ML20217Q218
| ML20217Q218 | |
| Person / Time | |
|---|---|
| Issue date: | 05/05/1998 |
| From: | Marlone Davis NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| GL-97-04, GL-97-4, NUDOCS 9805070282 | |
| Download: ML20217Q218 (17) | |
Text
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UNITED STATES :
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~ ' NUCLEAR REGULATORY COMMISSION 3
E, WASHINGTON, D.C. enmas mi
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May 5, 1998 s
- MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic lasues and Environmental Projects Branch' Division of Reactor Program Management, NRR FROM:
. Michael J. Davis', Project Manager Generic issues and Environmental Projects Branch [Np Division of Reactor Program Management, NRR
SUBJECT:
SUMMARY
OF APRIL 16,1998, MEETING BETWEEN THE NRC STAFF AND THE BWROG NPSH COMMITTEE On April 16,1998, representatives from the staff met with members of the Boiling Water Reactor' Owners Group Net Positive Suction Head (BWROG NPSH) Committee in Orlando, Florida to discuss issues pertaining to responses to Generic Letter (GL) 97-04, " Assurance
. of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps," the use of containment overpressure, and future containment overpressure license amendments. The staff presentation is provided as Attachment 1 and
. the list of attendees is provided as Attachment 2.
In the staff presentatien, the history of credit for containment overpressure and its relationship to NPSH for emergency core cooling system (ECCS) and containment heat removal pumps was discussed. This discussion included concems addressed by the -
Advisory Committee on Reactor Safeguards (ACRS), past licensing credit for containment osrpressure, and the staff expectations for a containment overpressure license
. amendment submittal. The staff also presented its categorization of licensee responses to Generic Letter 97-04. The four categories included 1) the GL 97-04 response was acceptable, 2) the GL 97-04 response was inadequate, 3) the GL 97-04 response was good -
' but needs some clarification, and 4) the GL 97-04 response indicates that a potential
- unreviewed safety question (USQ) exists.
The staff presentation caused a significant amount of beneficial discussion which resulted in the identification of several issues. The first was how the minimum overpressure profile should be used to support the necessary backpressure to prevent pump damage. It was readily agreed that when performed correctly, the minimum pressure analysis should represent the minimum containment pressure possible short of a major loss of containment
- air.
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it was the_ feeling of several members of the committee that the licensee should be able to
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- ,O # take full credit for the pressure below the minimum pressure profile. However, the staff took the position that only'the backpressure to prevent pump cavitation should be requested due
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to the fact that the closer to the minimum pressure curve, the more justification is needed MThe committee countered by.saying that they did not want to come to the staff with every small change in backpressure credit. The staff concluded that this suggestion also had WO$$
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L merit.' As a result, it was concluded that a slight increase in backpressure credit would be '
considered for this purpose.
After discussion concoming the status of the GL 97-04 responses, the staff asked if the individual licensees intended to update their responses if errors were identified or if added information was available that would be useful in understanding their NPSH status. Their response was that they would get back to us on their response.
As a result of the meeting, the staff was requested to consider and if appropriate, respond to the following BWROG concems.
1.
- Clarification of what the staff expects with regards to NPSH in the NRC Bulletin 96-03," Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors," response.
2.
Will Bulletin 96-03 be revised to clarify that the staff expects the new strainers to be installed by the end of December 1998 with the paperwork associated with Bulletin 96-03 to be completed soon after December 19987 3.
When evaluating a containment overpressure license amendment, the BWROG believes that is appropriate for the staff to approve credit for containment overpressure slightly above the required to account for modifications to the plant design. This could include changes such as an impeller modification, a valve change out, or coating issues. Approval of a slight margin would allow licensees to make modifications which could cause a slight increase in reliance of containment overpressure without submitting another license amendment, saving both staff and licensee resources. The BWROG understood that any modification that would place the reliance of containment overpressure above the approved credit limit would require -
. another license amendment.
The staff informed the committee that the appropriate staff members would be notified regarding items one and two above. The staff expects that a response to the committee will be generated in the near term.' The staff believes this meeting was beneficial to the staff and the BWR. industry, saving both time and resources.
Attachments: As stated
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~ T. Essig May 5, 1998 merit.' As a result, it was concluded that a slight increase in backpressure credit would be considered for this purpose.
After discussion concoming the status of the GL 97-04 responses, the staff asked if the
. individual licensees intended to update their responses if errors were identified or if added_.
information was available that would be useful in understanding their NPSH status. Their response was that they would get back to us on their response.
As a result of the meeting, the staff was requested to consider and if appropriate, respond to the following BWROG concems.
1.
Clarification of what the staff expects with regards to NPSH in the NRC Bulletin 96-03," Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water. Reactors," response.
2.
Will Bulletin 96-03 be revised to clarify that the staff expects the new strainers to be installed by the end of December 1998 with the paperwork-associated with Bulletin 96-03 to be completed soon after December 19987 3.
When evaluating a containment overpressure license amendment, the :
BWROG believes that is appropriate for the staff to approve credit for-
- containment overpressure slightly above the required to account for.
modvications to the plant design. This could include changes such as an impe.ler modification, a valve change out, or coating issues. Approval of a slight margin would allow licensees to make modifications which coo'd cause a slight increase in reliance of containment overpressure without sd.ntting another license amendment, saving both staff and licensee resources. The BWROG understood that any modification that would place the reliance of
. containment overpressure above the approved credit limit would require another license amendment.
