ML20062H220
| ML20062H220 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/03/1982 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8208130427 | |
| Download: ML20062H220 (33) | |
Text
{{#Wiki_filter:. - DIST: (Document:Contro1~(50;395)cra NRC PDR L PDR NSIC M 3M h (16) LB#1 Rdg. (2) Docket No. : 50-395 MRushbrook WKane Attorney, OELD Mr. O. W. Dixon, Jr. OIE Vice President, Nuclear Operations South Carolina Electric & Gas Company Post Office Box 764 Columbia, South Carolina 29218
Dear Hr. Dixon:
Subject:
Technical Specifications - Virgil C. Summer Nuclear Station On July 12, 1982 we transmitted revisions to the proof and review copy of the Appendix A Technical Specifications. Since that time additional pages have been revised to reflect responses from the staff on changes proposed by your organization. These changes are included in the enclosure. Please contact the staff's project manager if you have questions regarding the enclosure. Sincerely, original sisnea by A J. Youngblooi ; B. J. Youngblood, Chief , Licensing Branch No. 1 l Division of Licensing
Enclosure:
As stated cc w/ encl . : See next page 8208130427 820803 PDR ADOCK 05000395 A PDR nl1. OF F6CE ) D :L. ..,........ D1,
.... . . . . . . . . . . .. . . . . . . . .. t SURNAME) ,F, , p , , ,, , , ,,,, J3,J,y ggt , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , ,,
8 om> .. /. 3/. 82
.../..)^. ../. 82 Nnc ronu sia no-so> sacu o24o OFFICIAL RECORD COPY u w i-33 ,co
Mr. O. W. Dixon, Jr, Vice President,' . Nuclear Operations , South Carolina Electric & Gas Company Post Office Box 764 (Mail Code F-04) Columbia, South Carolina 29218
. cc: Mr. Henry Cyrus Senior Vice President South Carolina Public Service Authority '
223 North Live Oak Drive . 3 Moncks Corner, South Carolina 29461 J. B. Knotts, Jr. , Esq.
. Debevoise & Liberman ~
1200 17th Street, N. W. ~ Washington, D. C. 20036 Mr. Mark B. Whitaker, Jr. Group Manager - Nuclear Engineering & Licensing South Carolina Electric & Gas Company Post Office 764 Columbia, South Carolina 29218 Mr. Brett Allen Bursey
- Route 1, Box 93C Little Mountain, South Carolina 29076 Resident Inspector / Summer'NPS c/o U. S. NRC ' , "
Route 1, Box 64 .
- Jenkinsville, South Carolina 29065 Mr. James P. O'Reilly U. S. NRC, Region II 101 Marietta Street Suite 3100 .
Atlanta, Georgia 30303 4 e e 4 9 A
D e O e l ee - ew,
- are e
4 i 9 e e W 6 t i s h ENCLOSURE 1 i r I t P i 1 e I I I I t k 9
,g ..
s TABLE 2.2-1 2 .
$ REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS s Total
$ Functional Unit Allowance (TA) Z Trip Setpoint S Allowable Value s 1.2 Manual Reactor T' rip Not Applicable NA NA NA NA - -
- 2. Power Range, Neutron Flux -
- 7. 5 4.56 0
~
High Setpoint $109% of RTP $111.2% of RTP Low Setpoint 8.3 4.56 0 125% of RTP <27.2% of RTP - .f
- 3. Power Range, Neutron Flux ,1.6 0.5 0 liigh Positive Rate 15% of RTP'with 56.3% of RTP with
, a time constant a time constant
. 12 seconds , 22 secondsg
- 4. Power Range,' Neutron Flux 1. 6 0. 5 0 <5% of RTP with <6.3%.of RTP;with y liigh Negative Rate a- time constant m a time constant 22 seconds 12 seconds
- 5. Intermediate Range, 17.0 8.4 0 <25% of RTP <31% of RTP Neutron Flux -
- 6. Source Range,. Neutron Flux 17.0 10.0 'O , $105 cps $1.4 x 10s cps
- 7. Overtemperature AT.
lev ' I
- 7.1 2.94 pr8" See. note 1 See note 2
- 8. Overpower AT f. Z 4.5 1.4. 4 See note 3 See note 4
- 9. Pressurizer Pressure-Low 3.1 0.71 1.5 21870 psig 11859 psig
~
- 10. Pressurizer Pressure-High 3.1 0.71 1.5 52380 psig $2391 psig y 11. Pressurizer Water Level-liigh 5'. 0 2.18 1.5- $92% of iiistrument 193.8% of instrument q span
~
span . e 12. Loss of F1ow 2.5 l 1. 0 1. 5 >90% of 1o'op >89.2% of 1oop i ev g . Besign flow
- Uesign flow
- fL61mLAmfVmtJdV.vt=h
'i M h '
- i'
}
.\
- v. TABLE 2.2-1 (Continued)
E rj REACTOR TRIP SYSTEM INSTRUMENTATION ThlP SETPOINTS NOTATION , b H NOTE 1: OVERTEMPERATURE AT H 1 4 1 Mi -K 2 AT (y ta3) $ AT g [T (y # Ts3) - T'] + Ka(P - P') - f (AI)} i Where: AT r- Measured AT by RTD Manifold Instrumentation , 1 = lead-lag compensator on measured AT , ti, T2 = Time constants ut' ad in lead-lag controller for AT, 11 = 8 sec., I2 = 3 sec. , , 1 = Lag compensator on i..easured AT ' 1+T O 7 m 3 13 = TimeconstantsutilizedinthelagcompensatorforAT,ta=% secs. AT g = Indicated AT at RATED TilERMAL POWER Ki = 1.090 K2 = 0.01450
~
1+T54 = 1+1 3S The function generated by the lead-lag controller for T"VU . dynamic compensation . 14, & r3 = Time constants utilized in the lead-lag controller for T,yg, 1 4 = 33 secs., .
.t3 = 4 secs.
T = Average temperature F , " 1
=
ij y Tc3 Lag compensator on measured T,yg - O . . Ic = Time constant utilized in the measdred T avg lagcompensator,is=Ksecs.
'yJf(p.
.h r ;. a n-h'.Y ii w
eF .!
