ML19221A271
| ML19221A271 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 04/13/1979 |
| From: | Daniel J GENERAL PUBLIC UTILITIES CORP. |
| To: | Vollmer R Office of Nuclear Reactor Regulation |
| References | |
| 790414, NUDOCS 7905210120 | |
| Download: ML19221A271 (24) | |
Text
s% e - :..
Inter-Office Memorandum Daie.
April 13, 1979 m
'ISG-021 7
4 Subjec-Sample Analyses
~
~o:
Gary Miller Locahort Three Milc 1:11and a.
/
In order to better compare and document the radioactive samples being analyzed by dif ferent organiza tions, it is requested that the attached standardized form be used for reporting results of all analyses.
/J A.
Daniel JAD/51 ATT cc:
R.
C. Arnold
.-l
_ r_ av e.My r
Staudt/ File y_.
p_
2.
YGlMER f -)
Y
's,*, ' i.
e
%k ' ' ? :-
[..'[\\c ;. iy
_]. t =~
p.1-
.T
-f*fa k, tE!.';M 'f ah.h '* t.%jr.Y fz ~; '
1.
~
-_~
- a fbN
. h ' -.. f..
~..; s) [sr %.n ;s.,
2,c
-. m f-v.
. '_Q Q*'.3 k:' lT-Y.*
s
't b
~4 e.
. h. ' ~
lf A :..'.
'i - ' * ' '
i.;. %.-(,'ec>.;w-+..Z;
.,, ~
f :.:~
e.
q,. x. 3.
a
'+ r:
.c s
T..,**..]t..s ".*
1.*~1 w
sy 1
i'.3..,,,
8 u,. r.
b.
.;.f:
4'.
' 7.
.7-
.y..
\\ y, 7 r, }
n
/
7905210/EC kb
./
Inter-Office Memorandum Cate April 13, 1979 Time: 15:20 TSC/025 7
q Sutyrt TMI-2 Modification' Criteria for Alternato Method to Measure Steam ? : Y
.- M
.I' !L '
_",' * - M (-[.~.] -(, ),
3,r Generator Level-
-3 y ->j, 1,,
-i,;
Trailer City, 1;o. 16 ~n.I To,
W.
R.
Cobean i
Lccatort '
.,.., - su
.r
-- ~
)
a :i i.:
.c
,.. Cf.,j-3 J L.
. Q.LL;. g. d; 'i..,--
g..
t g,
~
j'.
-- T.R : t Y 'L [yi =., $ '$. ?> > !L d
~.n i _ 'Ql ' d b$ ' *15 C ? I '. ~ *- U i ~
r
-S.h *l.'. 9 p'..
5 u_,. s 7._
/..
- - > : a ; ; +, 4. c m,. p.
- 9. e. y....
- g :, - -
c '-
.. _ -. g-y
.1 5
- s. ;_,
Attached is design criteria for use in designing \\
an alternate
' method to measure steam generator level.
2
-?
=.
- ~. - \\
.?
2.
r t-# G. Capodanno GRC/jed cc:
D.
S3Lar 3f-fmi_VSTEV NRi5:_
G.
Capodanno R.
F. Wilson L.
l'a rd ing R.
Keaton T.
G.
Broughton Modification Cri~teria File G.
Troffer - Met Ed R.
Warren (6) - Met Ed J. McMillan - B&W r>
1
/,
,).T
}, 't
/L-b 3
^ C)
GPU Cemcc Ccarancn c a :uts.oary cf C(reral Putic Utat.es Ccrpceahcn
')
4/13/79
.r_
a
~
TECHNICAL MODIFICATION, TM 29 s
DESIGN CRITERIA FOR ALTERNATE S/G LEVEL MEASUREMENT
.,.'-.,*..a.-* U ~'",.I
.,... a.:c Ff- ',g's.
p f*j
'a 5.
