E9 C

== )' c.

2

-b Q- >= 3 - L Cg MZ Qb Q ut CC .J 3 L o 55 4 1-T W d @ cC - h h C. W 4 "o ett e= r0 Cd o - CJ Q Z W O-I Cm X% X 3 M O >= 3 Z *C C Qo Qv Z Z = A La. M Q Z aC m a-= c W e= W >= W P-=== Q U M MZ Z eC C

  • C 2x

= .o v = u W = a Q a = C= = \\ a a k ~ m \\\\ A' ef\\ NOV io g3eV Q SUMMER - UNIT 1 3/4 3-72 4 Y ~ + -m. 4 S9 e - + ^ p ,+M--- e-M e- - -ee .a

/~N ,w) A. ]i ( 's. v g TABLE 3.3-13 (Continued) (;C e RADI0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION E HINIMUM CilANNELS U INSTRUMENT OPERABLE APPLICABILITY ACTION e-* _3 4: REACTOR BUILDING PURGE SYSTEM (continued) 41 c. Particulate Sampler 1 36 d. Flow Rate Measuring Device 1 36 e. Sampler Flow Rate Monitor 1 4 5r HAIN PLANT VENT EXilAUST SYSTEM y 37 a. Noble Gas Activity Monitor - RM-A3 1 { b. lodine Sampler 1 41 O M w c. Particulate Sampler 1 41 h

  • "1 d.

Flow Rate Heasuring Device 1 36 % g ~ N Ttc. 36 e. Sampler Flow RateMieasuring-Device-1 I E l ~ j e i N o L

l{$. Ob INSTRUMENTATION I 3 (/ TABLE 3.3-13 (Continued) TABLE NOTATION At all tfmes. clov.n3 re [ccg3 VA N.3 p%

    • Ouring waste gas holdup system operation (treatment for primary system offgases).

ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release: a. At least two independent samples of the tank's contents are analyzed, and b. At.least two technically qualified members of the Facility Staff independently verify the release rate calculations , and discharge valve Ifneup; Otherwise, suspend release of radioactive effluents via this pathway. ACTION 36 - With the number of channels OPERABLE less than required by the-Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow , h rate is estimated at least once per 4 hours. N-ACTION 37 With the number of channels OPERABLE less than required by the Minimum Channels CPERABLE requirement, effluent releases via this pathway may-continue for up to 30 days provided grab samples are taken at least once per 8 hours and these samples are analyzed for gross activity within 24 hours. ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend ~ PURGING of radioactive effluents via this, pathway. e r o v7 e5%4 ACTION 40 - With the number of channnels CPERABLE coehless than required by the Minimum Channels CPERABLE recuirement, IgepJ5)$n of this, Y "j e tio system may continue for up to 14 days. Wit Q cha" rind s i o p A %, Jefoperable, be in at least HOT STAN08Y within 6 hours. ] 3CTION41-With the number of channels OPERABLE' less than required by the Minimum Channels CPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling 8 equipment as required in Table 4.11-2. U, I SUMMER - UNIT 1 3/4 3-74 NOV 19 1980 .m ~

/'N /N / .l -Q s E E J TABLE 4.3-9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 35 -4 CilANNEL H0 DES IN WilICH CilANNEL SOURCE CilANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CllECK CllECK CALIBRATION ' TEST REQUIRED 1. WASTE GAS !!0LDUP SYSTEM

a. Noble Gas Activity Honitor -

Providing Alarm and Automatic Termination of Release - RM-A10 P P R(3) Q(1) 2. WASTE GAS 110 LOUP SYSTEM EXPLOSIVE tJ GAS HONITORING SYSTEM g A wo i%: Tea.o*J p t' f

a. Allydrogen Monitor (upstream D

N.A. Q(4) N.A. ,g y of recombiner) q y cA %de m4TA 4. L

b. Oxygen HonitorA(2ddownstream D

N.A. Q(h N.A. of recombiner) A 0xygen-Monitor-(alternate) - - D N.A. Q(S) N;A. h- * *' -(1-upstream-of-recombiner)-- - - l i GrCONDENSER-EVACUATION-SYSTEM-t 39 T g,/ -a r-Nob l e - G a s Ac t i v i ty - Mo n i to r - - D. ____. _ H _- - R(3) -- ---Q(2) 96 / RM-A9 _b Iodine-Sampler-~- --~ ~~ W N.A. -H.-A. N. A.- ' ' ~- _._c Particulate-Sampler ~ - W- --- N. A. - N.A. H. A.-- ~ 2oj ti.-flow Rate Monitoring Device- -- --- D-N.A. -R- - Q ~ m g -e._ Sampler Flow Rate Monitoring 'D~~ ' ~ N. A.- --- R -~~ - - --Q ' ~~~^' g Device

L( 3 &n

k..,

I g TABLE 4.3-9 (Continued) c M 'RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

u E

CllANNEL MODES IN WilICil G CllANNEL SOURCE CllArciEL FUNCTIONAL SURVEILLANCE INSTRUMENT CllECK CllECK CALIBRATION TEST REQUIRED .3,4. REACTOR BUILDING PURGE SYSTEM

a. Noble Gas Activity Monitor -

ProvidinU Alarm and Automatic Termination of Release - RM-A4 0 P R(3) Q(1)

b. Iodine Sampler W

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

c. Particulate Sampler W

N.A. N.A. N.A. M M a W.9 doce c

d. Flow Rate W itor D

N.A. R Q ^C Y "A M

e. Sampler Flow Rate Monito D

N.A. R Q ^p 9 "'I 4,5: MAIN PLANT VENT EXilAUST SYSTEM M

a. Noble Gas Activity Monitor -

D M R(3) Q(2) RM-A3 b. Iodine Sampler W N.A. h. r. h.A.

c. Particulate Sampler W

N.A. N.A. N.A. Mw osm Daoix o

d. Flow Rate /Nonitor D

N.A. R R

e. Sampler Flow Rate Monitor D

N.A. R R !5 1 co f li5 I b

i t O INSTRUMENTATION Q)/ TABLE 4.3-9 (Continued) TABLE NOTATION Atalltimesdoe.n Hfcsrs b %.s [ day During waste gas h 1 dup system operation (treatment for primary system offgases). (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway ar.d control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates measured levels above the alarm / trip setpoint. -2. Circuit-failure.~ adromT PW 2-3: Instn.4ent indicatesta-downscale failure: ,5 -4.- Instrument controls not set in operate mode.G.e p+ o (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates measured leveis above the alarm setpoint. -2c-- Circuit-feilure. Apg L 3r Instrument indicates &a downscale. failure. 3 Ar Instrument controls not set in operate mode. b.c. poar c> (3) The initial CHANNEL CALIBRATICN shall be performed using one or more of the reference standards certified by tpe National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with N85. These standards shall 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 shall be used. ~- (4) The CHA.NNEL CALIBRATION shall include the use of standard gas samples containing a nominal: 1. One volume percent hydrogen, balance nitrogen, and 2. Four volume percent hydregen, balance nitrogen. / g The CHANNEL CALIBRATION shall include the use of standard gas samples / containing a nominal: 1. One volume percent oxygen, balance nitrogen, and 2. Four volume percent oxygen, balance nitrogen. g 5

