ML19332G340
| ML19332G340 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/08/1989 |
| From: | Stols R COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| TASK-***, TASK-OR 0421T, 421T, GL-89-21, NUDOCS 8912210114 | |
| Download: ML19332G340 (7) | |
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'y Commonwealth Edison
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. Address Reply to: Post Office Box 761
-l Chicago, lihnois 60690 0767 December 8, 1989' 1
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.l Dr. Thomas E. Murley,. Director j
' Office of. Nuclear Reactor Regulation
'U.S. Nuclear Regulatory Commission Washington, DC' 20555-T
Subject:
Quad Cities Nuclear Power Station Units 1 and 2 Response to Generic Letter 89 Implementation Status,of USI Requirement NRC_Dqckc1 Eor. 50-254 and 50-265 t
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Reference:
Letter from J.G. Partlow to Licensees dated-L(
October 19, 1989 (Received October 30, 1989)'.
Dr. Murley:
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.. Enclosed is the information requested by the subject Generic Letter
'concerning the implementation status-of. Unresolved Safety. Issues (USI) requirements relevant to Quad Cities Station.
.The status for each relevant USI has been de termined to the best of our ability in the' allowed time period (a' limited extension was granted by the~
.NRR Project Manager). Commonwealth Edison believes'the enclosed information accurately reflects the Quad Cities USI implementation status at this time.
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' However. should additional information become -available which dif fers f rom that enclosed, the revisions will be promptly communicated to the NRR Project Manager.
Please contact this office if you should need further information.
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Very truly yours, R. Stols Nuclear Licensing Administrator im Attachment cc:
A.B. Davis - Regional Administrator, RIII T.M. Ross - Project Manager, NRR p
R.L. !!iggins - Resident Inspector, Quad Cities 8912210114 891208
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UIRESOLVED SAFETY ISSUES FUE W ICE A FIN &L TEC MI QUAD CITIES WITS 1 AB 2 s.
USI/MPA NUMBER TITLE STATUS /1MIE RIMARKS A-1 Water Hansser C
12/80 High reactor water level feed pump trip is installed. The training upgrade requirements.
of NUREG 0737,. Item I.A.2.3 were incorporated into the training program prior to accreditation per J. Abel to D. Eisenhut letter.
dated 12/15/80.. Quad Cities was accredited in 1985.
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Asynunetric Blowdown N/A MPA D-10 Ioads on Reactor Primary Coolant Systens A-3 Westinghouse Steam N/A Generator Tube Integrity A-4 CE Steam Cenerator Tube N/A Integrity A-5 B&W Steam Generator N/A Tube Integrity i
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C - COMPLETE NC - NO CHANGES NECESSARY.
NA - NOT APPLICABLE I - INCOMPLETE E - EVALUATING ACTIONS REQUIRED 0421T:2
USI/MPA NiBB_ER TITLE SIAIIISJEAEE REJW IS A-24/
Qualification of Class C
11/85 Inspection Report (IR) 50-254(265)/87-011 stated MPA B-60 1E Safety-Related that preposed resolutions were found to be Equipment acceptable by the NRC in final EQ SER dated 7/19/84. All EQ modifications completed 11/85.
A-26/
Reactor Vessel Pressure N/A MFA B-04 Transient Protection A-31 Residual Heat Removal N/A Shutdown Requirements A-36/
6/83 D. B. Vassalo letter to D. L. Farrar dated C-10, Near Spent Fuel 6/17/83 provides SER for Phase I.
C-15 Phase I Phase II C
6/85 Generic Le+.ter 85-11 completes Phase II of NUREG-0612 based on improvements from Phase I.
A-39 Determination of SRV N/A A-7 addressed this for Mark I.
Pool Dynamic Loads and Pressure Transients A-40 Seismic Design I*
Waiting final NRR acceptance of EPRI -
Criteria Seisteicity Owner's Group position on Items 1, 2, and 3 of the proposed SRF.
Item 4 dealing with the design of flexible vertical tanks will be addressed as part of USI A-46.
- Completion dated will be based on receipt of NRR acceptances 0421T:5 t
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USI/MPA 52RLER TITLE EDLTUS/D_AIE
'N A-6 Mark I Containment C
12/77 Enperseded by USI A-7 Short-Term Program A-7/
Mark I Long-Term C
10/87 2/15/86 letter from J.A. Zwolinski to D.L.
