ML20004G119
| ML20004G119 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/08/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Mcgaughy J MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8106290223 | |
| Download: ML20004G119 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D. C. 20555
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s, v.....f Docket Nos. 50-416 JUN 8 19 81
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Mr. J. P. McGaugby, Jr.
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.. u 'ic$ iu' 7 4 Assistant Vice President, Nuclear Production
. ;s Mississippi Power and Light Company N
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Post Office Box 1640 g
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Dear Mr. McGaughy:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - GRAND GULF NUCLEAR STATION, UNITS 1 AND 2 As a result of our review of the information contained in the Final Safety Analysis Report for the Grand Gulf Nuclear Station, Units 1 and 2, we have developed the enclosed request for additional information.
Included are questions from the Auxiliary Systems Branch and Reactor Systems Branch.
We recuest that you amer.d your Final Safety Analysis Report to reflect your responses to the enclosed requests as soon as possible and to inform the Project Manager, Joseph A. Martore, of the date by which you intend to respond.
Sincerely, Ddw Robert L. Tedesco, Assistant 0.?ector for Licensing Division of Licensing
Enclosure:
Rcquest for Additional Information cc w/ enclosure:
See next page B10 6 20 0 'l-t-
". J. P. "c3aughy Assistant Vice President - Nuclear Procuction
- f ssissippi Dower & Light Company P. C. Ecx is'0 J :,.sen, "'s si s sippi - 39205 cc:
- srt E. "cGenee, Esq.
it se, Carter, Child, Steen & Caraway P. O. Box 651 Jact. son, idississippi 39205 Trey B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 P e nn sy l v a ni a fv e,'..
, N. W.
Washington, D. C.
20006 i'r. Adrian Zaccaria, Project Engineer Grand Gulf Nuclear Station Sechtel Power Corpor.ation Gaitnersburg, Maryland 20760 l'r. Alan G. Wagner, As:ident Inspector P. cute 2 Box 150 Port Gibson, Mississippi 39150 Mr. N. L. Stampley, Sr. Vice President Engineering, Production & Construction P.O. Box 1640 Jackson, Mississippi 39205 Mr. L. F. Dale Nuclear Project Manager P.O. Box 1640 Jackson, Mississippi 39205 Mr. Jchn P,1chardson P. O. Box 1640 J ackson, Itississippi 3920C d
P00R DEGNAL
l REOUEST FOR ADDITIONAL INFOR!% TION GRAND 6ULF NUCLEAR STATION UNITS 1&2 AUTILIARY SYSTEMS BRANCH Describe the mears provided in the design of the scram discharge system and 010.28 (4.6) verify that it meets the criteria enumerated in the Generic Safety Evalua-tion Report BWR Scram Discharge System, dated December 1,1980, and trans-mitted to you by NRC lettar dated December 22, 1980.
Demonstrate that a slow or partial loss of air pressure to the scram dis-010.29 (4.6)
RSP charge valves will not result in the following:
- 1) Rapid filling of both the scram discharge volume and the instrument volume due to the lifting of most or all scram discharge valves, witn consecuent loss of adecuate scram discharge volume.
- 2) Loss of reactor coolant due to the combination of lif ting of most or all scram discharge valves, without compensating Cosure of the vent and drain valves, with consequent environmental effects inside con-tainment.
Unless it can be demonstrated that no adverse effects car result, a system shall be provided and described in this section to protect against these two conditions.
010.30 Describe the effects on the safety and coerability of the control rod drive (4.6) hydraulic system if the drive / cooling water pre.sure control valve (F003) fails either closed or open.
P00RORGINAL 1
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2-Describe the means orovided in tihe control rod drive system design to meet 010.31 (4.6) the criteria enumerated in NUREG-0619 BWR Feedwater Nozzle and Control Rod full
'0' rive Return Line Nozzle Cracking and verify that this design is in compliance with this document.
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REACTOR SYSTEMS BRANCH 111.211 Calculations of NPSH available to ECCS pumps in SWRs are normally provided with reference to the pump suction. We are concerned that under certain post accident conditions the potential may exist for damage to ECCS pumps from cavitation because of local flashing in the system suction lines. The potential can result for example from local elevation changes in the piping runs. Calculations of NPSH available at the pump suction may erroneously assume if cuid continuity up to the point of pump suctior.. We require therefore that the applicants provic* : siculations demcastiating chat all points in all safety related suction piping, the NPSH available is adequate to preclude local flashing under the worst postulated conditions.
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