ML20040A290
| ML20040A290 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 07/22/1977 |
| From: | Cox T Office of Nuclear Reactor Regulation |
| To: | Parr O Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200713 | |
| Download: ML20040A290 (5) | |
Text
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UNITED STATES y
.~'g NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20666 r
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Jul. 2 219U Docket No. STN 50-561 MEMORANDUM FOR:
- 0. D. Parr, Chief, Light Water Reactors Branch No. 3, DPM FROM:
T. Cox, Project Manager, Light Water Reactors Branch No. 3, DPM
SUBJECT:
ACRS SUBCOMMITTEE MEETING ON BSAR-205 TIME & DATE:
8:30 AM Wednesday, July 27, 1977 LOCATION:
Room 1046, 1717 H Street, N.W.
Washington, D.C.
PURPOSE:
To conduct the ACRS Subcommittee review of the application by Babcock & Wilcox for a Preliminary Design Approval for the BSAs-205 standard nuclear steam supply
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system. A tentative detailed agenda is attached.
x PARTICIPANTS:
NRC Staff
- 0. Parr, T. Cox G.Mazetis,T.Novak B&W J. Taylor, J. Happell, J. Hamilton, R. Brockman, G. Brazill, D. Roy, E. Swanson, E. Hooker, G. Kulynych ACRS J. Arnold, H. Isbin, I. Catton, T. Theofanus, W. Lipinski, E. Epler, S. Ditto, R. Muller Tom Cox, P oject Manager Light Water Reactors Branch No. 3 Division of Project Management
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Enclosure:
Tentative Detailed Schedule 8201200713 810403 PDR FOIA MADDEN 80-515 PDR l
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ENCLOSURE i
f TENTATIVE DETAILED SCHEDULE BSAR-205 SUBCOMMITTEE MEETING JULY 27,1977 lASHItGION, D.C.
Approximate i
Times
- T 1.0 Executive Session (30 min) 8:30 a.m.
t 2.0 Introductory Statement (Applicant) (30 niin) 9:00 a.m.
i 2.1 Applicant Organization 5
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2.2 Overview of BSAR-205 2.2.1 Ccaparison with early designs 2.2.2 Scope of BSAR design 2.2.3 Other goteral items of special g
interest fo'r ACBS review s
t 2.2.4 Staff consnents (10 min) i L
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- RECESS ( 5 mi n) ****************
i.0 Staff Status Report on its Review (60 min')
9:45 a.m.
3.1 Scope of Review and Early Reviews Relied Upon 3.2 Outstanding Issues 3.2.1 Likely to be resolved by ACRS neeting l
3.2.2,Must be resolved before PDA l
3.2.3 Must be decided before construction permit 3.3 Staff Review icrk Outstanding 3.4 Other Matters of Special Interest to ACBS Review 3.5 Responses of Applicant (15 min) a
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Tentative Detailed Schedule BSAR-205 I.
Approximate Times
- 11:00 a.m.
4.0 Technical Presentation by Applicant (2 hrs) i 4.1 Envelop of Siting Criteria 4.2 Reactor Design vs. Earlier B&W Design - Nuclear -
Mechanical - Thermal - hydraulic Design - Margin Against Core Uplift - Rod Boving, etc.
4.2.1 Changes since issuance of Report to bCRS 7/3/77 4.3 Engineered Safety Features 4.3.1 Redundancy and separation 4.3.2 Review of verification test progr?ma for BSAR-205 refer to table 1.2 in Report to
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ACRS 3,'
4.3.3 Other inprovements over earlier designs and 8
items of special significance for ACRS review i
4.4 Safety Design Interface Requirements for BOP-PDA, Plant Construction Permit
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- WNCH ( 1 h r. ) * * * * * * * * * * * * * * * *
- 1:00 p.m.
5.0 Instrument and Control (1hr.15 min) 2:00 p.m.
5.1 Redundancy and Separation 5.2 Reactor Trip Systems - Analogue and Digital Processes, etc.
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5.3 Auxiliary Reactor Shutchwn Panels
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5.4 Environmental Qualification 6.0 Steam Generators (1 hr) 3:15 p.m.
6.1 Design l
6.2 Tube Denting - tube leakage - secondary water treatment
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's Tentative Detailed Schedule BSAR-205
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6.3 Contribution of turbine trip without bypass -
tube denting
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l l 'i 6.4 mter hamner 6.5 Flexibility of BSAR design to future design inprovements i
I' 6.6 Other itemu in special significance t'o ACRS review
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- B REAK ( 5 mi n) **************
4:15' 7.0 Additional matters to be discussed by ACRS Questioning according to time available (Attached) 4:20 p.m.
8.0 Connittee Caucus (15 min)
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4:30p.p.
(._. ' 9. 0 Consnittee Concluding Remarks (15 min) 4:45 p.m.
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- Anjou1NMENr * * * * * * * * * * * * * * * *
- 5:00 p.m.
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SUPPflMDirARY INEURMATION Rt.I.ATIVEJ AGENDA d.0 A.
BSAR design features and administrative procedures to provide added radiation protection for in-plant personnel.
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Systems interaction analysis between BSAR systens and BOP nystems.
C.
Design features to provide added protection against industrial sabotage and flexibility of BSAR design to accept' future im-provements.
D.
Selected AGRS generic itetrs (list to be supplied) '
E.
How soon does the B&W tutbine trip occur during transients-which can be anticipated during plant life? Is there a delay or does it occur instantly? Can an instantaneous trip invite trouble? Adverse effects on trnin pumps?
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F.
In the event of steam generatorA ailure is off-site power f
considered available? Wat dose level results if off-site
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power is off and condenser fails to function?
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Explain B&W start-up procedures. Are nonsafety grade G.
systems used in bringing the plant up to powcr? For hod long? Wat would be. the Q.A. categories of systerrs used?
H.
Has a study been done to determine the primary fluid level profile for small,. breaks in the primary systm? Especially during the time necessary to remstablish rutural con-vection cooling by the seceniary side.
Wat sort of margins are on primary fluid levels?
I.
Are high-point vents place on the Steam Generators? Can it be deomstrated that it is possible to remove noncondensables during a small break?
O' cod IRelief Valves si3cd? How much J.
Ilow are Primary and heat can tyr rejected by these values? In the relief system on the ptimary arvi secondary sides capable of reducing the pri-mary system pressure from a high pressure condition to a lcra pressure condition?
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