ML20147C456
| ML20147C456 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/26/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803030087 | |
| Download: ML20147C456 (61) | |
Text
-
1; TENNESSEE VALLEY AUTHORITY CHATTANOOGA TENNESSEE 374ol 5N 157B Lookout Place FEB 261988 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - EMERGENCY OPERATING PROCEDURES (EOPs) AND PROCEDURES GENERATION PACKAGE (PGP)
Reference:
TVA letter to NRC dated January 15, 1988, "Sequoyah Nuclear Plant (SQN) Units 1 and 2 - Emergency Operating Procedures (EOPs) and Procedures Generation Package (PGP)"
This letter provides an update on the status of the E0Ps for SQE and corrects a minor discrepancy in the PGP previously submitted by the
-referenced letter.
Emergency Instruction ES-0.3, "Natural Circulation Cooldown," has been revised to include further guidance for determining if reactor coolant system voiding has occurred and appropriate references to other procedures for operator response to voiding.
contains a list of new E0P Emergency Contingency Instructions issued since NRC Inspection 50-327/87-61 and 50-328/87-61. contains revised appendices for the PGP.
The minor discrepancy was caused by inadvertently including several pages in appendlx F that belonged with the information presented in appendix E.
If you have any questions, please telephone M. J. Burzynski at (615) 870-6172.
Very truly yours, TENNESSE3 EY AUTHORITY R. Gridley, rector Nuclear Lic sing and Regulator Affairs Enclosures cci see page 2 go@
t
'l 8803030087 800226 PDR ADOCK 05000327 l
P DCD An Equal Opportunity Employer
U.S. Nuclear Regulatory Commission.
gf{j
.cc'(Enclosures):
Mr. K. P. Bare, Acting Assistant Director
-for Inspection Programs TVA Projects Division
.U.S. Nuclear Regulatory _ Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
'Mr. G.-G.
Zech, Assistant Director ~
for Projects-TVA Projects Division U.S. Nuclear Regulatory Commission One White Filnt, North ll5!i5 Rockville Pike Roc lcville, Maryland 20852 Segaoyah Resident Inspectoe Segaoyah Nuclear Plant 26(0 Igou Ferti Road So3dy Dr.*ay Tennessee 37379 4
m-
' s' JJ List of New E0P Emergency! Contingency : Instructions -
Issued Since NRC Inspections 50-327/87-61 and 50-328/87-61 1.
ECA-1.1; "Loss ' of RHR Sump Recirculation," revision O.
~ 2.
ECA-1.2, "LOCA Outside Containment," revision 0.
3.
ECA-2.1, "Uncontrolled Depressurization of All Steam Generators,"
revision O.
4.
ECA-3.1, "SGTR and LOCA - Subcooled Recovery," revision O.
5.
ECA-3.2, "SGTR and LOCA - Saturated Recovery " revision O.
A F
i-t I
.~
i Revised Appendices for the Procedures Generation Package as I
4
Appendix E.1 COMPARISON OF SEQUOYAH TO THE WOG HIGH-?RESSURE REFERENCE PLANT a^
nic/0103R 2
TABLE OF CONTENTS SECTION PAGE
=
1.
-INTRODUCTION 1
- 2. -PLANT SYSTEMS-2
-2.1
~ Reactor Trip Actuation System 5-
~
2.2
- Engineered Safeguards Features Actuation 5-System 2.3 Nuclear Instrumentation System' 11 2.4 Control Red Instrumentation System 11 2.5 Radiation Instrumentation System 12' 2.6 Containment Instrumentation System 12 2.7 Reactor Coolant System 12-2.8 Safety Injection System 13
'2.9 b(J.
Residual Heat. Removal System 19 2.10' Chemical and Volume control System 22 2.11 Component Cooling Water System 24 2.12 Service Water System 24 2.13 Containment Spray System 27 2.14 Containment Atmosphere Control System 27 2.15 Main Steam System 29 2.16 Main Feedwater and Condensate System 31 2.17 Auxiliary Feedwater System 31 2.18 Steam Generator Blowdown System h
33 2.19 Sampling System 33 2.20 Spent Fuel Storage and Cooling System 33 2.21 Control Red Drive Mechanism Cooling System 33 2.22 Control Rod Control System 23 2.23 Turbine Control System 34 2.24 Electrical Power System 34 2.25 Pneumatic Power System 35 3.
PLANT INSTRUMENTATION AND CCNTROLS 36 HP REF PLANT 64789:1 i
Septemoer 1,1983
O
_ TABLE' 0F CONTENTS (Cont)
. FIGURE
. _P_ AGE 1.
REACTOR COOLANT' SYSTEM 14.
2.
CHARGING /SI SUBSYSTEM 17 3.
HIGH-HEAD SI SUBSYSTEM 18 4.
LOW-HEAD SI SUBSYSTEM 20
[-
5; SI-ACCUMULATOR SUBSYSTEM 21-
- 6. -RESIDUAL HEAT REMOVAL SYSTEM 23 7.
CHEMICAL AND VOLUME CONTROL SYSTEM 25 8.
COMPONENT COOLING WATER TO REACTOR COOLANT POMPS 26 9.
CONTAINMENT SPRAY SYSTEM 28
- 10. MAIN STEAM SYSTEM 30
- 11. AUXILIARY FEEDWATER SYSTEM 32
_ TABLE -
1.
PLANT SYSTEMS 3
2.
LEGEND FOR FIGURES 4
3.
INSTRUMENTATION AND CONTROL REQUIREMENTS 37 1
i l
HP REF PLANT 11 647ES:1 Septecer 1.19S3 v.
v 1-1 7
1.
INTRODUCTION Q
The emergency Response Guidelines (ERGS)-provide generic technical guid applicable to.all Westinghouse-designed commercial press'uri:ed water reactor i
plants.
The ERGS.are developed in low pressure (LP) and high pressure (HP)
' versions to address'the most significant difference in plant design configuration.from a standpoint of the plant response to emergency transie i.e.,- the maximum shutoff pressure of the safety injection system.
The HPl version ~is 4pplicable to plants that_are designed-with a safety injection system shutoff pressure greater than the reactor coolant system pressurizer power operated relief valve (PORV) pressure setpoint.
High pressure plants utilize.the charging pumps as safety injection pumps.
L The LP version is applicable to plants that are designed with a safety injection system shutoff pressure less than the reactor coolant system pressurizer power operated relief. valve (PORV) pressure setpoint.
i Low pressure plants do not utili:e the charging pumps as safety injection pumps.
Each serston of the ERGS is based on a generic reference plant configuration.
-f The reference plant is developed to sufficiently define a configuration for which technical guidance can be developed while maximizing tne applicability of the technical guidance. Application of the ERGS to a plant-specific i
configuration requires that. the utility review the plant specific configuration relative to the reference plant configuration.
1 This review will establish applicability uf the ERGS to the specific plant and provide inout to l
the plant-specific procedure development effort.
This document defines the reference plant for the HP version of the ERGS, i
The HP reference plant is basically a 4-loop plant with system design features similar to current Westinghouse-design plants.
I
(
s j
i HP REF PLANT 1
4 64788:1 September 1, 1983
r 2.
PLANT SYSTEMS The reference plant is defined in ten.is et twenty-five separate plant systems
~
which form a generic set that has general applicability to a broad range of plants.
The plant systems are grouped into four categories:
1)
Control and Protection Actuation Systems 2)-
Instrumentation Systems 3)
Process Control Systems 4)
Support Systems Each system is defined to the extent necessary to maximize technical guidance -
.with respect to-system-operation la response to an emergency transi< tnt and to maximize the generic applicability of that technical guidance.
The reference plant systems are identified by category in Table 1.
The-following subsections describe the systems from an emergency operations perspective.
Figures are incluced to show the reference plant' systems where appropriate.
Table 2 provices a legend of symbols used in the. figures.
Detail shown on the figures is consistent with the instrumentation and equipment specifically identified in the ERGS, aiding the user of this document in identifying and comparing the reference plant irm rumentation and equipment to the plant-specific instrumentation and' equipment.
Additional detail (e.g., valves) is not shown where the detail exceeds that specifically identified in the ERGS.