REACTOR COOLANT SYSTEM j 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall l i be OPERABLE: a. The reactor building atmosphere particulate radioactivity monitoring systemg(Em-Ag b. The reactor building sump level, and Either the reactor building cooling unit condensate flow rate or a c. reactorbuildingatmospheregaseousradioactivitymonitoringsystem(t+Ab. y APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the contain-O,_ ment atmosphere are obtained and analyzed at lcast once per 24 hours when the s.~ required gaseous or particulate radioactive monitoring system is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD , SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by: ,l a. Reactor building atmosphere particulate monitoring system performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, l ( b. Reactor building sump level performance of CHANNEL CALIBRATION at j least once per 18 months, l c. Reactor building atmosphere gaseous radioactivity monitoring system-perfomance of CHANNEL CHECK, CHANNEL CALIBRATION, AND CHANNEL-- FUNCTIONAL TEST at the frequencies specified is Table 4.3-3 d. Reactor building cooling unit condensate flow detector performanca of CHANNEL CALIBRATION at least once per 18 months. 1 O-SUMMER - UNIT 1. 3/4 4-17' M.2 0 I33I ,--e,- .-m,,._w,e-.-,e n.n -,, n-e,,, m-- ,-,..w,,, ,m,,.,,.wn-,w,,,.y ,,n,,-,,w.m e,-e--, --,n-,.-,, w-,..,n ,m,y

REACTOR COOLANT SYSTEM ( 3/4.4.10 STRUCTURAL INTEGRITY i LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.)10 to APPLICABILITY: All MODES ACTION: a. With the structural integrity of any ASME Code Class I component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temoerature more than 50*F above the minimum temperature required by NOT considerations. b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit cr isolate the affected component (s) prior to increasing t.7a Aeactor Coolant System temperature above 200*F. c. With the structural integrity of any ASME Code Class 3 component (s) s,,.. not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service. d. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REOUIREMENTS 4 i l 4.4.10 In addition to the requirements of Specification 4.0.5, each reactor I l' l coolant pump flywheel shall be inspected per the recommendations of. Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. O" SUMMER - UNIT 1 3/4 4-35 JAN 2 o 03I 1

DRAFTi o, U-TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING A 0 ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLO) Type Frequency Frequency Analysis (pC1/ml), A. Batch Waste P P ~I Release Each Batch Each Batch Principa} Gamma 5x10 d Tanks Emitters 1. Waste -6 I-131 1x10 Monitor Tanks P M Dissolved and One Batch /M Entrained Gases 1x10 5

2. Cend m ate (Gamma emitters)

Saminer41= .izer.Backwesh P M H~3 .-Receiving-Each Batch Ccmposite 1x10 5 b ~7 h-Gross Alpha 1x10 -6 P-32 1x10 ~8 P , Q Sr-89, Sr-90 5x10 b Each Satch Composite Fe-55 1x10 v ~I B. Continuous

  • W Principa} Gamma 5x10 l

Releases -Continuous"~ Composite Emitters C D G4 b k I-131 1x10-6 t

1. Steam Generator M

M Dissolved and -5 1 Blewdown Grab Sample Entrained Gases 1x10 l (Gamma Emitters)

2. Turbine Builging M

H-3 g e 1x10-5 Sump Continuous Composite D 6mh Ap/e. Gross Alpha 1x10 -6 l P-32 1x10 Q Sr-89, Sr-90 5x10 Continuous - Ccmposite" C -6 D Fe-55 1x10 { g,p ,, g l i i I j ri(.jj, SUMMER - UNIT 1 3/4 11-2 NOV 19 1930 l

t. I; m A (j TABLE 4.11-1 (Continued) TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample ~ ~~ a. that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 4.66 sb O* E V 2.22 x 10* Y exp (-Aat) Where: LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), h is the standard deviation of the background counting rate or of s tne counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), ~ V is the sample size (in units of mass or volume), h 2.22 x 108 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), Aistheradioactivedecayconstantfortheparticuiarradionuclide,and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of s used in the calculation of the LLD for a detection u system shall b4 based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E. V, Y, and at shall be used in the calculation. Kdt..? (occe., h b s less % LLD She.Il he oded G5 B tb M oil caema o cc60 d k,l;b/ C a lc o I d u s.~ /U) SU.MER - UNIT 1 3/4 11-3 ~ E I S ISc0 v

a DRAFL TABLE 4.11-1 (Continued)

  • h

. !) TABLE NOTATION b. A composite sample is. one in which the quantity of licuid sampled is ~ proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. Toberepresentativeofthequantitiesandcon;@;entraSignsofradioactive c. materials in liquid ' effluents, samples 'shall b' WE ^d centh::::1y-in proportion to the rate of flow of the effluent stream. Prior to analy:es, all samples takeri for the composite shall be throughly mixed in order for the composite sample to be epresentative of the effluent release. + e d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the 00CM, to assure representative sampling. e. A continuous release is the discharge of liquid wastes of a condiscrete volume; e.g., from a volume of system that has an input flow during the continuous release. f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, - h Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nt+i11 des are to be detected and reported. 4 Other peaks which are measurable and identifiable, together'with the above nuclides, shall also be identified and reported. c d kic. s mplev d d win g. %4 t-e ho le pa$ hc3 cq operde wWew % sq e Ji3doged. 9 T "0V 191980 ] SUMMER - UNIT 1 3/4 11-4

O RADI0 ACTIVE EFFLUENTS LIOPIO HOLOUP TANKS J LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material cantained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. e l d,54crageTank a. Condens rage Tanks ! f 03 f,$" M'! m #y, b. Outs k'.","l"

kbOEf,

"- ' ' - ".'.t )..; i i f,3,p,;. g, g$ Q, i Tl f.2MT,7' L[h'[C["P APPLICABILITY: ta times. j ACTION: g With the quantity of radioactive material in any of the above listed a. tanks exceeding the above limit, immediately suspend all additions or radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ] SURVEILLANCE RE00IREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above Ifmit by analyzing a representative sample of the tank's contents at least ence per 7 days when radioactive materials are being added to the tank. l ( l O1 i s SUMMER - UNIT 1 3/4 11-7 NOV 191980 I o