,e 2
- E .
TABLE 2.2-1 (Continued) - . . Li 9 REACTOR TRIP SYSTEM INSTRijMENTATION TRIP SETPOINIS- ~ l i . . c NOTATION (Continued) h* . y e NOTE 1: (Continued) 1 T' .$ 587.4"F Reference T avg at RATED THERMAL POWER Ka
= .0006728 ,
P =. Pressurizer pressure, psig = . .' '
-. i l 'P' = 2235 psigrNominal RCS operating pressure S = Laplace transform operator,;sec 1 and ft(o.) is a function'of the indicated difference betwee'n top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument
~
, '?
- response during D16nt startup tests such that:
(i) for qt ~9 b between - 34' percent and + 8 percent.f (AI) = 0 where qt and qb arepercep i RATED TilERMAL P0WER in the top and bottom halyes of the core respectively, and 'qt+qfis total TilERMAL POWER in percent.of RATED THERMAL POWER. . (ii)' for cacti percent that the magnitude of qt ~9b exceeds -34 percent, the AT trip setpoint ' shall be automatically reduced by 1.67 percent of its value at RATED THERMAL POWER. (iii) for each percent th'at the magnitude of qg gben:ceus +8 percent, the AT trip setpoint
, shall be automatica1"ly reduced by 1.11 percent of its value at RATED TilERMAL POWER. .
NOTE 2: The' channel's maximum trip setpoint shall not exc'eed its computed trip point by more than l
.e
- . -__ ..C kpercent 6T span.
- e. v ~. ,.
E, TABLE 2.2-1 (Continued) , S . 9 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS _ NOTATION (Continued) - 5 H NOTE 3: OVERPOWER AT e ( ATfl y 5 3 ( 1 Ta5
) AT g (K4 -K 3 (Y) 1 1 fz3) a T - Ks [T l yfTs3) - T9 - f 2(AI)]
,N Where: AT = as defined in Note 1 1 -
= as defined in Note 1 ,
ti, T2 = as defined in Note 1 ,
= as defined in Note 1 ,
m . 1+T53 O 13
= as defined in Note 1 :
AT, = as defined in Note 1 K4 1.091 K3 = 0.02/"F for increasing average temperature and 0 for decreasing average temperature
= The function generated by the rate-lag controller for T,yg dynamic,dompensation 1}'7 3 ,
17
= Time constant utilized in the rate-lag. controller for T,yg, 17 = 10 secs.
= as defined in Note 1 1 + Ts5 Is
= ' as defined in Note 1 .
1 Y , 8 ' 10
. 4
[q
- - TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS g NOTATION (Continued) O ' .
-4 :
NOTE 3: (Continued) - Ko = 0.001190/effor T > T" and Ks = 0 for T $ T" - T - as defined in Note 1 T" 5 587.4 F Reference Tavg at RATED THERMAL POWER S = as defined in Note 1 f 2(AI) = 0 for all AI t NOTE 4: Thechannel'smaximumtripsetpointshallnotexceeditscoNputedtrippointbymorethan 7 % percent AT span. W - 2.'( . 9
. I' b
o O e i, eso e M
_ _ _ _ . _ _ -- - - - - - -~ i
; , gd,, j, ! l *
.N'i
... (GIS 3.k.,..t h1. .
i ,l ' l . . i EE - ~ TABLE 3.3-4 (Con-.inued) I $ i c- ' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP Total f } Func.tional Unit i Allowance (TA) Z S, ' Trip Setpoint Allowable Value
- 4. STEAM 'LINE ISOLATION
- a. Manual .
. NA NA-b.
NA , NA - NA Automatic Actuation Logic NA NA and Actuation Relays NA NA NA
- c. Reactor Building Pressure-High 2 3.0 0.71 1.5 <6.35
~ '
<6.61
- d. Steam Flow in Two Steamlines- 20.0 13.16 1.5/
High, Coincident with < a function I
~
w 1.5 defined as
< a function defined h as follcws: A Ap follows: A AP corresponding *to 44%
w corresponding E of full steam flow
" to 40% of full between 0% and 20%
steam flow load and then a Ap between 0% and increasing linearly - 20% load and to a Ap corre-then a Ap, sponding to 114.0% increasing , ;
, linearly to a of full steam [ ,
Ap correspond- flow at full load. .-
~
ing to 110% of - full steam flow l1 at full load , ggg4 T - Low-Low , 4.0
^
- e. Steamline Pressure - Low .'20.0 1.12 M 1553*F 1550[5'F 10.71 1.5 >675 psig >635 psig II) .'
(1) p_. Time In 1 50constants secs. utilized T2 < 5 secs, in lead lag controller for steamline pressure low are.as follows: . r-a
. . ;, ' jk n ..
!;)> 'd 0.
,h 3M K, ' '
.La d C.X . :
_ ,l . . . .
- y. TABLE 3.3-4 (Continued)
M - 0 ENGINEERED SAFETY FEATURE ACTUATI'ON SYSTEM INSTRUMENTATION TRIP SETPOINTS e
.. Total -
5 Functional Unit Allowance (TA) - Z -S, Trip Setpoint Allowable Value H ,
- 9. ENGINEERED S.AFETY FEATURE ACTUATION SYSTEM INTERLOCKS INTERLOCKS
- a. Pressurizer Pressure, P-11 3.1 .71 1.5 1985 psig >1974 psig &' -
- f,1 . $1996 psig
' P-12 4.0 1.12 .2ba;, 553"F
~
> M"F d < 'F b.
ThLow-Lowi
- c. Reactor Trip, P-4 NA NA NA NA NA . '
n W . e e
= e W
e e
- - - . . - . . p
- m v UC
- ZW E
O
<2 J~ MM M fd' M . .
[ w .J 3 . . m f .
.-M MZWW
= =
- N N mm
. O, r}
~
W = N N N . g
> u v 41 en m m.
m -~ N N N N 1 en . .
.s.
N ' _ . - m e= e-
. m
- a >- .
><>= < CF- <
<JW . . . .
. J I-J w Z Z Z Z McW Z Cf" Z C Z M
W >. .