L L
HP REF PLANT 2
6478B:1 September 1, 1983
a 3l.
TABLE 1 PLANT SYSTEMS i
-Control and Protection A'etuation Systems-
'ReactorLTrip Actuation System i-Engineered Safeguards ' Features A' ctuation System
. Instrumentation Systems Nuclear Instrumentation System-Control Rod-Instrumentation System Radiation Instrumentation System Containment Instrumentation System Process Control Systems Reactor Coolant System SafetyzInjection System
'. Residual Heat Removal System Chemical and Volume Control System Component Cooling Water System Service Water System Containment Spray System
~
Containment Atmosphere Control System Main Steam System Main Feedwater and Condensate System Auxiliary Feedwater System Steam Generator Blowdown System Sampling System
(
Spent Fuel Storage and Cooling System
~ Control Rod Drive Mechanism Cooling System
- Control Rod Control System Turbine Control System
- (s_
Suenort Systems Electrical Power System Pneumatic Power System eb
(
HP REF PLANT 3
6478B:1 September 1, 1983
.ll TABLE 2
(
LEGEND FOR FIGURES SYMBOLS
(
Motor Operated Valve Hydraulic Operated Valve
^
Air Operated Valve O
Air Operated Control Valve Safety Valve Centrifugal Pump Positive Displacement (PD) Pump Instrumentation F - Flow T - Temperature L - Level P - Pressure ACRONYMNS (unique to Figures)
ACC Accumulator IRC Inside Reactor Containment Aux.
Auxiliary LHSI Low-head SI CHS!
Charging /SI ORC Out;ide Reactor Containment EX Excess RTD Resistance Temperature Detector HHSI
- High-head,5,I RV Reactor Vessel
{
HP REF PLANT 4
647cB:I September 1, 1983
2.1 Reactor Trio Actuation System h.t reactor trip actuation system monitors specified process parameters and equipment status and actuates reactor trip if conditions exceed specified limits.
The reactor trip actuation system incluces automatic actuations that occur concurrent with actuation of eactor trip.
The process parameters and equipment actuation system are plant specific. status monitored by the reactor trip A reactor trip signal is automatically generated if any condition exceeds its specified limit.
Concurrent with opening of reactor trip breakers, a P-4 signal is generated and provides the following:
o Turbine trip Input signal to feedwater isolation logic o
Input signal to SI block logic o
2.2 Encineered Safecuards Features Actuation Svstem The engineered safeguards features (ESF) actuation system monitors spec process parameters and actuates ESF operation if conoitions exceed specified limits.
The ESF Actuation System consists of the following automatic actuation signals.
Safety Iniection Sicnal (eh b O M[rc T4%)
The safety injection (SI) signal is the primary ESF actuation signal It is automatically generated on any of the following:
o*
Low pressurizer pressure o. Lu : c e. l i newewere- / 1 8 e' u f * [ f " '55 ^ S * " " " 5 'I ^ A
(
High-1 containment pressure o
Manual operator actuation o
S) % &
.n
!<> s /h. m li m b 4 c w code-1' y $ c:; on c o c'en t w ?l eiff e,
hs Nw %;
_ w. lf s 7ls, /,'n r e s s, m /_.
w s
HP REF PLANT 64783:1 5
September 1, 1983
n n
-The following plant equipment are automatically actuated by.an SI signal:
Reactor' trip o
=Feedwater isolation (including closure of feecsater isolation, flow o
control and bypass valves) o
' Auxiliary feedwater (AFV) start (including start of motor-driven AFW pum
{'
and closure of steam _ generator blowdown isolation and sample valves)
Diesel generator start o
~
e ecg no fer ; cele. 5., e fa r ef c ac7 f
- 5N'"^'
'f' 3
Safety in.jection system start o
Component cooling water system start
- {j,,,/ g$v./doy y ss'h w manf o
j
,7 Service water system start o-
-f.. / /,7 e s M'
, gj,
Containment ~1 solation Phase A o
. p;.,, e /<a/ "Om
'8
^
Containment ventilation isolation o
The SI signal actuation logic includes the following reset / block features:
Manual-block / reset for 'ow pressurizer pressure actuation signal o
(concurrent with a F-11 1.cw oressurize/E. ressure permissive signal) r Manual block / reset for h,3 h me-o wi th a ?.'.'
L.,
/.
h,, ; t t i ' ": p r e _I. t
,o - r 2.
4 actuation signal (concurrent r ; n. Rar g$
.v r:::.rc permissive signal)
Manual block / reset for SI signal (concurrent with upiration of the SI o
signal' reset time delay and P-4 reactor trip input signal)
Containment Sorav Sienal The containment spray signal automatically actuates on any of the follow 2.
High-[containmentpressure o
o Manual operator actuation HP REF PLANT 6
c478B:1 September 1, 1983
7
@%2n The following plant equipment > automatically actuate on a containment sora signal:-
1:
' Containment spray system' start o
[-
o Containment isolation Phase B L
X' io G.,. k i.< ne e f er.- re 7t.m 9fsfem s fa r f The containment spray sigaal' actuation logic includes the following reset capabilities:
Manual reset for containment spray system start signal
.o Manual reset for containment isolation Phase B signal o-Auxiliary Feedwrter Start Sicnal The auxiliary feedwater (AFW) system consists of one turbine-driven -and two motor-driven AFW pumps. These pumps are started on different actuation-signals.
(
The cotor-driven AN pumps automatically start on any of the following:
Trip of all main feedwater pumps o
o SI signal Blackout signal (generated by low voltage on normal power supplies feedin d
ac emergency buses) from associatec at emergency bus low-low level in any steam cenerator o
7 p. of oni. ea m / Esc (A7tr f ~,- s k 'N #~ {0"*'
o The turbine-drjven AFV pump automatically starts on any of the follewing:
(
SZ PJ &
o as ma m /Es/A p. -p s
/
c 7,.7, low level in any two steam generfters Low-o Loss of power signal (ger.erated by low voltage on RCP uuses) o Tr.n al on mo m As!w< 7'i s ? -p 0
a f,.s.
~ M A pas e
(
s An auxiliary feedwater start signal that actuates the AFW pumps also actuates v
closure of steam generator blowcown isolation and sample valves.
HP REF PLANT 7
647SB:1 Sectember 1, 1983
I Containment Isclation Phase A Sicnal The containment' isolation Phase A signal automatically isolates non essential containment penetrations to prevent or minimi:e the release of radioactive material outside containment.
This signal automatically actuates on any of the following input signals:
(
o SI signal Manual operator actuation of Phase A signal o
The containment isolation Phase A signal closes valves in plant systems that penetrate containaent.
The actuation logic includes secarate reset capability for each input actuation signal.
~
Containment Isolation Phase B Sional The containment isolation Phase B signal automatically' isolates essential containment penetrations to prevent the release of radioactive material outside containment. The signal automatically actuates on any of the following input signals:
2.
High-f ccntainment pressure o
Manual operator actuation of containment spray signal o
The containment isolation Phase B signal automatically closes the containment t
isolation valves in the component cooling water lines to the reactor coolant The actuation logic includes separate reset capability for each input pumps.
actuation signal.
L; I
HP REF P'LANT 8
6478B:1 Sectember 1, 1983 u
- Main Steamline' Isolation Sicnal Main steamline: isolation is actuated on any of the following:
High-2 containment pressure o
c Lc, ;;;; 1' ; ; :::u : " :ny m;in 3tranrHne-(when-pressuri:er-pressure Mer; I II'
"'9 -+ team-pressure-rate-in-annrirr nean44ne (--hen-peenm+etr pre swee-
<h 4 6 E-;;) -
Manual operator-actuation o
0
$1bse /7,e.n Ywa yfe'se /.,a Ar 4 Loo or u,,voch 7 w,14 yn.
/.u b,-tsss s 4."sncod* l "*.Oe',$ '* Y A ~ I ")-
The following plant equipment autcmatically actuate on a main steamline i solati,n. signa h Main steamline isolation valves close o
Main steamline isolation bypass valves close c,.
