ML19332E927
| ML19332E927 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/29/1989 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR 1741, GL-89-21, NUDOCS 8912130163 | |
| Download: ML19332E927 (8) | |
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TOLEDO
%me EDISON A Crnew tr.ery regwir DONALD C. SHELTON Vet 6% w t- % w 1410) 04D P3;O Docket Number 50-346 L
License Number NPF-3 Serial Number 1741
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November 29, 1989 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555
Subject:
Response to Generic Letter 89-21:
Status of implementation of Unresolved Safety Issue Requirements Centlemen The Nuclear Regulatory Commission (NRC) requested by Generic Letter 89-21 (Log Number 3099), dated October 19, 1989, that The Toledo Edison Company provide the status of the implementation of spe.cific Unresolved Safety Issues (USIs) at the Davis-Besse Nuclear Power Station, Unit Number 1. to Generic Letter 89-21 provided a table of USIs for which final technical resolution had been achieved by the NRC. Toledo Edison was requested to complete the table as to the summary status of its implementation of each USI requirement.
Enclosed is Toledo Edison's response to that request.
The table of USIs provided by the NRC's letter was completed by Toledo Edison utilizing the Guide for Updating USI Status enclosed with the letter.
Issue implementation is identified as complete for those issues which Toledo Edison has completed hardware, procedures and training (as applicable), although the NRC may not have yet issued an inspection report or a safety evaluation report on the implementation'of that issue.
The enclosed table contains the present status of the implementation of the USIs for the Davis-Besse Nuclear Power Station as ascertained to the best of Toledo Edison's knowledge under the thirty-day response time of the NRC's letter. This response does not contain any new or revised commitments and should be treated accordingly by the NRC Staff.
8912130163 891129 i
, I PDR ADOCK 05000346 P
PNV j
THE TOLEDO EDISON COMPANY E0lSON PLAZA 300 MADISON AVENUE TOLEDO OHIO 43652 l
-... Dock:t Number 50-346 ficens] Numb;r NPT-3 Serial Number 1741 Page 2 i
Approximately one-hundred and ninety (190) person hours vere necessary for Jresearching information sources, gathering and revieving the information and preparing the response letter and enclosure.
Should you have any questions, please call Mr. R. V. Schrauder, Manager - Nuclear Licensing, at (419) 249-2366.
r Very truly yours, f
DRV/ssg i
Enclosure cci P. M. Byron, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III T. V. Vambach, DB-1 NRC Senior Project Manager t
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. Dock;t Numb:r 50-346 Licen00 sumber NPF-3 l
S iial Number 1741 t
ENCLOSURE 1 i
Gul0E FOR UPDATING USI STATUS I
(1) Enclosure 1 Ifsts all unresolved safety issues (US!s) for which a final technical resolution has been achieved.
Please review the entire listing for each licensed reactor unit, Where an item is not applicable for your facility, mark "NA" in the status column, (2) Where an item is applicable to your facility, but no charges were necessary, mark "NC" in the status column, (3) Where an item is appifcable to your facility and changes are complete, mark "C" in the status column and indicate montn and year implementation f
was complete, including reference to any supporting doccnentation.
.(4) Where an item is applicable to your facility and is not fully implemented, provide your pro,iected implenentation date (month and year) and a short note identifying the outstanding item (e.g., hardware.
l procedures, training, Technical Specificetions), Mark "I" for incomplete.
(5) Where a USI resolution was only recently issued, such as A-40 and A-47, and you are evalu6 ting your response, identify expected response date and indicate "E" in the status colurtn, 1
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? Dock;t Number 50-346 License Number NPF-3 Seriel Number 1741.
ENCLOSURE.1 UNRESOLVED SAFETT ISSUES FOR VHICH A FINAL TECHNICAL RESOLITTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*
REMARKS A-1 Vater Hammer SECT 84-119 All C/08-80 SER issued by NRC NUREG-0927, Rev. 1 05/13/83; IR 82-32 NUREG-0993, Rev. I closed NUREG I.A.2.1 NUREG-0737 Item related to upgrade of I.A.2.3 operator training.on SRP revisions 12/22/82.
A-2/
Asymmetric Blovdovr.
NUREG-0609 PVR C/10-81 TE letter (Serial No. 746)
MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 submitted 10/05/81.
Coolant Systems SER issued 4/9/84 (Log No. 1480).
A-3 Westinghouse Steam NUREG-0844 V-PVR NA Generator Tube Integrity SECT 86-97 SECT 88-272 GL 85-02 (No requirements)
A-4 CE Steam Generator Tube NUREG-0844, SECT 86-97 CE-PVR NA Integrity SECT 88-272 GL 85-02 (No requirements)
A-5 B&V Steam Generator NUREG-0844, SECT 86-97 B&W-PVR C/07-89 TE Letter (Serial No.
Tube Integrity SECT 88-272 1161) responding to GL 85-02 GL 85-02.