&<> . m . .
mJm < M
. . m . m
<ww . v C. C. C. C.
s4 < M < E = P= Z E Z Z Z v . v t = E Z Z Z Zm Cw -
* ^
Z . . .. m C
**P"-
H
< M
. v
*=4
. m M*
<U Z E 2 Z Z
. . v C. v C.
** 3~ Z E Z E Z H WO Z UC w < -J i
- Z -
3 M Cs! & J
-~..:.
. m <
2 * .*;;q ' - *O Z .,~cw: m E M WWH M 5">t t w W <U<
=
2 c P.- >= K Z Z Z Z
*] M Z C. 3 M E >=
M P-= > W M 2 2 = 2 .2
.A C >= W MUwCw .
** **=
-.a m E &<CO&
w
- f. -
C Z %
' C O - J W a-. D <
v H C"' 2
< W C =
O = P N J a=* * < < m a P.- UW C w b-CZ<
< G JZMH Z Z E E E E Z Z Z E T
w< J Z <<wW Z = C. W w % <UCM a O J
= >=- -
< < w H w > Z L Z C C *
>- m H .
>- J< < <
W w= . .. . < w . Z C2 Z Z E % C. ' <.
.< Z~ % 2 Z Z.Z g m <J C
=<
UU w C W J w w
=
=M . .
c ZU
<w < <. <
= == Z Z m M W w UU W Z Z Z .*. O i
U h h
~
m :. C E C n C 6 L*: -J % C J m C C t. w % = 6 L
@ U -3 ob r-= U C C fJ Ch 6 M *C < =J CC a C f5 C- C C OO C
. *e 3 "E C - *
- Z
-- OGC O 3 -J eJ . J-# - - 3 3 C C 3 C -J w .C Q c2 H *- a w r3 r3 ci L m 3 .C
-C.C C 3 LQ = O M =C C3 H =J C T *~ CUC L C *- a 'es w JJ J C
< U C -Z -- -J C ad = U U H UU CJ u < . - *- .C Z C e <<
L .C << L1 C *J 3C 3QI 6
< 3< c3 i m U fc C3 +-Q C- C C U "O C U *C C C
- *- O -O >
C"a C. C*- - C w *- C cJ
=J *J L2 La # fD -
"J =
C i J fc w J - C e i H W - r5 U C e S w - ": I
** - i H % i EU ""
EV i 2 Z f5 E< *J 8 Em t- Z E- C *- >= 0 E-
- O C U U 'O C .C C C 0 .C*- r3 0 3 J C a *C rc L 0 C -J w *== 0> J CT U C -J O C >
C 3 C U C =.* == Z& =J U 0 C Z '7 C O .J Q _J = = < c = m m _; 3 <J w Z <_ m .J
< < -c ea mJ e w == c e
=.
c ~ . . .
= m w P-m . .= U =
- - =
.=
=
w
, .=. .
U SUMMER - UNIT 1 5_2 3/4 3-37* '
'gn.
i
# ' $i. ... ,
, l
,2 i
' r
( . p IABLE 3.3-6 g M i RADIATION HONITORING INSTRUMENTATION Pj -
.l '
HINIMUM i c_ . APPLICABLE ALARH/ TRIP HEASUREHENT i CllANNELS 5 H OPERABLE H0 DES SETPOINT RANGE ACTION . INSIRUMEN1 v *
- 1. . AllLA H0Hil0RS I 1
- a. Spent Fuel Pool Area (RM-G8) .j 4 1
1 15 mR/hr 10 - 10 mR/hr 25 I
- h. Reactor Building Hanipulator 5 28 6 1 1 R/hr 1 - 10 mr/hr Crane Area (Ril-G17A or 1 , ,
RM-G170) ,- Reactor Building Area e. 16
- c. 30 ,'
- 1. liigh Range RM-G7 and 2 1, 2, 3 & 4 'N/A . ;R ,10 R/hr 7 i lii0h Rahge IIH-G10 ,
10 - 105 R/hr 7) w - } 2. PROCESS HONITORS
.i (p a. Spent Fuel Pool Exhaust. - ,
g Vent.ilation System (RM-A6) *
-5 pCi/cc 10 - 10 6cpm
** < 1 x 10 27. -
- 1. Gascous Activity 1
. ' I TKr-85) '
6 Particulate Activity ^^ .N/A 10 - 10 cpm 27
- 11. 1 .
- b. Containment *
.I
- i. Gaseous Activity .
- Purge & Exhau:,L 5 Isolation (RM-A4) 1 6 1 2 x background *** 10 - 10 cpm 28 li. Particulate Activity ,
~
(RM-A2) - RCS Leakage 6 Detection 1 1, 2, 3 & 4 N/A 10 - 10 cpm . 26 . 6 E c. .ConErol Itoom Isolation 'l ,ALL H0 DES ~ $ 2 x background 10 - 10 cpm 29
" (RM-A1) " ^ With fuel in the storage pool or building .
fj ^^ With irradiated fuel in the storage pool N ^^^ Alarm /Lrip setpoint will be per the Operational Dose Calculation Manual when pdrge exhaust operations are in prouress .
)
,j -
m - g 1ABLE 4.3-3
- c '
U}
, RADI ATI0il MONI'IORIllG IllSIRilllElifATI0il SURVEILLAllCE ilEQUIREllLilTS c-55 *ilALOG CllAllilEL MODES FOR WillCil CilAtlilEL CllAiHIEL t'PERATIONAL SURVEILLANCE
[ IllSTl]UMEllT , CilECK CALIllRATION -TEST IS REQUIRED
- 1. AREA M0llITORS -
- a. Spent' Fuel Pool Area (RM-G8) S R *
.M
- b. Reactor Building Manipulator S R H 6 Crane Area (RM-G17A or RM-G170) -
- c. Reactor Building Area
- i. liigh Range (RM G7) S R# 'H 1, 2, 3 & 4 -
ii. liigh Range (RM-G18) S . R -p V - M 1, 2, 3 & 4
- 2. PROCESS M0ilITORS *
- a. Spent Fuel Pool Exhaust Area - '
R' Vent.ilation System (RM-AG)
- i. Gaseous Activity S R H ** ;
T ii. l' articulate Activity 5 H **
^ H
- b. Containment - -
- i. Gaseous Activity
- Purge & Exhaust '
Isolation (RM-A4) S R M 6 3 m ii. Particulate Activity
- RCS Leakage Detection ' ->
S R M' U 1, 2, 3 & 4 (RM-A2) .yD .
