ML20236P668
| ML20236P668 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/07/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20236P671 | List: |
| References | |
| NUDOCS 8708120462 | |
| Download: ML20236P668 (6) | |
Text
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TECHNICAL SPECIFICATIONS TABLE'0F CONTENTS (Continued)
PAGE 5.0 DESIGN FEATURES (Continued) 5.3 Nucl ear Steam Supply System.(NSSS).........................
5-2 5.3.1 P r ima ry Cool a n t Sy s t em.............................
5-2 5.3.2 Reactor Core and Contro1...........................
5-3 5.3.3 Emergency Core Cooling System......................
5-3 5.4 Fu e l S t o ra g e...............................................
5-4 5.4.1 New Fuel Storage...................................
5-4 i
5.4.2 Spent Fuel Stora ge.................................
5-4a l.
6.0 ADMI N I ST RAT I VE CONT R0LS.......................................... 6-1 6.1 Re s p o n s i b i l i ty.............................................
6-1 j
6.2 O rg a n i z a t i o n...............................................
6 '
6.2.1 Offsite.............
6-1
.6.2.2 Plant Staff........................................
6-1 6.2.3 Nuclear Activities Plant Organization (NAP 0).......
6-la 6.3 Plant Staff Qualifications.................................. 6-lb 6.4 T r a i n i n g...................................................
6-l b 6.5 Review and Audit...........................................
6-5 6.5.1 Plant Review Committee (PRC).......................
6-5 6.5.1.1 F u n c t i o n.................................
6-5
- 6. 5.1. 2 C omp o s i t i o n..............................
6-5 6.5.1.3 Alternates...............................
6-5 6.5.1.4 Meeti ng Frequency........................
6-5 6.5.1.5 Quorum...................................
6-5
- 6. 5.1. 6 Responsi bili ties.........................
6-5 l
6.5.1.7 Authority.................................
6-6 1
- 6. 5.1. 8 Recordt..................................
6-6a j
1 6.5.2 Nucl ear Safety Board (NSB).........................
6-6a 6.5.2.1 Responsibilities..........................
6-6a 6.5.2.2 F u n c ti o n.................................
6-6 a 6.5.2.3 Composition..............................
6-7 6.5.2.4 Al te rnate Membe rs....................... ~. 6-7 l '
6.5.2.5 Con s ul t a nt s..............................
6-7
(
l 6.5.2.6 Meeting Frequency........................
6-7 l
l 6.5.2.7 Quorum...................................
6-8 l
\\
v Amendment No. 77,$E.63,67,6E,gg,105 8700120462 070007 PDR ADOCK 05000255 PDR p
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e Table 4.2.1 Minimum Frequencies for Sampling Tests (1) A daily sample shall be obtained and analyzed if fission product monitor is out of service (2)Af ter at least 2 IFPD and at least 20 days since the last shutdown of longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
( )When iodine or particulate radioactivity levels exceed 10 percent of limit in Specification 3.9.6 and 3.9.9, the sampling frequency shall be increased to a minimum of once each day.
(5)If the air ejector gas monitor is out of service, the secondary coolant gross radioactivity shall be measured once per day to evaluate steam generator leak tightness. -
(
Reference Specification 3.8.5 for maximum bulk water temperature and monitoring requirements.
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I7) Reference Bases section of Specification 3.8 and section 5.4.2f of the Design Features for minimum boron concentration (2 1720 ppm).
1 i
4'14b Amendment No. 29.105
)
5.4 FUEL STOPAGE 5.4.1 New Fuel Storage The pitch of the new fuel storage rack lattice is > 9.375 inches, and a.
every other position in the lettice -hall be permaiiently occupied by an 8" x B" structural steel box beam or core plugs such that the minimum center-to-center spacing of new fuel assemblies in the alternating storage array is 13.26".
This distance in the alternating storage lattice is sufficient so that Keff will not exceed 0.98 where fuel which contains not more than 41.24 grams of U-235 per axial centimeter of active fuel assembly is in place and optimum (i.e., aqueous foam) moderation is i
assumed, and the Keff will not exceed 0.95 when the storage area is l
flooded with unborated water. The calculated Keff includes a conservative allowance for uncertainties as described in CPC letters of 12/18/78 and 1/12/79.
b.
New fuel may also be stored in shipping containers.
The new fuel storage racks are designed as a Class I structure.
c.
5-4 Amendment No. 35,0,105
5.4.2 Spent Fuel Storage a.
Irradiated fue? bundles will be stored, prior to off-site shipment in tht. stainless steel-lined spent fuel pool.
b.
(Deleted)
The spent fuel storage pool and spare (north) tilt pit are c.
divided into two regions identified as Region I and Region 11 as illustrated in Figure 5.4-1.
Region I racks are designed and shall be maintained with a nominal 10.25" center-to-center distance between fuel assemblies with the exception of the single Type E rack which has a nominal 11.25" center-to-center distance between fuel assemblies. The Region I spent fuel storage racks are designed such that fuel having a maximum U-235 loading of 3.27 w/o of U-235 placed in the racks would result in a K equivalent to 1 0.95 when flooded with unborated water. Tbe.
K,ff of 5 0.95 includes a conservative allowance for uncertainties.
d.
Region Il racks have a 9.17 inch center-to-center spacing.
.Because of this smaller spacing, strict controls are employed to evaluate burnup of the fuel assembly prior to its placement in Region 11 cell locations. Upon determination that the fuel assembly meets the burnup requirements of Table 5.4-1, placement in a Region II cell is authorized. These positive controls assure the fuel enrichment limits assumed in the safety analyses will not be exceeded.
After installation of the two-region high density spent fuel e.
racks, the maximum loading for fuel assemblies in the spent fuel racks is 3.27 w/o of U-235.
f.
The einimum spent fuel pool water boron concentration shall be 3720 ppm. Boron concentration shall be verified at least once monthly..
g.
The spent fuel racks are designed as a Class I structure.
h.
Spent fuel shipping casks shall not be moved into the fuel storage building until such time as the NRC has reviewed and approved the spent fuel cask drop evaluation.
1.
Storage in Region II of the spent fuel pool and spare (north) tilt pit shall be restricted by burnup and enrichment limits specified in Table 5.4-1.
NOTE: Until needed for fuel storage, one Region II rack in the northeast corner of the spent fuel pool may be removed and replaced with the cask anti-tipping device.
References FSAR Update Chapter 5 FSAR Update Chapter 9 5-4a Amendment No.105
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TABLE 5.4-1 Spent Tuel Burnup Requirements for Storage in Region II of the Spent Tuel Pit Initial Discharge Burnup w/o GWD/MT 1.5 0
1.6.
1.9 1.8 5.2 2.0 8.5 2.2 11.5 2.4 l14.1 2.6 16.6 2.8 18.8 3.0 20.9 3.2 22.9 3.27 23.5 i
Linear interpolation between two consecutive points will yield conservative results.
5-4c Amendment No.105 1
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