,f., [*-
.i
}
~,
{.-
7;*p 1-k, -.k'-,".*"
- \\.,
e
- f. a.,... ',;
2-: p... z -.-3.
y $ >,g d
c s
..3.,f s. s,.ns e
~,
.s
=
.s.
v.
~, :.
h w-ru... t g a.
a.
z-
- ^- 4.%v... ns
- m :r... *^,
,,. - g w
a-Design a plant.mo_dif.i.c_a_tio.n 'tc provide an alternate raethod _'&:\\>;]
a.
- t..',
- 1 g T -=3..
- b..:
u '-
C
- ~
.g *~ 2 'm.',7.9. p f
m p
' ' g. '7 3 1 measuring -steam generator -levr.1. 2 7 3.F J 'J
- y. is, j : -L'
.r-2 '-- W'L7 '1 C. 4 The design shallnot'Y{-lely on any electrical components located,: 1[ ii.' '?
~
inside the reactiar buildilig'.I,-
- .-4 li. 3 Z 4 y,m
- -._ &..;,4 3
- s.. c
-y Level shall be determined by measuring the differential pressurer?- s-across FW-DP-7883-1,
-2 (see B&R Dwg. Nos. 2002 and 2005) for steam generators A and B respectively.
This method will allow measurement of steam generator water level; (at low feed water flow) between the elevations of the feadwater and steam outlet nozzle connections.
This-is a range of approxi
,a, mately three feet.
.,1 r
r4AwW $ /
APPROVED Y
e a "
5 r
144 B-3
,{
INDEX 1.0 SYSTEMS CRITERLt 2.0 SHORT TERM DESIGN BASIS 2.1 Functional Performance
- 2. 2 Applicable Code And Standards 2.3 Sizit.g Requirements 2.4 Layout Requirements 2.5 Environmental Requirements 2.6
' Sampling Requirements 2.7 Material Requirements 2.8 Electrical Requirements 2.9 Testing Requirements 2.10 Instrumentation And Control 2.11 Water Chemistry Requirements 3.0 LONG TERM EASIS 3.)
Functional Performance Requirements 3.2 Applica' ale Codes and Standards 3.3 Design Basis 3.4 Sizing Requirements l
3.5 Layout Requirecients 3.6 Environmental Requirements 3.7-Sampling Requirements 3.8 Material Requirements 3.9 Electrical Requirements 3.10 Testing Regairements 3.11 Instrumentation And Control 3.12 Water Chemistry Requirements.
.7
) [t '
d
Page 1 of 8
THREE MILE ISLAND UNIT 2 System Criteria For Use Of Steam n ', ;
Generator "A" For Short And Long Term Cooldown -
g-q.
~
-. V.T.,-
u;1 1.0 SYSTEMS CRITERIA
,. _v.
~
,,,'_,$ 7
.3
, J-. -
.y,
.3
'Ihis document defines the design criteria for providing for water
- N' ' '-
to water cooling in steam generator "A" to remove decay heat on a short term and long term basis.
2.0 SHORT TERM DESIGN 2.1 Functionni Performance Recuirements
~
Use the existing condensate - feedwater system.
Operate one condensate
~
~
pump with the others standby.
"Ihe condensate booster pump and feedwater.
pump are not running and the cooling water is I 8mped thru (impellers locked and aux. cooling water not required.)
'Ihe feedwater heaters are bypassed and the water enters the steam generator thru normal main feedwater connection and out the main ~ steam connection to the main condenser via the condenser makeup line.
A manual means of locking.
.j '
the makeup control valve in position shall be provided.
Alternate diesel generator power must be suppled to electrical components where.
necessary in case of loss of off-site power to provide proper system -----.
operation._...
__._____.._._._..Q.,'._.
^
Circulating water system in normal. operation vill be used." One circulating water pump shall be supplied by the construction powcr line.
the south end of the island.
In case of loss of off-site plant..,,
at
'(
auxiliary power, backup power via either auxiliary diesel or g..?. ~ ' '
g, y,j construction power will be used for the circulating water pu.apM ';--. J., :x,.,-F
^
discharge valve.
