ML20040A700
| ML20040A700 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 09/20/1977 |
| From: | Newberry S Office of Nuclear Reactor Regulation |
| To: | Ross D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201210434 | |
| Download: ML20040A700 (1) | |
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'AOUTING AND TRANSMITTAL SLIP
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A affached inen<a Amu 7.1 14ssafa REMARKS rey uesfs as es/imfe. of &e 8-SM-2or SS2 in/"I schea' ale. An 9 q
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Do NOT use this form as a RECCRD of apprevals, concur:ences, disapp vals, clearsaces, and sirastar actions.
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UNITED STATES flUCLEAR REGULATORY COMMISSION
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AUG 19 B77 Docket No. 50-561 MEMORANDUM FOR:
T. Cox, Project Manager, LWR Branch No. 3, DPM THRU:
T. M. Novak, Chief, Reactor Systcms 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 on B-SAR-205.
The review status of the B-SAR-205 open items in the Reactor Systems area is as follows:
(1) HPI L4.ne Break - staff has reviewed all infor=ation submitted by B&W; however, we are scill discussing this matter with B&W with regard to required operator actions after the LOCA.
(2)
Boron Dilution Event - staff has reviewed all information subritted by B&W; however, we are still discussing this matter with B&W regarding the dilution events during plant conditions other than refueling or r
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 avaiting additional analysis of certain over-pressure events (start of R.C. pump, CFT isolation valve opening).
(4)~
Provisions for Shutdown - staff has reviewed information submitted by B&W, Information satisfies all of staff concerns.
(5)
Decay Heat Removal Isolation - staff has not yet reviewed.
B&W has not determined which design they will propose; (6)
ECCS Analysis - awaiting infornation 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.
Contact:
Scott Newberry, NRR 49-27911 T
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It is obvious that acceptable B&W responses of all these items will not be completed in time for staff review and documentation of conclusions prior to 8/25/77.
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Gerald R. Ma et
, Section Leader Reactor Systems Branch Division of Systems Safety i
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D. Ross
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Docket No.
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MEMORANDUM FOR:
James P. Knight, Assistant Director for E ineerin Division of Systems Safety Robert L. Tedesco, Assistant Director for Plant Systems Division of Systems Safety Denwood F. Ross, Assistant Director for Reactor Safety Division of Systems Safety FROM:
Domenic B. Vassallo, Assistant birector for Light Water Reactors, Division of Project Management
SUBJECT:
FINAL SER INPUT Oli BSAR-205 The subject information is overdue from three branches, Reactor Systems, Containment Systems, and Mechanical Engineering. All questions put to
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Babcock & l'ilcox have been responded to with the exception of four RSB questions issued September 1,1977, for which B&W has scheduled a September 21, 1977 response.
This effort is essentially the rewording of paragraphs in the July 8,1977 Report to the ACRS which discussed open issues which are now closed.
Estimates of your completion dates are necessary to establish the remainder of the schedule on this project.
The enclosed copy of a final SER input (from the Instrumentation and Controls area) is an example of the final input format which we would like you to use.
/
l Domenic B. Vassallo, Assistant Director Light Water Reactors Division of Project Management l
Enclosure:
l As Stated l
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T. H. Cox E. Chakoff
- 0. D. Parr S. Burwell D. Tibbits R. Cosnak f
T. Novak G. Mazetis G. Lainas J. Shapaker Q +Q" O c,
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,s ENCLOSURE Open Issue Number 10. ESFAS Preliminary Failure Mode and Effects Analysis Revise last paragraph in section 7.3 of the Report to the ACRS to read as follows:
Babcock & Wilcox has stated that a failure mode and effects analysis for the engineered safety features actuation system will be provided in a topical report prior to a Final Safety Analysis Report submittal for the BSAR-205. We requested Babcock & Wilcox to submit a proposed preliminary program plan including the criteria, methods, and. procedures they plan to use in preparing the final design failure mode and effects analysis.
In a letter response dated July 15, 1977, Babcock & Wilcox addressed this staff requirement.
We have evaluated their response and find it acceptable at the preliminary design stage of review.
Open Issue Number 11, Compliance with IEEE-323-1974 for Makeup Pump and Decay Heat Removal Pump Motors Revise the last paragraph in Section 7.8 of the Report to the ACRS to read as follows:
Babcock & Wilcox initialTy presented an abbreviated description of a program intended to demonstrate the environmental qualification of the makeup pump motors (high pressure injection) and the decay heat removal pump motors (low pressure injection). We reviewed their presentation in BSAR-205 and, at the time of the Report to the ACRS on July 8,1977, had several unresolved concerns about the program. 'In a letter to the staff on August 8,1977, Babcock & Wilcox committed to qualify Class lE inotors for safety related pumps in accordance with.IEEE Standard 323-1974.
They further committed to describe the qualification program, including methods and acceptance criteria for environmental qualification, in a suitable generic document such as a B&W topical report, or an Appendix to the BSAR-205, which would be submitted prior to a final design application referencing BSAR-205.
B&W further stated their commitment to the mutually satisfactory resolution of any issues that might develop from the review of their proposed qualification program.
We find the Babcock & Wilcox commitments acceptable at the preliminary design stage of review.
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