ML20112C430
| ML20112C430 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/15/1985 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 GN-548, NUDOCS 8503210428 | |
| Download: ML20112C430 (35) | |
Text
_. - _ _ - _. _ _ _ _ _ _ - - - _ _
Georgia Power Company Project Management RoutJ 2. Box 299A Waynesboro, Georgia 30830 Telephone 404 724 8114 404 554 9961 Vogtle Project March 15, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention:
Ms. Elinor G. Adensam, Chief Log:
GN-548 Licensing Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 REF: DENTON TO FOSTER, DATED 2/19/85, STAFF REPORT -
VOGTLE CONFORMANCE TO REG. GUIDE 1.97 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 REQUEST FOR SUPPLEMENTAL INFORMATION DSER OPEN ITEM 62 - REGULATORY GUIDE 1.97, REV. 2
Dear Mr. Denton:
Attached for your review are three copies of the GPC response to the referenced letter (Attachment 1) and three copies of the proposed FSAR change (Attachment 2).
If your staff requires any additional information, please do not hesitate to contact me.
Sincerely, l.
(* /
J. A. Bailey Project Licensing Manager JAB /sm Attachment xc:
D. O. Poster R. A. Thomas G. F. Trowbridge, Esquire J. E. Joiner, Esquire C. A. Stangler L. Fowler M. A. Miller
[
L. T. Gucwa p
G. Bockhold, Jr.
32 g g h 4
0039m E
ATTACHMENT 1 3.3.1.
REACTOR VESSEL WATER LEVEL Georgia Power Company procured the reactor vessel water level system as a fully qualified system.
This is reflected in the information provided in Table 7.5.2-1 on qualification, control room indication, and power supply columns referenced for this system.
For additional information concerning the qualification of this system, please refer to Amendment 15 Apendix 4A concerning the Reactor Vessel Level Instru-mentation System (RVLIS).
The Type / Category in FSAR Table 7.5.2-1 (Sheet 3 of 11) will be revised in Amendment 16 to B1, C2, D2.
3.3.2. CONTAINMENT ISOLATION VALVE STATUS The instrumentation and power supplies for the containment isolation valves, as noted in the FSAR Table 7.5.2.-1 (Sheet 3 of 11), meet the intent of Regulatory Guide Category 1 instrumentation.
For isola-tion valves in series, a single indication on each valve is sufficient to satisfy the requirements of Regulatory Guide 1.97 when those indica-tions are from different trains.
3.3.3.
PRESSURIZER HEATER STATUS Plant Vogtle has selected pressurizer heater breaker position as the variable for determining the status of the pressurizer heater banks that can be loaded on the emergency busses.
The breaker position is adequate for the following reasons:
1.
If a postulated short occurred in the heater banks while connected to the emergency busses (one bank is loaded on one train and the other bus is loaded on the other train), the circuit breakers associated with this short circuit would trip thereby isolating the short and precluding any power requirement that would exceed the capacity of either emergency diesel generator.
Alarms are initiated in the control room if any breakers trip on overload.
Plant Vogtle Emergency Operating Procedures (E0P's) allow full loading of stub bus INB01 for train A (or of stub bus INB10 for train B) under administrative controls.
Administrative controls are allowed after the Safety Injection (SI) signal has been reset and the Engineering Safety Feature (ESF) loads have been sequenced on their lE bus.
Plant Vogtle E0P's use heater breaker position for verifying heaters available.
2.
Section II.E.3.1 of NRUEG-0737 only requires that a certain number of pressurizer heaters (two banks for Plant Vogtle) be capable of being loaded on the emergency diesel generators.
Pressurizer heater current indication is not required by NUREG-0737 in the control room.
3.
The Plant Vogtle Emergency Operating Procedures instructs the operators to utilize heater breaker position to verify that the heaters are engaged.
l.
4.
Other parameters are provided that indicate performance of the heaters. These include:
o Pressurizer Pressure o Core Exit Thermocouples o RCS Subcooling As such, Georgia Power Company believes that heater breaker position is adequate to monitor the status of the pressurizer heaters.
1-3.3.4. ACCUMULATOR TANK LEVEL AND PRESSSURE i
ACCUMULATOR TANK PRESSURE Accumulator tank presure was originally specified as a Category 2, l
Type.D variable in Table 7.5.2-1 of the FSAR.
However, based upon plant design and preparation of plant specific Emergency Operating Procedures, accumulator pressure has been downgraded to a Category
- 3. Type D variable.
The primary post accident monitoring variable for monitoring the status of the accumulator pressure is wide range RCS pressure.
This variable is considered adequate for the following reasons:
1.
The wide range RCS presure transmitters for Plant Vogtle are located outside containment. The maximum channel inaccurancy calculated for these channels is 13 percent of range or 90 psi.
2.
The plant specific Emergency Operating Procedures utilize wide range RCS for determining the status of accumulator pressure and for accumulator isolation.
3.
The following additional variables are considered for determining accumulator isolation:
RCS Subcooling SG Pressure RCS Hot Leg Temperature As such, wide range RCS pressure and the additional variables provide adequate information to the oparator for determining the status of accumulator pressure, determining if the accumulator should be isolated or vented when proceeding to a cold shutdown condition, and determining if the accumulator has. discharged following a postulated accident.
Hence, the accumulator pressure variable can be downgraded to Category
- 3. Furthermore, the range of the installed accumulator pressure trans-i mitters is 5% above the safety setpoint of the accumulator safety valve.
a
~,,- -,-, -- -
ACCUMULATOR TANK LEVEL Accumulator-tank level has been classified as a Type D, Category 3 variable on Plant Vogtle.
Accumulator isolation valve positon (MOV-8808 A, B, C, D) and accumulator vent valves (HCV-943 A, B) and wide range RCS pressure provide the operator adequate information to monitor the status of the accumulator.
The accumulator isolation valve status
.and the vent valve status (one pair of lights per valve) are included in the emergency core cooling system valve status item listed in Table 7.5.2-1 (Sheet 5 of 11) in the FSAR.
3.3.5 CONTAINMENT ATMOSPHERE TEMPERATURE Containment atmosphere temperature is not a VEGP key variable.
The VEGP key variables for monitoring the accomplishment of containment cooling are containment spray flow, containment water level, containment spray valve statcs, containment spray pump status, containment pressure, containment fan cooler damper position and containment fan cooler breaker position.
Immediately after containment spray is initiated, the contain-ment atmosphere is saturated and the temperature is known because the pressure is known.
Since the operator will not use this parameter to verify containment cooling, containment atmosphere temperature has been classified as a Category 3 parameter.
Table 1 provides information on the Category 3 containment atmosphere temperature.
