ML20024B311
| ML20024B311 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/03/1979 |
| From: | Karrasch B BABCOCK & WILCOX CO. |
| To: | |
| References | |
| TASK-06, TASK-6, TASK-GB GPU-2436, NUDOCS 8307080354 | |
| Download: ML20024B311 (4) | |
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C2 Connell DE 1.einhart THE BABCCCK & WILCOX CCMF NY RS Davis AP Nc3 ride POWER GENERATION GROUP tr Dowling 1 Schroeder SM Duerson JS Shively 7,
l 3:1 Dunn JR Smotrel E. A. Womack. Manager. Plant Design I!J Fortune CJ Swanson JR Hamilton R3 Tornow Froe JJ Happell JS Td, fria.s
- 8. A. Karrasch. Manager. Plant Integration m.w,
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January 3.1979 t.
December. 1978 Progress Report F
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ACCOMPt.ISHMENTS The and of the year commitments on the SCP Criteria Project ami A.
The the Component Loading Specifications have both been met.
BOP Project milestone events were all net, with one exception, cr and several new documents were added to the list and completed The Component Loading Specification
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decing the course of the year.
comitment of 90% on-time completion was exceeded and close to 100%.
Detailed status reports on both of these Plant Design projects will
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be issued the first week in January.
3.
The Plant Design commitment to Phase I of the Standardization t.'
Program was completed as scheduled. All test sections and drawings for the Reactor Coolant System Requirements were issued as scheduled including resolution of cocz:ents by the af f ected hardware unite.
In addition, the standard AIRS document has also been issued r
following negotiation of the data with all input suppliers and the SMA Unit. All Component Loading Specifications and Functional
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Specifications have been issued and comments resolved from
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We now have a complete Component Engineering and Mt. Vernon.
package of Plant Design requirements for all FC5 components 7
included in the Phase I Treeze Progrse. In addition, the Phase II and III schedules for release of Plant Design Requirements Specifications remain on schedule. Ve are now in the process, on these systeme. of negotiating and resolving ccaments on the System
,l Requirements Specifications leading up to f reezing of this documen-t tation in early 1979. The Phase IV Analysis Freeze effort is b
somewhat behind schedule due to higher priority work at the end k
The overall program plan and list of the calculations of the year.
to be included in the Phase IV Treeze has been issued and thi.s
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prograa vill now get underway. Ve are targeting to obtain a definition of which cale packages can be frozen by 3/31/79.
r A number of meetings between the !!uclear Industry and the NRC C.
have culminated in a modified NRC ATWS position. The major points of the new NRC position aret CONFIDENTIAL COUNSEL gly F
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Larrasch to Wo=ack Page Two Jacuary 3,1979 December. 1978 Progress Reporc r.
Operating plants and plants in an advanced stage of construction I
1.
(e.g., WPfSS) vill only be required to add diverse scram instrumentation and demonstrate critical valve operability.
F Plants not neari=g coccercial operation vill be required to F
2.
install additional safety valves.
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The details of this position, givea in a supplement are expected to be received before the January 4 AC3.S !!earieg.
However, based on the inf ormation received to date, a significanc i
A detailed amount of design work will be esquired during 1979.
L status report on ATWS resolution will be published the first week of January.
A review of the PICt and CM design requirements was perfor=ed to D.
evaluate potential changes to f acilitate the hardware /sof tware t
In December, CI/A's were processed on the RPS-Il Ci I
design.
requirements to l
Relax the time response requirement to avoid a sof tware 1.
r redesign.
Define the two Ct flux inputs as being identical in order 2.
to shorten the qualification testing time.
k Define the flux value used to bypass the of fset calculaeion as 3.
to avoid a aero divide situation if the two
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inputs are not identical.
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In support of the Pict, work has been done to more fully define
- f limits on the 4 term in the DNBR trip that are more compatible with hardware capability. A CI/A vill be processed by January 5,1979 e
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to implement the added constraint.
The final meeting of the Mark C Design Review Board was held this f
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month to review the generic applicability of the Mark C core
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The DR3 components previously approved f or release on I'/A.
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agreed to approve the design for generic application upon satis-The final factory completion of the outstanding action items.
i DR3 report. is currently scheduled for submittal to the Departmenc Manager for signature by March 1.1979.
