05000285/FIN-2013013-22
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Finding | |
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| Title | Shutdown Cooling Piping and Pipe Supports Calculation Has Incorrect Acceptance Criteria for Anchor Displacement |
| Description | The Fort Calhoun Stations original code of record for safety-related piping is USAS B31.7, Nuclear Power Piping, 1968 Draft Edition. The licensee reclassified a number of systems and piping in the early 1990s. In addition, because of the reclassification of some Class I piping to Class II piping, fatigue analysis was not performed on some safety related systems. The licensee reconciled the code of construction for some safety related systems to newer ASME Section III code, which requires a fatigue analysis for Class II piping, but because the plant is licensed to USAS B31.7, no analysis was completed. The NRC issued a safety evaluation allowing the Fort Calhoun Station to utilize alternate seismic monitoring criteria (ASCM) but stated additional evaluation was required if a support is displaced more than 1/16 of an inch. This safety evaluation was issued in April 1993. The team reviewed Station Calculation FC07234, Evaluation of Shutdown Cooling Mode Temperature and Pressure Increase on the SI System Piping and Pipe Supports, and noted that a vendor had performed this calculation utilizing criteria that deviated from the ASCM acceptance criteria. Specifically, the vendor used one of their internal memoranda, dated May 1979, to accept support displacement not exceeding 1/8 of an inch without evaluating the deviation as required by the ASCM safety evaluation. In addition, Station Calculation FC07234 identified some piping support stress allowables that were exceeded and needed additional vendor evaluation, but the only vendor evaluation noted was an email, with no justification or explanation why the loading on the SI-1A/B pumps and nozzles were acceptable. There were additional supports that exceeded their stress allowables but no additional evaluation is noted in the calculation. Additional information is required to determine if Station Calculation FC07234 is adequate and fully supports operability evaluations for SI-1A/B pumps (High Head Safety Injection) and nozzles, AC-4A/B heat exchanger (Shutdown Cooling Heat exchangers) supply lines, high pressure safety injection and accumulator discharge piping, and the wall penetration bellows shown on Drawing IC-189. In addition, the open question regarding Class I and II reclassification that occurred in the 1990s needs to be reviewed to ensure that the right classification is applied to the Class I systems and that all of the thermal fatigue analysis, that is required, is completed. Additional NRC inspection is necessary to determine if Station Calculation FC07234 is adequate. The team considered this to be an unresolved item. |
| Site: | Fort Calhoun  |
|---|---|
| Report | IR 05000285/2013013 Section 1R21 |
| Date counted | Mar 31, 2014 (2014Q1) |
| Type: | URI: |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.21 |
| Inspectors (proximate) | J Dixon M Schneider P Elkmann R Kellarg Georgeh Barrett J Hanna J Jacobson J Josey J Polickoski J Robles J Watkins J Wingebach M Hay N Patel R Deese R Haskell R Telson S Laur S Makor T Lighty A Scarbeary C Baron C Henderson C Sanders C Smith D Loveless F Ramirez |
| INPO aspect | |
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Finding - Fort Calhoun - IR 05000285/2013013 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Fort Calhoun) @ 2014Q1
Self-Identified List (Fort Calhoun)
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