3.3.6 CONTAINMENT SUMP WATER TEMPERATURE Containment sump temperature is not required for emergency core cooling system (ECCS) operation or assurance of NPSH, because NPSH calculations conservatively assumed saturated water was present.
See FSAR Subsection 6.2.2.
Containment water level measurements indicate the amount of water and as described above, containment cooling is verified by other parameters.
Therefore, containment sump water temperature has been classified as a Category 3 parameter.
Table 1 provides information on the Category 3 containment sump water temperature instrumentation.
3.3.8 ACCIDENT SAMPLING The post accident sampling system is described in FSAR paragraph 9.3.2.2.5 and response to NRC question 281.12 (behind March 13, 1984 tab).
3.3.10 DEGREES OF SUBC00 LING As noted in Table 7.5.2-1 (Sheet 2 of 11), the qualification status, control room indication, and power supply meet the requirements of Regulatory Guide 1.97.
The Type / Category column will be revised in Amendment 16 to indicate A1, 81, D2.
k 3.3.11 CONDENSER AIR EJECTION RADIATION The condenser air ejection radiation monitors are located in a non-seismic designed building and are located in non-seismically qualified equipment.
Thus, these monitors cannot be qualified to meet Category I criteria.
A review of the E0P's has indicated these monitors serve in a back-up function to the steam generator level monitors and the main steam line radiation monitor. Based upon the usage of the monitor, the appropriate type / category is E-3 and Table 7.5.2.-1 will be revised accordingly.
3.3.12 AREAS OF ADDITIONAL NONCOMPLIANCE 1.
Reactor coolant system soluable boron concentration is a part of the post accident sampling system.
(See item 3.3.8 above.)
2.
Radioactivity concentration or radiation level in circulating coolant is part of the post accident sampling system (see item 3.3.8 above).
3.
Analysis of primary coolant (gamma spectrum) is part of the post accident sampling system.
(See item 3.3.8 above.)
4.
Containment effluent radioactivity is monitored by the plant vent monitor included on FSAR Table 7.5.2-1 Sheet 3.
The plant vent receives the discharge from the containment purge system, auxiliary building, control building, and the fuel handling building.
5.
Accumulator isolation valve status is a part of the ECCS valve status included on Table 7.5.2-1 Sheet 5.
6.
Reactor coolant pump break position will be added to Table 7.5.2-1 of the FSAR in a subsequent amendment as a Type D, Category 2 variable.
These variables are the same that are utilized in the algorithm for the Plant Vogtle Reactor Vessel Level Instrumentation System (RVLIS) to determine the appropriate scaling factors that should be used by the operator dependent upon the number of operat-ing reactor coolant pumps.
7.
Pressurizer relief tank level information is provided in Table 1.
8.
Pressurizer relief tank temperature information is provided in Table 1.
9.
Pressurizer relief tank pressure information is provided in Table 1.
- 10. High Level Radioactive Liquid Tank Level An indication of high tank level or other concerns associated with this system is annunciated to the control room.
An operator would be dispatched to the local control panel to clear the annun-ciated signal.
- 11. Radioactive Gas Holdup Tank Pressure An indication of high pressure would be annunciated to the control room.
An operator would be dispatched to the local control panel to clear the annuciated signal.
12.
Emergency Ventilation Damp Position This variable is included in Table 7.5.2-1 (Sheet 7 of 11) as a part of the heating, ventilation, and air-conditioning system status.
1 1
TABLE 1 MISCELLANE0US CATEGORY 3 VARIABLES QUALIFICATION NUMBER OF CONTROL ROOM POWER E0F TSC VARIABLE RANGE _
TYPE / CATEGORY ENVIRONMENTAL SEISMIC INSTRUMENTS INDICATION SUPPLY INDICATION INDICATION C:ntainment 0-4000F D3 No No 1
Yes Non-lE Yes Yes Atmosphere UPS Temperature Centainment 0-4000F D3 No No 2
Yes Non-1E No No-Sump Water UPS Temperature Pressurizer 0-100%
D3 No No 1
Yes Non-1E Yes Yes R31ief UPS Tank Laval Pressurizer 0-100 D3 No No 1
Yes Non-lE Yes Yes Ralief Tank psig UPS Pressure Pressurizer 50-3000F D3 No No 1
Yes Non-lE Yes Yes R311ef Tank UPS Temperature E
=
TABLE 1 MISCELLANE0US CATEGORY 3 VARIABLES QUALIFICATION NUMBER OF CONTROL ROOM POWER E0F TSC VARIABLE RANGE TYPE / CATEGORY ENVIRONMENTAL SEISMIC INSTRUMENTS INDICATION SUPPLY INDICATION INDICATION Centainment 0-4000F D3 No No 1
Yes Non-1E Yes Yes Atmosphere UPS Temperature Containment 0-4000F D3 No No 2
Yes Non-1E No No Sump Water UPS Temperature Pressurizer 0-100%
D3 No No 1
Yes Non-lE Yes Yes R21ief UPS Tank Level Pressurizer 0-100 D3 No No 1
Yes Non-lE Yes Yes R211ef Tank psig UPS Pressure Pressurizer 50-3000F D3 No No 1
Yes Non-1E Yes Yes R211ef Tank UPS Temperature
-J ATTACHMENT 2 The. ins humen falian reguire) 4. w\\
VEGP-ESAR-7 Qie a[/er A Seismic m /
\\
g p.
l is /be Saleh-reldal Cold Sbu/huur I
Design Criteria for Category 2. /ndrumen/a6 described in 7.5.2.3.2.3 Secis,on ?.V.
" ' _C A.
Category 2 instrumentation
4-*-
crfr*y
--'**ad ryrt: f"that are required to operate following a safe shutdown earthquake to mitigate a consequential plant incident are energized from a seismically qualified power source, which is battery backed where momentary interruption is not tolerable.
Otherwise, the instrumentation is energized from a
(
highly reliable onsite power source, not necessarily the emergency standby power, which is battery backed where momentary interruption is not tolerable.
The out-of-service interval is based on normal plan 4 Scheddel B.
T;;hnic:1 Specificati n ::quiremento fwu th: cy:ter i*,_
ser ::
?. crc applicable ci hes= spucified by viher %
aquir-mae =s ref uelig oidges.
C.
Servicing, testing, and calibration programs are specified to maintain the capability of the monitoring instrumentation.
For those instruments where the required interval between testing is less than the normal time interval between generating station shutdowns, a capability for testing during power t
operation is provided.
D.
Whenever means for removing channels from service are included in the design, the design facilitates administrative control of the access to such removal means.
_ E.
The design facilitates administrative control of the access to all setpoint adjustments 7 module calibration adjustments, and test points.
F.
The monitoring instrumentation design minimizes the potential for the development of conditions that would cause meters, annunciators, recorders, and alarms, etc., to give anomalous indications that could be potentially confusing to the operator.
