ML20217H808

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Summary of 980306 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2.List of Attendees Encl
ML20217H808
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 03/31/1998
From: Stewart Bailey
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9804060072
Download: ML20217H808 (6)


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p3 UNITED STATES n+rzfry jj. i NUCLEAR REGULATORY COMMISS!ON WASHINGTON, D.C. 30086 0001 March 31,.1998 LICENSEE: Commonwealth Edison Company (Comed)  ;

FACILITY: . BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND2 L

SUMMARY

SUMMARY

OF MARCH 6,1998, MEETING ON STATUS OF LICENSING ISSUES On March 6,1998, the NRC staff met with representatives of Commonwealth Edison Company l (Comed) in Rockville, Maryland, to discuss the status of licens!ng issues for Byron Station, Units j 1 and 2, and Braidwood Station, Units 1 and 2. The discussion covered the license amendment l

requests and other requests that Comed has submitted, as well as the status of Comed's l response to several generic communications (e.g., Generic Letters). A list of meeting attendees l Is attached.

One significant license amendment request relates to the containment integrated leak rate test  ;

! (ILRT)c. Comed has adopted Option B from 10 CFR Part 50, Appendix J. This option permits the testing interval to be extended from every 5 years to every 10 years provided two consecutive ILRTs are passed. Byron Station, Unit 2 and Braidwood Station, Unit 2 have not passed two consecutive ILRTs; however, Comed stated the failure on the previous ILRT was caused by a leaking steam generator secondary manway. In both cases the manway had been steam cut due to continued operation with a small steam leak, and the condition of the manway was known .

before the test. Comed contends they should be allowed to extend the test interval for these I

, units because they can identify a leaking manway during operation and take compensatory l L measures. Also, Comed contends that steam generator pressure remains above containment  !

l pressure following a Loss of Coolant Accident (LOCA), so the steam generator secondary

l. manway is not a viable leakage path for the release of radionuclides. The Byron Station and ~

Braidwood Station Technical Specifications would require the next ILRT some time during the I next cycle for Byron Station, Unit 2 and Braidwood Station, Unit 2; however, the test must be

, performed during an outage. It was agreed that Comed should justify an extension until the end l

of the next cycle, based on the above arguments, as opposed to extending the interval to 10 years. Comed and the NRC agreed to continue to pursue this issue in order to support the Byron Station, Unit 2 refueling outage, which is scheduled for the spring of 1998.

With regard to Comed's submittal to adopt the improved Standard Technical Specifications (iSTS) for. Byron Station and Braidwood Station, the staff informed Comed that the review schedule was being extended. The NRC staff noted that Comed's submittal contains many deviations from the standard format (found in NUREG 1431, Revision 1). Some of these deviations were based on TSTFs (named after the Technical Specification Task Force), which are industry-proposed changes to the NUREG, but rnany are unique to the Byron Station /Braidwood Station submittal and do not appear to be based on plant-specific requirements. Comed has only recently revised its submittal to remove some of the TSTFs that I

have been rejected by the NRC. Also, the staff noted that Comed has frequently disagreed with the NRC's comments related to using the standard format in lieu of the deviations that are unique to Byron Station and Braidwood Station. This is further prolonging the review of the Byron Station /Braidwood Station ISTS submittal. Because of this, the staff is giving higher priority to \ l other plants'iSTS submittals that are more readily reviewed and approved by the staff. The staff 9804060072 900331 '

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/h sm 20 RJ.E CENER ggPy t .

l O. Kingsley - 2- I4 _March 31, 1'998 stated that the earliest the review'could be completed is 'Geptember 1998. Thik is a delay of approximately.4 months from the previously reported schedule. The NRC requested additional information from Comed on their schedular needs. Comed and the NRC agreed to search for ways to accelerate the NRC's review.

The NRC staff also discussed with Comed the quality ef several recent license amendment requests. The staff noted that the safety focus of the submittals was generally good and the No Significant Hazards Considerations were of high quality. However, the staff noted that the review -

of some submittals was lengthened due to insufficient or erroneous information in the submittals.

For example, there were several errors in the vendor documents that were included in the recent submittal to incorporate a Pressure Temperature Limits Report (PTLR) into the Technical Specifications. Also, the request for crediting soluble Boron in the spent fuel pool for criticality

- control had to be resubmitted because the proposed changes to the Technical Specifications were not consistent with the supporting analyses.

With regard to Comed's comments on interactions with the staff, Comed noted that communications with the staff could be better. In particular, there have been instances where project managers have not been timely in retuming phone calls. On some occasions the project managers did not have the information or status requested by Comed. Nevertheless, it was agreed that it is important to maintain the communications on a regular basis.

Orig. signed by:

Stewart N. Bailey, Project Manager Project Directorate ill-2 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457

Attachment:

List of Attendees cc w/ encl: See next page Distnbution. Docket File'. PUBLIC PDill-2 r/f E. Adensam, EGA1 R. Capra S. Bailey G. Dick J. Hickman C. Harbuck_ . C. Moore R. Lobel OGC,015B18 ACRS, T2E26 M. Jordan, Rill DOCUMENT NAME:G:\CMNTSP\ BRAID-BY\BB0306hlT. SUM ~

- h ecosive e espy of this slecument, Indoeto in the boa: 'C' = Copy without enclosuree *E* = Copy with enclosuree *N* = No copy OFFICE PM:PDill-2 k. LA:PDill-2 PM:PDlll-2 e D:PDill-2 ld NAME SBAILEY5443 CMOOREOnh" ftr JHICKMAN GEIN ROAPRA%d L.

