ML17180B192
| ML17180B192 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 05/11/1995 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9505180303 | |
| Download: ML17180B192 (6) | |
Text
- '"
LICENSEE:
~
May 11, 1995 Commonwea~ Edison Company (ComEd)
- FACILITY:
Dresden Nuclear Power Station, Units 2 and 3 Quad Cities Nuclear Power Station, Units 1 and 2
SUBJECT:
SUMMARY
OF MARCH 23, 1995, MEETING REGARDING THE TECHNICAL SPECIFICATION UPGRADE PROGRAM (TSUP)
On March 23, 1995, a meeting was held at NRC Headquarters, One White Flint North, Rockville, Maryland, between ComEd (the licensee) and the NRC staff to discuss matters related to the Dresden and Quad Cities TSUP.
The meeting was held at the request of the licensee to discuss TSUP status.
The NRC staff stated that an individual had been assigned to work full-time coordinating TSUP activities with the two project managers.
The staff provided the licensee with its schedule for completion of all TSUP amendments (See Attachment 2), noting that the schedule is contingent on ComEd providing timely responses to the NRC's Request for Additional Information (RAI) dated February 22, 1995.
The licensee also. provided a table of TSUP status (See ). The staff discussed Generic Question No. 2 from the RAI in response to a question from the licensee. A clarification of Generic Question No. 2 is provided as Attachmeht 4.
- Docket Nos. 50-237, 50-249, 50-254 and 50-265 Attachments:
- 1. List of attendees Original signed by:
Donna M. Skay, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
- 2. NRC TSUP review schedule
- 3. ComEd TSUP status
- 4. Clarification of Generic Question No. 2 cc w/atts: see next page Distribution w/att 1-4:
Docket File PUBLIC PDII I-2 R/F DSkay PHil and, RI II Distribution w/att 1 only WRussell/FMiraglia RZimmerman EAdensam JHannon RCapra CMoore OGC ACRS (4)
EJordan BMcCabe, EDO TJKim JStang RPul sifer DOCUMENT NAME:
G:\\CMVLJR\\DRESDEN\\DQTSUP.LTR To receive a copy of this document. indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N"
= No copy OFFICE PM:PDIII-2
°'* D:PDIII-NAME DSKAY:avl):jf>1Q../ RCAPRA DATE 05/ 10/95 05/11 /95 OFFICIAL RECORD COPY
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9505180303 950511 PDR ADOCK 05000237 P
Dresden Nuclear Power Station Unit Nos. 2 and 3 Quad Cities Nuclear Power Station Unit Nos. 1 and 2 cc:
Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Mr. Thomas P. Joyce Site Vice President Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Mr. D. Bax Station Manager, Unit 2 Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Mr. J. Heffley Station Manager, Unit 3 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. NRC, 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 Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and Electric Company P. 0. Box 4350 Davenport, Iowa 52808 Mr. L. William Pearce Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 U.S. Nuclear Regulatory Commission Quad Cities Resident Inspectors Office 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, Illinois 61201 Mr. D. L. Farrar Manager, Nuclear Regulatory Service Commonwealth Edison Company Executive Towers West Ill, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515
NRC T.J. Kim John Stang Robert Pulsifer Robert Capra ComEd J.M. Johnson P. Piet A. Fuhs M. Wagner J. Schrage March 23. 1995 Technical Specification Upgrade Program MEETING PARTICIPANTS Attachment I
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CHA PT 1.0 2.0 3/4.0 3/4.1 3/4.2 3/4.3 3/4.4 3/4.5 3/4.6 3/4.7 3/4.8 3/4.9 3/4.10 3/4.11 3/4.12 5.0 6.0 SECTION OWNER Definitions Stang Safety L1m1ts Stana Applicability Stang RPS Pulsifer Instrumentation Pulsifer Reactivity Stang Control SLCS Stang ECCS Stang Primary System Kim Boundary Cont. System Kim Plant Systems Stang Electrical Kim Power Refueling Stang Special Tests Stang Power Dist.
Stang Limits Design Features Stang Administrative Kim DRESDEN/QUAD CITIES TSUP REVIEW SCHEDULE March 1, 1995 SHOLLY
&TS/
ASTS/
RAI 2nd DRAFT LA 2ND TECH OGC ISSUE TSUP TSUP RESP.
RA Is PKG CONC PM BRCH CONC DATE REVIEW TO LA CONC CONC Yes COMP.
COMP.
N/A N/A 1/30 1/31 1/31 N/A 2/6 2/16 3/17 COMP.
COMP.
N/A N/A 5/19 Yes COMP.
COMP.
N/A N/A 1/30 1/31 1/31 N/A 2/6 2/16 CRAI)
CRAil 8/18 (RAI)
(RAI)
~/8 Yes COMP.
COMP.
N/A N/A 6/2 Yes COMP.
COMP.
N/A N/A 1/26 1/26 1/26 4/7 (RAI)
(RAI) 8/18 Yes (RAI) 9/8 (RAI)
COMP.
