ML19312E546
| ML19312E546 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 05/28/1980 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TLL-254, NUDOCS 8006050280 | |
| Download: ML19312E546 (3) | |
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Metropolitan Edison Company
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Post Office Box 480 Middletown, Pennsylvania 17057 717 944 4041 Wnter's Direct Dial Number May 28, 1980 TLL 254 Office of Nuclear Reactor Regulation Attn: Harold R. Denton, Director U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Schedules for Future Work to Support the TMI-I Restart Safety Evaluation Report The enclosed schedule identifies completion dates and, in some cases, intermediate milestones for work products that you have asked to review.
These items are those essential for the prelimine.ry complecion of your Safety Evaluation Report (SER). Schedules have not been provided for general operating procedures, startup tests, or technical specifications since these items are not normally reviewed at this stage.
Sincerely /
f) k n
J. d. Herbein Vice President TMI-I JCH:EGW: hah Enclosure cc:
J. T. Collins B. J. Snyder R. W. Reid H. Silver D. DiIanni
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5
//
Metreco un Ec son Comery s a "emter o' *re Gere m Pubnc Ut a es System 800e o 50 2.go P
TLL 254 SCHEDULE FOR COMPLETION OF TMI-l SER OPEN ITEMS Scheduled Order Item Description Completion 79-05B-1 Analysis of Anticipatory Fill 7-1-80 of Steam Generaters 79-05C-LT-1 Automatic RCP Trip Design Details
.10-15-80 4
Fuel Handling Building Modifica-6-1-80 tion Design Details (R.G. 1.52 System) 5 Plan for Low Activity Storage 6-30-80 Permanent Solidification System Design for Radwaste Concept Finalization 6/82 (Est.)
Procurement 1/83 (Est.)
Installation 1/84 (Est.)
Operation 1/85 (Est.)
6 Details of New corporate Organi-7-1-80 zation Staffing Status of Organization 8-1-80 &
10-1-80 OQA Plan Equipment Qualification 7-15-80 List (Q-List) 7 Financial Qualifications 7-15-80 2.1.4 Containment Isolation - Rupture 7-15-80 Detection System Design Details 2.1.6.b Plant Shielding Study Phase I - Personnel Exposure Study Results 6-16-80 Modification Criteria /
l Concept 7-15-8u Modification Design Details 9-15-80 l
Phase II - Equipment Qualifications l
Study Results 9-15-80 l
Modification Criteria /
Concept 10-15-80 Modification Design Details 12-15-80
TLL 254 Scheduled Order Item Description Completion 2.1.7.a AFW Safety Grade Mods See Response to Sup. 1, Part 3, Ques-tion 4 2.1.8.a Post-Accident Sampling Shielding Study (Based on NUREG-0578 Source Term) 8-1-80 Modification Criteria / Concept (If Required) 9-1-80 Modification Design Details (If Required) 11-1-80 Additional Item No. 4 RCS Venting j
High Point Vents Design Details 9-1-80 Reactor Vessel Head Vent Con-ceptual Design 6-15-80 Detailed Design 9-15-80 Long-Term 1 ICS FMEA Address Recommendations 6-30-80 Conceptual Design 10-1-80 4