ML20101M128

From kanterella
Jump to navigation Jump to search
Forwards Application for Amend to License NPF-3,App A,Ts, Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units
ML20101M128
Person / Time
Site: Davis Besse 
Issue date: 03/29/1996
From: Stetz J
CENTERIOR ENERGY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20101M131 List:
References
2369, NUDOCS 9604050156
Download: ML20101M128 (2)


Text

. _-

! O h

GNTERf0R

,W ENERGY 300 Madison Avenue Jesui P, seser Toledo, OH 43652-0001 Vice President. Nuclear 419-249 2300 Davis-Besse I

Docket Number 50-346 License Number NPF-3 l

Serial Number 2369 l

March 29, 1996 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.

20555

Subject:

License Amendment Application to Revise Technical Specifications 3/4.6.4.4 - Hydrogen Purge System, 3/4.6.5.1 - Shield Building Emergency Ventilation System, and 3/4.7.6.1 - Control Room Emergency Ventilation System Ladies and Gentlemen:

Enclosed is an application for an amendment to the Davis-Besse Nuclear Power Station (DBNPS), Unit 1 Operating License Number NPF-3, Appendix A, Technical Specifications (TS). The proposed changes involve the subject TS regarding the Surveillance Requirements for charcoal filter laboratory testing to revise the testing methodology used to determine operability of the charcoal filters in the engineered safeguards features (ESF) air handling units. Currently, the DBNPS is required to test charcoal in the ESF air handling units per Regulatory Guide 1.52, Revision 2, " Design, Testing, and Maintenance Criteria For Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and l

Adsorption Units of Light-Water-Cooled Nuclear Power Plants," dated March 1978.

l However, the DBNPS has been utilizing an alternative method of testing which, although it provides accurate assurance that these air handling units will perform their design function, it does not literally comply with a strict l

reading of the TS.

The proposed changes incorporate the current testing j

methodology.

1 4

9604050156 960329 53 PDR ADOCK 05000346 P

PDR Operating Componses i t g Cleveland Electnc illurninating

\\

Toledo Edison l

Docket Number 50-346

' f.,icense Number NPF-3 Serial Number 2369 Page 2 The proposed changes are being submitted as an emergency license amendment application. Absent NRC approval of this emergency license amendment application, a plant shutdown is required due to the inability to perform the tests literally required by the TS in the time available. The Action statements of TS 3.6.4.4 and TS 3.9.12 (Refueling Operations - Storage Pool Ventilation) have been entered.

Technical Specification 4.0.3 allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for delaying i

the actions of TS 3.0.3 for TS 3.6.5.1 and TS 3.7.6.1.

These 24-hours will expire at 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br /> on March 29, 1996, requiring completion of the actions of TS 3.0.3.

Accordingly, Toledo Edison requests that the enclosed license amendment application be approved and issued by the NRC as an emergency license amendment in the manner allowed by 10CFR50.91(a), by 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br /> on March 29, 1996.

Toledo Edison has performed the attached environmental assessment and determined that the proposed amendment, if approved, will have no signifi-cant impact on the environment or irreversible environmental consequences.

Toledo Edison will evaluate ASTM D 3803-1989 " Standard Test Methcds for Radioiodine Testing of Nuclear-Grade Gas-Phase Adsorbents," for incorporation into the DBNPS Technical Specifications.

Should you have any questions or require additional information, please contact Mr. James L Freels, Manager - Regulatory Affairs, at (419) 321-8466.

Very truly yours, DHL/llh Enclosure cc:

W. L. Axelson, Director, NRC Region III, Division of Reactor Projects L. L. Gundrum, DB-1 NRC/NRR Project Manager i

Dr. Gail H. Marcus, NRC Project Director H. J. Miller, Regional Administrator, NRC Region III S. Stasek, DB-1 NRC Senior Resident Inspector J. R. Williams, Chief of Staff, Ohio Emergency Management l

Agency, State of Ohio (NRC Liaison) l Utility Radiological Safety Board i

i i

i

,