ML17188A126

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Summary of 980304 Meeting W/Comed to Discuss Licensing Activities Re Quad Cities Nuclear Power Station Units 1 & 2 & Dresden Nuclear Power Station,Units 2 & 3.List of Attendees Encl
ML17188A126
Person / Time
Site: Dresden, Quad Cities  
Issue date: 04/01/1998
From: Pulsifer R
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9804060370
Download: ML17188A126 (25)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 1, 1998 LICENSEE:

COMMONWEAL TH EDISON COMPANY (ComEd)

FACILITIES:

Quad Cities Nuclear Power Station, Units 1 and 2 Dresden Nuclear Power Station, Units 2 and 3 5t>--2'J1~~~

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SUBJECT:

SUMMARY

OF MEETING CONCERNING QUAD CITIES AND DRESDEN LICENSING ACTIVITIES On March 4, 1998, the staff met with ComEd to discuss licensing activities regarding the Dresden and Quad Cities Nuclear Power Stations. A list of attendees is provided as.

The objective of the meeting was to discuss active as well as future licensing activities. The discussion centered around the status of open activities under review by the staff and future actions under development by ComEd. Communications between the staff and ComEd were discussed and an assessment was provided by the staff of the licensee's performance regarding licensing activities.

The licensee provided a short presentation of their ongoing study of the loss of the Dresden lock and dam. ComEd addressed a dam failure coincident with a Loss of Coolant Accident (LOCA) and dam failure during normal plant operation as discussed in the Updated Final Safety Analysis Report (UFSAR) section 9.2.5. The licensee is proposing a license amendment to eliminate a

  • dam failure coincident with a LOCA as a credible accident from the UFSAR.

The licensee also discussed their plans.regarding the resolution of the post-LOCA reactor building temperature concerns. Dresden and Quad Cities had reconstituted the design basis reactor building temperature calculation and determined that maximum temperatures may be higher than previously assumed for the environmental qualification of equipment. The licens~e is presently developing a final resolution of this issue. An initial operability evaluation has been performed for Dresden. An operability evaluation has not been performed for Quad Cities station at this time because it is not operating. Near term actions planned at Dresden include replacing some electrical components; longer term actions involve installing additional air handling units for reactor building cooling. The licensee also anticipates preparing a Justification for Continued Operation for Dresden for the period after the current operability evaluation expires at the end of April 1998.

All active licensing activities were addressed with the licensee to discuss the status of the staffs review, the schedule for a response from the licensee on a request for additional information or the expected completion date for the licensing action.

A discussion was held concerning communications between ComEd and the NRR licensing group. It was noted that the quality of communications between these organizations were not consistent between the six ComEd sites and the NRR projects staff. ComEd is working on a program to improve the quality of communications between all the sites, the Downers Grove office and the NRC staff.

9804060370 980401 PDR ADOCK 05000237 P.

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  • An assessment was provided to ComEd on the licensing activities for Dresden and Quad Cities.

At Quad Cities the submittals from ComEd have been generally good. They usually provided sufficient information for the staff to provide an evaluation. Several Requests for Additional Information (RAI) were required on complex issues such as seismic qualification of electrical and mechanical equipment (unresolved safety issue A-46), IPEEE, and pressure locking and pressure binding of power operated gate valves (GL 95-07). Two issues needing closer attention by ComEd include a response needed for a RAI issued 05/28/97 for GL 95-07 and closure of R.G. 1.97 issues. Inadequate review of two submittals was also noted where the "Summary Report of Changes, Tests and Experiments Completed" dated October 31, 1997, included two safety evaluation descriptions that incorrectly stated there was a reduction in the margin of safety and the "Q2C15 Core Operating Limits Report, Revision 1u dated November 4, 1997, included propriety information that was not requested to be held in confidence.

At Dresden, the submittals from ComEd have generally. been satisfactory, although a few have been very good and a few were not well done. A few submittals, such as amendments 156/151 which removed the 24/28 Vdc batteries and distribution system from technical specifications, would have benefitted from a concise summary since they gave rather complicated descriptions of simple issues. Two issues needing.closer attention from Com Ed include documenting any changes in commitment dates and documenting closure of R.G. 1.97 issues.

