ML19329B696
| ML19329B696 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/17/1976 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Heineman R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002060708 | |
| Download: ML19329B696 (7) | |
Text
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UNITED STATES y
L NUCLEAR REGULATORY COMMISSION 4
S WASHINGTON, D. C. 20585 N
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DEC 171976 MEMORANDUM FOR:
R. E. Heineman, Director, Division of Systems Safety H. R. Denton, Director, Division of Site Safety and Environmental Analysis R. Boyd, Director, Division of Project Management THRU:
J. Stolz, Chief, Light Water Reactors Branch No.1 -
Division of Project Management FROM:
L. Engle, Project Manager, Light Water Reactors Branch No.1, Division of Project Management
SUBJECT:
DAVIS-BESSE, UNIT 1 ACRS SUBCOMMITTEE MEETING - TUESDAY DECEMBER 21, 1976 The Davis-Besse, Unit 1 ACRS Subcommittee meeting is scheduled for Tuesday December 21, 1976. The agenda for this meeting is provided in Attachment 1 to this memorandum.
There are presently 15 outstanding items in the SER that need resolution prior to issuance of an operating license. Attachment 2 to this memoran-dum list the outstanding items as listed in the SER. The SER also iden-tifies the staff's current evaluation of seismic intensity data at the Davis-Besse site which will be addressed in a supplement to the SER.
We request that the following branch staff personel be available for this ACRS subcommittee meeting:
(1) Reactor Systems Branch (2) Core Performance Branch (3) Analysis Branch (4) Auxiliary and Power Conversion Branch (5) Containment Systems Branch (6) Electrical Instrumentation and Control System Branch (7) Geology-Seismology Branch The appropriate staff members have already been notified by telephone.
L. Engle, roject Manager Light Water Reactors Branch No. 1 Division of Project Management cc: See Page 2 A
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2-DEC 171976 cc:
B. Rusche E. Case D. DeYoung F. Schroeder D. Vassallo W. P. Gamill
.J. P. Knight D. Ross R. Tedesco D. Skovholt i
Attachments: as stated i
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ATTACHMENT 1 SCHEDULE FOR DAVIS-BESSE UNIT 1 SUBCOMMITTEE MEETING WASHINGTON, D.C.
December 21, 1976 8:30 a.m.
1.0 Executive Session (0 pen) 9:00 a.m.
2.0 Meeting with Applicant and NRC Staff (0 pen) 2.1 Introduction by Applicant (20 minutes)
Brief plant description and changes since CP review Fuel load / operation schedule Organization / staffing for operation 2.2 NRC Staff Report Sunnary of SER and status of review Resolution of comments in ACRS report dated (8/29/70) 2.3 Outstanding Review Items (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)
Status of each outstanding issue (NRC Staff)
Response (Applicant)
Status of unresolved generic items (ACRS Report #4, dated 4/16/76) as related to other B&W reactors (NRC Staff) 2.4 Presentation by Applicant (40 minutes)
- Review of containment vessel paint problems Status of modified surveillance specimen tube holders Long term cooling capability without use of BOP
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components; steam generators; a.c. power Other items requested by Subcommittee or Applicant
Davis-Besse 1 2.5 Emergency Plans (Applicant) (30 minutes)
Status of fire protection evaluation in compliance with Appendix A to Branch Tech?.f cal Position APCSB 9.5.1 Instrumentation to follow the course of an accident Agreements with local and state agencies Ohio response plan 2.6 Plant Security (Closed) (20 minutes)
Procedures Operation features to prevent sabotage 5:00 p.m.
3.0 Subcommittee Caucus and Adjourment (0 pen) (10 minutes)
ATTACHMENT 2 1.7
' w ry of Outstandino Review items At this time, we have not completed our review of a neber of items, either because additional information is required from the applicant or because we have not yet These items will completed our review of information submitted by the applicant.
The current status be addressed in a supplement to this Safety Evaluation Report.
of each ites, and the section(s) of this report in which the items are discussed are identified below.
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n_.,_,3, (2) Analysis of reactor coolant system response to pressure transients that can potentially occur during startup and shutdown (Section 5.2 2).
(3) Leakage Detection System (Section 5.2.4).
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.(4) Performance of surveillance capsule specimen holder tube based on reactor internals vibration test assessment (Section 5.3).
(5) Analysis of the decay heat removal system relief capacity (Section 5.5.3).
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'(6) Evaluation of the reactor cavity pressure response analysis (section 6.2.1).
(7) Analysis for pressure respanse of the shield building following a postulated loss-of-coolant accident (Section 6.2.3).
(8) Evaluation of emergency core cooling system perfor nance considering minimum containment pressure, submerged valves, effects of boron precipitation, and
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single failure criteria (Section 6.3.3).
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(11) Verification of the reactor protection system equipment qualification testing (Section 7.2). Applicant will submit test results in December 1976.
(12) Modification in redundant reactor coolant flow transmitters in order to meet single failure criteria (Section 7.2).
(13) Evaluation that inadvertent closure of the low pressure to high pressure valves will not preclude decay heat removal to cold shutdown (Sections 7.3.4 and 5.5.3).
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(14) Evaluation of the modified steam and feedwater line rupture control system (Section7.4.1).
(15) Evaluation of separation criteria for redundant safe'ty related electrical cables in trays, wireways, and conduits (Section 7.4.2).
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n (17) Evaluation of the qualification of safety-related equipment in a postulated main steamline break accident environment (Section 7.7).
(18) Equipment failures due to degraded grid voltage drop (Section 8.2). The applicant has provided information wnich the staff is presently evaluating.
(19) Evaluation of the applicant's financial qualifications to operate the facility
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(Section 20.0).
1.8 Generic issues The following issues are generic in nature and are being pursued primarily with the vendor in question, and through the applicant where appropriate. We will require i
that any design or procedural change resulting from these generic reviews be incorporated in Davis Besse. Unit I as appropriate.
(1) Evaluation of reactor vessel supports under loss-of-coolant loadings (Section 3.9.3).
u (2) Pellet cladding mechanical interaction (Section 4.2.1).
(3) Evaluation of fuel rod bewing effects (Section 4.4).
(4) Emergency core cooling analysis modificajiens (Section 6.3.3).
Revisions by Sabcock and Wilcox are expected by "ecemcer 1976.
(5) Anticipated transients without scram (Section 7.2.2). Applicant has been -
requested to furnish additional information.
(6) Evaluation of facility fine protection capability for Appendix A to Branch Technical Position APCSS 9.5-1 (Section 9.6.1).
Appitcant will provide I
evaluation in February 1977.
MEETING NOTICE DISTRIBUTION Docket File J. Knight NRC POR D. Ross Local PDR R. Tedesco TIC S. Pawlicki LWR 1 File I. Sibweil NRR Reading P. Check B. Rusche T. Novak E. Case Z. Rosztoczy J. Miller T. Ippolito R. Boyd V. Benaroya R. C. DeYoung G. Lainas D. Skovholt V. Moore F. J. Williams R. Vollmer J. Stolz M. Ernst K. Kniel W. Gamill
- 0. Parr G. Knighton W. Butler B. Youngblood D. Vassallo W. Regan L. Crocker D. Bunch R. Clark J. Collins T. Speis W. Kreger P. Collins R. Ballard C. Heltemes M. Spangler R. Houston J. Stepp R. Heinenan L. Iblman R. Denton H. Snith ACRS (16)
V. Stello S. Varga Dr. Harold L. Ornstein H. Berkow Project Manager Attorney, ELD IE SD (7)
E. Hylton Receptionist Principal Staff Partici. pants B. Faulkenberry, IE
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