The main steamline isolation logic includes the following reset capabilities:
o haihk/re;e fe. lernesmMne7tersore ao cstion signal-(concurrent--
e f t F :. "
- ic, pre 33m 4 er pr m uru gemrssive signa +}--
e--MantrabtAec-kheseW nisa 2.r.-m-preuure-r-ate-actuation signal
-(ccatur-ret wrth a+12 lu vrersvriter-pressure-termissive signal)
Manual reset for main steamline isolation signal o
t
(
HP REF PLANT 9
6475B:1 September 1, 1983
Containment Ventilation Isolation Sienal The containment ventilation isolation signal automatically isolates containment ventilation penetrations ~to. prevent.the release of racioactive material outside c:ntainment.
This signal automatically actuates on any of the following input signals:
o SI signal High containment radiation o
Manual operator actuation of containment spray signal
.o Manual operator actuation-of containment isolation Phase A signal o
The containment ~ ventilation isolation signal closes damoers in the ventil!
The actuation logic includes separate reset capability for each input
. system.
actuation signal.
Ma'n Feedwater Isciation Sicnal The main feedwater isolation signal automatically isolates tne main feeowate i
lines to prevent excessive filling of the steam generators, The signal automatically actuates on any of the following input signals:
j o
SI signal High-high level (P-14 signal) in any steam generator o
Re2ctor trip (P-4 signal) coincident with low reactor o
coolanE system average temperature (T,yg) l I
HP REF PLANT 647ES:1 10 September 1, 1983 l
en O
a C
The main feeawater isolation signal closes the following valves:
Main feedwater isolation valves o
Main feedwater flow control valves o
C Main feecwater bypass valves o
The main feedwater isolation signal incluces the following reset / block capabilities:
C Manual reset for the reactor trip (C-4) signal coincident with RCS low o
T avg Manual reset / block for the SI signal. This is the same reset / block o
feature discussed under S! signal.
2.3 Nuclear Instrumentation System The nuclear instrumentation system (NIS) monitors anc displays the react state of the reactor core.
It censists of instrumentation that monitors leakage neutron flux outside the reactor vessel.
Neutron flux is monitored over the source, intermediate, and power ranges.
Startup rate is calculated over the source and intermeciate ranges.
The NIS includes a neutron flux recorder that can be switched to record diffe m nt ranges.
The source range neutron flux detectors automatically energize when flux decreases below the source range high flux trip (P-6) setpoint following a reactor trip, permitting the neutron flux recorder to be manually transferred to the source range scale.
2.4 Control Rod Instrumentation System The control rod' instrumentation system monitors and displays rhe position of the control rods in the reactor core.
It provides control rw3 position and red bottom light indications.
'\\..
HP REF PLANT 60SD: 1 11 Septemoer 1, 1983
2.5 Radiation Instrumentation System The radiation instrumentation system monitors radiation levels in specified process systems and specified areas internal and external to the plant.
It consists of_-the following:
Radiation instrumentation located inside containment o
,g,w c,., s u.
s.< t w
- Radiation instrumentation located in the %.
n::m system and steam o
generator blowdown system
(
Radiation instrumentation located inside the auxiliary buildirig o
2.6 Containment Instrumentation System The containment instrumentation system monitors the environmental condition and isolation status of containment.
It consists of containment pressure and temperature instrumentation, containment recirculation sump level instrumentation, and position indication for containment isolation valves and dampers.
2.7 Reacter Coolant System The reactor coolant system (RCS) transfers heat from the reactor core to the main steam system or residual heat removal system and provides a barrier against the release of reactor coolant or radioactive material to the containment environment.
The RCS consists of four identical heat transfer loops (connected in parallel to the reactor vessel), a pressuri:er and a pressuri:er relief tanL Each loop includes a*RTD bypass loop.
Flow frnm the RCS hot leg and cold leg enters a bypass loop and returns via a ccmmon header to the reactor coolant pump (RCP) suction.
Each bypass loop contains a hot leg and cold leg manifold that incluces RTD temperature sensors used in plant control and protection.
HP RET PLANT 12 64789:1 September 1, 1983
e
' The pressuri:er is connected to the hot leg of one loop via the pressuri:er surge line and the cold legs of two loops via the pressuri:er spray ~ lines.
The pressuri:er has two power operated relief valves (PORVs) with associated block valves, three ASME code safety valves, and heaters.
RCS pressure _is controlled by use of the pressuri:er where water and steam are maintained in equilibrium through use of the heaters, water spray, and steam release.
The pressuri:er PORVs and safety valves discharge to the pressuri:er relief tank where steam discharge is condensea and cooled by mixing with water.
Normal operating pressure of 2235 psig in the RCS is maintained by a Pressure Control System which automatically energi:es heaters and normal spray in the pressuri:er as '6ecessary to maintain pressure.
Pressurizer PORVs are automatically controlled to open at 2335 psig, and the safety valves have a lift pressure of 2485 psig.
A Cold Overpressure Protection System functions to limit RCS pressure to a C
programmed maximum (as a function of temoerature) at low RCS temperatures.
This control system
=t L
...c.ib olaced in service and utili:es only the pressuri er PORVs to limit RCS pressure.
The reference plant RCS is shown in Figure 1.
2.8 Safety Infection System
(,.4 4
u ur/sc EEG.)
The safety injection (SI) system provides borated water to the reactor coolant system for events that require engineered safeguards features operatien.
The safety injection system is designed to operate in three physical configurations or modes depending on the plant transient and time into the piant transient:
Cold leg injection ecde (short-term core cooling mode) o The cold leg injection mode is defined as that configuration in which borated water is delivered from the refueling water storage tank (RWST) to the RCS cold legs.
HP REF PLANT 13 647S3:1 Septemoer 1, 19E3 t_
N
,' :. n EU fft
- .mj Figure 1. REACTOR COOLANT SYSTEM Safety O
O Valves SG O
k SG bl k
Ak Loop 1 Loop PORV
~
- 4 H
- 4 w
4 HTD Manifottis
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"'" "a "o'd 5 g j g
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< L PHZR 9
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k
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- A ap / o,, J 3 l', ass a %w.fn a /.< A l o fu /c cndu- /
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0 D
- s. te
,,d.,p u.rct,, 4.es a,e O
O O
m: w Cold leg recirculation moce (long-term core cooling mode) o The cold leg recirculation mode is cefined as that configuration in which borated water is recirculated from the containment_sume to the RCS cold legs.
i This modeLis initiated by an automatic opening of the containment sump ~
isolation valves to the Safety Injection System resulting from a combin d "l e.
ow RWSTlevelad.SIl"sign?l.
M -;. c.t t em I.a o
Hot leg recirculation mode (long-term core cooling and boron concentration control)
The hot leg recirculation mode is that configuration in which borated water -is recirculated from the containment sump to both the RCS hot legs and RCS cold 7
legs. This mode is initiated by manual operator action based on time into the transient.
The safety injection system consists of the following four major subsystems.
C Charoino/SI Subsystem The charging /SI subsystem consists of two centrifugal charging /SI pumps and a boron injection tank (BIT). These pumps are part of the chemical and volume 4
control system and provide charging and RCP seal injection flow during normal operation.
Upon receipt of an SI signal, these pumps are automatically isolated from the normal charging function and aligned for SI cold leg L
injection.
The charging /SI pump miniflow isolation valves remain open following SI actuation.
In the injection alignment the charging /SI pumps take suction from the RWST and discharge through the BIT (and RCP seal injection) to all RC5 cold. legs.
During recirculation modes, the charging /SI oump su'ction is aligned to the discharge of the low-head SI pumps and the d remains through the BIT to the RCS cold legs.
The discha< 'e shutoif pressure of the charging /SI pumps is greater than the RCS prr er PORV setpoint pressure.
HP REF 15 647EE:1 Septemoer 1, 1953
The BIT contains 12 weight percent (21000 ppm boren) boric acid solution.
During normal operation the BIT contents are isolated by parallel inlet and
.{
outlet sets of motor operated valves.
i The reference plant charging /SI subsystem is shown it, Figure 2. -Those portions of the charging /SI subsystem that are part of the chemical and volume
('
control system are shown as dashed in Figure 2.