-s The staff informed the committee that the appropriate 1 staff members would be notified regarding items one and two above. The staff expects that a response to the committee will be generated in the near term. The staff believes this meeting was beneficial to the staff.
. and the BWR industry, saving both time and resources.
- Attachments: As stated
- DISTR'9UTION
- See attached page 4
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l List of Attendees Names Organization Peter Breglio NYPA - J.A. FitzPatrick
{
Paul Swinbume NYPA - J.A. FitzPatrick j
Carl Fagio Duke Engineering & Services Bruce Slifer Vermont Yankee.
J Paul Hansen GPUN - Oyster Creek Bob Bryer Detroit Edison - Fermi 2 Richard Tripp CP&L - Brunswick Skip Denny PECO Nuclear Mike McDermott IES Utilities - Duane Arnold Steve Shipman SNC - Hatch Bhau Shete Comed - Dresden Michael Jones NMPC - Nine Mile Point H. Lee Williams TVA-Browns Ferry Wendall Fiock GE Phil Harizi BECo - Pilgrim Jairo Pinzon NUS Information Services Kerri Kavanagh US NRC - Reactor Systems Branch Jack Kudrick US NRC - Containment Systems Branch i
i 16 4
i
i Project No. 691 Boiling Water Reactor Owners Group cc:
Thomas J. Rausch, Chairman Warren W. Glenn Boiling Water Reactor Owners Group Southern Nuclear / Georgia Power Commonwealth Edison Company E.I. Hatch Nuclear Plant Nuclear Fuel Services '
' P.O. Box 1295 M/C B052 1400 Opus Place,4th Floor E1Will
- Birmingham, AL 35201 Downers Grove, IL 60515 Carl D. Terry Dennis B. Townsend Vice President, Nuclear Engineering
- GE Nuclear Energy Niagara Mohawk Power Corporation
. M/C 182 Nine Mile Point-2 175 Curtner Avenue P.O. Box 63 San Jose, CA 95125 Lycoming, NY 13093 Drew B. Fetters Thomas A. Green PECO Energy GE Nuclear Energy Nuclear Group Headquarters Mail Code 182 MC 62C-3 175 Curtner Avenue 965 Chesterbrook Blvd.
' San Jose, CA 95125 Wayne, PA 19087 John Hosner K.K. Sedney Commonwealth Edison GE Nuclear Energy Executive Towers,4th Floor 175 Curtner Ave, M/C 182 1400 Opus Place San Jose, CA 95125 Downers Grove,IL 60515 George T. Jones Pennsylvania Power & Light MC A6 Two North Ninth Street Allentown, PA 18101 Lewis H. Sumner Southern Nuclear / Georgia Power E l. Hatch Nuclear Power Plant U.S. Route 1 North, Box 439 Baxley, GA 31513 L. A. England Entergy Operations Inc.
PO Box 31995 Jackson, MS 39286
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List of Attendees Names Organization Peter Breglio NYPA - J.A. FitzPatrick Paul Swinburne NYPA= J.A. FitzPatrick Carl Fagio -
Duke Engineering & Services Bruce Slifer-.
Vermont Yankee Paul Hansen GPUN - Oyster Creek = _
Bob Bryer.
Detroit Edison - Fermi 2 Richard Tripp CP&L - Brunswick -
Skip Denny PECO Nuclear-
.j.
Mike McDermott lES Utilities ; Duane Arnold '
Steve Shipman SNC - Hatch Bhau Shete Comed - Dresden Michael Jones' NMPC - Nine' Mile Point '
H. Lee Williams TVA - Browns Ferry
! Wendall Fiock GE Phil Harizi BECo - Pilgrim Jairo Pinzon NUS Information Servires
'Kerri Kavanagh US NRC - Reactor Systems Branch
' Jack Kudrick US NRC - Cont &,inent Systems Branch L
l=
l 16
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.s.
Project No. 691:
' Boiling Water Reactor Owners Group l
- cc: : Thomas J. Rausch, Chairman Warren W. Gleni:
Boiling Water Reactor Owners Group Southern Nuclear / Georgia Power -
Commonwealth Edison Company E.1. Hatch Nuclear Plant Nuclear Fuel Services P.O. Box 1295 M/C B052 L1400 Opus Place,4th Floor ETWill Birmingham, AL 35201 Downers Grove, IL 60515 e
Carl D. Terry Dennis B. Townsend Vice President,' Nuclear Engineering GE Nuclear Energy -
Niagara Mohawk Power Corporation M/C 182 Nine Mile Point-2 175 Curtner Avenue P.O. Box 63'
- San Jose, CA 95125 -
Lycoming, NY,13093 Drew B. Fetters
' Thomas A. Green
_ PECO Energy
' GE Nuclear Energy Nuclear Group Headquarters Mail Code 182 MC 62C-3 175 Curtner Avenue 965 Chesterbrook Blvd.
San Jose, CA 95125 j
Wayne, PA 19087 John Hosner.
. K.K. Sedney -
Commonwealth Edison _
GE Nuclear Energy Executive Towers,4th Floor.
175 Curtner Ave, M/C 182 1400 Opus Place ~
' San Jose,' CA 95125 -
Downers Grove, IL 60515 -
George T.' Jones Pennsylvania Power & Light MC A6-1 Two North Ninth Street Allentown, PA 18101 -
Lewis H. Sumner -
' Southem Nuclear / Georgia Power
. E. L Hatch Nuclear Power Plant U.S. Route 1 North,' Box 439 -
Baxley, GA 31513 L. A. England Entergy Operations Inc.
l
. PO Box 31995
[
Jackson, MS 39286
.