ML20205H176
| ML20205H176 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/06/1999 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20137F996 | List: |
| References | |
| NUDOCS 9904080090 | |
| Download: ML20205H176 (9) | |
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Edwin I. Hatch Nuclear Plant Request for License Amendment Spent Fuel Pool Storage Expansion Page Change Instructions Unit 1 Remove Page Insert Page 4
4.0-2 4.0-2 Unit 2 Remove Page Insert Page 4.0-2 4.0-2 I
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9904080090 990331 7
PDR ADOCK 05000321 P
PDR j
HL-5752 E3-1 j
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' Request for License Amendment
. Spent Fuel Pool Storage Expansion 10 CFR 50.92 Evaluation boiling. If pool boiling is postulated to occur, the impact on the radiological consequences previously evaluated for this event is minimal and remains acceptable.
- 2. Theproposed changes do not create the possibility ofa new or dgerent kind of accidentfrom anypreviously evaluated.
The new racks will not require their movement over any stored spent fuel during installation. Rack movements will be conducted using the single failure proof Hatch I reactor building crane. During the SFP expansion effort, all heavy load movements will be performed in accordance with SNC's commitments to NUREG-0612 to preclude any damage to fuel assemblies stored in the SFPs, and to preclude any damage to safe shutdown equipment. Crane operator training and load handling instruencas in concert with defined safe load travel paths will be provided together with proper crane inspection, maintenance, and testing to ensure reliable heavy loe:1
' handling operations.
As with the existing spent fuel storage racks, no special storage configurations will need to be imposed on the new racks, even with the closer spacing between fuel usemblies. Therefore, spent fuel will continue to be allowed to be placed in any storage cell location while maintaining a kerr less than or equal to 0.95. Also, the spent fuel storage expansion does not involve any rod consolidation or double-tiering of the spent fuel racks.
No new or unproven technology is utilized in either the construction process or the analytical techniques necessary to justify SFP storage expansion at Plant Hatch.
' Additionally, the rack vendor construction process and analytical techniques are substantially the same as those used for other recently completed storage expansion projects which have been accepted by the NRC.
- 3. Theproposed changes do not im>olve a significant reduction in a margin ofsafety.
The proposed small increase in storage capacity of the SFPs at Plant Hatch does not represent a significant challenge to the performance of existing plant systems and structures. As demonstrated in Enclosures 5 and 6, this license amendment request has been evaluated in accordance with the NRC acceptance criteria contained in "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications" dated April 14,1978, as amended on January 18,1979, and shown to be acceptable for normal and abnormal conditions relative to the criticality, thermal-hydraulic, radiological, seismic, structurA, material, and heavy load requirements contained therein.
HL-5752 E2-2 i
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Design Features 4.0 4.0 DESIGN FEATURES (continued)
-4.3-Fuel Storage 4.3.1 Criticality 4s3.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
k.gf.; 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 10.3.3 of the FSAR; and b.
A nominal 6.5 inch center to center distance between fuel assemblies placed in the storage racks.*
4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
a.
k.v, :s; 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 10.2.3 of the FSAR; i
b.
A nominal 11.5 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 203 ft 9 inches.
4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3349 fuel l
assemblies.
- The storage rack located in the contaminated equipment storage area of the spent fuel pool shall have a nominal 6.25 inch center to center distance between fuel assemblies.
HATCH UNIT 1 4.0-2 Proposed 98-127
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
k.,, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described'in Section 9.1.2 of the FSAR; and b.
A nominal 6.5 inch center to center distance between fuel assemblies placed in the storage racks.*
l 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
a.
k,, s 0.95 if fully flooded with unborated water, which include: an allowance for uncertainties as described in Section 9.1.1 of the FSAR; b.
A nomint.1 11.5 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 203 ft 9 inches.
4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2933 fuel l
assemblies.
- The storage rack located in the contaminated equipment storage area of the spent fuel pool shall have a nominal 6.25 inch center to center distance between fuel assemblies.
_1 HATCH UNIT 2 4.0-2 Proposed 98-127
L Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage acks are designed and shall be maintained with:
a.
k,,, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as i
described in Section 10.3.3 of the FSAR; and b.
