AECM-85-028, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal: Difference between revisions

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#REDIRECT [[AECM-85-0289, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal]]
| number = ML20205C859
| issue date = 09/12/1985
| title = Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal
| author name = Dale L
| author affiliation = MISSISSIPPI POWER & LIGHT CO.
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000416
| license number =
| contact person =
| document report number = AECM-85-0289, AECM-85-289, TAC-57619, NUDOCS 8509230269
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
| project = TAC:57619
| stage = Other
}}
 
=Text=
{{#Wiki_filter:1 l
4 MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi                          ,
W hMhM MdB        P. O. B O X 164 0. J A C K S O N. MISSISSIPPI 39215-1640 September 12, 1985 NUCLEAR LICEN$1NG & SAFETY DEPARTMENT U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention:      Mr. Harold R. Denton, Director
 
==Dear Mr. Denton:==
 
==SUBJECT:==
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 License No. NPF-29 File: 0260/15180/L-860.0 Additional Information on NLS-84/05 AECM-85/0289
 
==Reference:==
Letter to Mr. Harold R. Denton from Mr. O. D. Kingsley, Jr. dated May 6, 1985.
Mississippi Power and Light (MP&L) submitted a proposed change to Technical Specification 5.6 in the referenced letter. The proposed change specifies the spent fuel pool and upper containment pool storage capacity after the high density spent fuel racks are installed.
Subsequent conversations with the NRC staff have resulted in the attached              ,
modification to the technical specification change proposed in the referenced letter. The attached change specifies that the upper containment pool will be used for temporary storage of fuel only during refueling operations. Prior to return to reactor criticality af ter refueling, all spent fuel shall be removed from the upper containment pool. Since Section 5.1.1 of the attachment to the referenced letter and Section 6.2.7.3.3 of the Grand Gulf FSAR already contains this cotcmitment, the revised proposed technical specification change is provided only for clarification and to assure a mutual agreement between the NRC and MP&L concerning this issue.
If any additional information is required, please contact my office.
Yours truly, 8509230269 850912                                ,
PDR      ADOCK 05000416 p                        PDR                L. F. Dale Director WJH/SHH:vog Attachment cc:    (See Next Page)                                                                    gg J13AECM85090503 - 1                                                                      g L
 
a t'                                                      AECM-85/0289 Page 2 cc: Mr. J. B. Richsrd (w/a)
Mr. O. D. Kingsley, Jr. (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Mr. James M. Taylor, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. J. Nelson' Grace, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W.,  Suite 2900 Atlanta, Georgia 30323 i
                ~
  -J13AECM85090503 - 2
 
DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located cs shown on Figure 5.1.2-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with;
: a. Ak gf equivalent to less than or equal to 0.95 when flooded with unborated water, including all calculational uncertainties and biases as described in Section 4.3 of the FSAR.
4.26
: b. A nominal 4/ inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.1.2 The k,ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 202'S 1/4".
CAPACITY
: 5. 6. 3 + 'h  pent fuel :ter:g: p::1 i; d::igned :nd 05:l' be nint in:d with :
:t:r:;: ::p::ity limit:d t: n: = r: th= 1270 Nel as:; .bli 3.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7.1-1.
The spent bel stora)e ca.pe.c33 is d.esigneal. and. sha Il be h' mil:ect be no enore than 543'i8 het o.ssemlones in he. spent bel pool. The upper contodnrnent pool ha.s a. c.a po.c'it3 of FOO b el o.ssem bke s br femporar,,g storx$c. o9 inel onis cl.unn3 reSuehg opera *.i.n3. Prior to retu.<n to rea.ctor c/iti en.1 (L3 , au spent hel sbo.ll be removeol. 4 rom ne upper conbnmed pel .
GRAND GULF-UNIT 1                      5-6                  Aa ede d at- N' ~}}

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