RADI0 ACTIVE EFFLUENTS SETTLING POND LIMITING CONDITION FOR OPERATION ^ - - - - 3.11.1.5 The quarititiof radioactive materiaFc~ontained in each settling pond shall be limited by the following expression: h- < 1.0 excluding tritium and dissolved or entrained noble gases, where, 9 Aj = Pond inventory limit for single radionuclide "j", in curie. j = 10 CFR 20, Appendix B, Table II, column 2, concentration for single radionuclide "j", microcuries/ml. V = design volume of liquid and slurry in the pond, in gallons. 264 = Conversion unit, microcuries/ curie per milliliter / gallon. APPLICABILITY: At all times. ACTION: k With the quantity of radioactive material in the settling pond a. exceeding the above limit, immediately suspend all additions of radioactive material to the pond and within 48 hours reduce the pond contents to within the limit. b. The provisions of specifications 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REOUIREMENTS l l 4.11.1.5 The quantity of radioactive material contained in each batch of slurry (used powdex resin) to be transferred to the settling ponds shall be determined to be within the above limit by analyzing a represaatar.ive sample of the slurry, and batches to be transferred to the settling ponds shall be limited by the expression: b < -6d)-x-105-oCi/om O,ocg I C _pci/mL y 4 e ( ) SUMMER - UNIT 1 3/4 11-8 NOV'19 1980 e

  • nw

I l RADI0 ACTIVE EFFLUENTS j j j C SURVEILLANCEREQUIREMENTS(Conf.inued) O = concentration of radioactive materials in wet, h ein d slurry (used f powdexresin)forradionuclide"j"excludjngytritium, dissolved or entrained noble gas and radionuclides wit (gcaatar than 8 day half-Iffe. The analysis shall include at least Ce-144, Cs-134, Cs-137, Sr-89, Sr-90, Co-58 and Co-60 in-picocuries/ gram-(9 gge ). N w ->es/.g.n te,. Cj = 10 CFR 20, Appendix B, Table II column 2 concentration for single radionuclide "j", in microcuries/ milliliter. kdfc TF $0rVf b prucip/4. 8-94Ters resoA. n J efedab[. odway y+6r -% Te no LLb' t/clus TLde 4.11-l, FDr% oel s,.s 6r n % -t'- ea.Ifig m y nsoiopes,s nst rey, red ad acfddy is nst cus,dorf pre oJ m k s Drry, s em v 1 i l e,,/ SUMMER - UNIT 1 3/4 11-9 NOV 19 1580

nO ,Q v,)o y e ~ a TABLE 4.11-2 i RA010 ACTIVE GASEQUS WASTE SAMPLING AND ANALYSIS PROGRAM ij i h Hinimum Lower Limit of Sampling Analysis Type of Detection (gLD) M Gaseous Release Type Frequency Frequency Activit Analysis (pCi/ml) l ~4 U 1x10 A. Waste Gas Storage Each Tank Each ank Principal Gamma Emitters -4 Tank Grab Sample g a""I ~4 D b c-9 1x10 B. Reactor Building Eac Purge [~EachPurge; Principal Gamma Emitters i .uroe Grab -6 a Sample 11-3 1x10 0 ~4 N Principal Gamma Emitters 1x10 C. Main Pla %e M Ozl'I" Sample 11-3 1x10~0 d -12 D. Iodine and Parti-Continuous # W 1-131 1x10 culate Sampler Charcoal -10 w) Sample I-133 1x10 I d 0 -11 0

1. Reactor Building Continuous W

Principal Gamma Emitters 3xjg Purge ' Sampler Particulate (I-131,Others) Sample

2. Main Plant Vent

-Il i Continuous # M Gross Alpha 1x10 Sampler Composite Particulate Sample ( C6 Lihuous' Q $r-89 75r*90 - -3x10 ""S"# n Sampler _ -composite ) " / g _.AirJ enoval System-- Particulate < ample I ~0 I --Er-Noble _ Gases - All Con ti nuous -- Nobl e-Ga s-Nob l e - Ga s es - 1x10 r deJease_ Types-as MonitoV Gro W Beta &' Gemma, C listed in A.-8,--and-a ~ G ove 1* Waste Gas Storage-Tan k o n 2.. Condenser _Vaccuum-Exhaust g s g

3. Auxiliary Building Exhaust 47FiiEl llaiidling: Building-Exhaust e..

TABLE 4.11-2 (Continued) \\/ TABLE NOTATION ~ a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. - For a particular measurement system (which may include radiochemical separation): 4.66 sb LG - E V 2.22 x 10* Y exp (- M t) Where: LLD is the "a priori" lower. limit of detection as defined above (as microcurie per unit mass or volume), s is the standard deviation of the background counting rate or of t.e counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as, counts per transformation), [ V is the sample' size (in units of mass or volume), d 2.22 x 108 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environ = ental samples). The value of s used in the calculation of the LLD for a detection system shall bN based on the actua~1 observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of.E, V, Y, and at shall be used in the calculation. %he, bn(96fta 36^5 bss $c.n U-D Skg O he e rtd. O i acto m q H c sce 4 tol;ih h/ caltJkh 6-l i .R SUMMER - UNIT 1 3/4 11-12 NOV 1 9 I980 l -y-r -.,m-p p p- - -,, - - -g ,y.,-,w.-, r

L h TABLE 4.11-2 (Continued) TABLE NOTATION b. Analyses shall also 'be performed following~ shutdown, star' tup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL PCWER within a one hour period,o hen p w p i ,,n pmyg, c. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is ficoded, abon pg o,o pqress. d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL PCWER in one hourTand analyses shall be ccepleted within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust frora the spent fuel pool area, whenever spent fuel is in the spent fuel pool. f. The ratio of the sample floe rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3. y g. The principal gamma emitters for wnich the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported. I y'? C db Y ht>c>s. n o G{p y plad % l b m y, g % k m M.$ p g.E p p. is m p 7 ss, i i (- ( i .s SUMMER - UNIT 1 3/4 11-13 NOV 19 1980 l

~ (Q) RADI0 ACTIVE EFFLUENTS M/ GASECUS RADWASTE TREATMENT ) LIMITING CONDITI N"EdR OP$RIT[dA"' ] i 3.11.2.4 The GASEOUS RADW(STE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be JPERABLE. The appropriate portions of the GASEOUS RA0 WASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releas_es from the site (see Figure 5.1-3), when o,g,2,-ave ~ raged over 3Tliys, would exceed 0$r mrad for gamma radiation and GA trad for beta radiation. The appropriate portions of the VENTILATION EXHAUST ll] TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-3) when averaged over 31 days would exceed Q Epprem to any organ. o.83 APPLICABILITY: At all times. ACTION: a. With the GASEOUS RA0 WASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission within 30 days, J pursuant to Specification 6.9.2, a Special Report which includes the V following information: 1. Ider.t.ification of the ino'perable equipment or subsystems and the reason for inoperability, ' 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3. ' Summary description of act.3n(s) taken to prevent a recurrence. b. The provisions of Specificatio..s 3.0.3 and 3.0.4 are not applicable. SUrtVEILLANCE REQUIREMENTS . :~ _~. r _Z1. 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the CDCM. 4.11.2.4.2 The GASEOUS RA0 WASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RA0 WASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. (O.*h SUMMER - UNIT 1 3/4 11-16 NOV 191380 ...e em =*