G.
The instrumentation is designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.
H.
To the extent practicable, monitoring instrumentation inputs are from sensors that directly measure the desired variables.
An indirect measurement is made only when it can be shown by analysis to provide unambiguous information.
7.5.2-11
\\
\\
s.
TABLE 7.5.2-1 (SHEET 1 OP ll)
POST-ACCIDENT MONITORING INSTRUMENTATION Quallrication Number of implemen-power EOF TSC Range /
Type /
Environ-
. Instru-Control Room tation Sup-Indica-Indica-Va riable Status Category mental Seismic; pents Indication Date ply tion
$lon Conformance i
Re:ctor coolant 0 to 3000 A1, 81, Yes Yes j 4 per unit Plasma display coro load IE Yes Yes conforms to prossure (wide pst B2, C1, 9 9 meters Reg Culde rcoge)
C2, D2 1 dual 1.97, Boy 2 reca rde r gi RC3 wide range 50' to A1 2
Yes Yes ' 1 per loop Plasma display Complete 1E Yes Yes Conrores to 4 meters Reg Culde i
750*r i
l l 3 dual 1.97, Bev 2 m
Si recorders RCS wide r...ge 50* to Al, B2 Yes Yes ' I per loop Plasma display Complete 1E Yes Yes conforms to 4 meters Reg Culde T,
750*f j S dual 1,91, Bey 2 recorders Wic3 range O to 100 Al, Bl.
Yes Yes 1 per Plasma display Complete 1E Yes Yes Conforms to a
g sts:n genera-percent B2, D2 steam 4 meters Reg Culde g'
tar water or span generator I y dual 1.97, par 2 g
1: val l
recorders en en Harrow range O to 100 A1, Bl.
Yes Yes 't & pe r Plasma display Complete IE Yes Yes Conrores to
- p storm genera-pe rcent D2 steam 12 meters Reg Culde
- 3 ter water or span gene ra to r
-- ' r; 1 97, Rev 2 1N 10v31 Pressurizer 0 to 100 Al, 81, Yes Yes 3 per unit Plasma display Complete 1E Yes Yes Conforms to I val pe rcent D2 3 meters Reg Culde or span I recorder 1.97, rey 2 Containment 0 to 75 A1, 81, Yes Yes al per unit Plasma display Complete IE Yes Yes Conforms to pr ssure psig B2, C1, 4 meters Reg Culde C2, D2 1 dual 1.97, Rev 2 recorder Stsam line O to 1300 A1, B1, Yes Yes 3 per loop Plasma display Complete IE Yes Ves Conforms to pr ssure psig D2 12 meters Reg Culde 2 dual 1.97, Sev 2 recorders Refueling 0 to 100 A1, D2 Yes Yes 4 per unit Plasma display Complete 1E Yes Yes Conforms to w,ter storage pe rcent 4 meters Reg Guide t;nk level or span 1 dual 1.97, Bay 2 recorder Containment 0 to 8 8 A1, Bl.
Yes Yes por unit Plasma display Core load IE Yes Yes Conforms to 6
w2ter level in.
82, C2,
- =ser:ozzier Reg Guide (parrow range)
D2 1.97, Bev 2 w
l TABLE 7.5.2-1 (SHEET 2 OF ll)
Qualification k Number or Implemen-Powe r Ecr TSC Range /
Type /
Inviron-Instru-Control Room tation Sup-Indica-lodica-Va ria ble Status Category mental Seismic monts indication Data ply tion tion Conformance Containment 48 to 168 A1, 81, Yes Yes 2 per unit. Plasma display Complete IE Yes Yes conforms to water level in.
82, C2, 2 meters Reg Canide (wide range)
D2 1 dual 1.97, Rev 2 3
recorder condensate O to 100 A1, D2 Yes Yes 2 per tank Plasma display Complete IE Yes Yes conforms to stirage tank percent 4 meters Reg Culde I; vel of span 1 dual 1.97, Rev 2 reco rde r Ausci l la ry 0 to 1000 AI, 81, Yes Yes 2 per loop Plasma display Core inad IE Yes Yes conforms to reedwater riov gal / min D2 4 meters Reg Guide 1.97, Rev 2 h
Containment i to 10' A1, 81, Yes Yes 2 per unit Safety-Complete IE Yes Yes Conrores to rd lation level R/h 82, E2 related dis-Reg Guide o
(wide range) aplay consolo 1.97, Rev 2 42 I
containment 10 to A1, Bl.
Yes Yes 2 per unit sarety-Core load 1E Yes Yes Conforms to 4
rc0lation level 10 R/hr 82, E2 related dis-Reg Guide 8
i (narrow range) play console 1.97, Rev 2 y
Stramilne 10 to A1, 82, Yes Yes I per loop Safety-Core load IE Yes Yes Conforms to h
-3 3
rmjlation 10 pCl/ca' E2 related dis-Reg Culde monitor play consolo 1.97, Rev 2 Core exit 200 to A1, 81, Yes Yes 4 per core plasma display Core load 1E Yes Yes conforms to temperature 2300*r Cl quad rant Reg Culde Per train 1.97, Rev 2 A s,5 8, D Z.
i RCS subcooling 200*f sub-at-st Yes Yes 1 $ per unit Plasma display Core load 1E Yes Yes conforms to cooling to F
Reg Guido 35*r l
1.97, Rev 2
/ gg h superheet Condenser air p l# to M
Was No 1 por unit Communication Completo Non-1E Yes Yes S h (T g ejector i 1 Cl/cs g3 No console s
desmob-
[fy M
,7 pg 7g radiation Neutron flux 10 to p1 Yes Yes 2 por unit plasma display Core load IE Yes Yes conforms to E3T8M i C [/3 0 Pe r-Reg Guide cent or 1.97, Rev 2 rull power
' -6 10 i
o TABLE 7.5.2-1 (SiiEET 3 OF 11) s.
_,stua l i r i r.e t g ust Numtwil of implemen-rower (Of ISC staeule/
lylM?/
t rav s e me-Insten-Control Huam tation Sup-Indica-Indica-
,j el j_ga t i on..
._pate__,.
Illy __
tion
_g i ort Conrormaneg d
Yart @ ty 5 tp tges fayegot'y..F'! t d l bl!i. sm 8 9
. Pen t _s.,
accac tor vessui o to 100 iha-+f Yes vsr s 2 por exis t riassa display I'u s er load II Yes Yes (1) water level pcrrent p leseum El,C I,02.
lusight t to to laws P " E hp reactor ve s w l hd tun i gh t r un t a i sinceit open/
C2. 122 vus vos per I pair or Complete IE Yes Yes (a) p0N $%
his e so n.s t e un va l ves c losed valvo liglits per valve h
status 4^. mea s u s r u.9 o to 2/3 g
No No 2 per con-L a glit-emi t t ing Complete Non-li Yes Yes Conrores to trol rod diodes Reg Guid.
p.. s i...