A list of attendees is provided as Enclosure 1. A copy of the visual aids used by ComEd at this meeting outlining the licensee's presentation* of loss of the Dresden lock and dam is provided. as. A copy of a flow chart of actions the licensee is taking with respect to the post-LOCA reactor building temperature concerns is provided as Enclosure 3.

Docket Nos. 50-237, 50-249, 50-254, 50-265

Enclosures:

1. List of A~endees
2. Licensee's Visual Aids
3. Flow Chart cc w/encl: See next page fl~{//.

Rob~~~~

Project Manager Project Directorage 111-2 Division of Reactor Projects Office of Nuclear Reactor Regulation

OFFICE NAME DATE

  • April 1, 1998 An assessment was provided to ComEd on the licensing activities for Dresden and Quad Cities.

At Quad Cities the submittals from ComEd have been generally good. They usually provided sufficient information for the staff to provide an evaluation. Several Requests for Additional Information (RAI) were required on complex issues such as seismic qualification of electrical and mechanical equipment (unresolved safety issue A-46), IPEEE, and pressure locking and pressure binding of power operate<:! gate valves (GL 95-07). *Two issues needing closer attention by ComEd include a response needed for a RAI issued 05/28/97 for GL 95-07 and closure of R.G. 1.97 issues. Inadequate review of two submittals was also noted where the "Summary Report of Changes, Tests and Experiments Completed" dated October 31, 1997, included two safety evaluation descriptions that incorrectly stated there was a reduction in the margin of safety and the "Q2C15 Core Operating Limits Report, Revision 1" dated November 4, 1997, included propriety information that was not requested to be held in confidence.

At Dresden, the submittals from ComEd have generally been satisfactory, although a few have been very good and a few were not well done. A few submittals, such as amendments 156/151 which removed-the 24/28 Vdc batteries and distribution system from t~chnical specifications, would have benefitted from a concise summary since they gave rather complicated descriptions

  • of simple issues. Two issues needing closer attention from ComEd includ~ documenting a11y changes in commitment dates and documenting closure of R.G. 1.Q7 issues:
  • A list of attendees is provided as Enclosure 1. A copy of the visual aids used by ComEd at this meeting o.utlining the licensee's presentation* of loss of the Dresden lock and dam is provided as. A copy of a flow chart of actions the licensee is. taking with respect to the post-LOCA reactor buildir:ig* temperature concerns is provided as Enclosure 3.

Docket Nos. 50-237, 50-249; i~

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50-254, 5.0-265 t

Enclosures:

1. List of Attendees
2. Licensee*.s* \\/isoal Aids
3. Flow :ctiart
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Orig. signed by

Robert~. Pulsifer, Project Manager Project *Directorage 111-2

- Division* of Rea\\:tor Projects

'Off\\pe,of Nucl~ar Reactor Regulation*

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  • PM:P03-2 512-LRossbach OFFICIAL RECORD COPY
  • .An assessment was pr:ovided to ComE;d on_the licensing activities for Dresden nd Quad Cities.

At Quad Cities the submittals from ComEd have been ge.nerally good. They. ually provided

  • sufficient information for the staff to provide an evaluation. Several Reque s for Additional Information (RAI) were required on complex issues such as seismic quar cation of electrical and mechanical equipment (unresolved safety issue A-46), IPEEE, and pre ure locking and pressure binding of power operated gate valves (GL 95-07). Two is es needing closer attention by ComEd include a response needed for a RAI issued 05/28/97 f GL 95-07 and closure of R.G. 1.97 issues. Inadequate review of two submittals was als oted where the "Summary Report of Changes, Tests and Experiments Completed" dated ctober 31, 1997, included two safety evaluation descriptions that incorrectly stated there w
a. reduction in the margin of safety and the "Q2C15 Core Operating Limits Report, Revision 1" ated November 4, 1997, included propriety information that was not requested to be held i confidence.

At Dresden, the submittals from ComEd have gener y been satisfactory, although a few have been very good and a few were not well done. A f submittals, such as amendment_s 156/151 which removed the 24/28 Vdc batteries and dist

  • ution system from technical specifications, would have benefitted from a concise summa ince they gave rather complicated descriptions of simple issues. Two issues needing closer ttention from ComEd include documenting any changes in commitment dates and docume ing closure of R.G. 1.97 issues.

A list of attendees is provided as Enclo re 1. A copy of the visual aids used by ComEd at this meeting outlining the licensee's prese tation of loss of the Dresden lock and dam is provided as. A copy of a flow chart f actions the licensee is taking with respect to the post-LOCA reactor building temperatur concerns is provided as Enclosure 3.

