ML25273A410
| ML25273A410 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/29/2025 |
| From: | Vistra Operations Company |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML25273A408 | List: |
| References | |
| L-25-182 | |
| Download: ML25273A410 (1) | |
Text
Attachment 1 L-25-182 Information Removed from the PNPP USAR (Page 1 of 1)
In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees periodically report a brief description of information removed from the Updated Safety Analysis Report (USAR) and the basis for its removal. The following provides a summary of the information removed from the PNPP USAR and the basis for removal.
- 1. Removed references to red and black pen colors from Figure 11.5-1, Sheet 5. The pen colors were associated with the original paper chart recorder, which was replaced with an equivalent digital model. The pen colors are descriptive information that is not important to provide an understanding of the plant's design and operation from either a general or system functional perspective.
- 2. Removed excessive detail from USAR Section 8.3.1.1.2.9b.1. This section describes protective relaying and protective device setting criteria for Class 1 E 4,160 and 480-volt switchgear. The description of the time delay setting of the instantaneous ground overcurrent relay as being 2 cycles is removed as excessive detail that is not important to the description of the facility or presentation of its safety analysis and design basis. The mention of a fixed time delay setting remains for clarity; however, the specific device setting is removed.
Commitment Number/
Source I Date PY-L02384 PY-CEI/NRR-2320L 8/31/1998 L-25-182 Regulatory Commitment Change Summary Report (Page 1 of 1)
Commitment Description Change Reason for Change Complete an appropriate Closed.
The original commitment was engineering analysis made in response to a request associated with a postulated for additional information pipe rupture in the nuclear regarding resolution to Generic closed cooling system or Letter (GL) 96-06, "Assurance of modify procedure steps Equipment Operability and appropriately in lieu of the Containment Integrity During engineering analysis.
Design Basis Accident Conditions," issues. The committed action was to be completed by June 1, 1999. By letter dated September 16, 1999, the final resolution of GL 96-06 issues was submitted to the NRC, including a description of the completion of the action required by this commitment.
This was a one-time action that should have been closed when it was completed in 1999.