- i
- c. Control Room Isolation (RM-A1) S R
- d. H All MODIS CIO floble Gas Ef fluent Monitors (lli h0 Range) ' w'1 rg
, i. Main Plant Vent (RM-A13). 'S R H 1, 2', 3 & 4
. 11. Main Steam Lines hM
. (RM-Gl9A,11, C) S R H '
1, 2, 3 & 4 iii. Reactor fluilding Purge Supply & Exhaust System (RM-A14) Q
%1 S
R H 1, 2, 3 & 4 -<
'With fuel in th'e ilorage pool or building *
-n -n t L cddb b . *( Q abM, et Ay twp 1.mu ~ d eut h A A*" - *** * -
\'WP
.- . r, . ..
INSTRUMENTATION.
.' IABLE 3.3-11 .
FIRE DETECTION INSTRUMENTS
' ~
MINIMUM IliSTRU- . TOTAL NUMBER INSTRUMENT LOCATION MENTS OPERABLE * , OF INSTRUMENTS' HEAT SMOKE HEAT SMOKE-
- 1. REACTOR BUILDING Zone 1 Elev. 412' Room 12-01 NE .. 2
~
3 Room 12-01 SE 2 3
~
Room 12-01 SW 2 3 Room 12-01 NW . 2 3 Zone 2 Elev'. 412' ...". 7. L' j Room 12-03 1 2 C.-yij Room 12-07 . 1 2
- 7(>rS Room 12-08 - 1 2
- y;y - '
Zone 3 Eley. 436'
. Room 36-01 NE 2 3 Room 36-01 SE . 2 3
,. Room 36-01 NW 2 3 Room 36-01 SW 2 3 0,g Zone 4 Elev. 462' Room 12-03 1 2 Room 12-07 1 2 Room 12-08 .
1 2 20 6 000 Elev. 412' Room 12-08 1 2 Zone 000 Elev.. 463' - Room 63-01 SE 2 3 Room .63-01.SW , 1 2 Zone _PPP Elev. 412' Room 12-03 1 2 Room 12-07 . 1 2 Zone PPP Elev. 463' Room 63-01 NE '1 g 2, Room 63-01 NW 3 - SC
- 2. CONTROL BUILUlNG Zone Elev. 463' Room 63-02 1** 1**
Room 63-03 2** 3*' Room 63-04 1** 2*' 9 3/4 3-62
m ~ v
- - INSTRUMENTATION
- TABLE 3.3-11 (Cont.) -
MINIMUM INSTRU- ' TOTAL NUMBER (- INSTRUMENT LOCATION .' - . MENTS OPERABLE
- 0F INSTRUMENTS
. -. HEAT . ~' SMOKE HEAT SM0KE
- 2. CONTROL BUILDING (Cont.)
/ *
- Zone A Elev. 448'
~
. c.
Room 48-02 (Cable Spreading s: Roem Upper) 17** * ' 18**9 Zone A Elev. 436' gg/'O Room 36-02 1** 1+* g Rocm 36-03 2** 3**
.p p
r Room 36-04 - 1** 2**
'~
- Zone B Elev. 425' Room 25-02 (Cable Spreading
,7 ,
Room-Lower) . - 10** 11**
- j. '
Zone'B Elev. 412' .
- 73.gj Room 12-04 -
, 2** 3**
wn O'S
' Zone B Elev. 400' Below Room 12-05 1** '2**
.' Zone J Elev. 436' .
- i. Room 36-01 2** 3**
Zone J Elev. 448' Room 48-01 21** 22** Zone K Elev. 412' Rocm 12-02 2** 3** Room 12-03 3** 4** Zone X Elev. 425' , .N i Room 25-01 21** ..- 22** f
~ s r c .. '
Zone L Elev. 436' e- d Room 36-11 23***[ 4'" 24*** # 7 "~
.a.
Zone M Elev. 436' # .2 Rocm 36-10 14***' 1 15*** " .2 1 , l . Zone N Elev. 44S'
- Room 48-02 (Cable Spreading A~rea A . .J-for HVAC Cabinets) 11 -
21 "
.o a 6 b5 l'.ain Control Board) 3 6 Zone R Elev. 463' ~
Room' 63-05 (HVAC Control Board) 1 1 ) . 3/4 3-6'3 L
~ ' -
1NSTRUMENTATION . TABLE 3.3-11 (Cont.)' _ .: MINIMUM INSTRU- TOTAL NUMBER
~"
- ' MENTS ' OPERABLE * *0F INSTRUMENTS-INSTRUMENT LOCATION
- HEAT '~ SMOKE' HEAT SMOKE
~
- 2. CONTROL' BUILDING (Cont.) , ,- ,
' Zone S Elev. 44B' Room 48-02 (Cable Spreading Area d a#
forHVACCabinets) 9 17 Zone VV Elev. 436' Room 36-09 1 2 Zone W Elev. 463' _a. 4 Room 63-05 4 8 I
.- 1 1 l Room 63-06
'~
A3 Room.63-07 Room 63-09
.. I 1
2 1 l iTi _ 3f( 3 . Room 63-10 ' 1 1 1 1
+4 Room 63-11 .
~ ~ ~ ~
1
~~ ~2)} Room 63-12 ~~~ ~ . I Room 63-13 1 1-
. k.!
Zone XX Elev. 463' Room 63-14 , 1 1 Room 63-15 ~1 1
. Room 63-16 1 1 Room 63-17 . I '
1~ Room 63-18 1 ' 2 Room 63-19 1 l' Room 63-20 1 1 Room 63-21 . . 1 1 Room 63-22 1 2 Room 63-23. I 1 Zone NNN Elev. 482' 3 ,;. Room 82-01 - 4'g 8' ,_. Room 82-02 4 7 ' '-
. ri!M Room 82-03 2 3 1 2
. Room 82-04 Zone TTT Elev. 412' 1 2 Room 12-11 .
~ .
~
- 3. NORTH PENETRATION ACCESS AREA Zone EE Elev. 436' 2 3 Room 36-01
. Zone YY"Elev. 412' 4 6 Room 12-01 2 4"
p.:dy.u ~ . e .
