ML20085A463
| ML20085A463 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/01/1978 |
| From: | Kerrasch B BABCOCK & WILCOX CO. |
| To: | Womack E BABCOCK & WILCOX CO. |
| References | |
| TASK-06, TASK-07, TASK-6, TASK-7, TASK-GB 781901, GPU-0390, GPU-390, NUDOCS 8307060507 | |
| Download: ML20085A463 (4) | |
Text
_
i i e c
3 e
-..~...
_a
--=
- -~
~"
q m
'T:lE HACCCCX t. Ull.COX COMPA!JY POECR GE::cP.ATicil GROUP
.1 To.
l g
j E. A. Wonnck. P.:u.ager, Flaat Desjen From
.j
- 3. A. Karrasch,.".anager. Ficnt Integration Cost.
sos.62.s File Eo.
or Ref.
Sv6j.
Date August Activities Report s
?
l rw e -........
Septssaber 1. 1978 0
I.
ACCO'*Pt.Isu"ENTS.
A.
A progres has been established to perform a acchanical interface j
review of major RCS Ccaponents on claa l'alhein-Kacr11ch A plant.
3 g
The purpose of this study is to provide hi-b nasurance that the I
dccigned and manufactured.couponents will properly. fit during the
, l field instet11stion. and function during power operation.
The ffrst e
i phase of the progra a vill address only Reactor Vecnol/CSA/ Core interfaces as described in the progran plan recently suhaitted to IFI.
p
.j B.
A meet'ing vss held to review the status of the Fission Can Release Frogram and deteralac a strategy on the une of TACO in the ECCS Evaluation Model.
The current. approach is to obtain clarification free NRC on ECCS medel change crituria (TAFT to TACO input) and the
/
need for consistent fuel pin models in both the Tuel Pin Performance Codes and ECCS Analysis Codes.
This information will be used to l
establish a strategy on the Fission cas Rolesco Program by mid-September.
t
' i i
l C.
The Systera Requirement Specification for Service Conditions on B&W Safety Rolsted Equipment was issue 4 this month to support the Reg Cuide 1.59 product upgrade program. This dccicent includes design range and accietent environcents, required equipment operability times, and radiation levcis for all safety relt.ted equip.ient in the C4I and Fluid Syste=s area.
The docueent has been rojiaseil for use by C&I r.nd Fluid System Engincorir; in obtaining vendor qucten for meeting the new rcqui,rc.ments inaposed by the Reg Cuide.
D.
l A Cencric Fonition Statuicent on P.c.. Culde 1.97, "Instrumcatation' to Assess l'1aat Conditions. During and rollowing on Accident.".was forva.eded i
to Licensing for approval.
bc.ing devalc.p.d jointly eith CLI En.a.Jneerlu.e.A contin::cncy on Reg Culele 1.97 I
to assure that i:splertenta ttun of this R<g Catide is curri'ctly factored into the Stsndard Costs.
n-it-~ nLpa.
w,....
""q (Vu 7 Fo COUNSEL ONLY a
,,,,o M*
7-3 o1/ J.R. Danyo 8307060507 780901
._ }
PDR ADOCK 05000289 R
HOL
~ "
F15}O86]
[
m9 826)
}
w
y t
,4 p
1
.a l
~
t m
9 Karraw h to.'..a1ck Pago Two u
Aa.;ust Activitica Puport Septv.aber 1, 1978 j
a E.
A pros.ectatfun un Safety Crr.de Cold Shutdnwn (Re: Guide 1.139 ) was l-j
}
. rude to the.Wc and feefocek un our proposed resolution was obtained.
t F
}
As a result of c:w r.cetin::. a proposal has been duvoloped nnd provided to Prnject :tanagement to outline recow.cnded e pai;= cat changcu to cos. ply I
with the ::RC requirceent. The proposal i= a co..'ainacIon feasibility fi y
[
study ar.d equipe nc sizing analysis to:
0 il
~
1.
Define the capability of the 2:5S to cooldown under natural
[
- i circulation within the N;
- C rcquired 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A change to the -
l ll Atnaapheric Dump Valve design is recos:aunded to eneply with fiRC
(-
r
~
directive.
2.
Evaluate the capability of the baron addition syistem to achieve r
t suberiticality ac' cold chutdown conJItions without major system modificatLone.
t r
f l
3.
Define the depressurisation capability of the RCS usin~. current h
equips. ants or if currunt equipment is not satisfactory, show what
{
l is required for depressurization.
~
h' i
The proposal will provide information to allow the utilities to address f
the requirements of the NRC.. Follow-on studies will be required at i
a later date to set critoria and overall system requiroments for
[
l meeting this ' Reg Guide.
(;
-~
)
II. DTSPOSITION OF PREV 10tf5 PR03tCt5 t,
i-8 A.
The Hark C Gamme HeatinC Risk Program funding was approved and the P
}t program is underway. The delay in approval of this funding may result in soso slippage of the original cosciitsoats which were based 1
J on a start dare of June 1, 1978 leading to a December 31, 1978 2
'l completion. Tech Staff has completed their investigation fato the c
j need for a correction factor for the axial power shapes generated by L
FIEZ. The results indicate that a factor is r.at needed since the DOT code inherently accounds for this effect. This may help ease tha slipped connitment, scoewhat. The next action is to revise the Key Need Date for completion of the program and continue the. Safety r-i Analysis Calculations.
c.
