ML20054F889
| ML20054F889 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/10/1982 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-2.K.2.10, TASK-TM 825, GL-82-05, GL-82-5, TAC-49582, TAC-49583, NUDOCS 8206180132 | |
| Download: ML20054F889 (7) | |
Text
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TOLEDO
%ms EDISON Docket No. 50-346 R<><Ano P. CRaSE Vce Pres.oent License No. NPF-3
- =*-
(4193259-5221 Serial No. 825 June 10, 1982 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
This letter is to transmit a revised response of our submittal dated May 8, 1982 ' Serial No. 813) regarding Mr. D. G. Eisenhut's letter of March 17, 1982 (Log No. 929) concerning Post-THI Requirements (Generic Letter No. 82-05) as it relates to Davis-Besse Nuclear Power Station Unit No. 1.
The attachment provides Toledo Edison's revised response, which supersedes our May 8, 1982 submittal. All changes are denoted by change bars in the right margin.
In our May 8, 1982 letter we identified that Toledo Edison's current outage involved major repair activities which could impact the requested schedule. The attachment reflects changes to our current schedule due to outage related repair activities and their impact on our resources. We will keep you apprised our any further changes to the attached schedule.
Very truly yours, 3? CwM RPC: GAB: lab attachment cc: DB-1 NRC Resident Inspector Qf J i
8206190132 sEo'615 W
EDGON RAZA 300 WOSON MENW TOLEDO. ONO GM DR ADOCK 05000346 p
-10 CFR 50.54(f)
SUBMITTAL IN RESPONSE.
FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 FACILITY OPERATING LICENSE NO. NPF-3 This letter is submitted in conformance with 10_CFR 50.54(f) revising and superseding our submittal to Mr. Darrell G. Eisenhut's letter of March 17, 1982.
This deals with Post-TMI Requirements (Generic Letter 82-05), Enclosure 1.
By: COj/-
C.~T. Daf t VQuality Assurance Director Acting on behalf of R. P. Crouse, Vice President, Nuclear Sworn to and subscribed before me this 11% day of June, 1982.
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KUREC-0737 ITEMS LICENSEE RESPONSE Toledo Toledo NUREG-0737 Edison Edison Schedule Letters Schedule Remarks Item Title Description 1.A.3.1 Simulator Exams Include simulator exams in 10/1/81 8/4/80, #641 Completed licensing examinations 9/14/81, #741 No modifications proposed from the 11.B.2 Plant Shielding Modify facility to provide 1/1/82 3/21/80, #601 study c f II.B.2.1.
access to vital areas under accident conditions.
II.B.3 Post-accident Install upgrade post-accident 1/1/82 2/19/82, #779 June 1.
Reactor Coolant sample System:
1983 All outane telsted work will be com-Sampling sampling capability.
Pleted during the current refueling outage. Operators' panel will be in-stalled af ter outage with operation by June 1983.
December 2.
Containment Air Monitoring:
1982 Although an extended range Containment Air Nonitoring System is being replaced during the current outage, to insure sample analysis capability for the full range of NRC source terms of NUREC-0737 a grab sample system is being provided to meet this item.
Due to representative sample problems in design, this will not be operable until December 1982.
Interim Measures:
All interim systems are operational and will remain so unt ti the upgraded systems are operational. Additionally, the new Containment Air Monitoring will be
(
operational.
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NUREG-0737 ITEMS LICENSEE RESPONSE Toledo Toledo NUREG-0737 Edison Edison item Title Description Schedule Letters Schedule Remarks II.B.4 Training for Complete training program.
10/1/81 7/31/81, #740 Completed 3/16/82, #796 nitigating Core Damage II.E.I.2 Aux. Feedwater Modify instrumentation to 7/1/81 3/21/80, #601 Refueling Current initiation system is safety Initiation & Flow level of safety grade 9/16/81, #742 Outage 1982 grade. Presently modifying flow Indicator indication to safety grade, one per train. Steam Generator level is redundant and safety grade.
Interim Measures: Currently installed control grade flow indicators will remain (one per train).
II.E.4.2 Containment Iso-Part 5 - lower containment 7/1/18 1/30/81, #685 Completed. KRC letter dated 4/14/82 lation Dependability pressure setpoint to level (Log No. 961) Contained Safety Evalu-compatible with normal atlan Report for Item II.E.4.2.
operation Part 7 - isolate purge and 7/1/81 Completed. Part of original design.
vent valves on radiation signal.
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NUkEG-0737 ITEMS LICENSEE RESPONSE Toledo Toledo EUREG-0737 Edison Edison item Title Description Schedule Letters Schedule Remarks II.F.1 Accident Monitoring (1) install noble gas 1/1/82 4/20/82, #1-261 12/31/82 Station Vent Monitor:
effluent monitors.
Due to current associated outage probleme. manpower allocation preclude installation of effluent monitors until 12/31/82.
Compensatory Measure:
Until the effluent monitors are installed and operational, the interim effluent monitors will remain functional.
(2) provide capability for 1/1/82 1/25/82, #779 12/31/82 Station Vent Monitor:
ef fluent monitoring of 4/20/82, #1-261 Due to current associated outage problems, manposer allocation iodine.
preclude installation of effluent monitors until 12/31/82.
Compensatory Measure:
Until the effluent monitors are installed and operational, the interim effluent monitors will remain functional.
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4 NUREG-0737 ITEMS LICENSEE RESPONSE Toledo Toledo NUREG-0737 Edison Edison y
Title Description Schedule Letters Schedule Hemarks (3) install in-containment 1/1/82 1/25/82, #713 Refueling radiat+an-level monitors.
Outage 1982 (4) provide continuous indica-1/1/82 Refueling Containment pressure indication is tion of containment pressure Outage 1982 being extended to 5 times design.
(5) provide continuous indica-1/1/82 Refueling Two part level indication is provided Lion of contaisunent water Outage 1982 to a level of 0-4 leet (Narrow Range) level.
and 0-55 feet (Wide Range) in the Containment Building.
(6) provide continuous 1/1/82 Refueling The current indicator range is being indication of hydrogen Outage 1982 extended to 0-10% hydrogen concentr-concentration in contain-ation.
ment.
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w-NUREC-0737 ITEMS LICENSEE RESPONSE Toledo Toledo NUREG-0737 Edison Edison item Title Description Schedule Letters Schedule Res.a r k s ll.K.2.10 Safety Grade Trip Install anticipatory reactor 7/1/81 7/24/81, #735 1st Refueling
- Toledo Edison committed on trips.
9/8/81, #744 6 mos. after December 30, 1980 (Scrial No, 1/5/82, #765 NRC approval 670) to install the Safety Crade 4/14/82, #808 f f no changes Trip Systems (ARTS) the first refueling outage 6 months after NRC approval.
Compensatory Heasure:
Until the Final ARTS is installed and operational, the Interim ARTS will remain functional.
- Note:
NRC letter dated May 14, 1982 (Log No. 992) contained Safety Evaluation Report for item II.K.2.lO.
Tuledo Edison is currently installing the Safety Crade Trip System during this outage. Until Toledo Edison declares the Final ARTS operable,'the Interim ARTS will remain functional.
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