A nominal 6.5 inch center to center distance betweel uel assemblies placed in the storage f
racks.+
4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
I a.
k.ve s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 10.2.3 of the FSAR; b.
A nominal 11.5 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainace The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 203 ft 9 inches.
1 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than41&l-fuel assemblies.
3349
- T h e. s.hrage rack located inik codamirwtud eyipment storage area c4 he spent fud pm) shd Mw. 4 nomWI 6.zs inch center % cetter distance bebeen he\\
a ssernb bes.
HATCH UNIT 1 4.0-2
" :ai; cat M:. 105 Proposed 98-tr7
r Design Features l
4.0 l
l 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The. spent fuel storage racks are designed and shall be
)
l maintained with:
l a.
k.,, s 0.95 if fully flooded with unborated water, l
which includes an allowance for uncertaisities as described in Section 9.1.2 of the FSAR; and b.
A nominal 6.5 inch center to center distance betweeg fuel assemblies placed -in the storage racks 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
a.
k.,, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1.1 of the FSAR; b.
A nominal 11.5 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 203 ft 9 inches.
4.3.3 Caoacity "ae spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than-EB45-fuel assemblies.
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- The shrage rack locahd inihe conhtnakd eguipment storage aren e4 +be spent fue\\ pool skll have a nominal 6.7.5 \\nch center to centee distance between fuel i
Assembhes.
..rendment NO. 135 HATCH UNIT 2 4.0-2
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ProposecA 98-i2n Edwin I. Hatch Nuclear Plant Request for License Amendment Spent Fuel Pool Storage Expansion Environmental Assessment i
10 CFR 51.22(c)(9) provides criterion for and identification oflicensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment.
A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed license amendment would not:
- 1. Involve a significant hazards consideration;
- 2. Result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite;
- 3. Result in a significant increase in individual or cumulative occupational radiation exposure.
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Southern Nuclear Operating Company (SNC) has determined that the proposed Technical Specification changes described in Enclosure 1 meet the eligibility criteria for categorical l
exclusion set fonh in 10 CFR 51.22(c)(9). Accordingly, pursuant to 10 CFR 51.22(b), no environmental impact statement needs to be prepared in connection with the issuance of the license amendment for the proposed changes. The basis for this determination using the above criteria follows:
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- 1. As demonstrated in Enclosure 2, the proposed changes to the Technical Specifications do not involve a significant hazards consideration.
- 2. As demonstrated in Enclosures 5 and 6, the proposed changes to the Technical Specifications do not result in a significant change in the types or increase in the amounts of any effluents that may be released offsite. The Spent Fuel Pool (SFP) storage expansion does not require the installation of any new effluent release processing equipment, does not require existing plant systems to perform a different type of function than they are currently designed to perform associated with the processing of effluent releases, and does not require changes to existing plant surveillance requirements used to monitor effluent releases. Since the proposed increase in storage capacity o%e SFPs is small, any resuldng impact on the amount or types ofeffluents tbt may be experienced is considered to be negligible.
HL-5752 E4-1
Request for License Amendment
.. Spent Fuel Pool Storage Expansion Environmental Assessment
- 3. As demonstrated in Enclosures 5 and 6, the proposed changes to the Technical Specifications do not result in a significant increase in individual or cumulative occupational radiation exposure. The SFP storage expansion effort will be accomplished with detailed procedures in place that take into consideration as low as is reasonably achievable (ALARA) principles such that it is completed safely and efficiently with minimum radiation exposure to personnel.
- Based on the preceding discussion, there are no significant radiological or non-radiological impacts associated with this request to increase the spent fuel storage capacity at Plant Hatch. Therefore, SNC concludes that the proposed action will not have a significant effect on the quality of the human environment.
HL-5752 -
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c Edwin I. Hatch Nuclear Plant Request for License Amendment Spent Fuel Pool Storage Expansion l
Spent Fuel Storage Expansion Report (Proprietary) l 1
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HL-5752 1.
Edwin I. Hatch Nuclear Plant Request for License Amendment Spent Fuel Pool Storage Expansion Spent Fuel Storage Expansion Report (Non-Proprietary)
HL-5752
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