ML20155G891
| ML20155G891 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/03/1998 |
| From: | Pulsifer R NRC (Affiliation Not Assigned) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| References | |
| TAC-MA3447, TAC-MA3448, NUDOCS 9811090241 | |
| Download: ML20155G891 (6) | |
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November 3,1998 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA3447 AND MA3448)
Dear Mr. Kingsley:
In a letter dated August 31,1998, Commonwealth Edison Company (Comed) submitted an application for an amendment to the Technical Specifications, Section 3/4.7.D, Primary Containment Isolation Valves. The staff has reviewed this submittal and has the need for additional information to complete the review. The staff's request for additionalinformation (RAl)is enclosed. These questions were discussed with members of your staff on October 15, 1998, October 19,1998, October 21,1938 and November 2,1998. It was agreed that the responses would be provided within 30 days cf the date of this letter.
Sincerely, ORIG. SIGNED BY Robert M. Pulsifer, Project Manager l!
Project Directorate 111-2 y
Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation 4
Docket Nos. 50-254,50-265 PISTRIBUTION:
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WASHINGTON, D.C. 2066H001 November 3, 1998 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West 111 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA3447 AND MA3448)
Dear Mr. Kingsley:
In a letter dated August 31,1998, ' Commonwealth Edison Company (Comed) submitted an application for an amendment to the Technical Specifications, Section 3/4.7.D, Primary Containment Isolation Valves. The staff has reviewed this submittal and has the need for additionalinformation to complete the review. The staff's request for additionalinformation (RAl)is enclosed. These quest ons were discussed with members of your staff on October 15, 1998, October 19,1998, October 21,1998 and November 2,1998. It was agreed that the responses would be provided within 30 days of the date of this letter.
Sincerely, eobert M. Pulsifer, roject Manager Project Directorate 1112 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-254,50-265
Enclosure:
RAI cc w/ encl: See next page
. O. Kingsley Quad Cities Nuclear Power Station.
Commonwealth Edison Company Units 1 and 2 cc:
Michael 1. Miller, Esquire -
Commonwealth Edison Company Sidley and Austin Site Vice President-Quad Cities One First National Plaza 22710 206th Avenue N.
Chicago, Illinois 60603
. Cordova, Illinois 61242-9740 Commonwealth Edison Company Document Control Desk-Licensing Quad Cities Station Manager Commonwealth Edison Company 22710 206th Avenue N.
1400 Opus Place, Suite 400 Cordova, Illinois 61242-9740
' Downers Grove, Illinois 60515 U.S. Nuclear Regulatory Commission Mr. David Helwig Quad Cities Resident inspectors Office Senior Vice President 22712 206th Avenue N.
Commonwealth Edison Company Cordova, Illinois 61242 Executive Towers West lli 1400 Opus Place, Suite 900 Chairman Downers Grove,IL 60515
- Rock Island County Board of Supervisors Mr. Gene H. Stanley
.1504 3rd Avenue PWR's Vice President.
Rock Island County Office Bidg.
Commonwealth Edison Company Rock Island, Illinois 61201 Executive Towers West lli 1400 Opus Place, Suite 900 lilinois Department of Nuclear Safety Downers Grove,IL 60515 Office of Nuclear Facility Safety 1035 Outer Park Drive Mr. Steve Perry -
Springfield, Illinois 62704 BWR's Vice President Commonwealth Edison Company Regional Administrator Executive Towers West lll U.S. NRC, Region 111 1400 Opus Place, Suite 900 801 Warrenville Road Downers Grove,IL $0515 Lisle, Illinois 60532-4351 Mr. Dennis Farrar William D. Leach Regulatory Servicea Manager Manager-Nuclear Commonwealth Edison Company MidAmerican Energy Company Executive Towers West lil 907 Walnut Street 1400 Opus Place, Suite 500 P.O. Box 657 Downers Grove,IL 60515 Des Moines, Iowa 50303 Ms. Irene Johnson, Licensing Director Vice President - Law and Nuclear Regulatory Services Pegulatory Affairs Commonwealth Edison Company MidAmerican Energy Company Executive Towers West 111
-One River Center Place 1400 Opus Place, Suite 500 106 E. Second Street Downers Grove, IL' 60515 P.O. Box 4350 Davenport, Iowa 52808
O. Kingsley Quad Cities Nuclear Power Plant Commonwealth Edison Company Units 1 and 2 Commonwealth Edison Company Reg. Assurance Supervisor-Quad Cities 22710 206th Avenue N.
