JPN-94-040, Informs That Licensee Will Submit Application for TS Amend by 950131 Re Implementation Schedule for Recommendations of GL 89-19 on Reactor Vessel Overfill Protection Tech Specs
| ML20072B960 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/05/1994 |
| From: | Josiger W POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-19, JPN-94-040, JPN-94-40, NUDOCS 9408160327 | |
| Download: ML20072B960 (2) | |
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- Authority August 5,1994 JPN-94-040 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555
SUBJECT:
James A FitzPatrick Nuclear Power Plant Docket No. 50 333 Implementation Scht iule for the Recommendations of Generic Letter 89-19 Reaardina Reactor Vessel Overfill Protection Technical Soecifications.
REFERENCES:
1.
NRC Generic Letter 89-19, " Request for Action Related to Resolution of Unresolved Safety issue A-47 ' Safety Implication of Control Systems in LWR Nuclear Power Plants' Pursuant to 10 CFR 50.54(f)," dated September 20,1999.
- 2. NYPA letter, J. C. Brons to NRC dated April 30,1990 (JPN-90-036) regarding the response to GL 89 Reactor Vessel Overfill Protection.
- 3. NRC letter, J. E. Menning to W. A. Josiger dated June 30,1994,
" Transmittal of the NRC Safety Evaluation for the BWR Owners Group Response to Generic Letter 89-10," Request for Action Related to Resolution of Unresolved Safety issue A-47 ' Safety implication of Control Systems in LWR Nuclear Power Plants' Pursuant to 10 CFR 50.54 (f)", and Request for Additional Information - TAC No. M74943.
Dear Sir:
The NRC staff requested that all BWR plants provide automatic reactor vessel overfill protection and that plant procedures and Technical Specifications reflect provisions for periodically verifying the operability of the overfill protection system (Reference 1). The automatic overfill protection system functions to mitigate main feedwater overfeed events i
during power operation. An analysis performed by BWR Owners Group (BWROG) of the recommendations in GL 89-19 concluded that upgrading the existing automatic overfill i
protection systems would not be warranted. The Authority reviewed the BWROG report and verified that the generic aspects of the report are applicable to the James A FitzPatrick plant.
Reference 2 provided the FitzPatrick plant specific respense to GL 89-19.
The NRC's review of Reference 2 identified that the FitzPatrick Technical Specifications do not govern the availability of the main feedwater overfill protection system
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inst'rumentation (Reference 3). The NRC requested a schedule for submittal of the appropriate Technical Specifications or justify an alternate resolution. The Authority will submit an application for a Technical Specification Amendment by January 31,1995.
If you have any questions, please contact J. A. Gray, Jr.
Very truly your,
/
'fwe <x WM. Josi r Acting Exe ut' e Vice President Nuclear
.neration cc:
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 John Menning Project Directorate 1-1 Division of Reactor Projects - 1/ll U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555
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