Hich-Head SI Subsystem The high-head SI subsystem consists of two centrifugal high-head SI pumps.
These pumps are part of the SI system and are normally aligned for SI cold leg injection.
Upon receipt of an SI signal, the high-nead SI pumps automatically start in the SI cold leg injection mode.
In this mode the high-head SI pump!,
take suction from the RWST and discharge to all RCS cold legs (through the accumulator discharge lines).
During recirculation moces, the high-head SI pumps are aligned to take suction from th'e low-head SI pumo discharge and to discharge to all RCS cold legs or hot legs depending on recirculation mode.
The discharge shutoff head pressure of the high-head SI pumps is approximately 1600 psig.
The reference plant high-head SI subsystem is shown in Figure 3.
Low-Head $1 Subsystem (refer Le O Hr/zc EEGs)
The low-head SI subsystem consists of two centrifugal pumps and two heat exchangers. These pumps and heat exchangers are part of the residual heat removal system aid provide normal plant shutdown heat removal.
During normal l
operation, these pumps are aligned for SI cold leg injection.
Upon receipt of an SI signal, the low-head SI pumps automatically start in the SI cold leg injection mode.
In this mode the low-head SI pumps take suction from the RW$i and discharge to all RCS cold legs (through the accumulator discharge lines).
[
HP REF PLANT 16 6478S:1 Septemoer 1, 1983
r r'
e n
n n
n 4
4
_m
=~
lna 4
m e
5 Figure 2. CHARGING /SI SUBSYSTEM l
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CVCS Seal f,,,
Wales its 5" "
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HCS Cold Leo
=
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3 D
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CS Cofd Leg --==
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l ~g Figure 3. HIGH-HEAD SI SUBSYSTEM
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LHSI Discharge r s.,. 4 l
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iflfSI Ptsnp j
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a HHF4 Ita s l
re,. 4 LitSI/ACC Disc r6gtse 4 g
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,e Figure 4 l
g "ry b
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I tfISI/ACC Dese y
en regne 4 g
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SS70006846 000 Onc (Ti C
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During' recirculation modes, the low-head SI pumps are aligned' to take suction from the containment recirculation sump and to discharge to.the~ suction of the'-
-charging /SI. pumps and high-head SI pumps as well as to all'RCS cold legs or
.two.RCS hot legs depending on recirculation mode.
.('
The discharge shutoff pressure of the low-head SI' pumps is approximately 200 psig.
The heat exchangers are supplied with component ccoling water during SI recirculation modes.
The reference plant low-head SI subsystem is shown in Figure 4 Those portions of the^ low-head SI subsystem that are part of the residual heat removal system are shown as dashed in Figure 4.
SI-Accumulator Subavstem ( c.Se r 4 O HI / r(.,
E RGs)
The SI-accumulator subsystem consists of four accumulator tanks, each connecting to one RCS cold leg via an accumulator injection line.
Each tank 400 contains borated water and is pressuri:ed to a nominal E5Fosig with a nitrogen cover gas. A single isolation valve is proviced in each accumulator injection line and series vent valves -are provided in the accumulator nitrogen supply lines.
During normal operation the injection isolation valves are open with power removed from the valve operators.
The accumulators are available to deliver their contents to the RCS cold legs during the injection mode of any emergency transient that is accompanied by RCS depressuri:ation below the accumulator pressure.
The reference plant SI-accumulator subsystem is shown in Figure 5.
2.9 Residual Heat F. moval System
(_
i
~
l The residual heat removal (RHR) system removes heat from the reactor coolant system curing plant shutdown operations at low reactor coolant system pressures.
1 HP REF PLANT 19 6473B:1 Septemoer 1, 1983
[
i
?
es IE,%
. 'j Figure 4. LOW-HEAD SI SUBSYSTEM Inc I OnC J-In tS1 Pumps RWST
< ACS Hot L.g Fig 3 i
j tillSt I 'g 3
[ CllSIPumps n
\\
FIO2 HI e l
i (INISIPumps
.s.
080 2 n3 Fig 3 5
1 N'
Acc o..c,.....
T i
(FJ
& ~' - ~ ~ h - t e
i gI.
- 7 v:.:e-.
a
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(
I
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inisi i
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g
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i
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I
" :n*1--i. !i--- L _._gy- ^{j.u'= r-a lo
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73
'" - - " 'v~~ ~i~ ' ~ ~ ' * "
i i
l l
g up---
w I
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u W
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--Ikl n
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/
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ks noi t n
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i a
,,Cx,,o, <..
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cc3 n]
r o
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mr 0"
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- j Figure 5. SI-ACCUMULATOR SUBSYSTEM l
i mhs 6-
& Vent s
ACC
/
\\ Cold Lc0 y
/N u
LilSI/lillSI i
Pumps Figure 4 ACC U
[
RCS 3
\\ Cold Leg
- h --
N
-4 i
]
LH3f/F iSI Pumps I
I Figure 4 ACC g
/
RCS g
\\ Cold leg
/N to LilSI/flilSI
-g N Supply l
l
\\2 Pumps g
Figuro 4 ACC l
E i
RCS l
1 Q
Cold Leg
=W j
IRC ORC g
N, LilSI/lfifSt Pumps w
Figure 4 65T0000848 008
The RHR system consists of.two RHR pumps (that also function as low-head SI pumps);and two RHR heat exchangers.
The RHR. system provides,ormal shutdown
< heat removal when RCS pressure.and temperature are reduced to agoroximately 400.psig and 350 F.
During normal shutdown heat' removal operatior.s. each RHR pump suctioncis aligned to one RCS hot leg and' the RHR pump discharge is aligned to prf.RCS cold legs.
4wo Portions of the RHR system also function as part of the low-head SI subsystem.
This shared function is cescribed in Section 2.8.
The reference plant residual beat removal system is shown in Figure 6.
1 C.10 Chemical anc Volume Control System The chemical and volume control system (CVCS) provides water.to the reactor coolant system and provides core reactivity contrcl for normal operations and any event that coes not require ESF operation.
The CVCS consists of charging and letcown capability for contro: of RCS inventory.
Letdown capability is provided by two letcown paths (the let'down line and the excess 'retcown line, with the excess letdown line providing a lower capacity alternate letdown path to the letdown line).
Charging capability is proviced by three charging pumps (two centrifugal pumps that also function as charging /SI pumps and one positive displacement pump) that deliver flow to the RCS through a charging line and RCP seal injection lines.
The RCP seal injection lines deliver to each RCP and provide RCP seal cooling.
A single RCP seal return line returns RCP seal leakoff flow to the suction of the charging pumps.
The charging line is automatically isolated on an SI
(
signal and the letdown and RCP seal return lines are aute..atically isolated on a"containment isolation Phase A signal.
Suction flow to the charging pumps is provided by the volume control tank k'
(VCT) which is connected to the letdown line or by the refueling w:ter storage HP REF PLANT 22 6475B:1 Septencer 1, 1983
(
c c
o
.m n
n m
=J u,m i -j Figure 6. RESIDUAL HEAT REMOVAL SYSTEM b
b i
CCW System l
i I
i
- 1. -
s - - - -,
+t--,
DCS Cold Leo 9
g l%qt i
via ACC Discheroe
{]
- E V}
,[fg l
g g
g nientax O
l E " " " ~ ~ "" ~ '
s s
[
t-----
3 I
RitR (LilSI)
N I
como s
p-sis nwsr DCS Cold leg via ACC Discharge g
{
S*I I 4
j I
ni(R llX g
RitR (LliSI)
Pump xQQI x
x x
x N
N I
totleg r 3 g g
N N
\\
1 5
NSS Q
RCS liot tog r ir 7 I
inC ] onc n
6570000840 000 W
m, (f r[
(<:
'4 4
3,
- f. L
. tank:(RWST) located in the )S: sys em.
The-enarging pum:sisuction is normilly-
' aligned to the VCT, but is automatically transferrec to the RWST on'any of the:
- following:
.w
.o-SI signal
.,1 o VCT low-low level signal The CVCS includes a boric acia tank (BAT) tnat-provides boric. acid ' solution to the VCT or to the suction of the charging pumos for core reactivity control.