  • =pa

O RADICACTIVE EFFLUENTS D GAS STORAGE TANXS g .,..._m--u,..- LIMITING CCNOITION FOR OPERATION - 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 60,000 curies noble gases (considered as Xe-133). APPLICABILITY: At all times. ACTION: a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS O, j 4.11.2.6.lThe quantity of radioactive material contained in each gas storage V,y tank shall be. determined to be within the above limit at least once per 24-7 cbg3 . house when radioactive materials are being added to the tank. ~ho. eved of 6 drMed bel b"E I [ttt., 4.ll.2.lo,2. %1 pMdtf eF todmadA mc.brMl c d4;nd i n eack u) o3-{e._ 393 o 6b -Yd'o t $ k l{ b e e bP4ne E G ~ in 'fb e 41oJR L d Leo d ome.per 24 kom e ken to &ced e dr s 4 e IMC lee a d d e d b M e hce n t ibe p RJte,o.s 24 hors. n in t l m l l l U~ SUMMER - UNIT 1 3/4-11-18 NOV 191980

(m) r ("A n(,) / .u I kY g&i k 3 ' [Ld I TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM io VIRGIL C. SUMMER NUCLEAR STATION N 'N g s q. Sample s Criteria for Locations i Exposure Pathway Selection of Sampling and Loca-f ype and frequency T and/or Sample . Sample Locations ** Collection Frequency tion (1) H_1/Dir of Analysis. N / 1. AIRBORNE 'x / x I. Particulate A 3 Indicator samples Continuous sampler 2 1.1 SW Gross heta follow- ~ 1 . to be taken at operation with 5 1.3 SE ing filter chan0e; locations (in weekly' collection. 10 2.4 NNE Hor.thly composite different sectors (by location) for beyond but as ganna isotopic. practicable where the highest offsite sectoral ground .M level concentra-C N< N [ tions are 'N "M anticipated.g) 'N B 1 Indicator sample 6 1,1 ESE M to be taken in the 'N s sector beyond as 'N close to.the exclu-N' sion boundary as / practicable cor-responding to the residence having the hf0 hest anti-cipated offsite ground level con- _,.g centrgonor da5' (O 1 (N

k I l t J TABLE 3.12-1 (Continued) 1 E

j Sample in l

Criteria for Locations [ N Exposure Pathway Selection of Sampling and Loca-Type and Frequency 3 and/or Sample Sample Locations ** Collection Frequency tion (1) Hl/Dir of Analysis ./- _a x I4) AIRl10RNE N C 1 Indicator sample 14 5.2 W ~ i (continued) 'N. to be taken at the - N location of one of the dairies most s 'likelytoggg) affected. i D 2 Contro1' samples 17 24.7 SE to be taken at ,,i locations at least 16 28.0 W g 10 air alles from b ,g the site and not,in the most preval winddirect. ion. ggt q 7 I w II. Radioloaine A 3 Indicator' samples Continuous sampler 2 1.1 SW Gamma isot'opic to be taken at two operation with weekly 5 1.3 SE screening 'of all loci.tions as given cannister collection.~~ [ o. 2.4 NNE with conjunctive i n i. t'. above. screening of the x two controls. If ,'s screening is posi-tive, each sample will be subjected .\\ / 's to isotopic Nanalysis for / / iodine. N d,,/ \\ l B 1 Indicator sample 6 -1.1 ESE to be taken at the \\

n

,S location as given \\ 4 in I.81 ab<ve. 40 g c) I e

O O O J TABLE 3.12-1 (Continued) E Criteria for locations Exposure Pathway Selection of Sampling and Loca-Type and Frequency,- and/orsSample Sample tocations** Collection Frequency tion (1) Ml/Dir of Analysis ' c.% /' \\x'N C 1 Indicator sample 14 5.2 W ',/ H to be taken at the ,M location as given in I.C above. ~ ' Control samples 16 28.0 W D 2 to be'taken at g~ g locations similar b in nature to A-C above. "M 1.s III. Direct A 5 Indicator samples Monthly exchange.( ) # 's 2, 5, 6, 10, Gammadg =s9 + to be taken at the' Two or more dost-and 14. monthly

===={ g locations as given meters at each loca- ,4 in I.A throu0hD tion. above. B 3 Additional indi-1 1.3 S cator samples to 4 1.2 NW be taken in sectors .8 1.3 ENE / different from III.A above, beyond but as close to the exclusion boundary as practicable. C Control samples to 16 28.0 W be taken at the 17 24.7 SE g locations as given 'N in 1.0 above. s, 'N (D 7 O 2 ,.:. e

O O O i r 1 v.V. ws-i g TABLE 3.12-1 (Continued) 3 g N Criteria for 'ocations Selection of Sampling and a-Type and Frequency Exposure Pathway . *I and/or' Sample Sample Locations ** Collection Frequency uon(1) Ml/Dir of Analysis i c ~ N D 1 Additional con-18 16.5 5 N trol sample to be taken at a loca- / ' stions as set forth / 1 in I.0 above. / f l WATERBORNE \\ I 21(3) (6) 2.7 SSE Ganna isotopic with I IV. Surface Water A 1 Indicatorssample Time composite ' quarterly composite be taken at a' samples with i location which collection every (by location) to be analyzedgr allows for mixing month (corresponds tritium.g and dilution in toUSGScont.ingys w2 the ultimate sampling site receiving risar., / g i a D B 1 Control sample 22(3) 12-15 NNW ~ [E to be,taken at a location on the re'ceiving river, !,I l ,- sufficiently far l upstream such that no effects of g / pumped storage j operation are anticipated. /, s [ C 1 Indicator sample 17 24.7 S 's = location imme-N ' l diately upstream i of the nearest ~ = downstream munici-pal water supply g O l I i -m

s I i i J TAB 1.E 3.12-1 (Continued) 0 h Locations Criteria for x Exposure-Pathway Selection of Sampling and Loca-Type and Frequency and/or Sample Sample tocations** Collection Frequency tion (1) Hi/Dir of Analysis c5 \\ a v. D 1 Indicator sample Grabsaging 23(3) <1 E As in V above. to be taken in the monthly j y[ j upper reservoir '~.. of the pumped ,,/ i storage facility. ,/ i, I3) E 1 Indicator sample 18 16.5 5 to be taken in the '/ upper reservo'ir's non-fluctuating / recreational area. I \\"O ] F 1 Control sample to s- 18(3) 16.5 5 00) i:

  • di.9 be taken at a loca-my tion on a separated

'( '^ed e

==-.acj N unaffected, water-shed re,servoir. t V. Ground Water A 2,IndicatorsamplesQuarter1{ygrab 26 Onsite Gamma isotopic and ,to be taken within sampling 27 Onsite tritiumangses ,/ the exclusion quarterly / boundary and in the direction of / protentially affected ground . water supplies. B 1 Control sample 16 28.0W from an unaffected location. \\ ,a<* e* u2 (O$

.I g M J TABLE 3.12-1 (Continued) Q e c x . Criteria for Locations / 5 Exposure Pathway Selection of Sampling and Loca-Type and Frequ_ency H and/or Sample Sample Locations ** Collection Frequency tion (1) Hl/Dir of Analysis x / WATER 00RNE, ' N 8 1 Control sample 16 28.0 W ,/ l (continued) from an unaffected location. f' s VI. Drinking Water A 1 Indicator sample Monthlypgjb, 28 / 1.3 ESE Honthly(5) Gamma nearby public samplinD '/ isotopic.and gross ground water ,./ Detaanalggsand supply source. quarterly tri-f' tium analyses 8 1 Indicator Monthly gb 17 24.7 5 (finished water) saapitag N m P{ 2 sample from the / nearest downstream,/ m ';3 water supply.

  • s Ch

/ I0) INGESTION A 1 Indicator,sabple Semi-monthly when 14

5.. V Gamma isotopic and VII. Hilk(5) to be taken at the pasture,gggon monthly [83*"I~

animals ana!ysi location'0:' one of othertimes.pggthly the dafries most when animals are likely to on past [affected.ggIb) g;at monthly other times / 7' B 1 Control sample to 16 28.0 W be taken at the j ,/ location of a diary 1 [' 10-20 miles dis-tank and not in the most preval 3 winddirection.g l l g 'N tab l t +, ,e

l \\ i TABLE 3.12-1 (Continued) I g g m* 3 Criteria for Locations _ _ Exposure Pathway Selection of Sampling and Loca-Type and frequency l E and/or Sample _ Sample Locations ** Collection Frequency tion (1) Hi/Dir of' Analysis G N \\C 1 Indicator. grass Monthlywg 6 1.1 ESE amma Isotopic ~ N (for age) sample available ' l 'Nto be taken at y one of the loca- / tio'ns. beyond but / i : as close to the ~ !I exclusio'n boundary y l as practicable where the highest offsite sectoral N ground level con-i .y centrations g I anticipated. -1 g 4 VIII. Food Product: A 1 Indicator semple Annually at the 6 1.1 ESE Gamma isot'pic on- ~ o to be taken at a approximate median edible portion. I l nearby Garden harvest time for Radiofodine on likely to be the area. Samples. Green leafy e f fected. if available, will vegetables. include: green leary, fruit, and grain. I) B 1 Control sample 18 16.5 S I for the same foods taken at a location at least 10 miles distant and not in the most prevalent wind direction. a Ny m s O O

l p j TABLE 3.12-1 (Continued) 55 Criteria for Locations l Exposure Pathway Selection of Samplin0 and Loca-Type and Frequency ~ and/or' Sample Sample Locations ** Collection Frequency Lion (1) Hi/Dir of Analysis I) I3) IX. Fish A 1 Indicator sample Semi-annual 23 0.3-5 Gamma-isotopic on to be taken at a collection of the edible portions location in the following specie semi-annually ' upper reservoir. types if available; x' bass, bream, crapple; 's, catfish, carp; forage t '\\ fish (shad). INGESTION, 8 1 Indicato sample '21I) 1-3 (continued) to be taken at a x location on the receiving river, N D w D sufficiently far D g upstream such that }5

  • , s, no effects of s

o pumped storage %) operation are anticipated. s i AQUATIC X. Sediment A 1 Indicator sample Semi-agalgrab 23 0.3-4 Gamma isotEpic( ) I) to be taken at a sample location in the upper reservoir. I) AQUATIC, 8 1 Indicator sample 24 4-5 N, ' (contin'ed) to be taken'in the u f upper reservoir's non-fluctuatinD \\ f, reactional area. y 4. Y N ii. N 4 \\ f; 8 ! e i

i. n f b Q-O j TABLE 3.12-1 (Continued) \\ M \\ Criteria for Locations Exposure Pathway Selection of Sampling and Loca-Type and Frequency and/or Sample \\ Sample Locations ** Collection Frequency tion (1) Hi/Dir of Analysis 2 x U AQUATIC N C 1 Indicator sample 24(3) 4-5 N \\'shorelineofthe (continued) to be taken on the i ~ lower reservoir. I3) D 1ContrAlssamp1eto 22 12-15 l be taken in' receiv-ing river, suffi-i ciently far ups-stream such that no effects of C pumped storage W ,g operation are p anticipated. M S Location numbers refer to figures in the ODCH. (2) Sample site locations are based on the meteorological analysis for the period of recrod as presented in Chapter 5 and 6 of the FSAR. I3I Though generalized areas are noted for simplicity of sample site enumeration, airborne, water, and sediment sampling is done at the same location whereas biological sampling sites are' generalized areas in order to reasonably assure availability of samples. (4)Hilking animal and garden survey results will be analyzed annually. Should the survey ihdicate new dairylpg activity of a significant nature (5 or more cows milking) in a quadrant (s) other than W or NW- "and closer than 5-7 miles,,the owners shal.1 be contacted with regard to a contract for supplying I lufficient samples. If contractural arrangements can be made, the site (s) will be added for additional mi}ksampling. 2 3 (0)Not to exceed 35 days. (6) Time composite samples are samples which are collected with equipment capable of collecting an ~ <o m aliquot at time intervals which are short (e.g., hourly) relative to the compositing period. 8

\\ Q O) D Q...g ,. s t s s i I M j TABLE 3.12-1 (Continued) l

c i

IIAL least once per 100 days. y (8)At least once per 18 days. i (9)At least once per 200 days. l NOTE: Deviations from this 'samplino schedule may occasionally be necessary if sample media are j unobtainable due to hazardous conditions, seasonal unavailability, insufficient sample size, malfunctions of automatic samplin0 or analysis equipment and other legitimate reasons. If specimens are unobtainable'due to samplirg equipment malfunction, every ) effort shall be made to complete corrective-action prior to the end of the next sampling period. Seviations from sampling-analyses schedule will be described in the annual report, t / pJ c=- ~ ) x v1 's