,tep, m
4.97. Rev 2 e.ulicateun a:en t a i sumen t o to tu li t. Cl ves Yes 2 per unit 2 meters Complete it,
Yes Yes Conforms to g
I dual Reg Guide g
liydi valen pescent t osic en t ra t ion partial reco rde r 1.97, Rev 2 sig press"ro tn containment
-5 to 160 Cl. C2 Ves Yes 2 per unit Plasma display Core load IE Ves Yes Conforma to p
Reg Guide N
p s'e s sa.s o psig 1.9T, Rev 2 l
lestended 4
raswac )
riant vent to to C2 E2 Yes Yes 1 per unit 3 meters Corr eoad Non-lE Yes Yes Conforms to
_ level 10 Ci/cmo communication eH eee4 -
Reg Guide
([
bee $ sed 1.97, Rev 2 console radiogas Plasit vent prNA C2 (2 Yes Yes NA NA Complete NA MA NA Conforms to Reg Guide t icula tes asul 1.97, llev 2 ha logen ( pa s-sihe reiters)
- M
' Site enveron-MA C3, E3 N0 No NA M4 Complete NA NA NA Conforms to Reg Guide mental 1.97, Rev hh radiation sewel (D G
( po r t atale p ;3 samplang) ncS activity See C3 No No 1
PASS Complete NA Yes Yes (tm) 10 3 C3.
(post-accident pa rag raph g1 ye samp l issa 9.3.2.2.5 l
de W
[~ g l*O signal (rASS))
,-. e go c3 m
A g
MA C T eTe g6d(-
h Be4be7 Mhdj f.q ge v '2 Ital. h L m l
( f TTabt, 5M[!I8}
f iW d capleTe iE yas y,,
ksstTw Co*I**T otE@a O t.
it s-Ws i i pze P
u;r.,5 elesc pa af LyVsp*<f=*lf
~.
.4 fesSSurIW
'Y pl Nth Ec5 f 4PtV Y mTssa coarf eTe IE ye.s yas q) l Pr I volume control closed yelvg ll hts per lion-1E d*1selsT**/ g8'ig sy; tee valve ye ve t//3 J
/
st;tus 1
/.77 /(f g/ 7, Cheelcal and on/orf D2 Yes Yes I per pump 1 pair of Complete 10 Yes Yes (c) volume control lights per i
ty;tes pump pump st;;;tus j
Reactor 0 to 20 D2 age Yes 1 per pump al esters Complete lion-1 E Yes Yes (c) coolant pump gal / min UFS l
seal injec-l tion flow l
steam generator open/
D2 Yes Yes 1 per 1 pair of complete lion-1E Yes Yes Conforms to closed yelyg it Reg Guide
[ cteospheric veIhtsper llP3 1.97, p,y 3 -
()
roRY status v,
l Mein stese line open/
B2, 02 Yes Yes 1 per 1 pair of Complete IE Yes Yes (d) p isolation valve closed
.yglyg lights per w st;tus j
yelye l
-s I
co W
i h
TABLE 7.5.2-1 (SHEET 4A OP 11)
Qualification Number of implemen-Powe r EOF TSC Range /
Type /
Environ-Instru-Control Room tation Sup-Indica-Indica-Variable Status Cateoorv mental Seismic wnts indication Date olv tion tion Confo rma nce Main steam Open/
15 Yes Yes 1 per 1 pair or Complete IE Ies Yes (d) isolation closed valvo lights per valve bypass 8 1 0 2.
vaive isolation valve status O
M 1
M CO l>
lc I
H l
o l
p.
H A
NNa)
Ut m
i gem Ge:c48?
oz ya yo,
'F Do oy se g u 1"/
kre
/g yo y,
gj)
Is g 1*~
ya yo dated STw y
l 94sr oln Sfah 5 TABLE 7.5.2-1 (SHEET 5 OP 11)
Quallrication Number of implemen. power EOF TSC Range /
Type /
Environ-Instru-Control Room tation Sup-Indica-Indicq-3 Va riable Status Category septal Seismic sents indication Date ply
$100 tion Conformance Steam generator 0 to 5 D2 Yes Yes 2 per 8 meters Complete Non-1E Yes Yes Conforms to tystem status ellflon stese 4 recorders UPS Reg Guide main steam flow Ib/h generator 1.9h Rey a Maln reedwater Open/
D2 Yes Yes t I per loop 1 pair or Complete IE Yes Yes (d) control valvo closed lights per st:tus velve Main reedwater Open/
D2 Yes Yes 1 per loop 1 pair of Complete IE Yes Yes (d) typass valve closed lights per etetus valve (e)
No Main reedwater o to 5 D2 Yes yes.