(No requirements)
A-6 Mark I Containment NUREG-0408 Mark I-BUR NA Short-Term Program
- C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE I - INCOMPLETE
i Dock;;t Number 50-346 Licens2 Number NPF-3 Serici Number.1741
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ENCLOSURE 4 UNRESOLVED SAFETT ISSUES FOR VHICH A FINAL TECHNICAL RESOLITTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITT STATUS /DATE*
REMARKS A-7/
Mark I Long-Term NUREG-0661 Mark I-BVR NA D-01 Program NUREG-0661 Suppl. 1 GL 79-57 A-8 Mark II Containment NUREG-0808 Mark II-BVR NA Fool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SRP 6.2.1.1C GDC 16 A-9/
Anticipated Transients NUREG-0460, Vol. 4 All I/05-90 Install Diverse Scram MPA A-20 Vithout Scram 10CFR50.62 System: Hardware, Proc-edures, Training.
A-10/
BUR Feedvater Nozzle NUREG-0619 BUR NA MPA B-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All C/05-88 TE letter (Serial No.
Toughness 10CFR50.60/
1510) submitted 5/4/88.
82-26.
License Amendment 116 issued 8/19/88 to address RG 1.99, Rev 2 (Log No.
2676).
A-12 Fracture Toughness of NUREG-0577, Rev. 1 PUR NC Steam Generator and
.SRP Revision Reactor Coolant Pump 5.3.4 Supports
Dock;t Number 50-346
-License Number NPF-3
.Seri 1 Number 1741 -
ENCLOSURE 4 UNRESOLVED SAFETY ISSUES FOR VHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED
-USI/MPA NUMBER TI1LE REF. DOCUMENT APPLICABILITY STATUS /DATE*
REMARKS A-17 Systems Interactions Ltr: DeYoung to All I/09-92 GL 89-18 Resolution licensees - 9/72 1.a pending IPE results NUPEG-1174, NUREG-submittal scheduled for 1229, NUREG/CR-3922, 09-92. Resolution 1.b NUREG/CR-4261, NUREG/
complete per NRC letter CR-4470, GL 89-18 02/11/82 to TE.
(No requirements)
A-24/
Qualification of Class NUREG-0588, Rev. 1 All C/04-84 TE letter (Serial No.
MPA B-60 1E Safety-Related SRP 3.11 1039) submitted 4/3/84.
Equipment 10CFR50.49 SER on 1/31/85 (Log No.
Inspection Report GL 85-15 50-346/86-024 verified compliance (12/19/86).
A-26/
Reactor Vessel Pressure D0R Letters to PVR C/11-88 TE Letter (Serial No.
MPA B-04 Transient Ptotection Licensees 8/76 1613) Responding to NUREG-0224 GL 88-11.
NUREG-0371 SRP 5.2 GL 88-11 A-31 Residual Heat Removal NUREG-0606 All OLs After Shutdown Requirements RG 1.113, 01/79.
Control of Heavy Loads NUREG-0612 All C/10-84 NRC Letter (Log No.
C-10, Near Spent Fuel SRP 9.1.5 1634) dated 10/29/84.
C-15 GL 81-07, GL 83-42, GL 85-11 Letter from DG Eisenhut dated 12/22/80
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. Docket Number 50-346 License Number NPF-3
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Seriel Number 1741
' ENCLOSURE (
UNRESOLVED SAFETY ISSUES FOR VHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*
REMARKS A-39 Determination of SRV NUREG-0802 BVR NA
' Pool Dynamic Loads NUREGs-0763, 0783, 0802 and Pressure Transients NUREG-0661 SRP 6.2.1.1.C A-40 Seismic Design SRP Revisions, NUREG/
All
.NA Criteria CR 4776, NUREG/CR-0054 NUREG/CR-3480, NUREG/
CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/
Pipe Cracks in Boiling NUREG-0313, Rev. 1 BVR NA MPA B-05 Vater Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01 A-43 Containment Emergency NUREG-0510, All C/09-89 Letter from NRC Region Sump Performance NUREG-0869, Rev. 1 III to TE 09/29/89 (Log NUREG-0897, R.G.I.82 No. 1-2161).
(Rev. 0), SRP 6.2.2 GL 85-22 A-44/
Station Blackout RG 1.155 All I/7RF0 TE Letter (Serial No.
A-022 NUREG-1032 1651) addressed installa-NUREG-1109 tion of an alternate AC 10CFR50.63 power source during 7RFC (tentatively start 9/91).
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Dockct Number 50-346 Licensa Number'NPF-3 7,.
4 Serial Number 1741
%l ENCIASURE %
. UNRESOLVED SAFETY ISSUES FOR V3tICH-A FINAL TECHNICAL RESOLL' TION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*_
REMARKS A-45 Shutdown Decay Heat SECY 88-260 All E/09-92 IPE per GL 88-20 shocid Removal Requirements NUREG-1289 resolve.
NUREG/CR-5230 SECY 88-260 (No requirements)
A-46/
Seismic Qualification NUREG-1030 All I/Pending Complete Generic MPA B-105 of Equipment in NUREG-1211/
Implementation Progras' Operating Plants GL 87-02, GL 87-03 Valkdown by second refucling outage after final program issuance by NRC (not yet issued).
A-47 Safety Implication NUREG-1217, NUREG-All E/3-90 of Control Systems 1218 GL 89-19 A-48 Hydrogen Control 10CFR50.44 All, except NA Measures and Effects SECY 89-122 PVRs with of Hydrogen Burns large dry on Safety Equipment containments A-49/
Pressurized Thermal RGs 1.154, 1.99 PVR C/11-88 TE Letter (Serial No.
A-021 Shock SECT 82-465 1613) to NRC responding SECT 83-288 to GL 88-11.
SECY 81-687 10CFR50.61/
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