==s-I .m u m .~'s / NN 'O l ' C3 4 i s. q' , i, I t. .i t to ,~ _.g o i t 1. L

I TABLE.! 3.12-1 (.__ RADIOLOGICAL ENVIRONt! ENTAL MONITORING PROGRAM l VIRGIL C. SUMMER NUCLEAR STATION l I Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca-Type and Frequency of j and/or Sample Sample Number and Location Collection Frequency tion (l) Mi/Dir Analysis i AIRBORNE I. 'Particulates A 3 Indicator samples to Continuous sampler 2 1.1 SW Gross beta following be taken at locations operation with 5 1.3 SE filter change; Monthly (in different sectors) weekly collection. 10 2.4 NNE composite (by location) beyond but as close to for gamma isotopic. the exclusion boundary as practicable where the highest offsite~ g sectoral ground level 4 ' concentrations are anticipated.(2) s s 7 { B 1 Indicator sample to be 6 1.1 ESE w taken in the sector be-yond but as close to the exclusion boundary as practicable correspond-i , ing to the residence having the highest anticipated offsite ground level concentration or dose.(2) b) C 1 Indicator sample to be 14 5.2 W taken at the location of l' one of the dairies mos g g) likely to be affected. i t t t

f% r ~ ~ ~' -p TABLE 3.12.1' (Continued) i Sample - - ' '~ Locations Exposure Pathway Criteria'for Selection of Sampling and Loca g Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis AIRBORN E,' D 2 Control samples to be 17 24.7 SE (continued) taken at locations at least 10 air miles from 16 28.0 W the site and not in the most prevalent wind directions.(2) II. Radioiodine A 3 Indicator samples to Continuous sampler-2 1.1 SW Gamma isotopic screening be taken at two loca-operation with weekly 5 1.3 SE. of all five indicators tions as given in I.A cannister collection. 10 2.4 NNE-with conjunctive screen- 'above. ing of the two controls. If screening is positive, \\ each sample.will be sub-jected to icotopic analysis for iodine. N ~.1 ESE B 1 Indicator sample to 6 1 Y be taken at the lo-cation as given in I.B above. s C 1 Indidator sample to be 14 5.2 W taken at the location as / given in I.C above. D 2 Control samples to be 17 24.7 SE taken at locations similar in nature to A-C 16 28.0 W i above. 9

TABLE 3.12.1' (Continutd) i Exposure Pathway Criteria for Selection'of Sampling and Sample Locations Typh'iEd~ Frequency of~ and/or Sample Sample Number and Location Collection Frequency Location Mi/Dir Analysis 4

AIRBORNE,

(. antinued) III. Direct A. 5 Indicator samples to Monthly exchange.(5) ge s 2, 5, 6, 10, Garma dose monthly (5) be taken at the loca-Two or more dosi-and 14 tions as given in I.A meters at each through D above. location. B. 3 Additional indicator 1 1.3 S samples to be taken in 4 1.2 NW sectors different from 8 1.3 ENE s III.A above, beyond but as close to the exclu-sion boundary as j - practicable. C. Control-samples to be 16 28'.0 W +' taken at the locations 17 24.7 SE 3 R3 as given at I.D above. 4 I }Ut D. 1 Additional control 18 16.5 S sample to Lc taken at a location as set forth in I.D above i E. Additional Sites 3 .8 WSW' 7 1.7'E i 9 2.6 NE 11 3.6 NNE j 12 4.3 N i 13 2'.9 NNW 15-2.3 SSW 19 117.9 ESE I 20 22.0 NW F. Accident Evaluation . Quarterly exchange.(5) 41 3.7 s Gamma dose quarterly. Quarterly Exchange (7) Two or more dosi-42 3.6 SSW j Program meters at each 43 4.7 SW location. 44 2.3 WSW 45 5.4 WSW 46 3.7 WNW l 47 1.0 NW i

TABLE !3.12.1 (Continusd) i , i Exposure Pathway Criteria for Selection,of Sampling and ^ Sample Locations" Type and Frequency of and/or Sample' Sample Number and Location Collection Frequency, Location Mi/Dir

  • Analysis
AIRBORNE, I

(Continued) III. Direct 'F. (Continued) 48 2.4 NW' 49 4.6 NNW i.> - 50 5.6 N - 51 5.6 N s 52 4.3 NNE 53 3.6lNE a 54' 2.2 ENE. i .55 3.2 E ~ 56 2.0 ESE {', .57 2.7 SE

  • a

,58 2.4 SSE 1, 59 2.1 SSE h-I, 60 5.7 WSW )o .c-p i. ? ~. w s lf D 8 e. WATERBORNE V l' ~. l IV. Surface A. 1 Indicator sample to Time composite samples. 21(. 3) (6) 2.7 SSE Gamma isotopic with quarterly composite (by Water be taken at a location with collection every i which allows for mixing month (corresponds to location) to be analyzed for tritium.(7) I USG'cognuoussampling - and dilution in the 'y site). '," ). ultimate receiving '/ river. ..y-r ;, i i te r. .h. 9 ,e r p , 0,* ?,r. { 4 e a .a i i: i .r. ,U f,,_ i p .e. t j

V v j ( b _.....- I TABLE 3.'12-1 (Continusd) t 3 Locations Exponure Pathway' Criteria for Selection of Sampling and Loca-Type and Frequency of tion (1) Hi/Dir Analysia and/or Sampic Sample Number and Location Collection Frequency 22(3) 12-15 NNW. WATERBORNE, B 1 Control sample to be (continued) taken at a location on the receiving river, suffi-cientl'y far upstream such that no effects of pumped g storage operation are 4, anticipated. ./ 24.7 5 17 C 1 Indicator sample from location immediately t upstream of the nearest downatream municipal water supply 1 23(3) <1 E As in V above. (( D 1 Indicator sample to be Grab samp(ling taken in the upper reser-monthly 5) I i 'O voir of the pumped storage facility. 24(3) 4.7 N E 1 Indicator sample to be taken in the upper reser-t voir's non-fluctuating recreational area. 18(3) 16.5,5 F 1 Control sample to be taken at a location on a separated unaffected watershed reservoir. 26 Onsite Gamma isotopic and grab V. Ground Water A 2 Indicator samples to Qua rterly(7) 27 Onsite tritium analyses be taken within the ex-sampling quarterly.(7) clusion boundary and in the direction of poten- ] l tiall,y affected ground vater supplies. i

p, Q fT t TABLE, 3.12-1 y pCentinurd) l i Sample Locations Expooure Pathway Criteria for Selection of Sampling and Loca-Type and Frequency of and/or Sainple Sample ilumber and Location.