.The. 3AT contains / weight oercent (2000 ppm coron)- coric acid solution.
ox' zg Portions of the CVCS 'also function as part of the charging /SI suosystem..This
. shared function is described in Section 2.8.
The reference plant CVCS is shown. in Figure 7.
2.11 Cc=cenent Croline Water Svstem
.e The comooner.t cooling-water (CCW) system provides-heat removal from
. potentially radioactive. system processes and equipment, including the following equipment:
o RHR heat exchangers Seal ater. heat exchanger o
.... m.:cr. '. ;;. : :
s o-RCPs'(motor bearing oil coolers and thermal barrier)
The reference plant CCW system for supplying cooling water to the RCPs is shown in Figure 8.
2.12 Service Water Svstem U H Tl:e Ge&s u Cu 4.
The service water (a,
"< tem crovides heat removal from non-radioactive system processes and eoui; ment a o CCW system to the ultimate heat sink, f
a f
HP' REF DLANT 24 m:o. t Sectemoer 1. 1993
- ~... >
r r
o n
n n.
o j a Figure 7. CHEMICAL AND VOLUME CONTROL SYSTEM g
i (i)
I i
@s nCS
\\
A I
I__m tatdown f
g l l
^
i J Lv
- - Lefdown
'{~
T
'[~ Orificeo g
.i I
(EI.*,.,a 4
e o
Aus Spe e r n...o......,..x
,,c,
i I
=()
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I S.., ne,u,,,,,.
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?
YY W
ggg i
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9
/
- --?
i vg i
m j
i s u Ulf po cher@g Putnp I
n e
U l
,5-i g
- 4 V'T L --_ g J l
q y
ce ssi rump g
ricY M!
I I
4
~
3 g
inc -l onc V
U suooo.... o io
'"8"'""'
i p
i 35 i
ll' #;j Figure 8. COMPONENT COOLING WATER TO REACTOR j
COOLANT PUMPS i
f CCW System
'~
CCW System e-ORC l
lRC
) (
) {
) (
m m
g i
r-s Motor w
.- - - as J LJ i J kJ k J LJ L I
B
{
~
i I
I m
g I
I
]
g l
l Thermal k'
-I
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I Darrier i.
I 4
_m. _ _ i_
j.
e sRCPf l~~~l m
u__a 6570000840 O f 1 1
i
.~
./(
a, 2.13 Co'ntainment-Sorav system ( utu 4..onr/rc-sh,)
The containment soray system provides containment-pressure suppression and af roorne fission product removal for events that recuire ESF operation.
The containment spray system is. designed to operate in two modes:
- o. Injection made fX The injection mooe is defined as that configuration in which water is delivered from the RWST to the containment atmosphere.
o Recirculation mode e
.The recirculation mode is defined as that configuration in which water is
. recirculated from the containment recirculation sump to the containment atmosphere. The piping and valves which connect the containment recirculation-sume to the containment spray system are separate from the piping and valves which connect the containment recirculation sump to the low-head SI subsystem.
The containment. spray system includes two centrifugal containment spray pumos.
The reference plant containment spray system is shwn in Figure 9.
2.14 Containment Atmosonere Control System oa/Zc E%s ace 4 The co.
it. ment atmosobere control system provices containment atmosphere heat removal, filt on, and comoustible gas mixture control.
It includes the containment fan cooler. containment electric hydrogen recombiners and containment ventilation equip.. nt that provide for mixing of the containment atmosphere.
The fan coolers are used for contair. ment heat remov4' during emergency transients.
.-k HP REF PLANT 27 September 1. 19R3 a: :n.i
iii
- ,i:
s" Figure 9. CONTAINMENT SPRAY SYSTEM
- ~
-q I
Inc onc F
I i
(
a a
eRWSTa y
-. a llenders i
I I
0; I
I (r 3l l
Containment j i J L Spray Pumps 1
q 7 I
]
l c
I i.
i n n I
[
^
l g
IRC ORC 667D000846 017
.k 1
i
-2.15 Main steam; System
'The main steam system provices controlled heat removal from the reactor..
coolant. system via the steam generators.
It consists of separate main isteamlines from eacn steam generator that join to form a common steam heacer leading.to the turoine generator and condenser.
The steam generators can be isolated from the main steam neader by main steamline isolation and bypass-valves located in the indivicual main steamlines.
The valves can be selectively closed via operator action in the control. room to. isolate a specific' steam generator. All main steaalinefisolation and bypass valves automatically close on a main steamline~ isolation signal.
Main. steam release capability is provided via the condenser steam dump system and the atmospheric steam dumo system.
The condenser steau dump system uses the main steam heacer and steam dump valves to the condenser.
The atmospheric steam dump system uses power operated relief valves upstream of the main steamline isolation valves to release steam to the atmosphere.
Each main steamline contains ASME code safety valves for overpressure protection.
Steam supply lines from the main steamlines to the turbine-firiven AFW pump are provided from two steam generators.
The steam supply lines include isolation valves for initiation and isolation of steam supply to the turbine-driven AFV pump.
The design and normal operating (no-load) pressures of the main steam system so are approximately gg... psig and i.'00 psig, respectively.
s ee r The setpoint pressures of the main steamline safety valves and steamline PORVs
(
'oG4
(
are approximately MC t940 psig (lowest valve setooint) and. m psig, respectively.
In the "pressure control mode," concenser steam dumps are set to' maintain no-load pressure.
The reference plant main steam system is shown in Figure 10.
L HP REF PLANT 29 6478B:1 Sectemeer 1, 1983
1
,,. x U"
Figure 10. MAIN STEAM SYSTEM h
Safety Valves pony l
s L
s l l
)
SG r li
-4 pone l
Safety Valves W '999:M:M:M:N:Nook "g g
v.,1 coK 00K 00X Turbine v i es I
^
l l'
E
__h a
O O
O I
9,,
{
i'i,;;ii;I!
Y conlons. irs Y
g safoty valvos P-]N
/\\
]
/\\
Pony i
W,yyy:N:N N:N:N00 4
Y Y
so r;b l
g 4
oog ooK oor l
Safely Valves Pony w
,,,:u:w:u:w:vee y a
s, s,. c.e c i
g"l 4
m, urw s,sierii)
- i Q
l iP 1
- =
4 w
ss roons.<e& o.,
b
q q
4 4
F 2.'16 Main Feecwater and Concensate System The main feedvater and concensate system crovides water;to the seconcary side of tne steam generators curing plant power operation.
It consists of separate main feedwater lines-to eacn; steam generator that originate from a common. main feedwater header..The steam generators can be isolated-from the main feedwater neader by feedwater flow' control valves, bypass valves and isolation valves located in the individual main feedwater lines.
The main feedwater system includes en: - r --: '>c r d two turoine-driven feedwater pumps. The condensate system includes only motor-driven condensate The dis _ charge shutoff pressure of the concensate pumos.is pumps.
approximately 600 psig.
2.17 Auxiliary Feedwater System The auxiliary feedwater (AFW) system provides coolant to the secondary side of the steam generators during plant shutdown operations and for events that
~
require E5F operation.
It consists of two motor-driven AFW pumps and one turbine-driven AFW pump that deliver water from the condensate storage tank (CST) to each steam generator.
Each motor-criven AFd pump can be aligned to two steam generators.
The turbine-driven AFV pump can be. aligned to all four steam generators.
The ASW pumps can be aligned to <ernate water supplies if the CST inventory is depleted.
The AFW system includes cacability to permit AF4 flow to be isolated to any steam generator wnile continuing to supply AFW flow to the other steam generators.
The reference plant AFW system is shorn in Figure 11.
4 b
The
.500 AN
^
e HF REF DLANT 31 Sectemoe-1, 1993 G753:1
==
55i
~
Q Figure 11. AUXILIARY FEEDWATER SYSTEM s.
SO Q inc ' onc f~
l
- 1g4 i
4 cst W
li
?
