ML19319D440
| ML19319D440 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/16/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003170570 | |
| Download: ML19319D440 (5) | |
Text
.
4 Niic e s,q:.i 1 b, u *i. UUC f.L A N W..lL A ! O H Y c 9 Wi% h.f. i L&s C T N U -W.,
3.0.~_.3_O..L_. _
V'- "
I' l l ~' J U Y J E I t NrC LM.TmSUTION mn PM'.T 50 DCCi'ET T,1ATEfilAL
-ro:
FFiO41. Florida Power Corp.
"AT:W m'n' Mr. John Stolz St. Petersburg, Fla. 33733 12-16-76 J.T. Rodgers cArc ecccivro 12-20-76 hTTi n Unoromno e; ce usurForu qu'.mt s or cums m m e c o i
Mo.U. ANAL h CLASSifIET' Occ 'v 1 signed 39 CC cu,cr.n T m Ltr trans the following:
E N O'.OSU H E Response to Informal NRC Question Concerinng Pump Runout In Decay Heat System.l..
I (40 cys enc 1 ree'd) s I
l'. APT l'A!'r::
Crystal River Plant M
3,,,,,,r.,......-.
n.
.1%.w);,s*
&u&
l i
L s'a i'"!
FOR ACTIO:ul;> OW..ATiON
- - -,-,r, DHL. 12-22-76 I/
/,r..;;',.'5a M :
V4ssa //4 a <..i.a~. p r_e,.).r..
x._._.--..
.m....,. ; s,~.,,-:.
o /,
m.....,.
m mts.
_w.
/.
a t i,n ;'.m 'm- *: n.
/G, /e,.
P.'!O,7 cT i:wA:;ta:
r ne l
J,!C_. ? ' 9*.
//o o LIC. /.SS_T. :
i l
L.
I INTE Rip t. GISTit t:.UTIUN i_C '"O SYST"':S Sai'2TY fi F:.A.:r U':P'm(:
s... 2 ::? - ' -'? r.___._
y/ 1 m.
rd UCI.'E;'At!
,/
T:'T:7.C:'O 7" t"4 1_'"a____.__
'__ I b :.
- /
SCH?.003n
/
.2.:' ?.Oa".i,_
_ _,e";;tr_'.!_.t L
Mf.T.')
/'
T. A T. "M GG. IC:; 6. S '."; F E git":Enn:C
/.
I.pyc:.~'! C..
l.' 'E G "".~.C".
___.a. i c 7
"A C_._' _10.0,*
/i A"I'"n'. w* ~ Q 7.W C A! 2
/
K"ICilT I
M I.~. 7 1:. 7.mn
, /
SIP;E!T.
OPGATT:G :1EACTCRS
! Sr. !:G!.a..
1:',IJES3
/
PM&lg3I
,7, ST.':I.!.0 i
i*L.
--, r. r.
.. n,
I._~_1_"'...! *'CT ".* ? Ar.' " ':iT i
PEA.' TOT 3lyr,77
..C._I. U. TI:.'G TT.C!!.
/'._C. ' _. " iT..L_I..(2.)
s P., -;
/
'T...,.':;
'."__L. u_'J,"'
_T. T P
___. t : 0.:!.SK.. :.
/_
n032TC':ZY
,__.-_E*.'-
I__I n.
~.....
s.,
i.
p - a.?. *. *w' ei..xe r
~... rst e
.. pm... 3
'.4
f'**
- .,'T '"J a t i n'i ' 1 d' se i 6
4 L
.a *sa s p., a e U.. \\
6e J.f T:.
r;'i';3.;
/ i V O'J.:...'.
7
~5,., - e'
'4
' ~ ".. m.
._ v,,.,n......
~
., z!12t 13 __.
.g
. ~ '. '
p-..
y c p",'
i
~
.1
.. N,it Ul.sT.racuTsu[
ExiF:
i CC:a tu l. t!U:uE ri -.
.d........' : Ar.ptiL(rata,[M _. U ',T.._L J: :. _ _.
.]-.
,T_I_'11.,.
. 320m!*
': ?
/7w r.CG V,I;;
__._i::.2..r_K..
a.e_ _r_i.1 m
r_,l;;'n c :
1A PDR g,,
y,J
,3 Y 'i:
cc.::s r.:Jr '.'tr.S :
. _+_
s p,
v 1
V AC;;; h C'i3 6 n:UT_ tf s_C. A
.._ _12.. /__ __. '?_. 6 -
8 f LO.3 17 0
". O E %ii kl I'I') { e'. 7l's )
4
.,13
.? l J 6,,h,
, - +/ )
- T3 )
l-1 h/
[62U.I.CiC(... ~.,(U[
' ; j, >
s' M
< ^ '
Power cf h
co.,o...o~
December 16, 1976 O
DEC20 g > (. l g.g DV2/
+
..- g
'\\
bir. John Stol:
~
Branch Chief
Light -Water Reactors-Branch I s
Division of Project >fanagement U.S. Nuclear Regulatory Comnission Washington, D.C.