Cordova, Illinois 61242-974,0 Mr. Michael J. Wallace Senior Vice President 4 -
Commonwealth Edison Company Executive Towers West lll 1400 Opus Place, Suite 900 Downers Grove,IL 60515 1
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REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES'(UNITS 1 & 2) APPLICATION FOR AMENDMENT j
TO TECHNICAL SPECIFICATIONS. SECTION 3/4.7.D.
j PRIMARY CONTAINMENT ISOLATION VALVES i
1.
Describe how the lodine deposition constant assumed in the August 31,1998, request was derived from the deposition velocity assumed in the referenced (December 17, 1981) analysis. Provide length and diameter of main steam lines (MSL) at Quad Cities.
2.
The lodine deposition velocity used is based on the models in NUREG/CR-0009 for determining deposition in the reactor containment, post-LOCA. However, as described s
in Section 6.1.9 of NUREG/CR 0009, these models rely on the turbulent mixing of the containment atmosphere. Since the 30 cfh leakage per MSL will most likely result in laminar flow (therefore increasing the Importance of lodine transfer through the bulk gas phase), demonstrate that the assumed value is conservative and bounding.
l 3.
The Aur"::t 31,1998, request states that a suppression pool time-Integrated DF of five was assumed consistent with the Standard Review Plan (SRP) 6.5.5.Ill.1.
a.
Consistent with SRP 6.5.5.II.1 verify that all releases from the reactor core pass into the suppression pool, except for small bypass.
b.
Specify what pool bypass was used in the analysis and compare it to the minimum assumed bypass as discussed in SRP 6.5.5.ll.2.
i c.
Provide calculation for determinlng the overall decontamination factor (DF adjusted for bypass) consistent with SRP 6.5.5.111.2. What fraction of the pool bypass also bypasses secondary contair,'nt?
4.
The August 31,1998, request includes a revised analysis of the MSL break accident.
Since an increase in allowable MSIV leakage (the subject of the request)is not a i
parameter in the analysis, justify revising it as a basis for this request.
5.
Justify changing the MSLB design basis to a " puff" release model that is not consistent with the guidance in Regulatory Guide 1.5," Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Bolling Water Reactors." Provide the technical basis for the cloud diameter assumed. Were the cloud diameters and wind speeds assumed for calculating the EAB and LPZ doses the same i
as that assumed at the control room intake?
6.
In order to credit iodine plateout, the main steam line piping, the bypass / drain lines, the interconnected piping and the condenser will need to retain their structural integrity following a Safe Shutdown Earthquake (SSE). The licensee is requested to demonstrate the structural integrity of the entire leakage treatment path, including the above stated leakage path piping, the associated supports, the condenser structural members, and the associated anchorages, using seismic input data and analytical methodologies acceptable to the NRC.
ENCLOSURE
. 7.
To address the seismic ll/l issue, the licensee is requested to address the seismic capability of the turbine building.
8.
The licensee is requested to address the reliability of the entire leakage treatment path, including all of its boundary valves. This may include descriptions and diagrams of the intended leakage treatment path and boundaries, and assurance that valves required to open the leakage treatment path to the condenser are provided with a highly reliable power source. In addition, confirm that valves which are required to open the leakage treatment path to the condenser will be included as part of the plant inservice testing (IST) program with appropriate testing interval.
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