D-01 Program Farrar provides SERs for Pool Dynamic Loads Review and Structural Review. NRC Request regarding Tech Spec changes required was responded to in J.R. Wojnarowski letter to R.R.
D?nton dated 5/16/86. SER for drywell vscuum breakers (TAC's 57150, 57151, MFA D-20) was Jesued 1.1/26/86 and was not considered part of long ians program (addressed by GL 83-08).
Modification inata11ation work was completed in 12/82 (U-1) aM 10/87 (U-2).
A-8 Mark II Containment N/A Pool Dynamic Loads A-9 Anticipated Transients I
6/90*
Modifications for ARI, RPT were completed Without Scram U-1 3/85, and U-2, 2/84; SLCS U-1, 10/87 and U-2 1/87 Tech Spec change for SIES was cosmletted U-1, 3/88 and U-2,12/86 (TAC's 66621 and 63367). R2T and ARI Tech Spec change is to be submitted to NRC by 6/90.
B.L. Siegel letter to H.E. Bliss dated 11/8/88 (TAC's 59089, 59090, 59132, and 59133) states that "the ARI and RPT designs for Dresdon and Quad Cities units satisfy the requirements of the ATWS Rule except for diversity." 12/15/88 letter from J.A. Silady to T.E. Murley presented BWROG and CECO positions on this issue.
- Projected completion does not include NRR's response to 12/88 letter.
0421T:3
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i USI!MPA HL119}IR TITLE STATUS /DAIE REMMLS A-10/
11/83 Feedwater sparger nozzle temperature MPA B-25 Cracking modifications were completed 1/83 (U-1) and 6/80 (U-2).
A-11 Reactor Vessel Material I 6/90 Tech. Spec. asumendment to incorporate radiation Toughness effects into PT curves were submitted per R.G.
1.99.
Based upon the relatively low end-of-life fluence and the saml1 expected drop is end-of-life charpy upper shelf eaergy from HG 1.99, General Electric and CECO believe that there are no technical concerns with older BWR vessels dropping below the 50 ft.-lbe limit.
However, CECO plans to approach the BWROG to establish a generic program to develop baseline data for initial unitradiated charpy upper she11 values for older BWR vessels and provide the associated documentation. Based upon recent discussions with GE, CECO expects a report to be issued in approximately 6 months.
A-12 Fracture Tcughness of N/A Steam Generator and Reactor Coolant Pump Supports A-17 Systems Interactions CECO's response to GL 88-20 comunitted to an IPE pr 7 ram.
Water intrusion and flooding frons internal sources are part of the IPE.
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NLEBER TITLE SIATUS/DATE RE5ARLS A-42/
Pipe Cracks in Boiling 1
12/90 I4akage monitoring Tech. Spec. revision is MFA B-05 Water Reactors being prepared and will be submitted as part of Tech. Spec. improvement. Tech. Spec. require-ments for 151 program will be removed from the Tech. Specs. and included in the ISI program, following NRR review and approval of G.L. 88-01.
A-43 Containment Emergency N/A Sump Performance A-44 Station Blackout I
The 4/17/89 CECO response proposed the coping approach in combination with some hardware changes. During a working meeting held on 10/4/89, there appears to be a difference of opinion between the staff and CECO regarding plant acceptable blackout duration capability.
Discussions are on going.
A-45 Shutdown Decay Heat C
USI A-45 will be addressed by IPE as implemented Removal Requirements by GL 88-20.
Quad Cities IPE is expected to be completed by 12/93.
A-46 Seismic Qualification I*
Waiting for staff approval of SQUG generic of Equipment in inspection plan and issuance of the final SER.
Operating Plants SQUG walkdown will be conducted folicwing staff approval of GIP. Walkdown schedules will be developed following NRC approval.
A-47 Safety Implication E
Response to GL 89-19 is due 3/90.
of Control Systems on Safety Equipment
- Completion date will be based upon issuance of NRR acceptance.
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USI/MPA
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SIAESjyAIE mg3 A-48 Hydrogen Control I*
Waiting for NRR to issue Staff's position on Measures and Effects BWR Owx r's Group response to combustible of Hydrogen Burns gas control.
A-49 Pressurized Thermal N/A Shock
- Completion date will be determined upon issuance of NRR posiition.
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