ELV-00365, Forwards Comments on Sser 8.Spent Fuel Storage Racks Will Have Boraflex on All Sides,Including Sides Adjacent to Fuel Pool Walls

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Forwards Comments on Sser 8.Spent Fuel Storage Racks Will Have Boraflex on All Sides,Including Sides Adjacent to Fuel Pool Walls
ML20246L823
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 03/16/1989
From: Bailey J
GEORGIA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0211E, 211E, ELV-00365, ELV-365, GN-1584, NUDOCS 8903240283
Download: ML20246L823 (3)


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, .g . 1o; Georgia Fbwer Company

<Yj[t ;- , ' 40 Inverness Center Parkway

~o-Fbst Office Box 1295 L .

Birmingham, Alabama 35201 te Nuclear Operations Department . Georgia Power

- the southem electnc system -

GN-1584

'ELV-00365 0211e March-16, 1989 U. S.~ Nuclear Regulatory Commission  !

ATTN: Document Control Desk Washington, D. C. 20555 PLANT.V0GTLE - UNIT'2 NRC DOCKET 50-425 OPERATING LICENSE'NPF-79 COMMENTS 10N SSER-8 Gentlenen:

Attached are our comments -on Supplement Number 8 to the Safety Evaluation Report for Vogtle Electric Generating Plant Units 1 and 2.

Sincerely, d

J. A. Bailey Project Licensing Manager JAB /HWM/gm xc: NRC Regional Administrator NRC Resident Inspector Mr. P. D. Rice Mr. J. P. Kane ,

Mr. R. A. Thomas  !

Mr. B. W. Churchill, Esquire Mr. J. E. Joiner, Esquire

, Mr. J. B. Hopkins (2 copies) 0j Mr. G. Bockhold, Jr.

Mr. R. J. Goddard, Esquire [0 Mr. R. W. McManus gs ,

'/ogtle Project File 8903240283 890316 I?3 3 PDR ADOCK 05000425 mi

( PNV ;yj

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l ATTACHMENT l

Comments on SSER 8 '

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.na ge 2-2 Third paragraph, eighth line - the word "as" should be inserted between "well" and "other".

Page 3-3 The last sentence is not complete as continued on the following  ;

page. {

i Page 3-4 Item (3), second line, "and PR-2" should be deleted. Item (3), i last line, "Pi!-26" should be "RR-26". '

Page 5-1 Next to last paragraph, seventh line - the close parenthesis is j missing. i Page 5-2 Seventh paragraph, second line should be changed to, " components that include...".

Page 9-2 The second paragraph states that the outermost cell walls will not contain Boraflex. This is not true for the spent fuel storage racks in the Unit 2 pool. The Unit 2 racks will have Boraflex on all sides, including the sides that are adjacent to the fuel pool walls.

The fourth paragraph implies that without credit for the soluable  ;

boron, Keff will not exceed 0.95 under all conditions including misplacement of a fuel assembly. However, as stated in our December 23, 1987 letter this was considered to be an abnormal or accidental event for which credit could be taken for the borated spent fuel pool water.

The fifth paragraph states that the racks can withstand the impact of a dropped fuel assembly (including handling tool) without being damaged. This is more correctly stated on page 9-5 as, "... the  !

Unit 2 racks are sufficiently rugged to withstand the postulated  ;

impact phenomena without violating any of their functional j requirements."

Page 9-5 The section on criticality refers to the December 23, 1987 j submittal which contained a criticality analysis of the spent fuel q storage racks. This criticality analysis was amended by another submittal on August 12, 1988. This submittal was referenced on page 9-1 of SSER 8. The discussion of criticality on pages 9-5 l and 9-6 should be revised to reflect the August 12 submittal which  !

provided a value of 0.943 for Keff when using Westinghouse i standard fuel, which is the fuel design being used for Vogtle Units 1 and 2.  ;

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Page 9-6 Second paragraph, third line - the word "or" shoul'd be replaced with "of".

l l' Page 9-7 Last paragraph - reference to the spent fuel pool normal operating

' water temperature should be 1150F not 1050F as stated.

Page 9-8 Last paragraph, sixth line - the word " dated" should be replaced- )

l with'" data". ]

Page 9-13 Second paragraph - the word "retracking" should be replaced with "reracking".

Page 9-17 Third paragraph, fourteenth line, As written, SSER 8 states that sufficient concrete cover does not exist to comply with staff fire protection criteria for 6 locations. Our analysis did not state that the conduits were not embedded to a sufficient depth to afford 3-hour equivalent fire protection, but only that we could  !

not ensure that the- conduits were embedded deep enough in all l cases. Therefore, we recommend that the word "does" be replaced by "may".

Page 9-18 Fourth paragraph, fif th line - the word " reply" should be replaced with " rely".

Page 9-19 The third paragraph states that revised combustible -loadings for all fire areas were provided by letter dated October 13, 1988.

However, this letter supplied the combustible loading data for Unit 2 fire areas and revised the data for those Unit 1 fire areas ,

within the Unit 2 construction scope. ]

Page 9-21 The last paragraph states that each confirmatory inspection item performed-on Unit I has been completed for Unit 2. Our December 22, 1988 letter actually stated that all inspections required by the TDI Diesel Generator Owners Group are now completed.

Page 11-3 Third paragraph, third line - the word " building" should be added after " spent resin holding tanks located within the turbine".

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