  • Collection Frequency tion (1) ML/Dir Analysis I ^

I WATERDORilE, B 1 Control sample from an 16 28.0 W l i (tontinued) unaffected location. s VI. Drinking A 1 Indic$ tor sample from. Monthly grab Honthly(5) garna inotopic Water nearby public ground samplingt5) 28 1.3 ESE and groao Bct nalyaco g water. supply source. and quarterly tritium analyses 1-24.7 S B 1 Indicator (finished Monthly grab water) sample f rom the samplingt5) t' neareut downstream water supply. IliGESTIOtt

  • VII. HL1k(5)

A 1 Ii.dicator sample to Semi-monthly when ,;,14(4)' 5.2 W , Gamma footopic and I.g be taken at the location animals grq on J analysis semi-monthly pasture,l81 monthly whenanimalsare(o$,e 5 of one of the dairies other times.(5) pasture;. monthly l most like try e other times affected. Id 16 28.0 W D 1 Control sample to be taken at the location of a dairy 10-20 miles dis-tant and not in the most prevalent wind direction.(2) 4 C 1 Indicator grass (for-Monthly when available(5) 6 1.1 ESE Gamma Isotopic age) sample to be taken at one of the locations beyond but as close to the t exclusion boundary as i practicable where the highest offatto sectoral ground level concentra-ti onsi are anticipnted.(2) t

.~. - -, - - -..- -

.f (; .f .e 4 s TABLE 3.12-1 '(Continued) I ~l-'"'~~~~ ~ Sample Locations 3* Exposure Pathway Criteria for Selection of Sampling and Locag#. Type and Frequency of j and/or Sample Sample Number and Location' Collection Frequency tion Mi/Dir Analysis INCESTION, D 1 Indicator grass- (for- " 14 (4) 5.2 W 4 i (continued) age) sample to be taken l at the location of VIII.A above when animals are on pasture. I 's j E 1 Control grass (f rage) i , sample to be taken at the l location of VIII.B above. 16 28.0 W [ i;Q VIII. Food A 1 Indicator sample to be Annually at the 6 1.1 ESE Gamma isotopic on edibic Products taken at a nearby garden approximate median, portion. Radioiodine on l likely,to be affected. harvest time for green leafy vegetables. j the area. Samples,'. i s

N if available, will,

^ i I include: green j 4 i4 leafy, fruit, and-grain. t i B 1 Control sample for the 18(3). J 16.5 S j same foods taken at a (- l ( location at least 10 miles j distant and not in the 3 'most prevalent wind di-i i e. 4 rection. .t-I IX. Fish A 1 Indicator samp1'e to be Semi-annual (9) collec-23(3) -~ ' 0.3-5 Gamma isotopic on edible i taken at a location in tion of the following portions semi-annually I the upper reservoir. specie types if available:' I bass, bream, crappie; catfish, carp; forage fish (shad). ~. I i; i i. ] e

f 's , 2: _ D I a

s..

1 " ""* } TABLE 3.12-1 t Sample' Locations Exposure Pathway Criteria for Selection of Sampling and Locag Type and Frequency of l and/or Sample Sample Number and Location Collection Frequency tion H>iDir' Analysis INCESTION, B 1 Indicator sample ' to be 21( ) 1-3 (continued) taken at a location in the, lower reservoir 2,2, C 1 Indicator sample 'to be 24(3) ' 4-5 N ' ~ taken at a location in the ~ upper reservoir's non-fluctuating' recreational area. i

i

%e i ) t

s i ha 22( )

12-15 NNW D 1 Control sample to be r i taken at a location.on ~' i the receiving river, I sufficiently far up-- stream such that no effects l j of pumped storage operation are anticipated. i t <s AQUATIC y i . X. Sediment A 1 Indicator sample to be Semi-annual grab Gamma is~otopic (3) 0 23(3) 0.3-4 taken at a location in sample (9) the upper reservoir., ,L e b , ~,

b_ _ {' \\ 'f 7 1 -(Continued) L...._....._... TABLE 3.12-1 6 { l-_-

  • * = -

+ t Sample Locations Exposure Pathway Criteria for Selection of Sampling and Locag Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis AQllATTC B 1 Indicator sample-to be '24(3) 4-5 N (continued) taken in the upper reser-voir's non-fluctuating s <cireational area. 4 C l~ Indicator sample to be ' 21( } l-3 i taken'on the shoreline of the lower reservoir.' I3) D"'l Control sample to'be 22 12-15 taken in receiving river, sufficiently far upstream '., / s M such that no effects of d pumped storage operation .', i. are anticipated.. j j a ' - - ~ Location numbers refer.to Figures 3.0-1 and 3.0-2 in the ODCM. ~ (2) Sample site locations are based on the meteorological analysis for,the period of record as pres'ented in Chapters 5 and 6. t (3) Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment 3 5 i sampling is done at the same location whereas biological sampling sites are generaliz'ed areas in. order to 3 4 reasonably assure availability of samples. J .g j t t e

' ^ ' ', ( '- - i ^ ' ' 4 TABLE 3.12-1 k(Continued) f I._..,._....._.__..._..... 5 (4) Hilking cnimal and garuen survey results will be analyzed annually.- Should the survey indicate new dairying activity of a.significant n'ature-(5,or more cows milking) in a quadrant (s)-other than,W or tN and closer than; 5-7 miles, the owners shall be contacted with regard to a contract for supplying sufficient samples. If t contractural arrangements can be:made, the site (s) will be added for additional milk sampling. 9 (5) Not to exceed 35 days, I O (6) Time composite samples.are samples which are collected with equipment capable of collecting'an aliquot at 'A l time intervals which are short (e.g'. hourly) relative to the.compositing period., (7) At least once per 100 days. hg 7.' (8) At least once per 18l days. 1 . - s a +:c r. (9) At least.once per 200 days. T- - .c 1 i Q NOTE: ' Deviations from this sampling scliedule may occasionally be necessary if sample media ai e. unobtainable l ( . due to hazardous conditions, seasonal unavailability, insuf ficient: sample size, malfunctions of auto-l .matic sampling or analysis equipment and other legitimate reasons. If specimens are unobtainabic due i 1 to sampling equipment malfunction, every ef fort shall be made to complete corrective action prior to the' j C end of the next sampling period., Deviations from sampling-analyses schedule will be described in the { annual report. s. s. i i ) P } g r I ,,4 ) d g-D g \\ f