COMP.
N/A N/A 6/16 3/17 COMP.
COMP.
N/A N//A 5/19 3/17 COMP.
COMP.
N/A N/A 5/19 CRAil COMP.
COMP.
N/A N/A 6/30
-1 *NOTE: RAls were issued on 2/22/95.
Responses to the RAis are expected by 3/31/95. Meeting with ComEd on or about 3/15/95.
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M69019; M69020 M84321 M84321 M84321 M84928 M86n4 M86n4 M86n4 M86739 M86743 Dresden Nuclear Power Station Tech Spec Amendments and Other Technical Issues Priority Amendment/Title Descrlpllon/DNPS OSR#r=shollled Cogn.
Est/Last Est/Sched Status CC)rres.
ADorova.1.
____ :[f!~H SPECS (NON*TSUP) UNO ~A REVll:W BY NRR ( * =
Sholly Notice Publlshe(ll Med CREFS [D/Q)
Control Room Emergency Filtration System NRA 1/8/93 reauirements-#92-56 I C\\IM 5p1::1,;::; (NUN* I ;:)Ut"J UNDEH \\IC\\IU UCYCLUr'MCN I un n~v'ICYY Med 9~~~_!:ice~~I! Am~i:i.~ri:!~~ __ _:_ Submit information to justify 111 CCSW pump Site 3131195 NIA
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Proposeriecessary-fStosupport moving-RF-- ----*- ~----
Low 2~"Mo_~!~_9ycles outa11~s to 24 _!TIOnth cycles Site 12131195 NIA Low 02 License Recapture Recapture time from construction period of license; Site 12/31/95 NIA gains approx. 3 yrs, 11 mos.
TECH SPEC UPGRADE PROGRAM
- = Sholly Notice Published
_ __!:!!91!_ Section 1.0 i::§l,!~_!!!!_:_Q~~r:!i~Q!)~!#92-24
~RR 7129192 2/16195 Hi~~ Section 3/4.0 TSUP #1 a - Applicabil!!Y; #92-15
- NRA 7129192 2/16195
- Hig~ Section 314.3 TSUP #1 b - Reactivity Control: #92-21
- NRA 7129192 612/95
____!:!!!!~ Section 314.4 TSUP #2 - SBLC; #92-35
- NRA 10115192 417/95
-~i~
Section 2.0 TSUP_~~
- Safety LimitslLSSS;#92-30 NRA 9115192 5119195 section 314.11 High TSUP #3 - Special Tests; #92-38 NRA 9115192 5119195 High. Section 314.12 TSUP #3 - Power Dist. Limits: #92-31 NRA 9/15/92 5/19/95
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High Section 3/4.1 TSUP #4 - RPS;#92-37 NRA 12/8/92 8/18/95 High Section 3/4.10 TSUP #5 - Refueling;#92-49 NRA 2/16/93 6/16/95 High Section 3/4.9 TSUP #6 - Electrical Power;#92-47
-~!~~ Section 3/4.6 T~~!:>-~~!:>~~ary Sys!em_~~~ndary;#~?-55, etc.
NRA 9/17/93 9/8/95 High Section 3/4.7 TSUP #8 - Containment Systems;#92-58, etc.
NRA 9/17/93 8/18/95 High Section 314.8 TSUP #7 - Plant Systems;#92-59, etc.
NRA 9/10193 8118/95 High Section 3/4.2 TSUP #10- lnstrumentation;#93-167 NRA 8/31/94 9/8195 High Section 5.0 TSUP #9-Design Features;#93-127 NRA 12/15/93 6/30/95 High Section 6.0 TSUP #11 - Admininstrative Controls;#93-144 Com Ed 3/31/95 10/1/95
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Hi ah Overall Resolutions TSUP #12 -TSUP clean-uo oackaae.
Com Ed 3/31/95 10/1/95 As of 3/21 /95 Page 1
CLARIFICATION OF GENERIC QUESTION NO. 2 In reference to Generic Question No. 2, "Changes" or "deviations" would include: 1) deletion,.revision, or addition to the current TS requirements;
- 2) deletion, revisi~n, or addition of any plant parameters in the current TS; and 3) deletion, revision, or addition to specific terminology in the current TS (i.e., "steam dome" vs. "steam space").
Reformatting the sentences and paragraphs while retaining the plant-specific terminology of the current TS and without alterjng its meaning to follow the guidelines of the standard TS would not constitute a "change" or "deviation."
For each change or deviation, please provide justification and/or explanation.
If a change or deviation is in accordance with the guidelines of the standard TS and it is more conservative than the requirements in the current TS, a simple statement to that effect would be sufficient.
In addition, please determine and identify in your response any changes or deviations that constitute less restrictive requirements.
For each less restrictive requirement, please provide a plant specific justification, and demonstrate that the proposed TS maintains the current licensing basis as described in the Updated Final Safety Analysis Report (indicate specific chapter and paragraph).
ATTACHMENT 4