' INSTRUMENTATION _ .' ..
TABLE 3.3-11 (Cont.)' e I
- - - MINIMUM INSTRU- . TOTAL NUMBER
'MENTS-OPERABLE *_ 0F INSTRUMENTS INSTRUMENT LOCATION _ ' HEAT SMOKE HEAT ' SMOKE
/
- 4. EAST PENETRATION ACCESS AREA -
E Zone JJ Elev. 412' g 10 " 5 Room 12-02 Zone LL Elev. 436' h-5' 10 p Room 36-02
- 5. WEST PENETRATION AREA
'~
Zone Y Elev. 412' 4 4 8 4 Room 12-01 g#g ,
- ' .;k "3'Q '
Zone DD Elev. 436' - 4 A 8
~ ,~ % Room 36-01 - .q:yt.y ~
Zone II Elev. 463'
' . :; 3 2
-i Room 63-01 -
.39 64
~
Room 63-03
- 6. INTERMEDIATE BUILDING p"[
Zone AA Elev. 412' 22** e 23**
,gy. -y- Room 12-02 W ,
1**
.1*
- Room 12-13 A ; 1**
1.*
- Room 12-13 B 1** . l*
T" Room 12-13 C .. Zone BB Elev. 412' . n.J ' . ..
~ ,^ 17"*-
Room 12-02 E 1** 18]1 j, J Room 12-10, o Yg4 Zone CC Elev. 436'
.#_ / '# ~ -
5H 3**
- 4}
Room 36-02 ( g 4 ) Zone FF Elev. 423'-6" 3 5 Rocm 236-01 _ ~ Zone GG Elev. 412' 1
~
1
- Room 12-03 1 1 r g Room 12-04 Room 12-05 1
2 1 2 Room 12-06' 1 1 Room 12-07 1 1 s Poom 12-08 1 1 Room 12-12 1 1 Room 12-14 1 1 b[ y t " d Room 12-15 -
%,)Jl'I 3/4 3-65
s . INSTRUMENTATION
<- TABLE 3.3-11 (Cont.)
- ~
. . ,- MINIMUM IN.!iTRU- TOTAL NUMBER INSTRUMENT LOCATION .
- MENTS OPEPABLE* -
0F INSTRUMENTS HEAT ~' SMOKE ,' HEAT SMOKE
~ ~ '
- 6. INTERMEDIATE BUILOING (Cont.) ,
Zone KK Elev. 412' Room 12-09 - 1 i f/N Zone KK Elev. 423' Room 23-01 21 4 Room 23-02 - - 2 4". Zone KK Elev. 436' Room 36-01 2 3 3 M,,
.f'y Zone ld Eley. 463' s ,a_
1 Room 63-01 4* 8"
.dj ' ~~ Room 63-02 .- __ -.
~
35 6 f--
"--}. <v W . Room 63-03 -
~
1 2 Zone PP Elev. 436' -
# ~~ Room 36-02 .
'84 '
. 16-
3.' l
,.- Q~~ Room 36-03(CREP) 2 3 -
1 2
.dg.; MRoom 36-03 A oom 36-03 B (CREP) 1 2
# Room 36-04 1 -
1 Zone I'M Elev. 451' ' Room 51-01 4 3 ~..'. 6 .~.' 7M Room 51-02 , , 3' - 6 '~~ Room 51-03 1 2 Room 51-04 . 1 2 Zone FFF Elev. 436' 2-g Room 36-02 8" 16 4" Room 36-02 E
~
l 1 Zone UUU Elev. 426' . Room 26-01 2" 4-
@ Room 26-02 2" 4' '
- 7. AUXILIARY SUILOING Zone Q Elev. 436' .
Room 36-18 2 "' - 4l
/ one'HH Elev. 463' Room 63-01 .1 2 dcom 63:.04 . I 1 Room 63-06 1 2 M Room 63-17 1 1 O ll A S$._-._____.--__ _ _ - _ ._ _ _ . . . - _ - _
' ' ~
f' INSTRUMENTATION , TASL'E 3.3 (Cobt.)-
~
MINIMU!i INSTRU- TOTAL NUMBER MENTS .0PIRABLE* '0F INSTRUMENTS INSTRUMENT LOCATION ..
- HEAT SMOKE ' HEAT SMOKE
- 7. AUXILIARY BUILDING (Cont.)
Zone QQ Elev. 452' - n@.d Room 52-01 1 1 Room 52-02 - 1 ,- 1 Zone RR Elev. 463' n 'J./ Room 63-16 2** # 3** Y f 3'g Room 63-19 . . 1** 1**
- Zone ZZ Elev. 374' Room 74-12' 1 1 g Room 74-16 .,
~2 2
3 3
. Room 74-17 a..it ,
, ,dl Zone AAA Eley. 38S' '
%0 - Room 88-23 - 1 i ykC n8 ' Su Room 88-24 1 1 A Room 88-25 . 1 1 ,
's
-( Zone AAA Elev 397' Room 97-02 3C
~6 Y
My Room 97-02 N 1 1 Room 97-02 S 1 2 Zone BBB Elev. 388' Room 88-05 1 2 y Room 88-13 N Room 88-13 NE 2 1 3 1 Room 88-13,S ,
- 1 -
1
,.g Zone BBB Elev. 397' .
Room ~97-01 .1 2-v< j,S b ne BBB Elev. 400' Room 00-01
' l ' ,- p .
~
Room _00-02 1 2 1 3-Zone CCC Elev. 463' . M t> Room 63-09 2< "- 3 2
%47 Room 63-14 1 Zone EEE Elev..'374' Ro6m 74-01 1 2 y Room 74-07 1 -2 g,td I
Room.74-08 2, . 3, Room 74-09 3 '- , 5" Room 74-18 1 1 3/4 3-66a
~
INSTRUMENTATION .
. TABLE 3.3-11 (Cont.)
( .
.- - MINIMUM INSTRU- , TOTAL NUMBER INSTRUMENT LOCATION MENTS OPERABLE
- OF INSTRUMENTS
~
- 7. AUXILIA'RY BUILDING'(Cont.) , . ,
Zone GGG Elev. 400' g- ,
' Room 00-01 3 P' Zone HHH Elev. 412' .
