ML17187B139

Summary of 970313 Meeting W/Comed Re Proposed License Amend Concerning Final Resolution of Containment Overpressure Compensate for Inadequate Net Positive Suction Head for Emergency Core Cooling Sys Pumps

ML17187B139
Person / Time
Site:	Dresden
Issue date:	09/26/1997
From:	Stang J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9710060206
Download: ML17187B139 (8)

Text

LICENSEE:

FACILITIES:

SUBJECT:

. UNITED STATES NUCLEAR REGU~TORY COMMISSION WASHINGTON, D.C. ~1 Se~tefuber 26~ 1997 COMMONWEALTH EDISON COMPANY DRESDEN NUCLEAR POWER STATION, *UNITS 2 AND 3

SUMMARY

OF MEETING TO DISCUSS A PROPOSED LICENSE AMENDMENT*

CONCERNING THE FINAL RESOLUTION OF CONTAINMENT OVERPRESSURE TO COMPENSATE FOR INADEQUATE NET POSITIVE SUCTION HEAD FOR THE EMERGENCY CORE COOLING SYSTEM PUMPS On March 13, 1997, a public meeting was held between the NRC staff and Commonwealth Edison Company (ComEd or the licensee). The meeting was a followup meeting *to one held on March 4, 1997, to discuss a license amendment submitted by the licensee concerning the use of containment overpressure to compensate for a deficiency in net positive suction head (NPSH) for the emergency*cor~ cooling system (ECCS) p~mps. A list of attendees is attached as Enclosure 1.

The licensee's consultant, General Electric, was in attendance by telephone.

On February 17, 1997, the 1 icensee submitted a 1 icense amendment for review

• and approval. The license ame~dment evaluated an unreviewed safety queition (USQ) associated with the use of containment pressure to ~ompensate for a deficiency in NPSH for the ECCS pumps following a design basis accident (OBA).*

During the meeting the 1 i censee made a presentation to the staff, of the.

specific*details of the codes, models and types of analysis used in the license amendment to justify the resolution'of the USQ. is a copy of the licensee's handouts used ~uring the presentation.

Ftillowing the licensee's~resentation a question and answer period was held..

The staff asked questions regarding the use of models and analysis that had not previously been reviewed and approved by the NRC staff. The staff informed the licensee that if non-approved analysis and codes were going to be used to justify the USQ, then additional bench marking of the codes and analyses would have to be done.

The licensee indicated that they would provide additional information concerning theuse of all codes and analyses used in the justification of the USQ in a future submittal.

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By letters da~ted February 27, March 12, March, 26,.April 2 and April 10, 1997, the licensee provided additional information ~t the ~taff's request to better*

clarify the licensee's.February U, 1997, license amendment.

On April 30, 1997, the staff issued a licensee amendm*ent allowing Dresden, Units 2 and 3, to use containment pressure-'to compensate for inadequate NPSH for the ECCS

,Pumps following a OBA.

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Docket Nos. 50-237 and 50-249 John F. Stang, Senior Project Manager Project Directorate III-2 Division of.Reactor Projects*- III/IV Office of Nuclear Reactor R.egulation

Enclosures:

1.. List of Meet~ng Atte~dees

2.

Licensee's Handout cc w/encls:

See next page

,DISTRIBUTION.: -- -

.:_DQc;kE!t_f.ile __ (wf-_encl 1 and-2-)..

PDIII~2 r/f (w/encl 1 and 2)

ACRS, 1:2E26 W. Kropp, WJK (w/encl 1 and 2)

E-Mail: (w/encl 1)

S. Collins/F. Miraglia, *sJCl/FJM E. Adensam, EGA!

C. Moore, ACM G. Tracy, GMT K. Kavanaugh G. Hammer Public (w/encl 1 and 2)

OGC, 015Bl8 J. Stang, JFS2 (w/encl. 1 and 2)

R. Zimmerman, RPZ R. Capra, RAC!

T. Martin, SLM3 D. Terao J. Dawson J. Kudrick To receive a c AfA = Co y with enclosures ANA.= No copy OFFICE D:P03-2 NAME RCAPRA

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DATE 09 c 97

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• By letters dated February 27, March 12, March 26, April 2 and April 10, 1997, the licensee provided additional information at the staff's request to better*

clarify the licensee's February 17, 1997, license amendment.

