Document: NUREG-0800
Document ID: 1085af08-a4b7-4fe7-bfed-ca7a60f2022c
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070734.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
rrent review branch abbreviation, EELB. 42. Current PRB abbreviation Change made to reflect current PRB abbreviation, SRXB. 43. Current review branch abbreviation Change made to reflect current review branch abbreviation, EELB. 44. Current PRB abbreviation Change made to reflect current PRB abbreviation, SRXB. 45. SRP-UDP format item Change made to reflect SPLB responsibility for SAR Chapters 9 and 10. 46. Editorial Added a review interface with SRP Section 9.2.2. SRP Section 15.6.5 contains Acceptance Criteria, Review Procedures and Evaluation Findings with regard to reactor coolant pump seal integrity issues associated with TMI Action Items II.K.3.25 and II.K.3.40 (superseded by II.K.2.16). Reactor coolant pump seal integrity and conformance with these TMI Action Items are reviewed in SRP Section 9.2.2. 47. Current review branch abbreviation Change made to reflect current review branch abbreviation, EMEB. 48. Editorial Corrected references to SRP sections. 49. Current review branch abbreviation Change made to reflect current review branch abbreviation, EMEB. 50. Current PRB abbreviation Change made to reflect current PRB abbreviation, SRXB. 51. Current review branch abbreviation Change made to reflect current review branch abbreviation, EMEB. 52. Current PRB abbreviation Change made to reflect current PRB abbreviation, SRXB. SRP Draft Section 15.6.5 Attachment A - Proposed Changes in Order of Occurrence Item Source Description DRAFT Rev. 3 - April 1996 15.6.5-18 53. Current review branch abbreviation Change made to reflect current review branch abbreviation, EMEB. 54. Integrated Impact No. 579 Included in Areas of Review the requirement that SRXB request HHFB to review operation procedures relative to reactor coolant pump trip following a loss-of- coolant accident based on plant-specific safety evaluations. 55. Editorial Changed to standard lead-in sentence. 56. Editorial Revised designation to 10 CFR 50.46. 57. Integrated Impact No. 578 Deleted "and Appendix K to