DATE 03/m/98 03$498 03N/98 03/,A/98 @

OFFICIAL' RECORD COPY

< c O. Kingsley l

- stated that the earliest the review could be completed is September 1998. This is a delay of approximately 4 months from the previously reported schedule. The NRC requested additional information from Comed on their schedular needs. Comed and the NRC agreed to search for ways to accelerate the NRC's review.

The NRC staff also discussed with Comed the quality of several recent license amendment l requests. The staff noted that the safety focus of the submittals was generally good and the No Significant Hazards Considerations were of high quality. However, the staff noted that the review of some submittals was lengthened due to insufficient or erroneous information in the submittals.

, For example, there were several errors in the vendor documents that were included in the recent submittal to incorporate a Pressure Temperature Limits Report (PTLR) into the Technical Specifications. Also, the, request for crediting soluble Boron in the spent fuel pool for criticality control had to be resubmitted becauss the proposed changes to the Technical Specifications were not consistent with the supporting analyses.

j' With regard to Comed's comments on interactions with the staff, Comed noted that communicationr with the staff could be better, in particular, there have been instances where

! project managers have not been timely in retuming phone calls. On some occasions the project managers did not have the information or status requested by Comed. Nevedheless, it was l agreed that it is important to maintain the communications on a regular basis.

Stewart N. Bailey, P ec anager Project Directorat Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457

Attachment:

List of Attendees cc w/ encl: See next page l

O. Kingsley Byron /Braidwood Stations .

Commonwealth Edison Company cc:

Ms. C. Sue Hauser, Project Manager George L. Edgar Westinghouse Electric Corporation Morgari, Lewis and Bochius Energy Systems Business Unit 1800 M Street, N.W.

Post Office Box 355 Washington, DC 20036 Pittsburgh, Pennsylvania 15230 Attomey General Joseph Gallo 500 S. Second Street Gallo & Ross Springfield, Illinois 62701 1250 Eye St., N.W., Suite 302 Washington, DC 20005 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety Michael I. Miller, Esquire 1035 Outer Park Drive Sidiey and Austin Springfield, Illinois 62704 One First National Plaza Chicago, Illinois 60603 Commonwealth Edison Company Byron Station Manager Howard A. Leamer 4450 N. German Church Road Environmentallaw and Policy Byron, Illinois 61010-9794 Cer,ter of the Midwest 203 N. LaSalle St. Suite 1390 Commonwealth Edison Company Chicago, Illinois 60601 Site Vice President - Byron 4450 N. German Church Road U.S. Nuclear Regulatory Commission Byron, Illinois 61010-9794 Byron Resident inspectors Office 4448 N. German Church Road U.S. Nuclear Regulatory Commission Byron, Illinois 61010-9750 Braidwood Resident inspectors Office RR 1, Box 79 Regional Administrator, Region 111 Braceville, Illinois 60407 U.S. Nuclear Regulatory Commission 801 Warrenville Road Mr. Ron Stephens Lisle, Illinois 60532-4351 filino:s Emergency Services and Disaster Agency Ms. Lorraine Creek 110 E. Adams Street RR 1, Box 182 Springfield, Illinois 62706 Manteno, Illinois 60950 Chairman Chairman, Ogle County Board Will County Board of Supervisors Post Office Box 357 Will County Board Courthouse Oregon, Illinois 61061 Joliet, Illinois 60434 Mrs. Phillip B. Johnson Commonwealth Edison Company 1907 Stratford Lane Braidwood Station Manager Rockford, Illinois 61107 RR 1, Box 84 Braceville, Illinois 60407 I

O. Kingsley Commonwealth Edison Company Byron /Braidwood Stations .

Ms. Bridget Little Rorem Ms. Irene Johnson, Licensing Director Appleseed Coordinator Nuclear Regulatory Services 117 N. Linden Street Commonwealth Edison Company Essex, Illinois 60935 Executive Towers West lli 1400 Opus Place Suite 500 Document Control Desk-Licensing Downers Grove,IL 60515 Commonwealth Edison Company 1400 Opus Place, Suite 400 Commonwealth Edison Company Downers Grove, Illinois 60515 Reg. Assurance Supervisor- Braidwood RR 1, Box 79 Commonwealth Edison Company Braceville, Illinois 60407 Site Vice President- Braidwood RR 1, Box 84 Commonwealth Edison Company Braceville,IL 60407 Reg. Assurance Supervisor- Byron 4450 N. German Church Road Mr. David Helwig Byron, Illinois 61010-9794 Senior Vice President Commonwealth Edison Company Mr. Michael J. Wallace ,

Senior Vice President l Executive Towers West lll 1400 Opus Place, Suite 900 Commonwealth Edison Company Downers Grove,IL 60515 Executive Towers West lli 1400 Opus Place, Suite 900 Mr. Gene H. Stanley Downers Grove,IL 60515 PWR's Vice President Commonwealth Edison Company Executive Towers West 111 1400 Opus Place, Suite 900 Downers Grove,IL 60515 Mr. Steve Perry BWR's Vice President Commonwealth Edison Company Executive Towers West lil 1400 Opus Place, Suite 900 Downers Grove, IL 60515  :

Mr. Dennis Farrar Regulatory Services Manager Commonwealth Edison Company Executive Towers West lil 1400 Opus Place, Suite 500 Downers Grove,IL 60515 I

l l LIST OF ATTENDEES FOR MEETING HELD ON MARCH 5.1998 NAME AFFILIATION S. N. Bailey NRC/NRR/DRPW/PDill-2 G. F. Dick NRC/NRR/DRPW/PDill-2 l J. B. Hickman NRC/NRPJORPW/PDill-2 C. C. Harbuck NRC/NRR/ADPR/TSB l R.M.Lobel NRC/NRR/DSSA/SCSB i D. Chrzanowski Comed NLA l M. Lesniak Comed NLA D. Saccomando Comed NLA 1

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ATTACHMENT