2 per 8 meters Complete Non-1E Yes Yo, Conrores to flow million stese 4 recorders UPS Reg Guide Q
lb/h
. gene ra tor 1.97, Rev 2 g
Stsam generator Open/
D2 Yes Yes I per 1 pair of Complete IE Yes Yes (4) y blowdown closed i valve lights per en laelation valve
[
valve to status
~
H h-head O to 1000 D2 Yes Yes 1 per unit 1 meter Complete IE Yes Yes Conrores to strety gal / min j
Reg Guide 4
injection 9
1.9T, fiev 2 tow-head 0 to 800 D2 Yes Yes 1 per 2 meters complete IE Yes Yes Conforms to screty gal / min
!f(rein Reg Culde IRJection i
1 97, Rev 2 Hain reedwater Open/
D2 Yes Yes 1 per 1 pair or Complete IE Yes Yes (d)
Isolation valve closed valve lights per et tus valve Emergency core Open/
D2 Yes Yes 1 per 1 pair or Complete IE Yes
.Ye s (d) cooling system closed valve lights per v31ve status valve Accumulator 0 to 700 m D3 Wes Woe 1 per tank 4 meters Core load Non-1E Yes Yes
- fessure psig UPS i
p f /
l I
Safety injec-On/orr D2 Yes Yes 1 per pump 1 pair or Complete IE Yes Yes (d) tion pump lights per status pump Auxillary feed-Open/
D2 Yes Yes 1 per 1 pair of Complete 1Ef Yes Yes (d) water valve closed valve lights per flesp4C ststus Yalve i
l m
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i TABLE 7.5.2-1 (SHEET 6 OP 11)
I i
Quallrication llumber or leplemen-Powe r E0r TSC Range /
Type /
Environ-Instru-Control Room tation sup-Indica-Indica-Va riable status Category sental Selselc songs indication Date ply tion tion Conronsance Auxillary reed-dn/off D2 Yes Yes 1 per pump 1 pair of Complete IE Yes Yes Conforms to water pump lights per Aeg Guide g (*)
g pump 1.97, pov 2 status Containment 0 to 300 02 4le woe 1 per unit 1 meter
- Complete Non-1E Yes Yes (d) spray flow gal / min UPS g
Containment Open/
D2 Yes up 1 per 1 pair of Complete IE Yes Yes (d) spray valve closed volve lights per status Yd Y'IV' containment On/orr D2 Yes 3
1 per pump 1 pair or Complete IE Yes Yes jd) spray pump lights per l
status pump Cantainment Open/
D2 Yes Yes, 1 per 1 pair of Complete 1E Yes Yes (d)
]
ran cooler closed deeper lights per deeper position deeper Containment High/ low D2 Yes Yes ' 1 per 1 pair of Complete II:
Yes Yes (d) h fcn cooler speed, on/
breaker lights per
- ss i
b reake r off breaker po' j
position
- I
~
to)
M ComponentA 0 to 200 D2 Yes Yes 1 per 2 meters complete Non-1E Yes Yes (d) coollag water psig
+
pressure to) l Component 0 to 02 5
als 1 per 2 recorders Complete Ison-1E Yes Yes Conrores to cooling water 300'r trgin UPS Reg. Guide i
header 1.97, Itev 2 tempe ra ture ce) component 0 to 100 D2 er Yes l 1 per 2 meters complete Ilon-1E Yes Yes (d)
)
cooling water pe rcent f train 2 recorders Urs curge tank Fu (g
[
Isvol Component 0 to D2
%k Ye5 1 pe r 2 meters Complete leon-1E Yes Yes Conrores to cooling water 15,000 trein Urs peg Culde i
riow to gal / min 1.97, Rev 2 cng inee red 1
s3rety features i
components
,u.,r 1 pair of, Complete IE Yos-Yes (J)
(
component on/orr D2 Yes Yes 1 pe Iig,,ts,e coolI,,g uster i
pump status pump putu,qc.f[gf*,822 h-N8 No k
hs[ ze
- z.,,Je< s co+pl#c c u3 wenc i
e<
- s. ur cat
4 4
i TABLE 7.5.2-1 (SHEET 7 OP 11) 1
- ^
I J uallrication Number of Implemen-Powe r EOF TSC Range /
Type /
Environ-I n s t ru-Control Room tation Sup-Indica-Indice-monts Indication Data ply
$lon tion Conformance mental ) Selselc Varlsble Status Ca tego ry Ves (0 Nuclear service O to D2 gp Yes 1 per 2 meter Complete Non-1E Yes Yes (d) cooling water 10,000 train UFS system flow gal / min Nuclear service Open/
D2 Yes Yes 1 per 1 pair of Complete IE Yes Yes (d) toolln; water closed valve lights per valve status valve Yesl 1 per pump 1 pair or Complete IE Yes Yes (d)
Nuclear service On/of f D2 Yes cooling water lights per pump status pump N. clear service On/off D2 Yes Yes.
I por fan 1 pair or Complete IE Yes Yes (d) coollog water lights per fcn status fan p1 O
- Heating, open/
D2 Yes Yes.
1 per 1 pair of Complete IE Yes Yes (d) 93 I
v:ntilation, closed damper lights por cnd a i r-con-daeper
((
ditioning l}
system status Eng inee red High/ low D2 Yes Ye5 1 por ESF 1 s p a ra per Complete IE Yes Y95 (30 da s:rety component channel cnvironment (dj )
h fcatures (ESF) temperature
[SF environ-Open/
D2 Yes Yes 1 per ESF 1 pair of Complete IE Yes Yes (d) ment cooler closed componen$
lights per fcn status channel Ac, de, vital aus D2 Yes Yes 1 por bus 1 meter per complete IE Yes Yes Conforms to Instrument specific bus Reg Culde 1.97, Sev 2 v38tage y
Residual heat 80' to D2 Yes NDr 1 por 2 recorders Core load Non-1E Yes Yes Conforms to removal (RHR) 400*f grain UPS Reg Guide 1 97, Rev 2 beat exchanger d i scha rge tempe ra ture RHR flow 0 to 6000 u/
Yes Yes.
1 per 2 meters Complete IE Yes Yes Conforms to gal / min trein Reg Culde 1 97, Rev 2 RHR valve Open/
D2 Yes Yes 1 per I pair or Complete 1E Yes Yes (d) status closed valve lights per Yelve t
n
Si AeTudTIch Ln/
D2 Ves
%5; Ipe I og7
(,9je7e pg
/
YU hs (j) txT OT g.ra
,a m;n TABLE 7.5.2-1 (SIIEET 8 OF 11) ouallrication Number or mplemen-Power Ear TSC Range /
Type /
Environ-instru-Control Room tation Sup-Indice-Indica-Va ria b le Status Category mental Seismic ments Indication Date ply tion tion Conformance.
L RHR pump On/off 02 Yes Yes 1 per pump 1 pair or Complete IE Yes Yes (d) status lights per 4. Loser:1 l$
F"*P Reactor trip Open/
D2 Yes Yes 1 pe r
'l pair or Complets 1E Yes Yes (d) breaker closed Dreaker lights per position
(,)
breaker Turbine stop Open/
D2 No 1 per 1 pair or Complete Non-1E Yes Yes (d) valve status closed yelve lights per valve first stage O to 800 D2 Yes Yes 1 per 2 meters Complete IE Yes Yes (d) turbine psig train pressure c)
"U Plant vent 0 to W E2 Yes Yes 1 per 5: nit I meter Core load Non-1E Yes Yes conforns to I
y"3 Clrriov rate 300,000 d4esw4-Reg Guide It'/e'n Deshed 1.97, llev 2 ggg Area raalation (f) y monitors q
r Control room 10 2 to E3 No No I per communication Complete Non-1E Ye9 Yes (a) monitor 103 mr/h plant console diesel-t backed s
Radiochemistry 10*-1 to E3 No No I 1 per Communication Complete Non 1E Yes Ye9 (e) g3 lab monitor 10 me/h plant consolo diosal-backed fuel handling to-a to E3 No No i per Communication Complete Non-lE Yes Yes (c) building 10
- ar/h
~
i backed plant console diesel-sonitor No f 1 per Sampling room 10-1 to E3 No Communication Complete Non-1E Yes Yes (e) l3 monitor 10
- ar/h plant consolo diesel-g backed y Decontamina-10-1 to E3 No No 1 per Communication Complete Non-1E Yes Yes (9) tion station 10
- mr/h plant consolo diesel-g, (large paths) backed i
w Decontaa...a-10*1 to E3 No No !
