ML20040A697
| ML20040A697 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 08/19/1977 |
| From: | Mazetis G Office of Nuclear Reactor Regulation |
| To: | Cox T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201210430 | |
| Download: ML20040A697 (2) | |
Text
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'4 NUCLEAR REGULATORY COMMISSION 3
bY. j WASHINGTON, D. C. 2o556 r ~'
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Docket No. 50-561 MEMORANDUM FOR: L,Cox, Project Manager, LWR Branch No. 5, DPM j
THRU:
T. M. Novak, Chief, Reactor Systems Branch, DSS FROM:
G. R. Mazetis, Section Leader, RSB, DSS
SUBJECT:
RSB STATUS OF B-SAR-205 ITEMS We note that the Blue Book indicates an 8/25/77 due date for SER input
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on B-SAR-205.
The review status of the B-SAR-205 open items in.the Reactor Systems area is as follows:
(1) RPI Line Break - staff has reviewed all information submitted by B&W; however, we are still discussing this matter with S&W'with regard to required operator actions after the LOCA.
(2) Boron Dilution Event - staff has reviewed all information submitted by B&W; however, we are still discussing this matter with B&W regarding the dilution events during plant conditions other than refueling or 7
power operation, i.e., hot standby, startup, shutdown, etc.
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(3) Overpressure Protection - staff is reviewing the information submitted by B&W and is still awaiting additional analysis of certain over-pressure events (start of R.C. pump, CFT isolation valve opening).
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(4)' Provisions for Shutdown - staff has reviewed information submitted by B&W.
Information satisfies all of staff concerns.
8 (5) Decay Heat Removal Isolation - staff has not yet reviewed. B&W has not determined which design they will propose.
l (6) ECCS Analysis - awaiting information from B&W.
(7) Anticipated Transients - staff has reviewed all information submitted by B&W; however, we are still discussing this issue with B&W.
(8) Turbine Trip - staff has reviewed all information submitted by B&W.
Information satisfies all of staff concerns, t
Contact:
Scott Newberry, NRR 49-27911 8201210430 810403 PDR FOIA MADDEN 80-515 PDR
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,T. Cox AUG 19 E77
. It is obvious that acceptable M W responses of all these items vill not be completed in time for staff review and documentation of conclusions prior to 8/25/77.
Gerald R. Ma et
, Section 1.eader Reactor Systems Branch Division of Systems Safety cc:
D. Ross O. Parr T. Nov Q cwberr
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