ML20062D487

Summary of 901015 Meeting W/Util Re Revising of Fuel Handling Accident in Updated Sar,Per Air Bypassing Spent Fuel Pool Charcoal Filter.Conclusion That No License Action Required Not Valid.Attendees List,Agenda & Viewgraphs Encl

ML20062D487
Person / Time
Site:	Fort Calhoun
Issue date:	11/07/1990
From:	Bournia A Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9011130266
Download: ML20062D487 (20)

Text

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'g UNITED STATES

[ r NUCLEAR REGULATORY COMMISSION WA$HINGTON, O C. 205LS k . . . . . )i g November 7, 1990

. Docket No. 50 285 l

LICENSEE: Omaha Public Power District FACILITY: Fort Calhoun Station, Unit 1

SUMMARY

OF MEETING TO DISCUSS THE REVISING OF THE FUEL HANDLING ACCIDENT IN THE UPDATED SAFETY ANALYSIS REPORT AS A RESULT OF AIR BY-PASSING THE SPENT FUEL POOL CHARC0AL FILTER On October 15, 1990, NRR staff members met with the licensee to discuss the revising-of the fuel Handling Accident (FHA) in Fort Calhoun's Updated Safety Analys's Report (USAR) as a result of the Spent Fuel Pool (SFP) charcoal filter by-pus. Enclosure 1 is a listing of the meeting attendees.

The licensee made an overview presentation on this issue as shown in Enclosure 2 The licensee indicated that during a recent refueling outage, it was discovered that in-leakage of air through a roll-up door to the Auxiliary Building, where the SFP is located, could disrupt airflow patterns and prevent suction of

• radiological releasos from the SFP through its charcoal filter, VA-66. On January 1,1990, the licensee performed a test which found air by-passing the SFP charcoal filter. Based on this test, the licensee determined that the plant was not within the design basis established ty the USAR.. The analysis in the USAR assumes that in the event of an FHA in the SFP, all the air in the vicinity of the pool-passes through the charcoal filter. This item was also reported in the NRC Inspection Report 50-285/90-13 which stated that the issue was an unreviewed safety question; therefore, the licensee must reestablish the designa:onfiguration or obtain approval prior to moving spent fuel. Consequently, this meeting was held with NRR to resolve the issue. 7 in its presentation, the licensee indicated that it determined that the analysis for an FHA in the containment envelopes the consequences of an FHA in the SFP; hence, an FHA in the pool would not exceed regulatory requirements.

no actions are required to modify the. ventilation system to ensure Therefore,ir that the a passes through the charcoal filter. However, the staff stated

.that General Design Criteria 61 specifies that fuel storage systems should have i

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' 9011130266 9011o7 1 '

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. filtering systems. Therefore, this conclusion that no license action was l required is not valid. The staff requires that the updated FHA be submitted i for its review prior to its update in the USAR, and that the resolution of i this item be in-place prior to the licensee's 1991 refueling outage.

. I WG 0W Anthony Bournia, Senior Project Manager I Project Directorate IV-1 Division of Reactor Projects - !!!,

IV, Y and Special Projects Office of Nuclear Reactor Regulation l l

l

Enclosures:

l As steted cc w/ enclosures: l See next page l

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e

. Mr. W. Otry Gates Omaha Public Power District fort Calhoun Station, Unit No. 1 CC:

Harry H. Voigt, Esg.

LeCoeuf, Lairb, Leiby & MacRae 1333 New Harrpshire Avenue, NW Washington, D.C. 20036 Mr. Jack Jenser., Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Raymond P. Mullikin, Resident Inspector U.S. Nuclear Regulatory Connission Post Office Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockyille, MD 20852 Regional Adn.inistrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director

, for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington -Texas 76011 Harold Borchert, Director Division of Radiological Health

' Nebraska Department of Health 301 Centennial Mall, South Post Office Box 95007 Lincoln, Nebraska 68509 Mr. T. L. Patterson, Manager Fort Calhoun Station Post Office Box 399 Fort Calhcun, Nebratte 68023 i

i.-ii un- . n.--nimii.----

November 7, 1990 filtering systems. Therefore, this conclusion that no license action was required is not valid. The staff requires that the updated FHA be submitted for its review prior to its update in the USAR, and that the resolution of this item be in. place prior to the licensee's 1991 refueling outage.

Origtuelni M N Anthony Bournia, Senior Project Manager Project Directorate IV.1 Division of Reactor Projects - 11t; IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures:

See next page DISTRIBUTION Docket file NRC PDR Local PDR PD4 1 Reading M. Virgilio MS 13E4 T. Quay L. Beri/

A. Bournia OGC M515B18 E. Jordan MNBB 3701 ACRS (10) MS P-315 PD4 1 Plant file R. Mullikin, Region IV 0FC :PD4 1/LA ;PD4 1/FM ,,

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DATE  :// /// /90  :// //c /90  : // /'/ /90  :  :  :

OFFICIAL RECORD COPY Document Name: MEETING

SUMMARY

FT CALHOUN

, Enclosure 1 i i

I Meeting Attendees M Organization I A. Bournia NRR/DRSP/PDIV-1 l C. R. Nichols NRR/ DST /SPLB 1 R. E. Architzel NRR/ DST /SPLB J. Y. Lee NRR/DREP/PRPB T. R. Quay NRR/DRSP/PDIV-1 J. W. Chase OPPD i R. L. Phelps OPPD l B. Van Sant OPPD l B. Weber OPPD l l

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', Enclosure 2 OPPD Meeting With NRC on Fort Calhoun i

Fuel Handling Accident Analysis October 15, 1990 ,

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1. Introduction J. Chase j

2. Meeting Goals and Objectives R. Phelps

3. Review of VA 66 issues B. VanSant

a. LER Submittal

b. Current Status

4. Review of Current FHA Analysis W. Weber

a. No Credit for VA 66

b. SA0 Basis

c. USAR Revisions

5. Discussion of Changes to FHA-for Next Reload W. Weber 6.- Meeting Summary R. Phelps L -7.. Closing Remarks J. Chase l

I I

1 MEETING OBJECTIVES Clarify the design basis for our current Fuel Handling Accident (FHA) Analysis

- VA 66 Performance Reasons for LER and SAO No USQ Involved Discuss potential FHA analysis changes for the next reload submittal

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SUMMARY

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Current FHA' analysis will be documented through USAR revision Design basis for VA-66 clarified i

, I NRC document agreement that no USQ exists d t

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0 PPD' determine if reasonable alternatives exist to FHA analysis: '

a changes for next reload i J' l

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DISTRIBUTION (53EieTU1De -

.NRC PDR.

Fj; ' Local PDR PD4-1 Reading LM. Virgilio MS 13E4 T. Quay L. Berry A. Bournia OGC MS15B18.

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