I per Communication Complete Non-1E Yes Yps (p) h3 tion station 10 mr/h p*lan$
consolo diesel-w (small paths) backed V*
N Instrument de-10 3 to E3 No No 1 per Communication Complete Non-1E Yes Yes (g) 4 CD contamination 10
- ar/h plant
- console, diesel-a station
{
backed l
i
- .=.
l l
TABLE 7.5.2-1 (SHEET 9 OF 11)
I Cano;<maI~
NA g3 po p
NA' NA Co,epido gg pp
,,g
~
R Seq sllGlen
<a 4
Quallrication i flumber of implemen-Power
[0F TSC Range /
Type /
Environ-instru-Control Room totion Sup-Indica-lpdica-Verlsble Status Category mental Selselp
- ment, lodication pate ply tion tion Conformance Meteorological NA E3 80 0 No flA 16A Complete NA flA flA Conforms to ltog Guide carameters 1.97, llev 2 (f)
Containment etmospheric temperature f
(g) containment sump water p
45mpe ra ture j
Heat removal (h) by the con-tsineent ran M
heat removal O
'If system I
CIntainment (4)
]
sump, contain-h ment atmos-phere, and g
i prima ry q
crolant simpling
-(J)
Boric acid charging flow 6'
RCS extended (IL) r:nge pressure (m)
Accumulator tank level 6
l 6
o i
I
'?
TABLE 7.5.2-1 (SHEET 10 OP 11)
\\ c.,m;mT isalatu vatus u vah f on. powded w.7A ~ s%h nJiuTim n e-< L n tu,x jd;uTIO,tg {ar YWe llalMS Irt St v, s s y
pg Q c/,'((ege;7 Q,%,
t o.
Containment Isolation valve Status - variables which indicate actual breach, including containment isolation valve status, have been designated as preferred backup information and are qualified to Category 2 criteria. A RCS Activity - Post-accident sampling system will be used to, measure RCS activity, b.
Pressurizer Heater Status - Regulatory Guide 1.97, Rcv 2 specified that heater current was the preferred parameter for determining heater status, for the VfCP heater breaker position, not current indication, was selected for determining c.
pressurizer heater status due to hardware considerations. Dreaker position provides adequate indication to the operator 3
to ensure the pressurizer heaters are operable.
in the minimum set of parameters d.
The plant specific study performed on VECP indicated tha$ these parameters were included necessary to monitor the performance of:
safety systcas employed for mitigating the consequences of an accident and subsequent plant recovery to attain 1.
Plant a cold shutdown condition, including verification of the automatic actuation of safety systems.
2.
Other systems normally employed for attaining a cold shutdown condition.
h Area Radsation - VfCP will use health physics plant survey monitoring to determine radiation levels ire the areas or locations where post accident access may be required or which may contain a significant post-accident radiation source, e.
g Ibe VICP emergency response guidelines do not require the operator to take an action f
Containment Atmospheric Temperature -
As such, the eq f.
in adverse consequences if the containment temperature was indicating an erroneous value.
that would result containment temperature indication is considered a Category 3 parameter.
indication is not utilized by th operator to
g.
system is operating properly when taking suction from the containment sump. As s.,4j 744 camTeinme,T s,.y e,g T.4 r g /n,[~e. T/g 4
.M a s fu.
15 c o,e s,-de sc.(
4.
Ca feq a y J r
an/ Heat itemoval System - Other parameters were designated as VfCP type D variables to fl.
ifeat Hemoval by the Con t'a i nmen t demonstrate that the containment heat removal systems are operating properly. These include the following:
Containment spray flow.
'ontainment spray system valve status.
Containment pressure.
4
- Containment water level.
I Containment spray pump status.
- f an cooler damper position.
- f an cooler breaker position.
Sump and Atmospheric Sampling - Data obtained from containment sump and atmospheric sampling are not used by Hence, these parameters are considered
- i. Containment the operator to take any manual action to mitigate the consequences of an accident.
backup variables (Category 3) and included as part of the post-accident sampling system.
Doric Acid Charging flow - f or monitoring the performance of the emergency Core cooling system (fCCS), VfCP has designated refueling water storage tank level, high-head safety injection flow, low-head safety injection flow, containment water level, J.
and (CCS valve status.
Since the ECCS does not normally tahJ suction f rom the Doric acid tank (SAT), the Doric acid Cha rging h
I
........- ~
m j
l.
t s
TABLE 7.5.2-1 (SHEET 11 OF 'll) designated a key variable.
e r the operator uses the BAT for. boration following an accident, no rma l cha rg ing
[ rsow was not riow and reactor coolant system (RCS) sampling is used to demonstrate that the RCS is being borated, k.
RCS rutended Range Pressure - RCS vide-range pressure will be used.
I.
Althoogte reactor vessel water level provides userol information, it is not required for sarety. Reactor vessel water level instrumentation system (RyLIS) provides anticipatory indication of inadequate core cooling. For these reasons, RVI.lS has been designated Category 2.
/tesTar ces/nT sysfem pkss ettc c.
- ~
!a w r arc = r: indication and valve position indication for the accumulator discharge isolation and accumulator vent valves provide adequate status of the accumulators,
&ume Q,n Te tnSf 04 nteot]
YC**)0' *Y* fo* Tbt - Cfo'tisf b e No'n is speg,' fed n
h g,q q p
n.
Mt w:<susb wn-na, el p& f,
~ ~ - ch.cs
-rLT n do;; 4 f.c
~
ni aa
/E UPS.