On April 30, 1997, the staff issued a licensee amendment allowing Dresden, Units 2 and 3, to use containment pressure to compensate for inadequate NPSH for the ECCS pumps following a OBA.

Docket Nos. 50-237 and 50-249 John F. Stang, Senior Project Manager Project Directorate 111-2 Division of Reactor Proje~ts - *111/IV Office of Nuclear Reactor Regulation

Enclosures:

1~ List of Meeting Attendees

2.

Licensee's Handout cc w/encls: See next page DISTRIBUTION:

Docket File (w/encl 1 and 2)

PDIII-2 r/f (w/encl 1 and 2)

ACRS, T2E26 W. Kropp, WJK {w/ericl 1 and 2)

E-Mail~ (w/encl 1)

S. Collins/F. Miraglia, SJCl/FJM E. Adensam, EGAl C. Moore, ACM G. Tracy, GMT*

K. Kavanaugh G. Hammer Publi~ (w/encl 1 and 2)

OGC, 015Bl8 J. Stang, JFS2 (w/encl 1 and 2)

R. Zimmerman, RPZ R. Capra, RACl T. Martin, SLM3 D. Terao J. Dawson J.. Kudrick DOCUMENT NAME:

G:~CMNTJ ESDEN\\0313MEET.NPS To rece;ve a

t. ind;cate ;n

~ Copy without enclosures -e* = C with enclosures -.* = No copy OFFICE G-D: PD3-2 G

NAME RCAPRA. t-v-*../

• -*----*----*--*-*---~. --*--

• By letters dated February 27, March 12, March 26, April 2 and April 10~ 1997, the licensee provided additional information at the staff's request to better clarify the licensee's February 17, 1997, license amendment.

On April 30, 1997, the staff issued a licensee amendment allowing Dresden, Units 2 ~nd 3, to use containment pressure to compensate for inadequate NPSH for the ECCS pumps following a OBA.

Docket Nos. 50-237 and 50-249 o-..J~

J..

Stang, S. ior Project Manager Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation

. Entlosures: 1.

List of Meeting Attendees

2.

Licensee's Handout cc w/encls: See next page

cc:

Ms. I. Johnson Acting Manager, Nuclear Regulatory Services Conunonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, Illinois 60515 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Site Vice President Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Station Manager Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 U.S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station 6500 North Dresden Road Morris, Illinois 60450-9766 Regional Administrator U.S. flRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351

. Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Chairman Grundy County Board Administration Building 1320 Union Street Morris, Illinois 60450 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Dresden Nuclear Power Station Unit Nos. 2 ~nd 3

--~------*-----*-------*------*----~----**-- - *-****----...

NAME John Stang David Terao Kerri Kavanagh Jack Dawson Gary Hammer Bob Rybak Frank Spangenberg Linda Weir Kevin Ransden Bill Houston Carl Fago Greg Tice J.

• Kudrick George Stramback Saul Minz Gary Sozzi

• Dan Pappone

---. ~*

• --*------*-~ -. ----.. --------------

MEETING ATTENDEES MEETING HELD ON MARCH 13, 1997 COMPANY NRC NRC/EMEB NRC/SRXB NRC/SLSB NRC/EMEB Com Ed Com Ed Com Ed Com Ed Sequoia.Consult Group Yankee Atomic Elec.

Corn Ed NRC GENE GENE GENE GENE TELEPHONE NO.

301/415-1345 301/415-3317 301/415-3743 301/415-3138 301/415-2791 630/663-7292 815/942-2920 x 3800 815/942-2920 x 3109 630/663-3017 904/461-8774 508/568-2318 309/654-2241 x 3186 301/415-2871 408/925-1913.

408/925-1913 408/925-1913 408/925-1913

. ENCLOSURE 1

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• LPCI tOOOO DRESDl!N STATION UNITS 2 &3 tOO 000 MINIMUM CONT AJNMENT PRESSURE AV All.ABLE ANO CONTAINMENT PRESSURE REQUIRED FOR PUMP NPSH FIGURB 4.2.i6 (Figure 6.3-80 of Proposed UFSAR Change)

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Time (sec) 10000 DRESDEN STATION UNITS 2& 3 100 000 MINIMUM CONTAINMENT PRESSURE AVAILABLE AND CREDITED CONTAINMENT PRESSURE FOR PUMP NPSH FIGURE 1 f