Room.12-05 1 1 Room 12-06 1 ,. 1 Room 12-11 - 4- d ,7 c Room 12-11 N 1 ^1 Room 12-27 1 1
~
Zone HHH Elev. 426' ' Room 26-02'W 1 M 1 fj Room 26-02 E - 1 1 --g - Room 26-02 S . _ . 1 1 c.s.qq ' 64 koneIIIElev.412' -
-. Room 12-02 1 ,1
,. Room 12-03 A 1 -
1
, f.,eu) Room 12-09 - 1 1 Room 12-11 N 1 1 Room 12-15 1 1.
Room 12-18 1 1 Room 12-28 1 1 Room 12-31 1 1 Zone JJJ Elev. 412' - Room 12-02 1.. I d Room 12-11 4,a 75 Room.12-11 N 1 - 1 Zone LLL Elev. 436' - n cU Room 36-33 N 3'V 6' Zone RRR Elev. 388' 1 1 [ Room Room88-05 88-13 Room 88-13 S - 1 1 2 1 Room 88 1 . 1
\ Zone Wil Elev. 436' 3 -
6Y Room 36-33 3* Zone MM Elev. 446' N Room 46-01 . I 1 s. Zone YYY Elev. 412' Room 12-05 1 1 g j Room 12-27 1 1 Room 12-30 - l' . I
' INSTRUMENTATION _ ,
TABLE 3.3-11 (Cont.) MINIMUM INSTRU- TOTAL NUMBER
'0F INSTRUMENTS _
MEffTS.0PERABLE*_ INSTRUMENT LOCATI0t{ ~ 550KE ' HEAT SMOKE
' HEAT _
- 7. AUXILIARY BUILDING (Cont.)
.1 g Zone 111 Elev. 412' Room 12-01 1
~
1 y Zone 221 Elev. 436' 1 2 A Room 36-01 1 Room 36-03 1 1 Room 36-31 .
- 1 2 Room 36-33 S '
" 8. FUEL HANDLING BUILDING Zone EE Ele'v. 436' - 2 3 f - Room 36-01 W ,
9 1 1 M Zone EE Elev. 443-6" Room 436-01
~
Zone TT Elev. 463' 10 @ 201 Room 36-01 ,
./
i' p 10 >. 19 i eMZone Room UU Elev. 36-01 463'
# 9. SERVICE WATER PUMPHOUSE Zone Nil Elev. 425' 1 ~2,-
3 6-Room 25-04 3- . Room 25-05 , , Zone 00 Elev. 441' '- 1** 1** Ar N . Room 41-Oi [. -.a JD u ~3 O' Zone 00 Elev. 436' 8** 4 9** v Room 36-02 _v .
~
d:. 5P Zone DDD Elev. 441' 3-Room 41-01 , 1 one VVV Elev. 425' 1
# Room ~25-03, 10.' DIESEL GENERATOR BUILDING-Zone DG .Elev. 436' 1** 2**
Room 36-01 1** 2** Room 36-02 1** 1** pM Room 36-03 1** 1** .
'J k9 y W Room 36-04
'- 1 INSTRUMENTATION .
TABLE 3.3-11 (Cont.) MINIMUM INSTRU- TOTAL NUMBER
~
INSTRUMENT LOCATION , MENTS-OPERABLE *. OF INSTRUMENTS - HEAT SMOKE _ HEAT SMOKE
~
10.DIESELGENERATORBdILDING(Conteh -
, Zo'ne DG Elev. 427'.
4,4 Room 27-03 1.** 1** 3 1** 3Y Room 27-04 , 1** Zone KKK Elev. 400' Room 00-01 ~ ' 1 1 Room 00-02 1 .1
'! Zone KKK Elev. 427' Room 27-01 '
1 1 Room 27-02 I 1 ,
- 25 Room 27-03 2 3 w i Room 27-04 2 3 7 53 .
- n .
- The fire detection instruments . located within the Reactor Building are not required to be operable during perfo.rmance of . Type A Containment
- Leakage Rate Tests.
s
** Automatically Actuates Preaction Sprinkler System. -
*** Automatically Actuates low Pressure CO2 System.
~
l e
, 4 b /O $- $M
. s. , ' c- . . TABLE 3.3-13 - -
4 ' N RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION - g .. S' . INSTRUMENT MINIMUM CHANNELS OPERABLE ..' - APPLICABILITY ACTION H '.
+: .:-
T . WASTE GAS HOLDdP SYSTEM - U E .i , ,"f,i. '
- a. Noble Gas Activity Monitor'- Providing .
is j .; ,, Alarm and Automatic Termination of Release 1 *
'0 l ' ' *
- 38 '
s, RM-A10 or RM-A3 ',,' - t i .. . . . i 2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM ..s h!' . n., - a-, s s a .' 0xygen Monitorf @ 2 ! ,. .. , ** ' 44
.g t '
[ b. Hydrogen Monitor % 1 ' .' .' - ** 42 , , 3. MAIN PLANT VENT EXHAUST. SYSTEM .
. 2:
- a. Noble. Gas Activity Moiiltor -: Providing ,
Alarm and Automatic Termination of
. 1
- 40 ' ' '
o Release from Waste Gas Holdup System , RM-A3
- b. Iodine Sampler 1 * -
, 43 . l . c. Particulate Sampler 1 43 .l s.
- d. Flow Rate Measuring Device 1 ,
39
. e. Sampler Flow Rate Measuring Device 1 39 C .
I~ , to
- o -
~
je,, . . -
, _ _ . _ . ._. _f , _ _ _ _ _ _
^
- s. ,
INSTRUMENTATION ... . _ . TABLE 4.3-9 (Continued) TABLE NOTATION ~ At all times. During waste gas holdup system operation (treatment for primary system offgases). (1) The ANALOG CHANNEL OPERATIONAL 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. Loss of Power (alarm only).
. v e,-j 3. Instrument indicates a downscale failure (alarm only). , EU:id '
- 4. Instrument controls not set in operate mode.
r 1.y . rai .is
~
(2) . The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control
".1 room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Loss of Power.