g,g &g*tt 5 M
f in their ae7.ch a M se< wn erra:romed.r f., %. p/s,7 g
J,, A
't, parIw ~
f*' A L
- ^'^l ns u d fwTw -
cadmom N
he di W E' A
dr/
dr.-
p-
& mgerde. (auxilikry) P"> ep Stjpk/
or r J by de Al f"*"# "'
s l
(
l c
I i
VEGP-FSAR-7 t'
TABLE 7.5.4-1 (SHEET 1 OF 5)
SUMMARY
OF VARIABLES AND CATEGORIES Type and Category Type Type Type Type Type A
B C
D E
Variable Reactor coolant system (RCS) 1 1,2 ({},2 2
pressure (wide range (WR))
r 1
l WR T hot (hf 1
WR Tcold WR steam generator level 1
1,2 2
Narrow range (NR) steam 1
1 2
generator level 1
1 2
Pressurizer level 1
1,2 1,2 2
Containment pressure 1
1 2
Steam line pressure 1
2 Refueling water storage tank level Containment wa'ter level 1
1,2 2
2 (WR and NR)
Condensate storage tank level 1
l 2
1 1
2 Auxiliary feedwater flow Conta'inment radiation level 1
1,2 2
M4) d (WR an 1
2 2
Steam line radiation monitor 1
1 1
{
Core exit temperature
.RCS subcooling
/()
((h, (hl JP'
-PJ Condenser air ejector 1
eutron flux l
z Edtdel reje i
VEGP-ESAR-7 TABLE 7.5.4-1 (SHEET 2 OF 5)
Type and Category Type Type Type Type Typs Variable A
B C
D E
[I h1 Reactor vessel water level i
2 2
Containment isolation valve status
[
3 Control rod position 1
1 Containment hydrogen concentration 1,2 Containment pressure (extended range) 3 RCS activity Plantvent[b$f:tirlevel
'2 2
N Asiliary 8 4141a3 AAlaNeLueI(.P'f4Ol*4""f"d)
J 3
3 Site environmental radiation level L
feactae. reera.t yme shk h
Powir7o* pep [ ale N elief valve (PORV) status 2
Primary safety valve status-2 Pressuriser heater breaker
_ position 2
Charging system flow p_
(lod E mergency Cha r
2 Letdown flow 9-
&^erpe.y lehdoson 2
Volume control tank. level 2
Chemical and volume control system (CVCS) valve status 2
CVCS pump status 2
Reactor coolant pump seal injection 1.ow
w
}
VEGP-FSAR-7
'i TABLE 7.5.4-1 (SHEET 3 OE 5)
Type and Category Type Type Type Type Type A
B C
D E
Variable' 2
Steam generator atmospheric PORV status 2.
2 Main steam line isolation le is,lauen val **-hr*58 88* l*b *
- A valve status main s 6 esm n
valve o f Wa.1 2
Steam generator safety valve status-main steamflow 2
Main feedwater control valve status 2
Main feedwater control bypass valve status 2
Main-feedwater isolation y
valve statusiselatien ky ass v*fue. Slabs-p thin (ccJ w atec 2
l Main feedwater flow 2-Steam generator blowdown 2
Stenn genersW smpte. tine,1selskl** *N 545 isolation valve status 2
~
High-head. safety.
~ ~ - -
injection flow l
l 2
Low-head safety injection flow l
(
2 l
Emergency core cooling system valve status j
.2-J l
Accumulator pressure 2
Auxiliar'y feedwater valve status 2
Containment spray' flow 2
Containment spray valve status l
I i
t
.-jq VEGP-ESAR-7~
I
~
TABLE 7'.5.4-1 (SHEET 4 OE 5)
Type and Category Type Type Type Type Type Variable A
B C
D E
2 Containment spray pump l,.
(
status c.g. w - - +an cooler damper position 2
A c, an dcooler break position ea 2
3 2
Component cooling water (CCW) header pressure 2
CCW surge tank' level 2
CCW flow Nuc1I"aYsTk"Yde cookuk N'* WP'Is i
~,uk cooll e
ing water system flow t
2 i
Nuclear service cooling water system valve status y
A 2
Residual hdat removal (RHR)
- - -- - - heat-exchanger _/discharget _ _... _...., _ _ _,.
temperature 2
RHR flow 2
RHR valve status 2
RHR pump s.tatus 2
l Engineered safety features (ESE) environment temperature 2
i EST environment cooler l
status Heating, venk:1lation, and air-2 l
conditioning system status 2
ac and de vita' instrument $
voltage l
l
~
VEGP-FSAR-7 TABLE 7.5.4-1 (SHEET 5 0F'5)
Type and Category Type Type Type Type Type A
B C
D E
Variable
.I
$I 4e.fuaH e=
2 Reactor trip breaker position 2'
f-Turbine stop valve position 2
First-stage turbine pressure 2
Auxiliary feedwater pump status 2
Safety injection pump status.
2 Nuclear service cooling water pump status 2
Nuclear servicts cooling water fan status 2
CCW pump status Area radiation 3
Control roorrr monitor r"
- Radiochemistry lab monitor - - -
.___.._3._
3 Fuel handling building area radiation 3
Sampling room monitor 3
Decontamination station (large parts) 3 Decontamination station (small parts) 3 Instrument decontamination station Plarit vent 2
A:.rfitw rate 3
Meteorological parameters J
CowWmenf Sg Ruliation
1 u
3, VEGP-ESAR-7 t
TABLE 7.5.3-1
SUMMARY
OE' TYPE A VARIABLES Variable Type /
Function Category Variable l
RCS pressure (wide range (WR))
Key Al Key Al That (WR)
Key Al
~Tcold (WR)
Steam generator level (WR)
Key Al Steam generator level (narrow range (NR))
Key Al Pressurizer level Key Al Containment pressure Key Al Steam line pressure Key Al Containment water level (WR)
Key Al Containment water level (NR)
Key Al Condensate storage tanle level Key A1
- AL_
- - ' RefUieling~witer storage-tankElever nr--Keyr -
Auxiliary feedwater flow Key Al Containment area radiation level (WR)
Key Al Co..u.Anmanu a s... u.ui wwu le. el ( L*. )
K:y 21 Core exit temperature Key Al Steam line radiation monitor Key Al Ke 3yaay (Fj' F W Al RCS subcooling l
Ceudense: ;;; ge ;e:.edictier -criter 3;;kay (F)
A2. ~ ~
- D2p ' ?-)
- f :: ! b = ^"-~
'\\
. 9
-\\
\\N
J VEGP-ESAR-7 TABLE 7.5.3-2 (SHEET 1 OF 2)
SUMMARY
OF TYPE B VARIABLES Function Variable Type /
Monitored Variable Function Category
!!lderiJed W Reactivity 4 Neutron Flux.
Key
~
B1 Backup (P)
B2
(
control WR T hat WR Tcold Backup (P)
B2
-C:ntr:1 red posi;ica Or. kup 2':' -
Key xe B1 gi pressure Containment pressure Backup (
B4 control Containment area radiation Backup (P)
B2 (WR)
(UR Tu c -- 4
- n r;;
- ei-tie-
Stream line radiatiert Backup.(P)
B2 Reactor Pressurizer level Key B1
, _, tej BiiF 81
, coolant
- Reactor vessel water
__my inventory level control Containment water Backup (P)
B2 level (NR)
Containment water Backup (P)
B2 level (WR)
WR steam Backup (P)
B2 generator level g
K 3
-Reactor Z ore exi-t:--temperature: -
Ke Ke Gl.
~
63
~
Bac p(
core WR That Backup (P)
B2 cooling WR Teold RCS pressure (WR)
Backup (P)
B2 RCS Sdeeli peg,2,;;i. g 2 4 (r) 42-C5 T l.e'el ho s vesser w. m.
22 kup (?)
B2 %
Ruetw vena.1 1 c;:. - -
wee sevst Heaf sink NR steam generator level Key B1 maintenance WR steam generator level Key 31 Auxiliary feedwater flow Key B1 Core exit temperature Key B1 Steam line pressure Key Bl Main steam line isolation Backup (P)
B2 valve status And b pass y
_ 1 VEGP-ESAR-7 TABLE 7.5.3-2 (SHEET 1 OF 2)
Variable Type /
Function.