20555
Subject:
Crystal River Unit #3 Operating License DPR-72 Docket No. 50-302
Dear Str. Stol:
At the request of members of your staff, we are formally sub-mitting the attached information concern'ing pump runout in the Decay Heat System at Crystal River Unit #3.
This informa-tion was informally sent to Afr. Engle of your staff on October 26, 1976.
Since that time, we have retested the runout scheme of the Decay Heat System at the lower flow setpoints of 2800 and 3100 gpm, and the test was successful in that flow control was maintained continuously between these talues.
The test to verify the ability to gravity drain from the hot e
leg of the Reactor Coolant System to the Reactor Building Sump via the D.H. drop line was performed with the following prerequisites:
- 1. Reactor Vessel Head removed.
- 2. No fuel in the core.
- 3. Four inch water level in the hot leg piping of the Reactor Coolant System.
>Y General Office 3201 Thirty-fourtn street sout,. P.o Box 14o42, St Petersburg. Florida 33733 813-866-5151
Mr. John Stol: December 16, 1976 As indicated in our December 10, 1976 letter, this test successfully verified a flow rate of greater than 40 gpm in the D.H. drop line.
If you require further discussion, please contact us.
Very truly yours, J.
Rodgers Asst. Vice President JTR/iw Attachments.
October 26, 1976
" f-
.2
....~D RESPONSE TO INFORMAL NRC QUESTION CONCERNING PUMP RUNOUT IN DECAY llEAT SYSTEM Cct's IA*
0 ';;! # l
~
PD.N.@'
_dM::dh 1.
Previous Response:
{;Eg,;,7,7 ;,.,q,7 q On July 16 and September 3, 1976 we submitted informally a description of the proposed modifications to the Decay Heat System to prevent pump runout.
In summary, we stated that automatic flow switches would be installed to monitor the discharge flow of DHP-1A and DHP-1B and as the Reactor Coolant pressure decays following a LOCA, the switches would automatically throttle DHV-110 and DlIV-111 as required to maintain the flow between 3000 and 3300 gpm during both the injection and recirculation phases of operation.
The flow and alarm setpoints for this modification vere stated as follows:
Automatic Flow Switch Setpoints Alarm Setpoints Injection Phase GPM GPM liigh Flow 3300 3400 Low Flow 3000 2800 Recirculation Phase GPM GPM liigh Flow 3700 3400 Low Flow 3000 2800 II. Test Status:
The above automatic flow switch' modification has been tasted for the 3000 to 3300 gpm range and does function
- properly, III.New NRC Concern:
Since our submittal of the above proposed modification, the NRC has expressed some concern relating to the available.
NPSil vs. the required NPSil at the 3300 gpm flow iate from the Reactor Building Sump during t.he recirculation phase of operation.
m G
- .C i
October 26, 1976
....IV. Response to NRC Concern:
For the Decay Heat System the low flow control setpoint shall be lowered to 2800 gpm with a 2750 gp'be lowered to 3100 gpm m low flow alarm and
.the high flow control setpoint shall with a 3150 gpm high flow alarm.
The normal flow rate of the system within this range will be approximately 3000 gpm.
The high flow rate setpoint of 3100 gpm maintains the Decay Heat Pump within the calculated available NPSH for the entire system operating spectrum (Initial Injection and Recirculation Modes) and the lo' flow-rate setpoint of 2800 gpm is above the minimum flow rate (2700 gpm) required to adequately cool the core.
The results of BGW Topical Report 10103 dated June 1975 and titled, "ECCS Analysis.of BGW's 177-FA Lowered-Loop NSSS" demonstrates that 2700 gpm is an adequate flow rate.
The 300 gpm flow band between the low and high flow setpoints is required in order for the automatic flow switch on the Decay Heat valves to function properly and prevent valve cycling.
V.
Retest of Decay Heat System at Lower Flow Setpoints:
Retesting of the new control range of 2800-3100 gpm will be performed once the replacement Decay Heat Valves DHV-110 and DHV-111 are installed.
Current delivery of these valves is November 5 and 10 respectively.
Approximately 2 weeks will be required for installation and testing of these valves.
However, during this time the instrumentation associated with the automatic flow switches will be reset to the revised values.
I
.