- 3. Instrument indicates a downscale failure.
4 Instrument controls not set in operate mode. (3) 'T'he initial CHANNEL CALIBRATION 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) The CHANNEL CALIBRATION shall include the use of standard' gas samples containing a nominal: l
' Fi(+cen hundred ppm
- 1. {n: ce!"- pe ::nt hydrogen, balance nitrogen, for the outlet hydrogen monitor and
- 2. Four volume percent. hydrogen, balance nitrogen for the inlet hydrogen monitor.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containin a nominal:
- seysn -fies pro, '
- 1. In: : . :: ;;r::nt oxygen, balance nitrogen, for the outlet oxygen -
monitor and tirec and one-half' 2-
'monitor.
c u T J';; g ; ,;5 ,rg5 .; 4 ft oxygen, balance nitrogen for the inlet oxygen SUMMER - UNIT 1 3/4 3-79 MAR 3 352 <
EMERGENCY CORE COOLING SYSTEMS e SURVEILLANCE REOUIREMENTS (' Continued)
- 2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
- e. At least once per 18 months, during shutdown, by: ,
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection actuation and containment sump recirculation test signal. .
'~j 2. Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:
a) Centrifugal charging pump b) Residual' heat removal pump .
- f. By verifying that each of the following pumps develops a differential pressure on recirculation flow when tested pursuant to Specifica-tion 4.0.5:
-[
q
- 1. Centrifugal. charging pump >2472 psi {
(2%
- 2. Residual heat removal pump > g psi [
- g. By verifying the correct position of each mechanical position stop l for the following ECCS throttle valves:
- 1. Within 4 hours following completion of each valve stroking operat. ion or maintenance on the valve when the ECCS subsystems are. required to be OPERABLE. .
- 2. At least once per 18 months. ,
HPSI System Valve Number
~.
a 8996A
- b. 8996B .
- c. 8996C *
- d. 8994A .
- e. 8994B
- f. 8994C .
- g. 8989A
- h. 8989B
- i. 8989C l j. 8991A -
- k. 8991B
- 1. 8991C APR 151982' SUMMER - UNIT 1 3/4 5-5 -
CONTAINMENT SYSTEMS -
~ ~ ~ '
3/4.6.5 COMBUSTIBLE GAS CONTROL " , HYDROGEN MONITORS LIMITING CONDITION FOR OPERATION 3.6.5.1 Two independent containment hydrogen monitors sha'l be l OPERABLE. APPLICABILITY: MODES 1 and 2. .
~
. . _ ACTION:
~
With one hydrogen monitor inoperable, restore the inoperable monitor to .
---_DPERABLE status within 30 days or be in at least HOT STANDBY within the 6 ext-@:
,. 3 , . - - hour's. . sd em
... l:.n SURVEILLANCE REQUIREMENTS 4.6.5.1 Each hydrogen monitor shall be demonstrated OPERABLE by the performanG of an ANALOG CHANNEL OPERATIONAL TEST at least once per 31. days, and at least once per 92 days on a STAGGERED. TEST BASIS by performing a CHANNEL CALIBRATION using sample gasMontainingd 19.T 2- 0. Cn; volume percent hydrogen, balance nitrogen.
-b. ."c m c:1u-a aarra + g dergen , 5 :;c,,e ,, ;, ;;;n,J>-
d SUMMER - UNIT 1 3/4 6-21 R 151982
ELECTRICAL POWER SYSTEMS AC.Tso0:(k6.tk) . _SORVEILLANCE REQUHiEMENTS -- - x
- d. _
With one D.C.gus not energized from its associated Battery Bank, re energize the D.C. bus'from its associated Battery Bank within 2 COLDhours or be in atwithin SHUTDOWN leasttheHOT STANDBY following 30 hours. within the n' ext 6 hours a 4.8.3.1 The specified busses shall be determined energized in the required manner at indicated voltageleast once perbusses. on the 7 days by verifying correct breaker alignment and
+_ 1-jh.y.i;
.,-~ . .
Wa * *- ?f ar-_y % Hl3 F.~:hff::
- e. -
1
\.
t 1 . j . 4 l
.( ..
^
I SUMMER - UNIT 1 3/4 8-14 JUL
' k .,i .
[ 1..i. nr 3. -.
' ' .4:v i r l'
l .h . ~ 7% [) ' f . s 4 1 1 l
! E TABLE 3.8-1 (continued) 4 g . .
I !B I l i CONTAINMENT PENETRATION' CONDUCTOR OVERCURRENT PROTECTIVE' DEVICE TEST SETPOINT CRITERIA
~
he E ]. s EQUIP N0'.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME' 5
. 480 VAC'MCC, CONTIhUED: -
155) XVG 31090-SW/R.B. RECIRC. PRIMARY XMCIDP.Y/211M 45 Amps 5 100 Sec.
. UNIT D ISO MTION VLV. , .
g BA'CKUP XMCIDB2Y/211M 45 Amps < 100 Sec. 156) XVG 8702A-RH/RHR LOOP 1 PRIMARY XMC1DB2Y/4AE. 225 Amps N/A - INLET ISOLATION VLV. > l, . I j q BACKUP XMC1082Y/4AE : e 45 Amps 5 100 Sec. .
-n -
oo 157) XVG 87028-Ril/RHR LOOP 3 PRIMARY XMCIDB2Y/4FJ 225 Amps N/A . g INLET ISOLATION VLV. ij BACKUP XHCIDB2Y/4FJ 45 Amps i 100 Sec. 158) XVG 8808B-SI/ ACCUMULATOR B PRIMARY XMCIDB2Y/161M 300 Amps -4 200'Sec. - ISOLATION VLV. ', , BALKUP XMCIDB2Y/16IM 300 Amps 5 200 Sec. J 159) XVG 8000A-RC/ PRESS. RELIEF ISO.LATION VLV.
, PRIMARY X'CIDB2Y/3IM M h Amps . N/A lis BACKUP XMCIDB2Y/3IM' 45 Amps $ 100 Sec -
i 160) XVG 8095A-RC/ REACTOR HEAD VENT PRIMARY XMCIDA2X/5IN 225 Amps N/A - - VLV. TO PRESS. RELIEF TANK ,
] h DACKUP XMCIDA2X/5IM 45 Amps i 100 Sec. .
a cm
RADICACTIVE EFFLUENTS .
