ML071920004
| ML071920004 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/11/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | |
| Wengert, Thomas J, NRR/DORL, 415-4037 | |
| Shared Package | |
| ML071920002 | List: |
| References | |
| EA-02-026, TAC MD4498 | |
| Download: ML071920004 (3) | |
Text
ENCLOSURE 1 REVISED PAGE OF FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by the date of the letter issuing this page and contains marginal lines indicating the areas of change.
REMOVE INSERT License NPF-3 License NPF-3 Page 6a Page 6a
- 6a -
2.C(7) Steam Generator Tube Circumferential Crack Report Following each inservice inspection of steam generator tubes, the NRC shall be notified by FENOC of the following prior to returning the steam generators to service:
a.
Indication of circumferential cracking inboard of the roll repair.
b.
Indication of circumferential cracking in the original roll or heat affected zone adjacent to the tube-to-tubesheet seal weld if no reroll is present.
c.
Determination of the best-estimate total leakage that would result from an analysis of the limiting LBLOCA based on circumferential cracking in the original tube-to-tubesheet rolls, tube-to-tubesheet reroll repairs, and heat affected zones of seal welds as found during each inspection.
FENOC shall demonstrate by evaluation that the primary-to-secondary leakage following a LBLOCA, if any, as described in Appendix A to Topical Report BAW-2374, July 2000, continues to be acceptable, based on the as-found condition of the steam generators. For the purpose of this evaluation, acceptable means that a best estimate of the leakage expected in the event of a LBLOCA would not result in a significant increase of radionuclide release (e.g., in excess of 10 CFR Part 100 limits). This is required to demonstrate that adequate margin and defense-in-depth continue to be maintained. A written summary of this evaluation shall be provided to the NRC within three months following completion of the steam generator tube inservice inspection.
2.C(8) Mitigation Strategy License Condition l
l The licensee shall develop and maintain strategies for addressing large fires and l
explosions and that include the follow key areas:
l l
(a)
Fire fighting response strategy with the following elements:
l 1.
Predefined coordinated fire response strategy and guidance l
2.
Assessment of mutual aid fire fighting assets l
3.
Designated staging areas for equipment and materials l
4.
Command and control l
5.
Training of response personnel l
l (b)
Operations to mitigate fuel damage considering the following:
l 1.
Protection and use of personnel assets l
2.
Communications l
3.
Minimizing fire spread l
4.
Procedures for implementing integrated fire response strategy l
5.
Identification of readily-available pre-staged equipment l
6.
Training on integrated fire response strategy l
7.
Spent fuel pool mitigation measures l
l (c)
Actions to minimize release to include consideration of:
l 1.
Water spray scrubbing l
2.
Dose to onsite responders l
l Amendment No. 252 Revised by letter dated July 11, 2007