ML20024B309
| ML20024B309 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 02/28/1979 |
| From: | Karrasch B BABCOCK & WILCOX CO. |
| To: | |
| References | |
| TASK-06, TASK-6, TASK-GB GPU-2435, NUDOCS 8307080351 | |
| Download: ML20024B309 (4) | |
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<F JA Castanes DE I.einhart THE SABCCCX & Wit.CCX CCMPANY CW Connell AF McBride R3 Davis JS Shively j
POWER GENERATION GROUP EF Dowling JR Smotrel s
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SH Duerson EW Swanson 7
BM Dunn RN Tornow
'r E. A. Vomack. Manager. Plant Design HJ Fortune JS Tulenko C
From JJ Happell RA Wallin F.
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- 3. A. Karrasch. Manager Plant In tegra tion n
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File No.
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Date February Monthly Activities Report February 23, 1979 l
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SICITTtCANT ACCOMPt.ISte'E*rrs b
A.
The Mark C Fuel Assembly Loading Cricical Product Problem is successfully resolved. The standard fuel assembly loading analysis has been completed and now provides an acceptable y
enveloping analysis for au backlog 105FA plants. In addition u
to the cost benefits to backlog and future plants improved
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modelling and analysis techniques were developed by Fuel struc-k.-
tural Analysis.
8.
An action plan to resolve the concern over internal pressure in the affected loop RC pu:rp during LOCA has been established between
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Plant Design and Equipment Engineering. The following highlights the key elements of the action plans g
1.
A PSC win be written against the Consumers' RC pumps and all backlog contracts win be identified as affected.
- 2.
CI/A's win be initiatedron the 1235 or 14/.2 Specs, as
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appropriate, for backlog contracts 12, 13. 15. 16, 17, 18 23, 24, 31, and 32. These CI/A's win invoke a loading b
combination table which includes operating pressure in the i-affected RC pump during LOCA. Preliminary investigation in-i dicatas that NSS's 3-11 and 14 win not be affected; and the j
BJ pumpe on TIco, Ohio, Deco and the Standard have this change included.
t-3.
Pumps and Drives will revise the Reactor Coolant Pump E-Specs on af fected backlog contracts e.xcept those with the Bingham
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RC pumps. For the Singham pump, an in-house evaluation vin L
be performed using the available finite element RC pump model 4
to show acceptable stress levels.
t C.
The Parallel Hybrid Module Design Raving Board was conducted on g
February 5 and resolution of action itess has been expedited to support a March connaitment for resolution. Upon completion of these action items, we hope to propose the PHM to T7A as a technically superior replacement for the C.31c Module. The Engineering Department I.
position is that the Pici is a technically superior system, has considerably more flexibility for future change, and should be sold as a product upgrade to all backlog RPS-II contracts, g
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Xarrasch ta Jo=ack Page 2 february Monthly Activities Report February 23. 1979 s
D.
The Tuel Handling Equipment System Requirements Specification for the Standard has been completed and all co::ments from Fuel and
. j Equipment Engineering have been resolved. Several r.ajor changes j
have been made to this specification which now docu=ents Tuel
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' g Engineering Control Component load deflection criteria, includes updated Control Component interface drawings, and containment environmental conditions for the transfer tube seal. The require-ments spec has been frozen with the initiation of a CI/A meeting a key commitment to the Standardization Program.
E.
The final program plan for a generic 205FA Plant ECCS !.arge 3reak Analysis to accommodate the fission gas release problem was issued.
This work is required tos 1.
Justify acceptable LOCA limits for three cycles of operation for Mark C fuel.
1 2.
Properly reflect the most recent Mark C fuel assembly design.
I 3.
Provide consistency between fuel performance analysis and ECCS analysis through the utilization of TACO fuel gap heat transfer model.
Based on prelisir.ary scoping analysis, acceptable three cycle LOCA limits will result. Included in the program are the Mark C resinter work, verificition of !". ark C coolable geometry, and a partial pump analysis for ECCS. The program is scheduled for completion in 31d-1980.
T.
The generic FSAR analyses program preposed last month has now been modified to specifica1.ly focus upon ruel Engineerir.g and Plant
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Design calculations foc bota the kTPSS FSAR and T7A power level upgrade from 3600 to 3760 h t.
A strategy for completing this analysis e
in TT80 has been proposed te obtain a k7PSS license at 3800 Mut, a TVA operating. license at 3760 Mut, and frozen SAR Calculational Packages for the Phase IV Analysis Frene.
t!* are now in the prosess of preparing a detailed workacope, schedules and cost estimates and will present this plan to Project Management early in March. The additional funding required above the b7PSS SAR is $4CCK; this tesults in a $75CK decrease in the original estimate to provide the TVA upgrade to 3760 Mut.
