Loren Data's SAM Daily™

FBO DAILY ISSUE OF AUGUST 25, 2007 FBO #2098
MODIFICATION

U -- NEW REACTOR TRAINING- ABWR DESIGN

Notice Date

8/23/2007
 

Notice Type

Modification
 

NAICS

611430 — Professional and Management Development Training
 

Contracting Office

Nuclear Regulatory Commission, Office of Administration, Division of Contracts, 11545 Rockville Pike, Rockville, MD, 20852-2738, UNITED STATES
 

ZIP Code

00000
 

Solicitation Number

07-716
 

Response Due

9/10/2007
 

Archive Date

9/25/2007
 

Description

AMENDMENT NO. 04 - THE PURPOSE OF THIS AMENDMENT IS TO PROVIDE RESPONSES TO QUESTIONS SUBMITTED BY OFFERORS. 1. Question: For the training outline provided the technical specifications refer Condition I, II, III and IV events. The following is provided as requested: I'm not familiar with the "Condition I, II, III, IV" terminology. However, I suspect it relates to the following event classifications which are "defined" in subsection 15A.2.2 of the NSOA for the ABWR (see attached ABWR DCD/Tier 2, Appendix 15A): (a) Normal (Planned) Operations (b) Moderate Frequency Incidents (Anticipated (Expected) Operational Transients) (c) Infrequent Incidents (Abnormal (Unexpected) Operational Transients) (d) Limiting Faults (Design Basis (Postulated) Accidents) (e) Special (Hypothetical) Events Specific events in each of these classes are identified in tables 15A-8 thru -12. I recommend that you the NRC contact to clarify their expectations for that subtopic. Response: NRC Regulatory Guide 1.70 Revision 3 address these as initiating events (for example see section 15.x.x. Event Evaluation; where these are listed as (a) Incidents of moderate frequency, (b) Infrequent incidents, and (c) limiting faults). American National Standard N18.2-1973 section 2.1 provide definitions of Condition I: Normal Operations, Condition II: incidents of Moderate Frequency, Condition III: Infrequent Incidents, and Condition IV: Limiting Faults and gives more specific details. ANSI/ANS-51.1-1983 categorizing schemes is based on frequency of occurrence and use Plant Condition PC1 through PC5. Terminology used in NRC certified Design Control Document (DCD) will be acceptable. 2. Question: Is there any way to request an extension of the submittal deadline? Response: The close date for this combined synopsis/solicitation is extended from September 10, 2007 to September 13, 2007 by 12:00 noon (local time). The hard copies are due on September 14, 2007 by 1:00 p.m. ALL OTHER TERMS AND CONDITIONS REMAIN UNCHANGED.
 

Place of Performance

Address: U.S. Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD, , , , , ,

Zip Code: 20852-2738

Country: UNITED STATES
 

Record

SN01383447-W 20070825/070823222820 (fbodaily.com)
 

Source

FedBizOpps Link to This Notice
(may not be valid after Archive Date)

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