Function Category Monitored Variable Containment Containment pressure Key B1 environment Containment area. radiation Key B1 (WR)
Cen t ri =:nt,u m. & diction Mcy L1 -
~
C B1 Containment water Key level (NR)
Containment water Key B1 level (WR)
Containment hydrogen Key B1 concentration
- m w
" * = * -
"m_..___,-
6
m s-
_g VEGP-ESAR-7 TABLE 7.5.3-3
SUMMARY
OE TYPE C VARIABLES Function Variable Type /
' Monitored Variable Condition Function Category Incore Core exit Potential Key CL
(
fuel clad temperature for breach Reactor vessel Potential water level for breach Backup (P)
C2 RCS Actual Backup C3 activity breach RCS RCS pressure Potential Key C1 boundary
-(WR) for breach RCS pressure Actual Backup (P)
C2 (WR) breach Containment Actual Backup (P)
C2 pressure breach Containment Actual Backup (P)
C2 water level breach (NR)
Containment Actual Backup (P)
C2 water level breach (WR)
Containment-Containment Potential Key Cl boundary pressure for breach (extended
..._. _ ~.. _ _ _ _..
Containment Potential Key Cl hydrogen for breach concentration Plant vent Actual Backup (P)
C2 radiation breach level Containment Actual Backup (P)
C2-isolation breach valve status Containment Actual Backup (P)
C2 pressure breach (extended range)
Site environ-Actual Backup C3 mental breach radiation Au xiUg Gdig A
Gackup D **
Rulist ten
\\
e
\\\\
Y
c.
4
- J.
VEGP-ESAR-7 i
TABLE *7.5.3-4 (SHEET 1 OE 3)
SUMMARY
OF TYPE D VARIABLES Variable Type /
Variable-Functiort Category System Pressurizer level Power-operated relief Key D1 valve (PORV) status and pressure
.I control Safety-valve status.
Key D2 Pressurizer level Key D2 RCS pressure (WR)
Key D2 Pressurizer heater Key D2 og power availability g,3 Press < riser pressure CVCS Charging system Key D1 flow Letdown flow Key D2 Volume control tank Key D2 level Seal injection flow Key D2 CVCS valve status.
Key DZ Secondary Steam generator Key D2 pressure and atmospheric steam dump valve status level control ~ ^ Yt: 1..
3.u rawr..f:tp Key DZ
- .* O ve1;; et_;..,
Neto Main steam isolation Key D1 valve and bypass Key-DI
~~ ~~
. ;, valve-status
_.. Key D1_ _
~
Steam generator blow-dowrt isolation valve status.
Steam line pressure Key D2 Auxiliary feedwater Key D2 flow Steam generator level Key D2, (WR)
Steam generator level Key D2 (NR)
Main feedwater control Key D2 and bypasa valve status Main feedwater Key D2 isolation valve status Main feedwater-flow Key D2 line IseI< tion 01 Gykl Atacbc Cool d ACS Subcooli) kg Da Snslers SMue befor Coeluf pmmpsklus key 02 02 kVt 11 ge3
.v.
..m,
,m
,_y.
....w
.,_.,_-,_w.._
J 1
VEGP-ESAR-7 TABLE' 7.5.3-4 (SHEET 2 OF 3)
Variable Type /
System Variable Function Category ECCS Reactor water storage Key D2 level l
HHSI and LHSI flow Key D2 I
Containment water Key D2 l
level (NR)
Containment water Key D2 level (WR)
ECCS valve status Key D2
?::urcalatc; ressurr Key D2 Ac.s press ure.
Auxiliary feed-Auxiliary feedwater Key D2 water flow Auxiliary feedwater Key D2 valve status Condensate storage tank level Key D2 Containment Containment spray-flow Key D2 cooling Containment water level Key D2 (WR anci NR)
Containment spray Key-D2 valve status Containment spra.y pump. status Key D2 Containment pressure Key D2
- ~ Fan - cooler damper-~ ~~ - - - - ~ ~
- - - ~..
position Key D2 Fan cooler breaker position Key D2 dgatam4 1.seldien vdue gey M
CCW IfeacEe'r pressure Key D2 Header temperature Key D2 Surge tank level Key D2 CCW flow Key D2 Nuclear service Valve status.
Key D2 cooling water System flow Key D2 system Fan status Key D2 02 Pmp SW4 eg
J VEGP-ESAR-7 g-TABE 7.5.3-4 (SHEET 3 OF 3)
Variable ' Type /
System Variable Function Category RHR Heat exchanger Key D2 discharge temperature Flow Key D2 i
Valve status Key D2 RCS pressure (WR)
Key D2 pump stedws Reg O G.
Environment for ESF Key D2 HVAC components System status Key D2 ESF environm9nt Key D2 cooler stat.us Electric power ac/dc vital inst.'a--
Key D2 ment voltage Verification of Reactor trip Key D2 automatic actu-breaker position gr g g;,a y,,,
ke3 Og ation of safety-systems Turbine stop valve Key D2 position First-stage turbine Key D2 pressure l--
~ _ _ ~.. _...
~-
Auxiliary feedwater Key D2 pump status l
Safety injection Key D2 pump status Nuclear service Key D2 l
cooling water pump status CCW pump status Key D2 Containment isolation Key D2 valve status Co,tf ai n**f 6n co.ier s+atu RHR pump status Key D2 CVCS pump status Key D2 01 KU 7
Edvalef Raye Neafre. FI-D2
'* ' '1**
coere\\ Rod Posik n Indte*he Kc3
J f
l VEGP-ESAR-7 TABLE 7.5.3-5
SUMMARY
OE TYPE E VARIABLES Variable Type /
Function Category Variable I
E2 Containment area radiation (WR)
Key ri Cuneiracat ar-2 r:dictisu DT.)
2 E2 Plant vent radiation level Key E2 Key Steam line radiation E2 Key Plant ve'nt air flow rata
-EE-E2 Condenser air ejector radiation
-iter Sadap (P)
Area radiation monitors Backup (P)
E3 Control. room monitor Backup (P)'
E3 Radiochemistry lab monitor Backup (P)
E3 Euel handling building monitor
}
Backup (P)
E3 Sampling room monitor Backup (P)
E3 Decontamination station m &-
r.(large parts).__
~
Backup (P)
E3 Decontamination station (small parts)
Instrument decontamination station Backup (P)
E3 i
Site environmental radiation level Backup (P)
E3 Backup (P)
E3 Meteorological parameters Conhanmrd Swmp Mi sfio" Ga.k..p (,9)
E3
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