Makeup shall be taken from the condensate storage.-
?f -F.
~
tanks by gravity to the condenser by manual control.
-- '>~.V'
.?8 n,.q. p.
- s p.
Loss of condenser vacuum requires opening of, the vacuum breaker '(to.
' t,,, x - --
. c3
~
' '/,; -f.'
be diesel powered), and recirculation of the' condensate pump discharge
'!g.
to cool condensate in hotwell.
System shall be checked. for_ correct
.,C j '
valve alignment.
Those items dich could interfere with, the proper'
, fyg:'
- fy.
function of the system shall be locked out..
7~
,..g ~f, f
,- a x-c.v, Connections shall be provided for tie in of the long term cooling '.:. v
~",.
. ~
. Cf -
'Ihese connections and any non-isolatable portions of the short }: 3 system.
term cooling scheme shall be of adequate pressure class to be co=patible with the design pressure of the long term system.
,;- ~,1, M., _ [.
2:
.a classification shall be non-seismic Category I.-
~ ~
(-
seismic c
^h*@
s g
- /
s._e%
) 7, 3, ;I; f,. dy g,,.
. J ~,'7.- '.r.
44-YkbSiE$5 N-
~
Page 2 of 8
S*
Provisions shall be made for slow, controlled filling of the steam generator to avoid water hammer (steam bubble collapse) and too rapid cooling of the steam generator.
2.2 Applicable Code And Standards Piping
- ANSI B31.1 Heat Exchanges
- ASME Section VIII Tanks
- ASME Section.VIII Pumps
- ASME Section VIII or API Valves
- ANSI B16.5, B16.34 2.3 Sizing Requirements Flow to stecm Generator 3000 to 5000 gpm.
Steam Generator inlet temp. S./G. Inlet 80 F.
Steam Generator outlet temp. S./G. Outlet 80 F to 250 F
' System Pressure Capability of existing componegts Heat Exchanger Duty 30 x 10 Btu /hr River Water Inlet Temperature 32 to 850 y River Water Flow 17,100 gpm
- 2. 4 Lavout Recuirements Reference Figure 1 attached.
Secondary side shall utilitze existing ccndensate, feedwater, and main steam systems.
On the river water side, the nuclear services cooling water system shall be cross connected to the circul ating water system to provide cooling on loss of off-site power.
Cross connections shall be made in the pumphouse from the nuclear services river water system, and in the turbine building from the secondary services river water system to die circulating water system.
The cooling water syt, tem to steam generator "A" must be isolated from steam gene:ator "B" cooling system.
I 2.5 En ironmental Recuirement i
All equipment is or shall be located indoors in the river water pump h o"se u.
iiire building except the alternate diesel generators which shall be suitable for outdoor installation.
2.6 S ecr.tr.4 Requirements S.impling provisions on the steam generators inlet and outlet for water chemistry ari radiation monitoring.
2.7 Material Requirement All materials shall be compatible with the fluids'being pumped.
4 356
Inter-O!fice Edemorandum Date:
April 14, 1979, 0600 y-
- a=v i.r p J
- $ g
- g[ge
= 2 subject:
IMI - 2 Modification Criteria for
.g h
%7 Use of Steam Generators for Short and Long Term Cooldown (Rev. 2)
To:
MR. W. R.
COBEAN Location:
Trailer City, #11-Attached are reficed criteria for use in designing plant modifications to use the " A" and "B" steam generators as water to water heat exchangers for decay heat removal.
These criteria have been changed as follows:
Maximum closed loop temperature has been changed to 250 F.
a.
b.
Cooling water flow rate has been revised to indicate a 5,000 gpui maximum flow, c.
Design pressure for the closed loop long term schemes has been changed to 750 psig.
d.
Amended chemistry requirement, per B & W transmittal of April 12, 1979.
(Instruccion No. 309) c.
