ML20077L773
| ML20077L773 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/03/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20077L772 | List: |
| References | |
| NUDOCS 9501110518 | |
| Download: ML20077L773 (7) | |
Text
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4 ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2-DOCKET NOS. 50-327 AND 50-328 7
(TVA-SON-TS-95-01)
LIST OF AFFECTED PAGES Unit 'l 4
3/4 9-7 Unit 2 3/4 9-8 t
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REFUELING 0PERATIONS f
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3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA LIMITING CONDITION FOR OPERATION 1
3.9.7 Loads traveling over fuel assemblies in the spent fuel pit area shall be l'
restricted as follows:
a.
Spent fuel storage pool:
Loads in excess of 2100 pounds
- shall be prohibited from' travel over fuel assemblies in the spent fuel storage pool.
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b.
Cask loading area of the cask pit:
1.
Loads which meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 may be carried over fuel assemblies stored in the cask loading area of the cask r
pit if the impact shield is in place over the cask loading area.
2.
Loads which do not meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 shall be prohibited from travel over the cask loading area of the cask pit when fuel is stored in it.
APPLICABILITY: With fuel assemblies in the spent fuel storage pool or in the cask loading area of the cask pit.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.9.7.3 Crane interlocks and physical stops which prevent crane hook travel over the storage pool shall be demonstrated OPERABLE within 7 days prior to 4
crar,e use and at least once per 7 days thereafter during crane operation.
4.9.7.2 When fuel is stored in the cask pit area, verify administrative requirements concerning the impact shield are met prict to moving loads in excess of 2100 pounds across the cask pit area.
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- The spent fuel pool transfer canal gate and the spent fuel pool divider gate may travel over fuel assemblies in the spent fuel pool.
SEQUOYAH - UNIT 1 3/4 9-7 Amendment No. 91, 167
REFUELING OPERATIONS 3/4.9/7 CRANE TRAVEL - SPENT FUEL PIT AREA LIMITING CONDITION FOR OPERATION 3.9.7 Loads traveling over fuel assemblies in the spent fuel pit area shall be restricted as follows:
a.
Spent fuel storage pool:
Loads in excess of 2100 pounds
- shall ne prohibited from travel over fuel assemblies in the spent fuel storage pool.
b.
Cask loading area of the cask pit:
1.
Loads which meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 may be carried over fuel assemblies stored in the cask loading area of the cask pit if the impact shield is in place over the cask loading area.
2.
Loads which do not meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 shall be i
prohibited from travel over the cask loading area of the cask L
pit when fuel is stored in it.
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APPLICABILITY: With fuel assemblies in the spent fuel storage pool or in the cask loading area of the cask pit.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE00'REMENTS t
4.9.7.1 Crane interlocks and physical stops which prevent crane hook travel over the storage pool shall be demcastrated OPERABLE within 7 days prior to 4
crane use and at least once per 7 days thereafter during crane operation.
4.9.7.2 When fuel is stored in the cask pit area, verify administrative requirements concerning the impact shield are met prior to moving loads in excess of 2100 pounds across the cask pit area.
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- The spent fuel pool transfer canal gate and the spent fuel pool divider gate may travel over fuel assemblies in the spent fuel pool.
SEQUOYAH - UNIT 2 3/4 9-8 Amendment No. 81, 157
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'l ENCLOSURE 2
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PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE.
SEQUOYAH NUCLEAR PLANT (SON) UNITS-1 AND 2
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DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-95-01) i 4
DESCRIPTION AND JUSTIFICATION FOR CRANE TRAVEL - SPENT FUEL PIT AREA - PERMISSIVE f
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Descriotion of Chance TVA proposes to modify the Sequoyah Nuclear Plant (SON) Units 1 and 2 technical specifications (TSs) to allow the auxiliary building bridge crane interlocks and phyr.ical stops to be defeated during the implementation of an approved spent-fuel pool storage capacity increase modification.
Surveillance Requirement (SR) 4.9.7.1 will have the "#" sign placed at the end of the sentence. A statement will be added to correspond to the # sign at the bottom of the page that will state that it is permissible to defeat the crane interlocks and remove the physical stops for activities associated with the spent-fuel pool rerack project.
Reason for Chanae I
The present TS does not allow the auxiliary building crane hook to be moved over the spent-fuel pool. A change is necessary to complete the spent-fuel pool rerack project.
Justification for Chanaes in order to remove the old spent-fue!. cool racks and install the new ones, the auxiliary building crane interlocks and physical stops must be defeated.
Contained in the original rerack license amendment submittals, TVA addressed four load-handling accidents and provided plans to address each one. TVA also developed a safe-load path for each rack. At no time will the old or new racks be carried over fuel assemblies in the spent-fuel pool. The defeat of the crano interlocks and physical stops will not add additional accident scenarios that have not previously been addressed in both the TVA submittal and the NRC Safety Evaluation Report.
Environmental Imoact Evaluation The proposed change does not involve an unreviewed environmental question because operation of SON Units 1 and 2 in accordance with this change would not:
1.
Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or decisions of the Atomic Safety and Licensing Board.
2.
Result in a significant change in effluents or power levels.
3.
Result in matters not previously reviewed in the licensing basis for SON that may have a significant environmental impact.
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i ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 i
COCKET NOS. 50-327 AND 50-328 -
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(TVA-SON-TS-95-01)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSiOERATION j
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Significant Hazards Evaluation TVA has evaluated the proposed technical specification (TS) change and has determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of Sequoyah Nuclear Plant (SON) in accordance with the proposed amendment will not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The SON TSs prohibit loads in excess of 2100 pounds from travel over fuel assemblies in the spent-fuel pool and require the associated crane interlocks and physical stops to be periodically demonstrated operable.
During the installation process, the crane interlocks and physical stops must be defeated to allow the removal and installation of racks and associated tools to be moved over the spent-fuel pool. Additionally, administrative controls are in place to return the crane interlocks and physical stops to an operable status after each phase of crane use. It should be noted that movement over fuelin the spent-fuel poolis prohibited. Therefore, the defeat of the interlocks and physical stops does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
Create the possibility of a new or different kind of accident from any previously analyzed.
A fuel movement and rack change-out sequence has been developed that...
illustrates that it will not be necessary to carry existing or new racks over fuelin the cask loading area or any region of the pool containing fuel. A lateral-free zone clearance from stored fuel shall be maintained.
Accordingly, it can be concluded that the bypassing of the interlocks and removal of the physical stops does not create the possibility of a new or different kind of accident from any previously analyzed.
3.
Involve a significant reduction in a margin of safety.
The SON rerack project will ensure maxiraum emphasis to mitigate the potential load-drop accident by implementing measures to eliminate shortcomings in all aspects of the operation. Elimination of shortcomings will be accomplished by comprehensive training of the installation crew, redundancies built in lifting devices, procedures to address each phase of the project, and prohibitions of lifts over fuel assemblies in the spent-fuel pool. Therefore, defeating the crane interlock and physical stops to perform the required lifts does not involve a significant reduction in a margin of safety.