L taain I
. oodwalor xii
,n,,,
i Supply
{
O
=
g 0
l Mo,or - Driven g
L Main R
s Feedwater d
SG Q
[
l O
R 3(f
, :A:
I y
I I 'i doo72"aior 1.u...... -
mio.,,...
sa p
[
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=
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uou,, o.....,
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Feedwater Ad C
I l
5970000845 084 IRC I ORC
2.18 Steam Generator Blowcown System-The; steam generator blowdown system provides letcown from the secondary side f
ofithe. steam generators.
It consists of separate blowcown lines frera eacn steam generator that-join to form a common neader to a recirculation or discharge location.
The steam generators can be isolatec by blowcown isolation valves located in tne individual blowcown lines.
2.19 Sarolino System The sampling system provides means for sampling process systems.
It cohsists of the sampling system equipment that can be used ta sacole the RCS, steam generators and containment recirculation sumo.
2.20 Soent Fuel Storace and Cooline System The spent fuel storage and cooling system controls fuel storage positions to
- (~
ensure a subtritical geometric configuration and provides heat removal to maintain stored fuel within specified temoerature limits.
It incluces the level instrumentation for the scent fuel pit.
2.21' Control Red Drive Mechanism Ceoline Svstem The control rod crive mechanism (CRCM) cooling system provices heat removal from the control red drive mechanisms.
It consists of the ventilation fans used to circulate air around the control red crive mechanisms.
2.22 Control Red Control System o
The control rod control system controls the position of the control rods in the reactor core.
It includes those controls used to manually insert control rods.
!~
HP REF PLANT 33 Seotemoer 1. 1983 64780: 1 e
2.23 Turbine Control System
{'
- 7heLturbine control
- system controls the turbine generator.
It includes those controls used to manually runcack the turbine generator.
2.24 Electrical Power Svstem ( c 6 4o. o nr[.Tc recs ) -
The electrical power system providet ac and d:: electrical. power to ecuipment that require electrical power to accomplish their function..
It consists'f o
an offsite ac power supply and onsite emergency ac-and cc powered supplies.
The emergency ac' power supply is a two train system powered by secarate diesel generators. The de power supply is a two train system powered by.
separate battery b'anks.
Vital ac instrument power can be supplied by either-the emergency ac power supply or the de power supply via inverters.
The emergency diesel generators automatically start on the following:
o SI signal.
Blackout signal (generated oy low voltage on normal power supplies f,eeding o
ac emergency buses)
The diesel generators automatically energize their as;ociated emergency buses if offsite power is not available.
The following major loads are sequenced on
.the ~energi:ed ac emergency busses in accorcance with associated start signal.
o Blackout signal:
Charging /SI pumps o
o' CCW pumps (A
o SW pumps S-t:f- : t ';-
-e %
c. (,,
4 ONr/rc E4&s o AN o
hr A M **3 e
HP REF PLANT 34 f 47co.1 -
secte m e 1 1c=1
(..
.i.
o.SI signali o ' Charging /SI pumps "o.High-head SI pumps o low-head SI pumps i
~ o' CCW pumps o'
SW' pumps 3-^.;i m::: *;; ;a: m ( reier +, vuZ/ic G&s )-
o APW
. o,- Containment-spray signal':
Containment spray pumps o
-2.25 Pneumatic. Power Svstem The pneumatic power system supplies pneumatic power (typically control-air) to equipment that require oneumatic power to accomplish their functions. Equipment in this category include:
c' " r ; ; ;..- i ; e. T ".',' a o Steam generator'PORVs o Condenser steam dump valves o Letdown line isolation valves The air' supply to equipment located insioe containment is automatically isolated on a containment isolation Phase / signal which closes the containment isolation valves in the air supply line(s).
HP REF PLANT 35 Scote-oer 1 1 cal A'7:Q.1
- 3.. PLANT INSTRUMENTATION AND CONTROLS The reference plant consists of instrumentation and controis-necessary to
~
operate the reference plant systems in response to the emergency transient.
Instrumentation and controls are defined to the extent neess u ry to maximize technical guidance with respect to system operation while maximi:ing the generic applicability of the technical guidance.
The instrumentation and controls associated with the reference plant systems
(
are identified in Table 3.
These instruments and controls are within the defined scope of the reference plant and specifically identified in the ERGS.
These instruments and controls are also consistent with the ficures in Section 2.
Plant-specific systems utilize instruments anc centrols in addition to those itemized ~in Table 3.
Table 3 is provided to aid the user of this document in identifying and comparing the reference plant instrumentation and controls to the plant specific instrumentation and controls.
Instrumentation and control requirements are discussed, as approcriate, in the GENERIC INSTRUMENTATION document in the Generic Issues section of the Executi..VolumeandintheERGbackgrounddocumentsintheBackgroundYolumes.
L L
HP REF PLANT 36 6CES:1 Sectemoer 1, 1983
,~
I-i TABLE 3
. INSTRUMENTATION AND CONTROL REOUIREMENTS ITEM REQUIREMENTS
_1(1).
_CII)
' Reactor Trio Actuation' System Reactor Trip Annunicator X
Reactor. Trip 'and Bypass Breakers X
-Reactor Trip Signal X
X Turbine Trip Signal X
-X ESF Actuation System SI Annuncfator X
SI Signal X
X-SI S.ignal, Reset / Block g4 y m ~ n.s X.
X
-L Ster9:
- n.,a SI Actuation Signal-Block X
X Low PRZR Pressure SI Actuation Signal Block X
X Containment Isolation Phase A Signal X
X Containment Isolation Phase A Signal ~ Reset X
X Containment Isolation Phar,e B Signal Reset X
X Feedwater Isolation Signal Reset X
X Containment Spray Signal X
X Containment Spray Signal Reset X
X Main Steamline Isolation Signsl X
X Nuelear Instrumer.tation System Power Range Neutron Flux X
Intermediate Range Neutron Flux X
Intermediate Range Startup Rate X
HP REF PLANT 37 647EB:1 Sectember 1, 1983
f TABLE 3'(Cont):
I?
- INSTRUMENTATION AND CONTROL 2REOUIREMENTS ITEM-
. REQUIREMENTS
. g ( l')
C(1)
Nuclear' Instrumentation System (Cont)'
. Source' Range Neutron Flux X
Source Range Startup Rate
.(,
X Neutron Flux Recorder-X X
Source Range Detectors (Energize)
X X
Control Red Instrumentation System Control Rod Position X
Control Rod Bottom Lights X
Radiation Instrumentation Svsteg Containment Radiation X
SG Blowdown Radiation-X 1
Conder.ser Air Ejector Radir. tion X
Auk'.11ary Building Radit.cion X
s... uine neuios mo se
--h---
Containment Instrumentation System t
Containment Pressure X
Containment Temperature X
Containment Recirculation Sump Level X
Containment Hydrogen Concentration (Samole)
X Phase A Containment Isolation Valves X
X Phase B Containment Isolation Valves X
X Containment Ventilation Isolation Dampers X
X HP REF PLANT 38 647:n 1 seotemoer I 1983
t TABLE 3 (Cont):
~ l..-
_ INSTRUMENTATION AND CONTROL RECUIREMENTS ITEM-REOUIREMENTS
~'
Reactor Coolant-System
_y(l)
_Ck1)
RCS Pressure X
- (--
PRZR Pressure X
RCS Hot Leg Wide Range Temperature X
RCS Cold Leg Wide Range Temperature X
'RCS Average iemoerature X
Core Exit TC.Te'3cerature X
PRZR Water Temoerature X
1 PRZR Level X
t 9:::te
'!e re' '_'cufd
-cc.ntary_Syste.T. (RVL:3) s'.-
Reactor Coolant Pumos X-X f
PRZR PORVs X
'X PRZR PORV Block Valves' X
X PRZR Spray Valves X
X Reactor Vessel Vent Valves X
X Pressurizer Heaters '
X X
.(%
- HP REF PLANT 39 Sectember 1, 1983
- 6?758:1
TABLE 3 (Cont)
INSTRUMENTATICN AND CONTROL REOUIREVENTS-ITEM REOUIREMENTS II)
C(I)
I
'{-
Safety In.iection System Boron Injection Tank (BIT) Temperature X
Refueling-Water Storage T. ink' (RWST) Level X
Charging /SI Flow X
-High-Head SI Flow X
High-Head SI Pumps
~X
.X Accumulator Iscriation Valves X
X Accumulator Vent Valves X
X BIT Inlet Isolation Valves X
.X BIT Outlet Isolation Valves X
X Low-Head SI Pump Suction Valves X
X from Containment Recirculation Sump Low-Head SI Pump Suction Valves from RWST X
X High-Head SI.Pumo Suction Valves from RWST X
'X Low-Head SI Pumo Discharge Valve to RCS Hot Legs X
X Low-Head SI Pump Discharge Valves to RCS Cold legs X
X Si Valves X
X HP REF PLANT 40 647E3:1 Septemcer 1, 1983
,7-.
