ML20149F085
| ML20149F085 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/18/1997 |
| From: | Curry D AFFILIATION NOT ASSIGNED |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20149F090 | List: |
| References | |
| NUM2-PPNR-0316, NUM2-PPNR-316, NUDOCS 9707220034 | |
| Download: ML20149F085 (2) | |
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PARSONS Parsons Power Group Inc. 2675 Morgantown Road a Reading, Pennsyh,ania 19607 * (610) 855-2000 Fax: (610) 855-2001
' i July 18,1997 Docket No. 50-336 Parsons NUM2-PPNR-0316-L U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Millstone Nuclear Power Station Unit No. 2 Independent Corrective Action Verification Procram UCAVP)
. Gentlemen:
In accordance with Section IV.2.a of the NRC ICAVP Oversight Inspection Plan, the NRC will approve Critical Design Characteristics (CDCs) to be verified by the ICAVP contractor. Functional / System level CDCs will be developed by the Millstone Unit 2 ICAVP Accident Mitigation System Review (AMSR)
Program. The CDCs will be compared with the "as-documented" design and will be validated as present in the "as-installed" plant configuration. This letter forwards the Critical Design Characteristics for the FSAR Chapter 14 overcooling events for NRC approval.
The CDCs will be developed from the information contained in FSAR Chapter 14 and submitted for NRC approval, as follows:
Submittal 1 - Overcooling Events Submittal 2 - Reactor Coolant Pressure Boundary Events Submittal 3 - Balance of the Chapter 14 events.
The following method was used to develop the overcooling event CDCs. Five (5) overcooling events are described in section 14.1 of the FSAR. Each event was reviewed and design inputs extracted. Each design input was assigned to one or more Critical Safety Functions (CSFs). The CSF diagrams were then used to develop functional / system level CDCs for each event.
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9707220034 970719 PDR ADOCK 05000336 P
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U.S. Nuclear Regulatory Commission NUM2-PPNR-0316-L July 18,1997 Page 2 Note that section 14.1 provides the Reactor Coolant System analysis for the Main Steam Line Break
(.MSLB) events. The containment analysis for the MSLB events is provided in FSAR section 14.8. The CDCs associated with the MSLB contaimnent response will be included with the Reactor Coolant Pressure 4
' Boundary CDC submittal.
NRC approval of the overcooling event CDC's is requested.
Please call me at (610) 855-2366 if you have any questions.
j Sincerely, l
Daniel L. Curry Parsons ICAVP Project Director DLC:djv i
Attachments:
, - Overcooling Event CDCs j - Critical Safety Function Diagrams.(4) i - Tier-2 System Boundary Diagrams (9)
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cc:
E. Imbro (2) - USNRC H. Eichenholz - USNRC i
R. Laudenat - NNECo i
J. Fougere - NNECo Rep. Terry Concannon - NEAC 3
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