Docket Nos. 5~ 37, 50-249, 50-254, 50-2

1. List of Attendees
2. Licensee's Visual Aids
3. Flow Chart See next page DISTRIBUTION: See next page Robert M. Pulsifer, Project Manager
  • Project Directorage 111-2 Division of Reactor Projects Office of Nuclear Reactor Regulation DOCUMENT NAME: G:\\CMNTSP\\DRESDEN\\D&QMTG.304 IN THE BOX: *c* =.COPY WITHOUT ENCLOSURES "E".. COPY WITH ENCLOSURES "N" OFFICE t..-- D:PD3-2 NAME RPulsifer RCapra DATE 3/h 3/

/98 3/

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/98 OFFICIAL RECORD COPY

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Mr. 0. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 500 Downers Grove, Illinois 60515 Michael I. Miller, Esquire Sidley and Austin One First National. Plaza Chicago, Illinois 60603 Commonwealth Edison Company Site Vice President - Dresden 6500 N. Dresden Road Morris, Illinois 60450-9765 Commonwealth Edison Company Dresden Station Manager 6500 N. Dresden Road Morris, Illinois 60450-9765 U.S. Nuclear Regulatory Commission Dresden Resident Inspectors Office 6500 N. Dresden Road Morris, Illinois 60450-9766 William D. Leach Manager - Nuclear MidAmerican Energy Company 907 Walnut Street P.O. Box 657 Des Moines, Iowa 50303 Vice President - Law and Regulatory Affairs Mid American Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, Iowa 52808 Dresden Nuclear Power*Station Units 2 and 3 Quad Cities Nuclear Power Station Units 1and2 Chairman Rocle Island County Board of Supervisors 1504 3rd Avenue Rocle Island County Office Bldg.

Rocle Island, Illinois 61201 Regional Administrator U.S. NRC, Region Ill 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 Commonwealth Edison Company Quad Cities Station Manager 22710 206th Avenue N.

Cordova, Illinois 61242-9740 U.S. Nuclear Regulatory Commission Quad Cities Resident Inspectors Office 22712 206th Avenue N.

Cordova, Illinois 61242 Commonwealth Edison Company Site Vice President - Quad Cities 22710 206th Avenue N.

Cordova, Illinois 61242-9740 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515

Mr. David Helwig Nuclear Services Senior Vice President Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, IL 60515 Mr. Gene H. Stanley PWR's Vice President Commonw~alth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, IL 60515 Mr. Steve Perry BWR's Vice President Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, IL 60515 Mr. Dennis Farrar Regulatory Services Manager Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 500 Downers Grove, IL 60515 Ms. Irene Johnson, Licensing Director Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 500 Downers Grove, IL 60515 Commonwealth Edison Company Reg. Assurance Supervisor** Dresden 6500 N. Dresden Road Morris, Illinois 60450-9765 Commonwealth Edison Company Reg. Assurance Supervisor~ Quad Cities 22710 206th Avenue N.

Cordova, Illinois 61242-9740 Dresden Nuclear Power Station Units 2 and 3 Quad Cities Nuclear Power Station Units 1 and 2 Mr. Michael J. Wallace Senior Vice President Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, IL 60515

DISTRIBUTION:

Hard Copy w/encls 1, 2 & *3 PUBLIC ACRS, T-2E26 RPulsifer E-MAIL w/encls 1 only*

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John Stang Robert Pulsifer Larry Rossbach Mark Ring John Fox Steve Tutich Linda Weir John Nosko R~ D. Freeman Tom Petersen Chuck Peterson Frank Spangenberg Mark Wagner Tony Fuhs Denny Farrar Bob Rybak March 4, 1998, Meeting Between Commonwealth Edison Company and NRC Dresden/Quad Cities Licensing Activities Company NRC/NRR NRC/NRR NRC/NRR NRC/Rlll Com ED/Dresden Com Ed/Dresden Com Ed/Dresden Com Ed/Dresden Com Ed/Dresden ComEd/Quad Cities ComEd/Quad Cities Com Ed/Dresden

. ComEd Com Ed Com Ed Com Ed ENCLOSURE 1

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  • Dam Failure Coincident With a LOCA