An Engineering Department commitment to the helear Parts Center 7
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was established to prepara a master list of safety related components L
and piece parts and to define functional components for all equipment
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The workscope was divided into three L,
on B&W backlog contracts.
separate phases, and nanhour estimates were received foe each Pucos and Drives, Fluid Systems phase from Mechanical Equipment.We now have a firm commit =ent in place to assisc and CSI Systems.
the helear Parts Center in decernining functional component classification across all the bac.kb5 contracts.
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q Page Three Karrasch to Womack January 3, 1979 Dece=ber,1975 Frogress Report II.
DISPOSTTTON OF P'.E'MOUS PROSLEMS A dual serpoint for control of AF'J and design improve:nents.
A.
for the to include cavitating venturis and automatic piggyback HPI system have been identified as alternatives to resolve the 205 Small 3reak Problers. Design, equipsent f abrication, testing and installation costs across the 205 Product line are now being developed for both design alternatives to achieve a decision g j., d *'
early in 1979 for the overall program resolution.
A cost impace picture is presently anticipated to be complace by J/01/79.
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Additional analysis for a SL5 with a forty foot AW level and a small LOCA with the i= proved RP1 systesa performance are also to be completed and documented leading to a final decision on resolution of this prnblem by 3/31/79.
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Documentation of both analytical and test data has been prepared 5.
and submitted to TEco to support the interim and lor.g-tern AW control system design. Plant operation was evaluated and shown to be acceptabla during r.or=al reactor trip events and other antici-pated transients such as the loss of offsite power and the loss of main feedwater with OTSC levels controlled at a 35* level.
In addition, the consequences resulting from the operator's failure to control steam generator levels at 35 inches, in the interim, has also been evaluated and shown to be acceptable.
Additional questions have also been received f rora TEco, primactif in the ses11 break area. Ef forts will be initiated to prepara to responses prior to February 15 to support a TEco cocaitment supply a problem summary report to the NRC.
III. NEW PROst.D*S r
Small LOCA for the 177FA plants have always been evaluated assuming A.
a loss of offsite power. This assumption resulta.in an RC pump coastdown, a loss of main feedvater, and reliance on auxiliary feedwa ter. The validity of the assu=ption to produce the most limiting LCCA consequences (small break) is now being evaluated.
Small 14CA analysis are now planned on the 205FA Flant LOCA model assuming the RC pumps are operative, main f eedwater is available, and the ICS functions to maintzia OTSC levels at the i'
two-foot elevation. If these analysis do not produce acceptable a,nd, less conservative results than those assuming a loss of of f site power, a potential will exist f or extensive reanalysis efforts in the small break area. Equipment design changes on the backlog 177FA plants may also be required to assure that AW is added to the steam generators during post LCCA conditions. This problem is currently being evaluated by ECC3 Analysis.
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Page Pour Karrasch to '.fo ack January 3,1979 I
December,1978 Progress Report IV.
AVAf tA31!.ITf PROCRAM A.
A revised Availability Improvement Program for High Chlorides.
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in the RCS received R&3 :*.anagement approval acd =anhou allocat. ion.
The ouciine for this revised program is as follows:
l.
Fonitor the chloride problem noting any new creeds and develop understanding for those trends.
2.
Review data and information available within :s?CD from demineral-i F
iser resin manufacturers. pertinent utilities and 301 resident engineers to gain better probles definition and develop rossible' ef fective problem solutions, including the following specific considerations Possible relationships becween demineralizar resin loading a.
age and tendency for chloride spiking occurrences.
b.
Chemical interactions which promote chloride spiking.
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Problem status and conclusions as viewed by demineralizar c.
resin manufacturers.
d.
Utility corrective actions on this problem and effectivenese
,y of same.
3.
Develop a final report by April 1,1979 based on above activities.
addressing the following I
a.
Problem definition.
b.
Recomendations' to alleviate the problem.
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Dafinitive criteria on resin bed changeout.
d.
Recommended further activity on the probles. if any.
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IatebMonth Previ b Month Cu LCD I.C) for (October)_
(September) g Coal 1977 7.2 ttish Chlorides 0
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