Criteria has been re-formated into a criteria document for the "A" generator and a separate criteria document for the "B" generator.
The crire la as revised and its impact on systems design has c
been reviewed with the NRC and the on-site design grcup.
Both organizations are aware of the changes and the design work has been proceeding accordingly.
Design features to account for start up of the system have also been discussed and input froci those groups developing procedures / contingency plans has been passed on to the design group for their consideration in developing the design.
"he criteria for use of "A" steam generator for short term cooldown has been furt.her revised to provide for power to one circulating water pump to be provided by the construction power.
from the south end of the site.
I
! /m M y,
Cipodanno/8 C.
CRC /fw cc:
D.
Sicar T. G.
Broughton j'
G. Troffer - Met Ed svms. nrgge py Dhtuino R. Warren (6) - Met Ed R. F. Wilson J. McMillan - B & W L.
Harding' R.
E. Allen - GPU; Reading R.
Keaton Modification Criteria File b
i A lph. -/
Page 3 of 8 2.8 Electrical Requirements (later) 2.9 Testing Reauirements Provision shall be made for preoperational testing of the system, including hydrostatic testing and flushing of new piping.
2.10 Instrumentation And Control Review existing instrumentation and controls to assure proper function of system under new conditions.
Specific consideration shall be given to the effects on system operation of spurious automatic control signals to existing plant components that are part of this system.
Instrumentation to be provided for the following:
Flow 0
6,000 gpm range Temperature, 0
500 F Pressure Pump shut off head Radiatico Monitoring Area monitoring where equipment and componenes are i stalled Hot Well Level Instrumentation and controls shall be local.
Flow and temperature control shall be manual.
Critical instrumentation shall be redundant.
2.11 Water Chemistry Requirements The system water chemistry shall be maintained in accordance with the following:
PH @ 770 7 9.3 - 10.5 (controlled by NH ou ddition) 4 02 (dissulved) 100 PPB max (OTSG < 300 F) 2 Cation Conductivity 10 u mho / cm Hydradine At least 3007. of stoichimetric 0 e acentration 2
The makeup and fill water chemistry shall be in accordance with the folling:
02 (dissolved) 100 PPB max OTSG (300 F)
Cation conductivity 1 u mho / cm, m ax.
thI Means shall be provided to add ammonia hydroxide and hydrazine to systes.
~.
=..
144 358
'~
page 4 of 8 3.0 LONG TERM EASIS 3.1 Functional Performance Recuirements Recirculation of high pressure closed cycle cooling water thru the secondary side of the steam generators for removal of decay heat from the primary coolant.
The ultLnate heat sink shall be river water.
3.2 Applicable Codes and Standards Piping
- ANSI B31.1 Heat Exchanges
~
Tanks
- ASME Section VIII Pumps
- ASME Section VIII or AP 1 Valves
- ASNI B16.5, B16.34 Electrical (later)
~
Note: ASME Section III components will be utilized when availabic 3.3 Design Basis 3.3.1 The system shall ba designed as non setsmic category I.
3.3.2 The system shall be d6 signed for long term continous cooling for a minimum of two years.
3.3.3 The system shall be designed to operate with a loss of off-site power.
3.3.4 The system shall have the ability to accommodate changes in fluid volume and temperature in the closed loop.
3.3.5 The system shall have the capability to-regulate the temperature of cooling water entering the steam generator.
3.3.6 Th e sys tem shall be designed to operate at 1007. capacity with a loss of a single active component.
l.
3.3.7 The system shall be qquippe/. with sufficient test and instrumentation connections for system'preoperational testing and normal operation.
3.3.8 The system shall be designed to supply cooled water to the steam generator through:the main feedwater nozzle and receive heated water th rou gh th : main steam nozzle.