A mana:ement review of the ECCS Sas21 Break Probics on 205 plants b
B.
van hold this conth to review the diruction of the program and k
determine specific action items to evaluate the use of a 40' OTSG icyc1 for Al".1 Initiation. After cuch discussion, the following action itens were established:
I l'
1.
Amness the lopact of a 40' icvel an all Chapter 15 sofory analysis events and Id.ntify potential problems with currently submitted f
analynes. D.W.I.anelle - 9/15/78.
L V
2.
Assess tha impact of instumentation ceror on normal operating lintts in the IC:: and the SI:CT hased upon unin;; full range caps on the steam generator. R.A.Dsvlu-9/15/78.
t 3.
Prepare and L.eue a revir.len to curves in the 10')2 Tg*cc ro-refIcct i
the up.* **f a 40' st i.'re n.*o. r.arur 1. vel upcn In tti.it lan of c=crcency fecdwa t.'r.
!!.B.D vis- *.8/15/73.
L
,s l
r e
s..
~-
F 15 I7087J 324[0521)
~
' h i.'
1 1
t e.
o
~ "
^
Karrasch to *. mck Pa:,e Three August ActivIgles n,.purt Septu:aber 1,1978 y
i 3
4.
Frcrare un evalesation of the stress es in the str:aa ccnair.ator i
be.4ed u:un utilising a ad' sceau ;ccuratur level.
L.H.Bohn-10/15/78.
' i In addition ta the shove coa;:sico$ta, the C&I Inte. ration Croup is t
evaluatin; sov.aral al:cenativa designs for' ohtaining a 40' level usius the current r.SFl.S aaJ.CCI syacens. This evaluation will be cc.rpleted 10/01/73 to hulp in cl.,decJstois-makir.g process on futura direction for the resolution of this pre!alea.
3
'C.
As reported last Ponth, the TVA Spectrum Analysis of Steam Lina...
1 Broska indicated that the envelopo for qus11fication of IE equipment j
was exceeded.
This prob 1c:a can be resolved by changir.g the reactor building apray astpoint from 25 psig to 10 psig and using the resultant e
]l steam line break analysis to deternine the buildin; conditions for equipment qualification. Two CI/A's have been initiated by Plant-l Integration to resolve this problems i t 1.
Clwnce the TVA Euildtug Spray setpoint froo 25 psig to 10 psig.
,- l 2
Invoke the TVA Euilding temperature versus time for the small I
steam lino break on affected safety rolsted equipment.
- l The CI/A has recuived expedited sp;roval for the CLI cask to allow d
us to obtain cost qucrees from Bailey Meter Ccogany leading to customer cost recovery.
e III. NEtt PROP.t.E"S kb 1
A.
A dircrcpancy has been identified between the incore monitoring system 4l l l
requirements sud the installed equip::sent capability on our operating 177FA plants.
The Fuel En.ineering accuracy requirements for the Incore l'.onitoring System to determine Tech Spec limits and fuel H
managener.t information are not confirmed by operating data Several meetings have been held to evaluate altcenate solutions to the problem, and we are currently pirtsuing a combination of reducing the accuracy requirements and codifying the octcctor design to achieve consistency.
Next action will be to summarize the actica and obtain Section Manager review.
?
1 lgjhf&
1 W"
9 i
BAK:dh
/
Attach s
.t T
.(M f
F15 7 0 8 8J
, -9NE 324 i
~
y U.-.
=
t
- c.
s em m-
I 1
o V
~ ~
..[_
4._ 'A L---
[
4'
- \\
~.
_CO""*
- a... a *:TM a S."f"*0!r;"
.* UC*ST I
4
}
I.
A.
CD*0*IT 'C:7 CO'*:*t.ETC Cozpletion 4
pate
~
Prepare and Issue CRDL Systen Requirement
( !
Spec Drawing.
8/18/78 1
Prepare and lasue Reviston to Standard Plant 7/31/78 AIRS for RCS3A of Jet Ir.pingement i
f 3.
CE20ffT**!!*:TS MISSED
?
None e
1 C..
REVISED C e TIT T M,
f Revise Standard System Requirements for Decay neat Removal System 12/31/78 l
D.
Nest CEDD*IT M 1
i
}
Define Impact of Plaintaining 40' OTSC I.cvel*
s 11/13//s for Initiation of Auxiliary recdwar,ar on 203rA i i Plants..
j g
Suppo' rt Product Standardization Program and P,elease A
12/31/78 P1 Docicentation per Product Coi figuration Schedule f
. r for Product Stasdardization Prograa G
.{
Prepare and Issue Preliminary Asymetric Cavity I.cading Analysis for 177FA Plant Loading Syndrome 11/01/78
'h Prepare Strategy and Reco=nendation for Addressin8 9/08/78 NRC Concern on OTSC Overfill Preparo Recommendation for Selected Items of Study 11/13/78 in 075C Secondary System Review P
Prepare and Issue Envircremental Service Conditions 9/01/78 E
Specifications for all Cf.I and Fluid Systems Equipacnt in D&V Scope of Supply Ucvelop Lint of P' lant Desten Docu :ent: to be Incitaded 12/31/78 in St..ndard Free:c Program for Ca, sis for,the Plant Design Obtaln-95'. of Allocated Stafflag by 1:1d-197S.and
}laint.alo for K.:AlcN'er o* Year 12/31/78 E.
D r.l.**TisW ;
Notti!
?
T-
-~ ~ ~
.~.-....a c
r e-F15 3 0 8 9j-324 ' O 5 2 9)
... _ =e5...-
^
._ g.. =
.4 l0 =
~
'