...x
-TABLE'3 (Cont)_
yh
_ INSTRUMENTATION AND' CONTROL' REQUIREMENTS' 4
-ITEM-
' REQUIREMENTS g(l)
- C.( 1) '
Residual Heat Removal-System Low-Head'SI (RHR) Flow X
.X-X Low-Head SI (RHR) Pump Suction Valves from RCS X
X Chemical'andVB[ume-ControlSystem-Boric Acid Tank Temperature X
Charging Flow X
.RCP Seal Injection Flow X-Letdown Flow
- (
X RCP Number 1 Seal Leakoff Flow X
RCP Number'l Seal Differential Pressure X
Charging /SI Pumps X
X Positive Displacement Charging Pump X
X Charging /SI Pump Suction Valves from RWST X
X Charging /SI Pump Section Valves from VCT X
X Charging Line Isolation Valves X
X Charging Line Flow Control Valve X
X Charging Line Hand Control Valve X
X Pressurizer Auxiliary Spray Valve X
X
.RCP Seal Injection Outside Containment Isolation
.X X
' Valves RCP Seal Return.Outside Containment Isolation Valve X
X Letdown Isolation Valvas X
X Letdown Orifice Isolation Valves X
X Low Pressure Letdown Control Valve X
X Excess Letdown Isolation Valves X
X HP REF PLANT 41 Sectemoer., 1983 6'752:1
-r
i TABLE 3 (Cont)
INSTRUMENTATION AND CONTROL REOUIREMENTS
_ ITEM.
REQUIREMENTS-II)
'C(I)
I I
Chemical and Volume Control System (Continued)
'(.
VCT Makeup Control-System.
X X
VCT Makeup Control Sys' tem (mode selector).
(
X X
Comoonent Coolino' Water System.
~
CCW Pumps X.
.X RCP Thermal Barrier CCW Return Inside Containment X
~ X Isolation Valve CCW Valves X
X
~
Service Water System
~
Service Water Pumps X
X Service Nater Valves
'X X
Containment Soray System Containment Spray Pumps X
X
. Containment Spray Valves X
X HP REF PLANT ~
42 64728:1 Seotember 1. 1983 l'
e.,
TABLE 3'.(Cont).
INSTRUMENTATION AND CONTROL REQUIREMENTS ITEM REOUIREMENTS
'C.
_y(l)
C(I)
Containment Atmosohere Control System
. Containment Ventilation Isolation Dampers X
X Ccc,W -- rE 4-N 'cr;-
X --
Hydrogen Recombiners.
X X
Containment Air Circulation Equipment ecCu 4 X-X Containment Filtration Equipment our /rc ge s X-X Main Steam Svstem SG Pressure X
SG Narrow Range Level X
SG Wide Range Level X
X Condenser Steam Dump Valves X
X Main Steamline Isolation Valves X
X Main Steamline Isolation Bypass Valves X
X Steam Supply Valves to Turbine-Oriven AFV Pt.=p X
X Turbine Stop Valves X
~
Main Feedwater and Condensate System FV Flow Centrol Valves X
X FW Flow Control Bypass Valves X
'FW Isolation Valves i
X X
i
~
l HP REF PLANT 43 647EB:1 September 1, 1983
.o
~
TABLE 3 (Cont)
INSTRUMENTATION AND CONTROL REQUIREMENTS
'n ITEM RECUIREMENTS 1(1).
.CII)
LAuxiliary Feedwater System Nuxiliary-Feedwater' Flow X
Condensate Storage Tank Level X
X' Condensate-Storage Tank to Hotwell Isolation Valves
.X X
AFW. Valves X-X
' Steam Generator Blowdown System SG Blowdown Isolation Valves X
X Samoline ' System SG Blowdown Sample Isolation Valves X
X Spent Fuel Storace and Cooline Svstem Spent Fuel Pit Level X
Control Rod Drive Mechanism Cooline System Control Rod Drive Mechanism Fans X
X
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1-L l-HP REF PLANT 44 l.
647S8:1 Septem er 1, 1983
TABLE'3 (Cont)
(.
' INSTRUMENTATION AND CONTROL-REOUIREMENTS ITEM
,REOUIREMENTS
~
1;
.t(1)~
. C(I
' Control Rod Control System-Control Rods X
X Turbine Control System Turbine Runback' X
X Electric Power System Diesel-Generators X.
X Pneumatic Power System'
. Instrument Air Compressor X'
X Instrument Air Valves X
X Notes C
(I)
I - Instrumentation requirements column C - Control requirements column
~-
An "X" entry -indicates an instrumentation or control requirement within the scope of the reference plant.
A " " entry indicates no requirement.
L HP REF PLANT 45
~6475B:1 Septemoer 1, 1983
Appendix L,2 Evaluation of the Differences Between SQN and the WOG Hir,h-Pressure Reference Plant we
y,
..g 1*
2.2
'Safetv'Iniection Signals.
The safety. injection signals are evaluates and ~dese t "3 in'th'e t
C FSAR~ chapter:7 and Technical Specification 3.3.2.
~
- ese differences do not affect the generic guidelines.
s.
The emergency gas treatment (ECTS) start sic al'is evaluated and described in the FSAR chapter 7.
The effect of EGTS is included e
in the UHI/IC ERG ~.
The auxiliary building gas treatment system start, auxiliary.
building isolation, and main control isolation signal is
~
evaluated and described in the FSAR chapter'7.
These features-will be included in.the plant specific procedure when auxiliary building and main control room isolation is required.
The manual block / reset for high steam flow actuatinn is evaluated and described in FSAR chapter 7.
This feature will be
-included in the plant specific procedure when the high steam flow actuation sign-l.is blocked / reset.
Containment Sorav Sienal The containment sr. ray signal is evaluated and described in the FSAR chapter 7 and-Technical Specification 3.3.2.
This effect is included in the.HI/IC ERG.
The containmett air return system start is evaluated and described. int the FSAR chapter 7.
This effect is included in the UHI/IC ERG.
Auxilitrv Feedwater Start Sienal The a af.11ary feedwater (AFW) start signals are evaluated and desc>ibed in the FSAD. chapter 10.
The AFW 7u.mp start after one main feedwater pump trip does not effect the generic guidelines.
The piant specific procedure will veri:y all AFW pumps are running following a reactor trip or safety injection.
Containment Isolation Phase B Sienai The phase B signal is evaluated and described fu the FSAR chapter 7 and Technical Specification 3.3.2.
This effect is included in the UHI/IC ERG.
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nic/0103R L
-c Main Steamline Isolation St.enal
'The main steamline isolation signals are evaluated and described-in the FSt.R chapter 7 and Technical Specification 3.3.2.
The P-11 block does not atfact the steamline isolation logic andi therefore, the plant specific procedure will delete the P-ll block wher. used to prevent steamline isolation.
2.5 Radiation Instrumen:ation System i
l l
The main condense: eA aust radiacion monitor is listed in the
(
-Technical Specifi:ation 1.3.3.10.
The effect of SGTR identification /antlysis is c ;cribed and evaluated in FSAR 15.4.3.
The FSAR describes utilizing rising S/G level and E/G blowdown to determine ruptured S/C.
The plant specific procedures will atilize the condenser exhaurt radiation monitor, rising S/G 1evel, S/G blowdcen radiation monitor, and/or local a
surveys of the main steamlines instead of the main steamline
(
radiation monitor.
