ML20034E412
| ML20034E412 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/17/1993 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20034E413 | List: |
| References | |
| 2115, NUDOCS 9302260124 | |
| Download: ML20034E412 (2) | |
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'l Donald C. Shelton 300 Madison Avenue -
1 Vice President Nuclear -
Toledo, OH 436524)01 i
Davis-Besse (419)249-2300 y
1' Docket Number 50-346 License Number NPF-3 Serial Number 2115 February 17, 1993
,j United States Nuclear Regulatory Commission Document Control Desk 1
Vashington, DC 20555 Subj ect s. Supplemental Information for License-Amendment. Request (LAR) to Delete Technical Specification (TS).3/4.9._9, Refueling Operations - Containment Purge and Exhaust Isolation System t:
-and its Bases, and. Revise TS 3/4.3.2, safety-System-
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Instrumentation - Safety Features Actuation System (SFAS)
Instrumentation and TS 3/4.9.4, Refueling Operations -
l Containment Penetrations and its-Bases
-i Gentlemen:
On July 28, 1992, Toledo Edison (TE) submitted an application (Serial.
Number 2051) for an amendment to the Davis-Besse Nuclear Power Station I
(DBNPS) Unit Number'1 Operating License Number NPF-3, Appendix A, Technical Specifications (TS) 3/4.9.9,-Refueling Operations -
Containment Purge and Exhaust Isolation System and its Bases, TS
-3/4.3.2, Safety System Instrumentation -. Safety Features Actuation ~-
.j System Instrumentation, and TS 3/4.9.4,-Refueling. Operations -
Containment Penetrations and.its Bases.
As agreed in a meeting with the.NRC. Staff on December 15, 1992, and confirming information.provided during a telephone call with the NRC Staff on January-14, 1993,'TE provides the following supplemental information:
1.
Regarding power supplies, the RE 50520 monitor is powered from-non-essential 120VAC uninterruptible instrument distribution panel YAU.. The associated flov' pump is povered'from'non-essential ^480VAC' HCC E23A.
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Dockat Numb 2r 50-346' Liccnsa Numbar NPF-3 Ssrial Numbsr 2115-o Page 2 2.
Regarding radiological effluent data for the last refueling outage (Seventh Refueling Outage (7RFO)), during the cooldown into 7RF0, a containment purge batch release commenced after entry into Mode 5 (cold shutdown), and lasted approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and 39 minutes.
A total of 151 Curies of noble gases were released, of which approximately 80 percent was xenon-133. The gamma air dose for this release was 2.52 E-03 mrad, or 0.05% of the quarterly limit from the DBNPS Offsite Dose Calculation Manual (ODCH). The containment purge system continued to operate while the plant was in Mode 6 (refueling), to control temperature and humidity.
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review of the station vent analysis da % for this period showed a slight statistical increase above norma'. background levels.
However, the radiation levels were a small fraction of the ODCH limits.
3.
The attached corrected figure, as discussed during the December 15, 1992 meeting, replaces the containment purge system sketch provided "for information only" as an attachment to the July 28, 1992 letter.
4.
To clarify information provided in the July 28, 1992 letter, in the event of high airborne radiation inside containment during core alterations or fuel movement, as detected by SFAS area radiation moni tors.
- ontainment purge and exhaust valves CV 5004, CV 5005, CV 5006, CV 5007, CV 5008, CV 5009, CV 5016, and CV 5021 receive SFAS Level 1 signals to close. The containment purge supply and exhaust
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fans do not receive a direct SFAS signal, but will stop when.the above-mentioned valves close. This information was discussed at the December 15, 1992 meeting.
This information does not affect the Significant Hazards Consideration previously provided by Toledo Edison in its license amendment application of July 28, 1992.
Should further information be required, please contact Mr. Robert V. Schrauder, Manager - Nuclear Licensing at (419) 249-2366.
Very truly yours, HKL/lkg ec:
A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC Senior Project Manager S. Stasek, DB-1 NRC Senior Resident Inspector J. R. Villiams, Chief af Staff, Ohio Emergency Management Agency State of Ohio (NRC Liaison)
Utility Radiological Safety Board
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