  • .j

/ s s o 2, I ) f g s i ?-- q 8 y*

L RADI0 ACTIVE EFFLUENTS 1" ..h BASES 3 . _ _ _ _ _ _ _ _ _ _ _ _. ~ 3/4.11.1.3 LIQUIC VASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures thet this system will be available for use whenever liquid effluents require treatment prior to release to the environmen'.. The requirement that the appropriate portions of this systes be used when specified provides assurance that the releases :f radioactive materials in liquid effluents will be kept "as low as ~ is reason.aly achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction 3f the dose design objectives set fwth in Section II. A of Appendix I,10 CFR Part 50, for liquid effluents. 3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantit9 of radioactive material contained in the specified tanks provides assurance that in the avent of an uncontrolled re* ease of the tanks' cc: Ants, the resulting concentrations would-te less than the limits of n 10 CFR ? art 20, Appendix 8 Table II, Column 2, at the nearest potable water Vm supply and the nearest surface water,' supply in an unrestricted area. G 3/4 11.1.5 SETTLING PON05 The inventory limits of the settling ponds (SP) are based on limiting the consequences of an uncontrolled release of the pond inventory. The expression in Specification 3.11.1.5 assumes the pond inventory is unitJrmly mixeds that the pond is located in an uncontrolled area as defined in 10 CFR 20, and that the concentration limit in Note 1 to Appendix B of 10 CFR 20 applies. The batch limits of slurry to the chemical treatment ponds assure that radioactive material in the slurry transferred to the SP are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in Specification 4.11.1.5 assures no batch of slurimj will be transferred to the. SP unless the sum of the ratios of the activity of the radionuclides U to their respective concentration limitation is less than the ratio of the 10 CFR 50, Appendix I, Section II. A, total body level to the 10 CFR 20,105(a), - whole' body dose limitation, or that: Ij 3 mrem /yr = 0.006 jC _00 mrem /yr y where Oc}=radioactiveslurryconcentrationforradionuclide"j"enteringthe unrestricted area SP, in microcuries/ milliliter j p... V SUMMER - UNIT 1 B 3/4 11-2 v) NOV 19 ISe0 me, .e.e e=p e e

t 1 O h RADI0 ACTIVE EFFLUENTS BASES j 3/4 11.1.5 SETTLING PONDS (Continued) C) = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j", in microcuries/ milliliter. 'NFor the design of filter / der.ineralize'rs using nowder resin, the slurry, wash} volume'and-the weight of resin used per batch is fixed by the cell surface area and the slurry' volume to resin weight ratio is constant at 100 milli 11ters/ gram of wet, drained resin with a moisture content of approximately 55-to 60% (bulk (f density of about 58 pounds per-cub c feet). Therefore, y ' c Q N / J N_~ I ,I 0.006' and j (10' ml/gm)(10' pCi/pci) s j j C j k < 6-x TO x /* J N~ Iyhere'thetermsaredefinedinSpecification4.11.1.5. The batch limits provide assurance Uiafadiilt9 input to the SNIbe ~ ~ (] minimized, and a means of identifying radioactive material in the inventory W. limitation of Specification 3.11.1.5. C' 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 00SE' RATE This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provido reasonable assurance that radioactive material discharged in gaseous effluents will not result in 8 the exposurs af an individual in an unrestricted area, either'within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). . For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the ' atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rater above tackground to an individual at or beyond the site boundary to Tess than or equal to 500 mrem / year to the total body or to less than or j. equal to 3000 mrem / year tc *.he skin. These release rate limits also restrict, e at all times, the correspanoing thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem / year for the nearest cow to the plant. nU NOV 191980 i' SUMMER - UNIT 1 B 3/4 11-3 %./ --.m_.

4 t C' ' ' P ' ~ N 5.0 DESIGN FEATURES 8 k) ~ 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1. LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1-2. F SITE BOUNDARY FOR GASEOUS EFFLUENTS

  1. 5.1.3 The site boundary for gaseous effluents shall be as shown in Figure 5.1-3.

SITE BOUNDARY FOR LIQUID EFFLUENTS 5.1.4 The site boundary for liquid effluents shall be as stown in Figu e 5.1-4. 5.2 REACTOR BUILDING CONFIGURATION

  • Pre-5dresse4Fest es;o,d b

5.2.1 The reactor containment building is a steel lined,krainforced concrete butiding of cylindrical shape, with a dome roof and having the following design features: a. Nominal inside diameter = 126 feet. b. Nominal inside height = 187 feet. c. Minimum thickness of concrete walls = 4 feet, d. Minimum thickness of concrete roof = 3 feet. e. Minimum thickness of concrete floor pad = 4 feet. f. Nominal thickness of steel liner = 0.25 inches. 6 g. Net free volume = 1.842 x 10 cubic feet. DESIGN PRESSURE AND TEMPERATURE

5. 2. 2 The reactor containment building is designed and shall.be maintained for a maximum internal pressure of 57 psig and a temperature of 283*F.

e. iG'i '2 91980 b SUMMER - UNIT 1 5-1

  • ee e esume 9

e

  • ** ee e e

e e C* ACRES 1 1 'r "i

SITE AREA: 2200 1

j ___ p___ 1 \\. h Mi;id __ ^ N S g-7 t/g "- MONTICELLO RESERVOIR _ vlierlELo' I .f 's 's F-PUMPED., N _ '- 's .'w' 5 STORAGE::: . FACILITY::'. i y y '3ay y".

f. -

s f'/- m

v. :

se,Y,m x O' xv T-e 2 Q ', - Ns j 'A AUXILIART ,\\ i BUlLDING - CAM \\ \\ [-OAM '7 ,x 3.t rJ" O,1;AM \\ 1- ~' f f-l \\~ -s.- [\\'_ f SERveCE ,-w=; ~,m l .,f ". NN2Fh' / \\ i ^ V, ~ WATER g j s-1 PONO & *qcp ~/ g "/}, I 1) N ( / "E, -~ ]s Q. TURSINE 7 g e_ __, \\/ mm kSUBST ilON h C.W. O lSCH ARGE + 7* CANAL f g g,.,

q
y:b

[i W h St E BOUNDAR% E'ACLUSICN AREA AND PLANT PRCPERTY LINE\\ g ,4 l

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) s a - l5 l h l l l SUPv l l DSS l [ OPER MAINT TECH ADMI4 i SUPV SUPV SUPV SUPV I l TRNC COORD i l STATF 1 COORD SUPPORT j i' ASST } OPS SU?V MECH ELECT 16C MATL LEAD SHIFT TECH PERF STA CHDI NUC MP INSP OFFICE BtERC I l SUPv Surv SUPv SUrv ENCR TECH SERV COMr NuC SUrv TRNC CROUP CROUr SUrv COORD t ADVISORS COORD LNCR ENGR CROUP 5 D I I I i I SHIFT r 1' g SUPV5 MECH ELECT I&C MATL ENCR TECH FERF NUC CHEM PERSONNEL DOCUMENT NORD 6-CROUP CRO'.!P CROUP CROUP CROUP SERV COMP ENCR CROUP CROUP CROUP FROCESS l g CROUP CROUP CROUP CROUP 1 l lOPERATORSf I i t I i I F.: i I FIGURE 6.2-2 i 3 V.C. StiefER NUCLEAR STATION l Pt1sCT10NAL ORGANIZATION } l d f. 4; } . ~. - - l 4 O I e 4 ,}}

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