ML20024B354
| ML20024B354 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/30/1977 |
| From: | Rosalyn Jones BABCOCK & WILCOX CO. |
| To: | Dunn B BABCOCK & WILCOX CO. |
| References | |
| TASK-*, TASK-GB GPU-2463, NUDOCS 8307080528 | |
| Download: ML20024B354 (5) | |
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u THE BABC0CK & WILC0X COMPANY POWER GENERATI0il GROUP
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B.'4. Dunn, Manager, ECCS Analysis
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From t1 J R.C. Jones, ECCS Analysis (2066)
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sos 663 5 Cust.
j File No.
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Date June Activities Report June 30, 1977 i
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Supervisory Engineer - R.C. Joncs Engir.eers - G.E. Anderson W.L. Bloomfield C.W. Jones M.J. Means N.H. Shah I.
Accomplishments 1.1 Scheduled Activities
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A.
The pre-test prediction of LOFT test L1-4, Standard Problem 7 has been completed.
A first prediction was submitted to flRC on 6/21/77, but an improved evaluation was submitted on 6/24/77, flRC has agreed to acceot the latter result as the final pre-test prediction from B&W.
Work remaining on this topic includes tabulation of the results for llRC, report writing, and documentation cleanup.
B.
Work of Davis Besse 2&3 is progressing.
Since the last progress report, an error has been discovered in the reflood input for the DE break cases.
This has been corrected and the mini-spectrum analysis results are summarized below:
Break Peak Claddina Temo.
2 8.55 ft DE, C = 1.0 2122 F D
2 6.55 ft DE, CD = 0.8 2100 F 2
8.55 ft Spli t', C = 1.0 2076 F D
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A method for performing whole core metal-water calculations for DB-2 & 3 has been developed.
Duscussions will be held with NRC in order to determine whether the approach is acceptable.
C.
Some work was performed on the EPRI pump program this month.
Specifically, this relates to EPRI conments on the pump model effects report. These comments were reviewed and incorporated into the report when necessary.
The report was sent to the Technical Reports iroup tur typing.
D.
Work was initiated to perform a PASNY specific large break analysis.
This item was discussed in detail as Problem B of last month's progress report.
Both the CRAFT and REFLOOD runs have been completed and work is progressing on the THETA analysis.
A design memo on the revised PASNY "as-designed" minimum containment backpressure analysis was issued incorporating Stone & Webster's comments.
The analysis should be completed before the July l'5th commit date.
E.
An analysis has been performed for the U-baffle problem on the Oconee class plants (see Problem A of last month's progress report).
The new analysis resulted in a PCT decrease of 85 F relative to BAN-10103.
Therefore, the LOCA limits in BAW-10103 remain valid.
A report will be iss'ued to NRC in early July.
1.2 Unscheduled Activities A.
Mass and energy release rates for an HPI line break were transmitted to Bechtel for Davis-Besse 2 & 3.
B.. A memo was issued to P.roject Management assessing the impact of the Rev. 2 SAR guide on the WPPSS contract.
C.
Support work to Safety Analysis was performed.
This work consisted of assisting in development of a CRAFT model to answer NRC questions concerning tube ruptures during a steamline break.
D.
Attended meeting concerning ECCS's oreliminary coolable geometry criteria.
At present, Fuels Engineering cannot meet the criteria.
Work will be initiated in July to relax this criteria.
E.
A meeting was attended concerning auxiliary feedwater level control for the 205 FA plants.
At present, a 6-foot level control is designed for the system and this may not be sufficient to mitigate small breaks.
In BAW-10074, 205 FA small leak analysis, a 40-foot level control was used.
In light of present SG status (shipped,
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g stress-relieved, etc.) it was deci8cd that ECCS will show that a 6-foot level is acceptable.
No plans are now formulated for
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adding additional level sensing taps on the SG.
This work will be scheduled to be performed starting November 1977 and will be completed by 3/1/78.
F.
A meeting was held with NRC on 6/26/77 discussing schedule and analytical relief on the LOCA " hits" recently imposed by NRC.
B&W's position on additional analysis on BAW-10102 was rejected by NRC and 3 large breaks and 1 small break will need to be analyzed.
For Davis Besse 1, it now aopears that only one additional large break will be necessary.
The present ECCS schedule will be revised next week to incorporate the above analyses.
II.
Problems No new problems occurred this month.
III.
Resolution of Previous Problems A.
An analysis for the Oconee-class plants U-baffle problem, discussed in Item A in last month's progress report, has been performed. The d
results are discussed in I.l.l.E.
B.
The PASNY specific analysis, Item B of last month's progress report is being performed and has been elevated to a scheduled activity.
This topic is discussed in I.l.l.D.
C.
The additional ECCS analysis work requested in the Davis Besse 10.L.,
Item C of last month's orogress report, has been defined by NRC and will be treated as a scheduled item (see discussion Item I.l.2.F).
IV.
R&D Progress Report See attached R&D quarterly progress report.
V.
Administrative Mary Jane Means joined the Unit on June 13, 1977.
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1977 R&D QUARTERLY PROGRESS REPORT SECOND QUARTER PROGRAM - 845-7703 PROJECT 01 - ECCS DEVELOPMENT PROJECT LEADER - R.C. JONES 1.
Project Status 1.1 Objective The objective of this project is to provide B&W with a LOCA analysis technology and expertise necessary to respond to changing NRC acceptance criteria, utility and industry standards and competitor product development.
i 1.2 Objectives for Second Quarter A.
Release of 1976 R&D Program Letter Report B.
Receive NRC aoproval-of steam cooling model.
C.
Start work en the effect of loco seals in the pump suction during reflooding.
D.
Review BXC correlation for impact E.
Industry Cognizance 1.3 Accomolishments This Guarter A.
The 1976 R&D Program Letter Report was issued in April.
B.
Preliminary work on the impact of the BXC correlation was initiated.
Using the revised THETA code, cladding temperatures were found to increase s10F for'the 205 FA plants. A CRAFT analysis will be performed in the future to determine whether the SXC correlation l
impacts the blowdown transient.
C.
The 1978 R&D Program was developed and presented to the R&D Unit i
on Aoril 12.
The proposed Program 01 was approved for planning purposes.
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A memo was written to Risk fianagem$nt to transfer funds spent in the R&D accounts for the "no-return-to-nucleate boiling" fix to an NSC account.
The use of funds sections has been modified to include this transfer.
E.
A memo has been written on the new oroposed ANS standard on decay heat.
While the new standard is still preliminary in nature, the memo shows that for the first 100s the present ANS standard is approximately 200% higher than the cronosed standard.
This work is documented in the memo, C.W. Jones to R.C. Jones, "New Decay Heat Curve", May 26, 1977, File No. 2Al2.2.
F.
Conversations were held with W. Hodges,'NRC, about the status of the steam cooling model review.
At oresent, a review by HRC is being performed but there is some concern on the method used to demonstrate consideration of blockage effects.
More conversations will be held to resolve NRC's comments.
1.4 Objectives for Third Quarter A.
Receive NRC approval of the steam cooling model.
B.
Industry Cognizance C.
Start work on the effect of loop seals in the cumn suction during reflooding.
2.
Use of Funds 2.1 1977 Budoet 1660 manhours and 14 computer hours
- 2. 2 Excenditures This Guarter
-14 manhours and -3.6 comcuter hours (These numbers are negative due to transfer of hours noted in 1.30) 2.3 Excenditures To Date 198 manhours and t024 computer hours.
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