ML19318C041
| ML19318C041 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/20/1980 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| FOIA-80-505 ACEM-80-136, NUDOCS 8006300469 | |
| Download: ML19318C041 (5) | |
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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi EdMhhMd5 P. O. B O X 16 4 0. J A C K S O N. MIS SIS SI P PI 3 9 2 0 5 June 20, 1980 mmODUCTeoM DEPARTMENT U.S. Nuclear Regulatory Commission Licensing Branch No. 3 Division of Licensing Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention:
Mr. A. Schwencer, Acting Chief
Dear Mr. Schwencer:
SUBJECT:
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416/417 File 0272/0277/L-344.0 Proposed Meeting and Agenda to Resolve Draft SER Open Issues, FSAR Sections 3.6 through 3.10 AECM-80/136 We have completed our review of the draft Safety Evaluation Report (SER) input for FSAR Sections 3.6 through 3.10, inclusive.
This material was transmitted to MP&L by the NRC letter dated April 22, 1980.
We are currently in the final stages of response preparation to resolve the open items identified by the Mechanical Engineering Branch regarding the above referenced FSAR sections.
We wish to propose a meeting with Mechanical Engineering Branch personnel and their consultant, scheduled for July 8, 9, and 10, 1980.
The purpose of this meeting is to discuss and resolve the open items mentioned above. We further propose that the meeting be held at the following address:
Bechtel Power Corporation Gaithersburg Power Division Conference Room No. 2 20 Firstfield Road Gaithersburg, Maryland 20760 We recommend that each session begin promptly at 9:00 A.M.
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MI'?fl2CIPPI POWER Q LIGHT COMPANY U.S. Nuclear Regulatory Commission AECM-80/136 Licensing Branch No. 3 Page 2 In accordance with the NRC letter referenced above, we have prepared and attached a proposed agenda for this meeting.
Should any additional information be required, please contact our Manager of Safety and Licensing, Mr. John D. Richardson (601-969-2630) or Mr. H. M. Brooks, Licensing Engineer, Bechtel Power Corporation (301-258-4395).
Yours truly, W
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_ M L. F. Dale Nuclear Project Manager a
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Attachment:
Meeting Agenda, Draf t SER Open Item Resolution cc:
Mr. N. L. Stampley Mr. R. B. McGehee Mr. T. B. Conner Mr. Victor Stello, Jr., Director Division of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 4
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Attcchment to AECM-80/136 MEETING AGENDA: DRAFT SER OPEN ITEM RESOLUTION FSAR SECTIONS 3.6 THROUGH 3.10 INCLUSIVE Draf t SER Draft SER, Open Item No.1 Subject Page Reference2 3.6.2-1 Reduction of jet force and reaction 2
by taking credit for restraint of one end of postulated pipe break 3.6.2-2 Use of mechanistic approaches to 2
reduce flow area of longitudinal breeks 3.6.2-3 Assumed crack propagation time F.
3.6.2-4 Stress summary data in Tables 3.6A-1 3
through 3.6A-13B 3.6.2-5 Employment of non-Category I equipment 3
to bring the plant to a safe shut-down condition 3.6.2-6 Use of non-seismic piping inside 3
containment 3.6.2-7 Selection of break and crack locations 3
in non-seismic CAT I piping 3.6.2-8 Verification of acceptance of BN-TOP-2, 4
Revision 2, " Design for Pipe Break Effects" 3.7.3-1 Compliance with the fatigue evaluation 7
requirements of Standard Review Plan Section 3.7.3 3.7.3-2 Combination of modal responses in the 7
case of closely spaced modes 3.9.1-1 Verification of computer programs 9
employed in static and dynamic component analyses 3.9.1-2 Computation of tee stresses using 10 Program ME-632, " Seismic Analysis of Piping Systems" 3.9.1-3 Description of methodology used in load 10 tests of the BWR6 Orificed Fuel Support
Attcchment to AECM-80/136 P g3 2 MEETING AGENDA: DRAFT SER OPEN ITEM RESOLUTION FSAR SECTIONS 3.6 THROUGH 3.10 INCLUSIVE Draf t SER Draft SER, 2
Open Item No.1 Subject Page Reference 3.9.1-4 Procedures and assumptions used in 10 elaatic-plastic analysis of the hydraulic control unit under the SSE faulted condition 3.9.2-1 Preoperational vibration test program, 13 presentation of piping systems included in program 3.9.2-2 Acceptance criteria for steady state 13 vibration and transient snubber loads 3.9.2-3 Transients included in BOP preopera-13 tional testing program 3.9.2-4 Instrumentation on BOP piping systems 13 3.9.2-5 Verification of the calculated values 14 against which the preoperational test program measurements will be compared 3.9.2-6 Summarized results requested for 14 preoperational test program 3.9.2-7 Vibrational measurement and inspection 17 programs to be conducted during preoperational and initial startup testing (components baternal to reactor pressure vessel) 3.9.2-8 Analysis of combined loading of 18 simultaneous LOCA and SSE 3.9.3-1 Omission of fatigue calculations in 20 studying combined stresses due SRV and OBE loads (Load Case 2) 3.9.3-2 Methodology for combining peak 21 responses to multiple dynamic loads (acceptability of use of SRSS method) 3.9.3-3 FSAR Table 3.9-2, data missing from 21 this table (New Loads) 3.9.3-4 Cracked nozzles in control rod drive 22 return lines 3.9.3-5 Design and use of mechanical snubbers 25
Attcchment to AECM-80/136 Pega 3 MEETING AGENDA: DRAFT SER OPEN ITEM RESOLUTION FSAR SECTIONS 3.6 THROUGH 3.10 INCLUSIVE Draft SER Draft SER, Open Item No.1 Subject Page Reference2 3.9.3-6 Single load pulse testing of BOP 25 mechanical snubbers 3.9.3-7 Performance and qualification of 26 NSSS and BOP snubbers at load frequencies above 33 H2 3.9.5-1 Combinatica of closely spaced modes 29 3.9.5-2 Plastic deformation of reactor 29 internals and resultant mechanical interference during fault conditions 3.9.6-1 Preservice and inservice testing of 31 safety related pumps and valves Mississippi Power & Light does not have the lead responsiblity for the resolution of several items mentioned in the draft SER.
These items are listed below.
It is requested that these items also be discussed at the proposed meeting, addressing the status of resolution or review, review schedule, and anticipated problem areas, if any.
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Independent analysis of sample Grand Gulf piping system (Pacific Northwest Ltboratories)
Cracking in BWR jet pump hold down beams Review /Re-evaluation of Grand Gulf Nuclear Station by Seismic Qualification Review Team (SQRT)
Review of information submitted in response to Office of Inspection and Enfortement Bulletin 79-02, " Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bo.cs" 1 The open item numbering system was developed to serialize the issues presented in the draf t SER according to the affected FSAR section.
Pages numbers are referenced from Grand Gulf Draft SER document, transmitted in NRC letter to MP&L, dated April 22, 1980.
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