" '~~
EXPLOSIVE GAS MIXTURE . _ . LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to4% exceeds less than or equal to 2% by volume whenever the hydrogen. concentration by volume. APPLICABILITY: At all times. ACTION: '
- a. .
. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal to 4% by volume, restore the con ~ centration of oxygen to within the limit within 48 hours. ,
' b. With the concentration of oxygen in the waste. gas holdup system
? -
greater than 4% by volume, immediately suspend all additions of waste gases to the system and rpduce the concentration of. oxygen to less than 4% by volume within h hour and less than or equal to 2% by volume within 48 hours.
- c. The provisions of Specifications 6.9.1.12.b, 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.5 The concentration of hydrogen and oxygan in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen 9 and oxygen monitors ' required OPERABLE by Table 3.3-13 of Specification 3.3.3.>67 l
- l SUMMER - UNIT 1 3/4 11-17 l/ . .. i
;;g-l
RADI0 ACTIVE EFFLUENTS
~ ~ ~
BASES _ _ _ _ to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for deter-mining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiciodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual ,' . - inhalation of airborne radionuclides, 2) deposition of radionuclides onto
= green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat-producing animals graze with consump-tion of.the milk and meat by man, and 4) deposition on the ground with subs ~equent i exposure of man.
* =
~[ . 3/4.11.2.4 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the
. VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents . require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reason-ably 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 objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of'the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is ' l maintained below the flammability limits of hydrogen and oxygen. Automatic
. control features are' included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic o
control features include ._ _ me __,4__ isolation of the source of hydrogen and/or oxygeqp/ _____< ---e to reduce the concentration below the flammability limits. Maintaining the concentration of hydrogen and 'oxyge.n below their flammability limits provides assurance that the releases of radio-active materials will be controlled in conformance with the requirements of ' l General Design Criterion 60 of Appendix A to 10 CFR Part 50. y w- . c5z SUMMER - UNIT 1 B 3/4 11-5 9
. - i-'
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9 . G. SUMMER - UNIT 1 6-3
- e. - ~-
ADMINISTRATIVE CONTROLS . i
~.4
} AUDITS . _, ,
)@.5.2.8 Th NSRC shall have cognizance of the audits listed below. Audits may be performed by using established SCE&G groups such as the ISEG and QA or by outside groups as determined by the NSRC. Audit reports or summaries will be hebasisforNSRCaction: '
g a. The conformance of unit operation to provisions contained within the g Technical Specifications and applicable license conditions at least once per 12 months.
- b. The performance, training and qualifications of the entire unit staff at least once per 12 months. . - .
- c. The results of actions taken to correct deficiencies occurring in -
unit equipment, structures, systems or method of operation that 4 affect nuclear safety at least once per 6 months. ,_
- d. The performance of activities required by the Operational Quality
~
,. Assurance Program to meet the criteria of Appendix "B", 10 CFR 50,
. e-p 3
at least 'nce o per 24 months. ,
. e E e. The Emergency Plan and' implementing procedures at least-once--per. _.
y ~24 months.
]
3 f. The Security Plan an'd implementing procedures at least once per - g 24 months. - M g. Any other area of unit operation considered appropriate.by the NSRC or the Senior Vice President, Power Operations. N..h The Fire Protection Program and implementing procedures at least once per 24 months.
] i. An independent fire protection and loss prevention inspection and I j9 audit shall be performed annually utilizing either qualified offsite P -Y licensee personnel or a qualified outside firm.
- d- j . An inspection and audit of the fire protection and loss prevention -
d program shall be performed by an outside qualifieti fire consultant at intervals no greater than 3 years.
. k. The radiological environmental monitoring program and the results l q thereofgat least' once per 12 months.
- 1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at
. least once per 24 me.nths.
- m. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.
M. e pArform ce activities" required by the uality Assurance gf p iee t r tev at . ide . a, +ivo 1, ~ - ruary 19 at least once per 12 months. AUTHORITY . 6.5.2.9 The NSRC shall report to and advise the Senior Vice President, Power Operations or, those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8. SUMMER - UNIT 1 6-10
,jgL ci.
,-,,--.-,--e~~- c=~-.-.- , . . - - - - --
.-~~7-- -
l ADMINISTRATIVE CONTROLS _ 6.9 1.9 The radioactive effluent release reports shall include a summary of I the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 2.21 " Measuring . Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Efflucats from Light-WaterCooled Nuclear Power Plants," Revision 1, June 1974, with data summarir.ed on a quarterly basis following the format of Appendix B thereof. The radioactive effluent release report to be subcitted within 60 days after 4 January 1 of each year shall include an. annual sumrrary of hourly meteorological { data collected over the previous year. This annual st.mmary may be either in .' q
-- the form of an hour-by-hour listing of wind' speed, wind direction, and atmes- %
= pheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and 7 atmospheric stability. This same report shall include'an assessment of the ~
radiation doses due to the radioactive liquid and gaseous affluents released j t o from the unit or station during the previous calendar year. This same report r-shall also include an assessment of the radiation doses from radioactive Df
,% 7 liquid and gaseous effluents toimembers of the public due to their activities inside the site boundary (Figures 5.1-3 and 5.1-4) during the report. All jg ny assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. 9 4 meteorological ,$ 4I conditions concurrent with the time of release of radioactive materials in
. gaseous effluents (as datermined by sampling frec;uency and measurement) shall be used for determining the gaieous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The radioactive effluent release report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely snost exposed member of the public TQ)m reactor releases and other neart,y uranium fuel cycle sources (including ooses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show-conformance with' 40 CFR 190, Environmental Radiation Protection Standards ~ for Nuclear Power Operation. Acceptable methods for calculating the dose contribu-tion from licuid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. The *adioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:
- a. Container volume, ,
- b. Total curie quantity (specify whether determined by measurement.or. .
estinate ), j
- c. Principal radionuclides (specify whether determined by measureme'nt or estimate),
- d. . Type of e ste (e.g., spent resin, compacted dry waste, evaporator bottois'),
, . g .,
C.,. a.u SUMMER - UNIT 1 6-17
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