/
12. 7 Reactor Coolant System (RCS)
The cold overpressure protection system is evaluated and described in the FSAR chapter 5.
This difference does not effect the generiq guideline.
The pressurizer spray lines are r7nnected to RCS loops 1 and 2.
This does not effect the generic guidelines.
The reactor vessel head vent system is evaluated and described in the FSAR chapter 5.
The discharge of vent system is routed to the pressurizer relief tank.
This feature will be included in the plan 2 specific procedure when the reactor vessel head is vented.
The RCS pressure transmitters are connecte/ to loops 1 and 3.
The WOG Generic Instrumentation states that the RCS (? :ssumed to have at least two wide range pressure transmitters connected to the RHR hot leg suction lines.
This instrumentation is assumed to be subject to adverse containment conditions. SQN, in its review of the needed characteristics (e g. accuracy) for c
this instrument (RCS wide range pressure and RCS subcooling),
decided that a more accurate indication is required than would be provided if lo:ated inside containment (due to the harsh environment).
SQN has therefore relocated the transmitter outsiue contoineent. This parameter does meet the WOG guidelines with respect to range and number.
nleiO103R q-,'
~~
4 4
.. o s
-The pressurizer: air-operated PORVs have been replaced with:
E
. solenoid-operated PORVs. Therefore~, there is no need to
('
establish air-to containment to' operate pressurizer PORVs.'- This feature will.be included in plant specific 1 procedure.-
.The reactor vessel-head vent valves are solenoid operated valves.:-This feature does not effect the generic: guideline.
2.3 Safety Infection Svstem.
The containment sump swap over logic is describe..and evaluated
'in the SQN FSAR 6.3.2.2 and 7.6 and Technical Specification
- 3. 3. 2. - The containment sump logic-input is added to do containment swapover procedure, nThe other changes are described and evaluated in the UHI/ICIERGs.
~
2.9 ~
Residual Heat Removal (RHR) System
?
The RHR system is evaluated-and' described'in FSAR 5.5.7. for.the normal plant shut-down operations at low reactor coolant system pressure. This difference does not affect the WOG ERGS.
(
2.10' Chemical and' Volume control System (CVCS)
The CVCS is evaluated anc deceribed in FSAR.9.3.4 This difference does not effect the WOG ERGS.
2.11.
Comeonent coeling Water System The component e mling water system is described in FSAR 9.2.1.
The UHI/IC IRGs eval
- ss this change.
2.12 Service Water System This is described and evaluated in UHI/IC ERGS.
2.13 Cantainment Serav Svstems The changes are described and evaluated in UHI/IC ERGS.
2.14 Containment Atmosehere This change is described and evaluated in UNI /IC ERGS.
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2.15L Main Steam System The-Main Steam System-is' described'ind evaluatedlin FSAR 10.3.
t
=This difference does not effect the WOG ERGS.-
,EC 2.16 Main'Feedwater and Condensate System!
- The' Main.Fie'dwater andlCondensatc System is described and
~
evaluated L in FS4R'10.4.7. -This dif f erence does not 'ef f ect the WOG' ERCS.
2.17 Auxiliarv Feedwater System
~
The SQN ATW system design' includes automatic level control Talve (LCVs) which are evaluated and described in FSAR 10.4.7.-
- This, feature will_be includedtin the' plant specific procedure vise manual control of Art.*.
a
'2.24 EEee^trical Power System i
The containment fon coolers deletion is evaluated and describedJ in UHI/IC ERGS.
The other changes are evaluated and described inFSAR 8.3.
These~ changes.do not effect the WOGLERGs.
2.25' Pneumatic Power System-The pressurizer air-operated PORVs have been replaced.with so.!enoid-operated PORVs.- therefore there.is no need'to establish air to containment to operate pressurizers-PCRVs.
This feature will be included in plant specific procedure.-
r The containment isolation signal for containment air. valves is described'and evaluated in FSAR 6.2.4 Therefore this system ~
will not isolate at phase A.
There is no need'to' reestablish instrument air to containment until after phase 3.
This feature i
will be included-in plant specific proceaures.
L3F Actuation Svstem The high steam flow SI actuatier. signal block is evaluated and described in FSAR chapter 7.
This feature will be included in j
the plant specific procedure when the high steam flow actuation signal is blocked.
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nic/0103R,
~.
F-Radiation Instrumentation System The plar t specific radiation instrumentation does not include steamline radiation monitors. The plant specific procedures will utilize the condenser exhaust radiation monitors, steam generator blowdown radiation monitors, and/or local surveys of the steamlines instead of the main s.eamline radiation monitors.
Reactor Vessel Licuid Inventory System (RVLIS)
TVA, in accordance with our letter from J. A. Domer to E. Adensam dated August 14, 1985, has implemented non-RVLIS version of E0Ps at SQN.
The status regarding RVLIS and its impact on E0Ps, Safety Parameter Display System (SPDS) and Technical Support Center (TSC) was discussed in a meeting held on July 28, 1985 with NRC representatives.
In accordance with our commitments with you, TVA will implement a RVLIS version of E0Ps before startup from the unit 2 cycle 3 refueling outage.
Containment Atmosehere Control Systems The changes to the plant specific guideline is described and evaluated in the UHI/IC ERGS.
Main Feedwater and Condensate System Valve position of the feedwater control bypass must be determined locally.
The feedwater control bypass valves are non-safety grade and described and evaluated in FSAR 10.4.7.
The plant specific procedure will be revised to locally check the valve position if main feedwater flow is indicated.
Condensate Storace Tank (CST) Level Instrumentation The WOG Generic Instrumentation requires at least two channels of a v. elta P measurement system are available to monitor the level in each CST.
SQN CSTs have one level indicator per tank, however, the tanks are tied together by way of the supply'to ATW pu=ps.
In addition, in accordance with FSAR,'0.4.7.2 and 9.2, the ERCW system is considered the safety-grade supply to ATW pu=ps.
SQN therefore finds t!ais deviation acceptable.
\\
~5-
n Appendix F SIGNIFICANT DEVIATION FROM WOG ERCS n
l l
l I
nic/0103R l
/,.:o Revised FR-S.I. "Respouse to Nuclear Power Generation /ATWS" Concerning Tripping the Turbine SQN received several ' validation and verification' comments concerning tripping the turbine within 30 seconds of an ATWS event. To alleviate these concerns. TVA has analyzed a postulated loss of feedwater ATWS for SQN assuming no automatic or manual actions within the first three minuters of the This analysis was_ performed using the RETRAIN 03 MOD 003 computer code event.
in conjunction with a SQN specific model.
The analysis was based on reactivity parameters characteristic of unit 1 cycle 3 beginning-of-life core data to remove conservatisms and credit the partial burnup benefit in the moderator temperature coefficient.
Results of this analysis show that ASME pressure limits are not exceeded and, hence, no short term mitigative actions, manual or automatic, are necessary. See the attached table for a comparison of component maximum pressures as computed by this analysis and the maximum allowable pressures based on the ASME limits.
In addition, TVA has committed to implement an ATWS mitigating system actuation circuitry (AMSAC) at SQN to meet the requirements of 10 CFR 50.62 per our letter"from R. H. Shell to Harold R. Denton dated October 11, 1985.
The AMSAC system to be implemented is logic to actuate a turbine trip and auxiliary feedwater pump start upon sensing that steam generator water levels are below the low-low setpoint.
This logic senses conditions indicative of an ATWS event when the loss of a heat sink has occurred, but actuation will not occur until after the reactor protection signals should have been generated.
i I
l i
nic/0103R i
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PRESSURE LIMIT COMPARISON TABLE UIC3 Peak -
Limit
--(No Turbine T ip)
(ib/in2 )
(1b/in2.)
a Reactor Ves:S1 3215 3044'
'Pressuriser
.3885 2926 RCS; Piping.
3742 3042-Reactor Coolant Pump 3246 3006-Control Rod Drive Mechanism 3849' 3038
'RCS Pressure Boundary Valves-Valve Bodies 4740
-3042 Valve Bolting 4740 3042 i-Valve Disks 3166 3042
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