- UFSAR Section 9.2.5.3.2

  • Dam Failure During Normal Plant Operation

- UFSAR Section 9.2.5.3.1

- IPEEE Seismic

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- Earthquake, loss of*dam, loss of Class II systems, loss of offsite power

- Water level drop_s to 495*'

- CCSW intake pipes in Bay 13 at 500'

- Refuse pit pumps needed to refill Bay 13

>>Install Stop Logs

>> Open CW Drain Valves

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- 2 Hours Before Containment Cooling is Needed, Only 1 CCSW Pump Used Discrepancies With UFSAR Description

- All existing LOCA Analyses Are Based on:

>> Containment Cooling Within 10 Minutes, Not 2 Hours

>> 2 CCSW Pumps, Not 1

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Dam Failure Coincident With c' aLOCA

- Standard Review Plan

>> <1.0E-07 is incredible

>> <1.0E-06 is incredible is qualitative arguments indicate that realistic probability is lower

  • Systematic Evaluation Program
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>> Review criteria for UHS included ability to handle LOCA in one unit and safe shutdown in the other

>> Dam failure coincident with a LOCA was not evaluated I~

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Dam Failure During Normal 1 Plant Operation

- Earthquake, loss of dam, loss of Seismic Class II systems, loss of offsite power

- Rapid decrease in pool level to 495'

- Loss of condenser vacuum then scram

- Isocondenser actuates

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- Make-up to lsocondenser pe~.:

>>Diesel-driven make-up pumps from clean demin tank (not in orig. FSAR)

>> Clean demin water pumps from clean demin tank

>>Condensate transfer pumps from CST's

>>Diesel-driven fire pump*from UHS

>> Service water pumps from UHS (not in original FSAR)

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  • UFSAR Description (cont'd)

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- Service water pump could be used to cool RBCCW and achieve cold shutdown via the shutdown cooling heat exchangers

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- Fire pump_ suction is at elevation 492 '-0"

- Diesel generator cooling water pump suction is at elevation 487' -8

- 2.5 million gallons required by each unit over a 30-day period (implies that water.in -the Ultimate Heat Sink must eventually be used)

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Discrepancies With UFSAR

- None o*f the Isocondenser make-up sources are Seismic Category I

- Suction _strainer for fire pump becomes uncovered at 495'-10", not 492'

- Top of service water pump inlets is 493 '-6.5" but no NPSH or vortex calculations exist

-*No procedure to isolate failed FP piping

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  • UFSAR Change Per 1 OCFR50.59

- Short-Term Make-Up to Isocondenser

>>SEP did not credit fire pump with immediate make-up capability (time available following an earthquake is insufficient to isolate failed FP -piping)

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- Long-Term Make-Up to Isocondenser

>> Bay 13 stop logs and refuse pumps are needed to use diesel-driven fire pump

>> Service water pumps offset any decreased reliability of fire pump

>> Generate NPSH and vortex calculations for service water pumps

>> Portable gasoline powered pumps for each unit which draw from the canals and pump to the isocondenser system will further improve reliability

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- CCSW Selected As Decay Heat Removal Path for Safe Shutdown

>> It takes 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to install stop logs, align CW drain valves, and align refuse pumps to refill Bay 13

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Discrepancies With* IPEEE Submittal

- Refuse pumps and support equipment not on SQUG list

{NTS exists.to perform)

- Piping and breaker for refuse pump cannot be SQUGed

- No calculation exists to demonstrate that 2-hour delay in establishing CCSW is acceptable

- No tests have been performed to prove that CW drain valves can deliver the required flow without the CW pumps on

- NRC concern about leakage though stop logs

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!3 Dam Failure During Normal,l

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Plant Operation

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~ Proposed Resolution

  • Revise IPEEE submittal to indicate that the isolation condenser must be used to achieve safe shutdown following a dam failure

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C:\\ABC\\RXBLOG.AF3 Wednesday, March 4, 1998 8:31 AM Rx Bldg Post LOCA Temp> 120 Long Term Identify Affected Eqpt Evaluate TOL and Instruments Perform Cales or Field Work OK to Maintain Perform Initial Operability Evaluation Purchase AHU at Risk Prepare JCO Refine Operability Evaluation 1-------.i; PresentJCO to NRC

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o Hot SIC LT Page 1 Design Modification Install Modification Rx Bldg <120 Post LOCA Long Term

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