ML043280308
| ML043280308 | |
| Person / Time | |
|---|---|
| Site: | Boiling Water Reactor Owners Group |
| Issue date: | 12/03/2004 |
| From: | Bo Pham NRC/NRR/DLPM/LPD4 |
| To: | Gramm R NRC/NRR/DLPM/LPD4 |
| pham b m, nrr dlpm lpdiv-2, 301-415-8450 | |
| Shared Package | |
| ML043280495 | List: |
| References | |
| TAC MC4934 | |
| Download: ML043280308 (4) | |
Text
December 3, 2004 MEMORANDUM TO: Robert Gramm, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Bo Pham, Project Manager, Section 2
/RA by Mel Fields for/
Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 10, 2004, WITH THE BOILING WATER REACTORS OWNERS GROUP (BWROG) TO DISCUSS PROPOSED TOPICAL REPORT (TR) ON RELAXATION OF SAFETY RELIEF VALVE (SRV) POSITION INDICATION REQUIREMENT (TAC NO. MC4934)
On November 10, 2004, the BWROG met with the U.S. Nuclear Regulatory Commission (NRC) staff to discuss its plans to develop and submit a TR which requests for the relaxation of requirements for post accident SRV position indication. A list of participants is attached.
The meeting began with the BWROG giving a presentation on the background of requirements for post accident SRV position indication stemming from the Three Mile Island (TMI) accident and the issuance of Regulatory Guide (RG) 1.97. The BWROG then proposed its case for relaxation of the requirement, mainly on the bases that SRVs do not serve the same boundary integrity role in BWR plants as they do in pressurized-water reactor plants, and that reactor vessel pressure and suppression pool temperature also provide additional position indication in post accident conditions.
The BWROG indicated that some BWR plants would implement this relaxation through changes in their technical specifications, while others would make changes through regulatory commitments.
The NRC staff suggested that the BWROG be clear in its submittal whether it proposes to request relaxation for the requirements or provide alternatives for indication, as mixing the two could confuse its argument. The NRC staff also noted that there have been previous exceptions to requirements imposed from RG 1.97, and that each has been evaluated on a case-by-case basis; the TR that the BWROG intends to submit would be evaluated against the original bases for RG 1.97's safety evaluation. The NRC staff had no regulatory objections to the approach intended by the BWROG.
R. Gramm The BWROG indicated that it intends to submit the TR in approximately one month. At the meeting's conclusion, the NRC staff thanked the BWROG for its participation. The slide presentation is available in ADAMS under Accession No. ML043230434 and is also attached.
Project No. 691 Attachments: As stated cc w/atts: See next page
ML043280308 NRC-001 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME MFields for BPham:mp DBaxley RGramm DATE 12-2-04 12/2/04 12/03/04 E:\\Filenet\\ML043280308.wpd
ATTENDEES MEETING WITH THE BOILING WATER REACTORS OWNERS GROUP (BWROG)
NOVEMBER 10, 2004 BWROG J. Kenny V. Peter NRC B. Pham G. Thomas S. Lewis G. Tartal B. Marcus R. Lobel