ML19327B427
| ML19327B427 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/17/1989 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML19327B426 | List: |
| References | |
| 4000-3555-89-01, 4000-3555-89-01-R01, 4000-3555-89-1, 4000-3555-89-1-R1, NUDOCS 8910310163 | |
| Download: ML19327B427 (3) | |
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SA No, 4000-3555-89-01
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PEH0 VAL OF f1ETALLURGICAL SAMPLES i
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No.
I 4000-3555 89-01 T888 Safety Evaluation Report for Removal of Metallurgical Samples Page 2 of 29 l
froin The THI-2 Reactor Vessel SUMhAARY OF CHANGE Approval Date
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4000-3555-89-01 i
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As this operations proceeds, the potential exists that activities or (quipment described in this report will need to be modified or new activities and/or tooling developed.
Any modifications to existing activities or equipment or the introduction of new activities or equipment will be reviewed and documented in accordance with TMI-2 administrative procedures to ensure that no potential hazards or safety y
concerns, not bounded by this SER, are created.
If no such hazards or i
safety concerns are created, this operation may proceed based on the new or modified activities or equipment without a requirement to revise this SER; however, such changes would be evaluated in accordance with and would be reported annually per requirements of 10 CFR 50.59, " Changes, Tests, and Experiments."
l 2.0 PREREQUISITES AND MAJOR ACTIVITIES The sampling operations will be performed in accordance with detailed, i
approved procedures. Any of the approved activtties performed or tools
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used during initial, core region, Lower Core Support Assembly / Lower Head (LCSA/LH) defueling, or Upper Core Support Assembly (UCSA) defueling are considered acceptable.
Appropriate limits and requirements of the f
relevant SERs will be in effect when performing these approved activities.
2.1 Prerequisites It is important to recognize that this operation is designed to take place after all RV defueling activities have been completed and it has been determined that the remaining residual fuel does not pose a
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criticailty concern. Once this defueled condition exists, all remaining risks of operations in the Reactor Vessel, such as this sampling, are minimal.
To put this in perspective, the following is a list of prerequisites that will be met prior to initiating any new activities associated with this samp1tng work.
The Reactor Vessel and Reactor Coolant System will have been defueled to the extent reasonably achievable as required by the THI-2 Technical Specifications.
The remaining residual fuel will be in a subscritical configuration.
However, Mode 1 controls will remain in place (Reference 1) until such time as the Technical l
Specification requirements for transition to Mode 2 have been i
l satisfied.
l Sections of the lower core support plates will have been disassembled and removed from the RV to allow sufficient access to l
the bottom head.
The lower head will have been cleaned of fuel material and l
vacuumed of loose debris. A thin layer of tightly adherent l
non-ccnductive material may exist on the bottom head prior to sampling operations. Those areas will be cleaned locally as needed to cut samples.
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l Rev. 1/0480P l
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