ML043030277
| ML043030277 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 06/29/2004 |
| From: | Lobel R, Stutzke M Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| FOIA/PA-2004-0362 | |
| Download: ML043030277 (16) | |
Text
CREDIT FOR ACCIDENT PRESSURE IN CALCULATED NPSH FOR ECCS AND CONTAINMENT HEAT REMOVAL PUMPS Richard Lobel Marty Stutzke June 29, 2004
Purpose of Briefing TO INFORM THE EDO OF THE STATUS OF THIS ISSUE TO OBTAIN CONCURRENCE WITH (1) THE PROPOSED POSITION FOR FUTURE REVIEWS, AND (2) PROPOSED ACTIONS Definition of Available NPSH NPSH AVAILABLE = hATM + hSTATIC - hLOSSES - hVAPOR where hATM = pressure of containment atmosphere hSTATIC = pressure due to height of water above pump suction hLOSSES = pressure losses in piping, fittings, and screens hVAPOR = vapor pressure of pumped fluid NRC Guidance On NPSH 1970 Regulatory Guide 1.1 Guidance on NPSH
....adequate NPSH is provided to system pumps assuming maximum expected temperatures of pumped fluids and no increase in containment pressure from that present prior to postulated LOCAs.
Some reactors licensed with overpressure credit 1974 Regulatory Guide 1.82 Guidance on PWR Sump Design The available surface area in determining the design coolant velocity [at the entrance to the sump screen] should be based on one-half of the free surface area of the ... inner screen...
NRC Guidance On NPSH (CONT.)
1981 SRP 6.2.2 Rev 4 Containment Heat Removal Systems for BWRs: hatm 0 for PWRs: hatm = hvAPoR, or, hatm = 0 "NPSH analysis will be acceptable if it is done in accordance with ...Regulatory Guide 1.1, i.e., is based on maximum expected temperature of the pumped fluid and with atmospheric pressure in containment."
SRP 6.2.2 allows overpressure credit for subatmospheric containments during the first hour following a LOCA.
NRC Guidance On NPSH (CONT.)
1985 GL 85-22 (GSI A-43) LOCA Debris Guidance h10,, increases No backfit; consider for modifications Regulatory Guide 1.82 Rev 1 Issued.
Fibrous insulation debris should be considered as uniformly distributed over the available debris screen area Did not address containment conditions assumed in determining NPSH, only design of sumps and ECCS suction strainers NRC Guidance On NPSH (CONT.)
1996 BULLETIN 96-03 BWR ECCS STRAINER BLOCKAGE hioss increases Result of the 1992 Barseback event (strainer blockage).
BWRs should Install suction strainers. Results in greater pressure losses Increased suction losses due to larger strainers and consideration of debris NRC Guidance On NPSH (CONT.)
1997 GL 97-04 Request for information on NPSH calculations for containment heat removal and ECCS pumps including credit for containment overpressure.
Prompted by credit for overpressure w/o prior NRC review and approval.
Reviews of all operating reactors performed.
Criteria developed for the review allowed credit for containment overpressure. These criteria were not documented at this time.
NRC Guidance On NPSH (CONT.)
All BWR NPSH calculations revised as a result of Bulletin 96-03. Some BWRs received credit for overpressure. Some BWRs licensed with credit for overpressure and the credit for overpressure was increased. Some BWRs did not need overpresssure in order to comply with Bulletin 96-03.
2003 Bulletin 2001-03 Guidance on PWR Sump Blockage Some PWR licensees may request credit for containment overpressure to compensate for higher head losses RG 1.82 Rev 3 Guidance ECCS and containment heat removal systems should be designed so that sufficient available NPSH is provided to system pumps assuming maximum expected temperature and no increase in containment pressure from that present prior to LOCA For certain operating reactors for which the design cannot be practicably altered, conformance with the previous position may not be possible. In these cases, no additional containment pressure should be included in NPSH analyses than necessary to preclude pump cavitation.
For certain operating reactors for which the design cannot be practicably altered, credit may be taken for pump tests which demonstrate that a cavitating pump will continue to deliver the design basis flow rate; The time period is no longer than that of the test.
Risk Consideration A risk calculation is performed using realistic input values and assumptions.
Vermont Yankee personnel indicate that when using realistic input and assumptions, no credit for containment overpressure is required.
Therefore, the licensee states that the risk increase is negligible.
^11-
Risk Consideration (Cont)
A staff calculation using the VY IPE and SPAR model calculated the change in CDF given that containment pressure is required This was determined as (Large LOCA frequency)(Probability of failure of containment isolation)
It was assumed that loss of overpressure is equivalent to loss of ECCS pumps and therefore core damage.
ACDF = 1.3E-07 = ALERF THIS IS SMALL AND ACCEPTABLE ACCORDING TO RG 1.174 Postulated Accidents for which Overpressure Credit Has Been Allowed LARGE BREAK LOCA ATWS STATION BLACKOUT APPENDIX R SAFE SHUTDOWN FIRE Reactors Which Have Received Overpressure Credit Beaver Valley Unit 1 (PWR)
Browns Ferry Units 2 and 3 (BWR Mark I Containment)
Cooper (BWR Mark I Containment)
Dresden Units 2 and 3 (BWR Mark I Containment)
Duane Arnold (BWR Mark I Containment)
FitzPatrick (BWR Mark I Containment)
Fort Calhoun (PWR)
Hatch Units 1 and 2 (BWR Mark I Containment)
Monticello (BWR Mark I Containment)
North Anna Units 1 and 2 (PWRs)
Oconee Units 1, 2 and 3 (PWRs)
Oyster Creek (BWR Mark I Containment)
Peach Bottom Units 2 and 3 (BWR Mark I Containment)
Pilgrim (BWR Mark I Containment)
Quad Cities Units 1 and 2 (BWR Mark I Containment)
Surry Units 1 and 2 (PWRs)
Proposed Modified Position Credit for overpressure is allowed when a conservative calculation demonstrates that sufficient containment pressure is available No test of "necessity" or specific cause of the NPSH deficiency is part of the criteria for allowing credit for containment overpressure.
No limit is placed on the amount of pressure that may be assumed available as long as the pressure is determined conservatively.
Risk considerations to be determined as part of Vermont Yankee review.
Plan For Re-evaluating Credit For Containment Accident Pressure
- 1. Withdraw RG 1.1
- 2. Modify RG 1.82 Rev 3 to reflect the modified position
- 3. Modify SRP 6.2.2 to reflect modified position