C.
TVA has infor:ied us that they would like to increase the heatup and cooldown rates for the Se11efonte Units to approximately 100*F per hour to enhance plant availability. As a result. TVA is expected to authorize a study to evaluate the increased rates. If it is deemed feasible, we believe IVA will request us to proceed into an evaluation of utilizing nuclear heacup to increase the heatup rate beyond that which is now possible with use of the reactor coolant pumps alone. This analysis to improve the availability at TVA could be a significant contract price revision if an increase in heatup and cooldown rates is feasible.
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Karrasch to Womack Page 3 Tebruary Monthly Activities Report February 28, 1979 P
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A meeting was held with Region 3 N2C Inspectors. Toledo Edison, and other operating plant customers to discuss the concern with pressur-izer draining following auxiliary feedvater initiation. NPCD showed that the current NSS-14 operating procedures were acceptable and that no sig-I.
nificant safety concern existed. The NRC investigators agreed that V
CDC 13 does not apply to pressurizer level and that loss of a level indication is not an unsafe condition. Ve also showed that the other e
operating 177 plants do not have the sa=a problem and the NRC inspectors, therefore, found no items of non-co=pliance. In addition, all information developed has been submitted to TEco following full certification and Q/A; this concludes the pressurizer level problem on the TICo units.
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A recommendation has been accepted by NPCD Management tr-propose i
that SW manage and execute an upgrade of the Florida Power C2-III
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Salance of Plant to 2772 Mvt.
Follovup investigation and discussion O
with Florida Pcuer personnel indicates they are receptive to a
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proposal for such an upgrade. Following a successful trip to r
Florida by Messrs. Bohart and Kelly, we have made a commitment to D
prepara a proposal to be submitted to Florida on 3/31/79. This l."
effort has a significant potential for master services, in addition to providing a unique opportunity for SW to enter the business of 307 power upgrades on operating plants.
I J.
The Korea pre-avard engineering activity has been completed and a report issued to document the results. The purpose of this pre-award engineering work was to establish and document the analytical workscope inputs and assumptions for the Korea plant in order that.
a PSAR could be submitted to Korea 7 months af ter contract award.
r II. DISPOSITION OF PREVIOtJS P t05t. Cts
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A.
A decision has been nade to pursue a change to the High Pressure Injection system to incorporate cavitating venturia to increase the HPI flow for ECCS small breaks. This design change was recommended in favor of increasing the OTSC level. The Engineering Department L
position is that the HPI fix is far superior and has such less risk in obtaining acceptable resolution to the problem. The cost I
differential is $25CK less for the cavitating venturi design.
Following successful completion of two ECCS confirmatory calculations, i
ve plan to initiate CI/A's to implement the HPI redesign for all IZOT3G contracts.
S.
The three Midland PSC's concerning hot safe shutdevu have been resolved and removed from the category of significant safety concerns.
As a follow-on, Plant Integration has a cocmitment to issue a generic hot safe shutdown position which will be applicable to all the backlog contracts. This position will be used to establish action to assure that all contracts meet our SAR cossait=ents to maintain i
a hot safe shutdown.
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Page 4 Karrasch to Womack February 28, 1979
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Tebruary Hoothly Activities Report L
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The NRC formally transmitted their proposed requirements for early C.
nese proposed requirements, which supplement 6.
verification for ATVS.
the recommendations of NCRIC-M60, were substantially core detailed r
A work plan has been prepared to achieve minimum than expected.
complaince with the NIC requirements. This plan was presented to our utility customers on Febru.ary 28, prior to 34W presentation The 34W owners g
to the NRC on P. arch 1 and to the ACKS on F. arch 2.
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are taking a firs position that NPC3 should do nothing in respea.se to the NRC request to address the issue.
III. NI"4 PPJD3t.Ca.S P
We have been informed that Selfab is fabricating a substantial number I
A.
of incare detectors which do cot meet the thermal current requirements This high thermal current specified in the Equipment Specification.
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is thougbc to be caused by sacerial dif f erences in the A1 O The increase of thermal currect impacts detector accuracy significantly.
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23 A sound basis for judging the acceptability of these detectors, how-ever, does not currentry exiset the required detector accuracy is under investigation in the 1215 Uncertat.ncy Program, scheduled for completion this Fall. We are pursuing resolution on this issue with 2
Equipment Engineering and fuel Engiseering.
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