3.3.9 The system design shall employ all welded connections to the greatest extent possible to minimize system leakage.
3.3.10 The cooling system locp for the '!A" steam generator shall be designed to minimize the unavailablity of the "A" steam generator when bringing the cocling system on line.
lkk
Page 5 of 8 3.3.11 The system shall include provisions for future addition of automatic controls and alarms.
3.3.12 The system design shall maintain containment integrity.
3.3.13 The system design shall provide means for controlling cooling water chemistry requirements as specified by B & W.
3.3.14 The system design.shall minimize the use of auxiliary support systems (bearing cooling water, lubrication oil, ins t rument air.)
3.3.15 The system shall be designed to operate at a pressure higher t he primary coolant pressure so there will be no leakage of primar, r
l'~
into dae closed cooling system.
- 3. 3. 56 ~
The system shall be designed to remove the required heat load with variations in the temperature of the ultimate heat sink.
3.3.17 The system design must include the capability to degas the cooling water.
3.3.18 The system shall have provisions for a future clean-up system snould the cooling water become contafminated.
3.3.19 The system shall be provided with proper overpressure relief devices.
3.3.20 The system shall have provisions for proper system flushing prior to startup.
3.4 Sizing Requirements 3.4.1 The system shall be designed to meet the following requirements:
(a) flow through steam generator 3,000 to 5000 gpm (b) steam generator inlet temperature 80 F (c) steam generator outlet. temperature 80 to 250 F (d) design pressure at S/G inlet 750 psi (e) river water temperature 3.4 to 85 F (f) river water flow rate as required to re.nove heat load with a 10 F or less
}.
increase in river water t emp era ture 3.5 Layout Requirements 3.5;1 The system equipment shall be located to facilitate construction and ~
ease of acesss during operation.
3.5.2 The sys t em flow path shall consist of cooled water entering the steam generator through the main feedwater no::le, exiting the steam generator thratgh the main steam line, entering the heat anchangers (coolers) and returned back to the steam generator using the system pumps.
(Reter to figure 3. )
The ultimate heat sink shall be provided by the nuclear services. river wa ter sys t e=s.
144 360
Page 6 of 8
+
3.6 Environmental Recui rement s 3.6.1 All equipment shall be located indoors except the alternate diesel generators which shall be suitable for outdoor installation.
3.7 Sampling Recuirements 3.7.1 Adequate sampling connections shall be provided for water chemistry and radiation monitoring.
3.8 Material Recuirements 3.8.1 All wetted materials shall be compatible with the water Leing handled.
3.9 Electrical Requirements 3.9.1 (later) 3.10 Testing Requirements 3.10.1 Provisions shall be made for preoperational testing of the system, including hydrostatic tests.
3.11 Ins trumentation And Control Requirement s 3.11.1 The system shall be designed to providc instrumentation sufficient to monitor functional performance requirements including:
(a) pump discharge prer.sure, 0 - 750 psig.
(b) steam generator inlet and outlet temperatures 50 - 2500 F (c) flow rate, nominally 3,000 gpm, maximum 5000 gpm (d) river water inlet and outlet temperatures 0 - 100 F Critical instrumentation shall be redundant.
Area radiation monitoring shall be provided wherc the equipment and components are installed.
Specific consideration shall be given to the ef fects on system cperation of spurious automatic control signals to existing plant c omponen t s that are part of this system.
3.12 Water Ch emis t ry 3.12'.1 The system water chemistry shall be maintained in acco sith the following:
(a) pH @ 77 F
- 9. 3 - 10. 5 (controle
. bg NH 0H)
F)4 (b) 0 d is s olved 100 ppb max. (UTSG < 30u 2
(c)
Cation conductivity 10 umho' / cm, max (d) Hydrazine at least 3007. of s toichiometric 02 cor antration (c) Surge tank level The makeup and fill water chemistry shall be in accordance with the following:
02 (dissolved) 100 PPB max '(OTSB ([ 300 F)
E, max.
Cation Conductivity 1 umho / cm Means shall be provided to add ammonia hydroxide and 1.ydrazine to the system.
144 36i
.