NRC-98-0029, Forwards Markup Copy & Retyped Version of Sheet 2 of Table 3.3 Which Deletes RCS Recirculation Flow Trip Functions
| ML20199G214 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/28/1998 |
| From: | Gipson D DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20199G219 | List: |
| References | |
| CON-NRC-98-0029, CON-NRC-98-29 NUDOCS 9802040240 | |
| Download: ML20199G214 (3) | |
Text
,
Douglu R. Glpwn Senior Vic e President, Nuclear Generation
-e rermi:1 M% North thda llwy, Nenn Mkhigan 481M Tit 311rM1 dol fa: alltM 4172 Detroit Edison January 28,1998 d
NRC-98-0029 U. S. Nuclear Regulatory Commission
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Attention: Document Control Desk Washington, D C 20555-0001
References:
1)
Fermi 2 Docket No. 50-341 License No. NPF-43 2)
Detroit Edison Letter to NRC, NRC-97-0105," Proposed Technical Specification Change (License Amendment)-
Neutron Monitoring System," dated Deceraber 10,1997 3)
Licensing Topical Report," Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC-PRNM)
Retrofit Plus Option Ill Stability Trip Function," Volumes i and ?, NEDC-32410P-A, October 1995 a
Subject:
"roposed Technical Specification Change (License Amendment)-
Neutron Monitorine System Cpr ection Pace Reference 2 proposed revisions to Fe:an 2 Technical Specifications (TS)in support of the planned replacement of the power range portion of the Neutron Monitoring System. Because the Power Range Neutron Monitaring system (PRNM) will include Reactor Coolant System Recirculation Flow.,ignal processing which is currently accomplished using separate hardware, Reference 2 described the need to revise TS to consolidate these functions. This would be accomplished for Control Rod Block Instrumentation by revising TS Tables 3.3.6-1,33.6-2, and 4.3.6-1 to add the Flow Upscale control rod block in the Average Power Range Monitor (APRM) trip functions and to delete the Reactor Coolant System Recirculation Flow Upscale trip.
gh The Inoperative trip is also deleted from the Reactor Coolant System Recirculation Flow trips because this function is included in the APRM Inoperative trip, and the Comparator trip is deleted in accordance with Section 3.2.11 of Reference 3.
However, Reference 2 did not include sheet 2 of Table 3.3.6-2 (TS page 3/4 3-44a) to delete the Reactor Coolant System Recirculation Flow trip functions. Therefore, a mark-up copy of this sheet and a retyped version are provided with this letter
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i NRC 98 0029 Page 2 Detroit Edison has evaluated the proposed Technical Specifications against the criteria of 10CFRSO.92 and determined that no significant hazards consideration is involved. The significant hazards evahiation provided in Reference 2 remains valid for this correction. The Fermi 2 Onsite Review Organization has reviewed and recommended approval, and the Nuclear Safety Review Group has reviewed the proposed Technical Specifications and concurs with the enclosed determinations. In accordance with 10CFR50.91, Detroit Edison is providing a copy of this letter to the State of Michigan.
i If you have any questions, please contact Mr. Joseph Conen at (734) 586-1960.
i Sincerely, Enclosure cc:
A. B. Beach B. L. Burgess G. A. Ilarris A. J. Kugler Supervisor, Electric Operators, Michigan Public Service Commission w.
USNRC NRC-98-0029 Page 3 I, DOUGLAS R. GlPSON, do hereby affirm that the foregoing staMments are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
9 DOUGLAS If GIPSON Senior Vice President Nuclear Generation l
Onthis day of 44W&
A998 before me personally appeared Douglas R. Gipson, being thfj duly sworfand says that he execu'ed the foregoing as his free cet and deed.
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k MaAl b 0 M b Notary Public ROSAGE A. MA Ng%[3gyggj,3jy[,
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