ML19305E082

Submits List of SEP Topic References in Response to NRC .Includes Info Re Potential Hazards,Severe Weather Flooding,Tornado Missiles,Reactor Vessel Integrity & Control Room Habitability

ML19305E082
Person / Time
Site:	Dresden
Issue date:	04/14/1980
From:	Janecek R COMMONWEALTH EDISON CO.
To:	Ziemann D Office of Nuclear Reactor Regulation
References
NUDOCS 8004220332
Download: ML19305E082 (5)

Text

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Commonwealth Edison One First Nationsi Plaza. Chicago, tthnois Address Reply to. Post dffde' Boi 767 Chicago, Ilkrois 60690 April 14, 1980 Mr. Dennis L. Ziemann, Chief Operating Reactors - Branch 2 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C.

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Subject:

SEP Topic References Dresden Unit 1 NRC Docket No.50-10 Reference (a):

Dennis L.

Ziemann Letter to D.L.

Peoples Dated Februcry 14, 1980

Dear Mr. Ziemann:

In response to reference (a) Commonwealth Edison has completed the following list of references.

II-1.C -

Potential hazards or changes in potential hazards due to transporation, institutional, industrial, and military facilities.

1. GEAP-1044, " Preliminary Hazards Summary Report for the Dresden Nuclear Power Station," revised June 24, 1957

2. GEAP-0878, " Final Hazards Summary Report for the Dresden Nuclear Power Station," January 1957, revised 1970 3.

" Plant Design and Analysis Report, Volume III, Dresden Nuclear Power Station, Unit 2," Commonwealth Edison Company, April 15, 1965 4.

" Final Safety Analysis Report, Dresden Units 2 and 3,"

Commonwealth Edison Company, revised March 1968 5.

" Final Environmental Report, Dresden Units 2 and 3,"

Commonwealth Edison Company, November 1973 Il-2.A -

Severe Weather Phenomena

1. GEAP-1044, " Preliminary Hazards Summary Report for the Dresden Nuclear Power Station," revised June 24, 1957

2. GEAP-D878, " Final Hazards Summary Report for the Dresden Nuclear Power Station," January 1957, revised 1970

3. NPG-126, " Environmental Factors at Proposed Site of Dr sden Generating Statinn," June 15, 1955 4.

" Plant Design and Analysin Hepurt, Volume 1, Dresden Nuclear Power Station, Unit 2," Commonwealth Edison Company, May 17, 1965

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Commonwealth Edison 5. " Final Environmental Report, Dresden Units 2 and 3,"

Commonwealth Edison Company, November 1973

6. Licensee Event Reports 11-3.8 -

Flooding Potential and Prctection Requirements

1. Environmental Factors at Proposed Site of Dresden Generating Station, June 15, 1965

2. Final Hazards Summary Report

3. Review of Dresden Station Facilities to Resist Flooding Capabilities, October 13, 1972

4. Flooding of Critical Equipment at Dresden Units 1, 2, and 3, August.23, 1973 III-4.A - Tornado Missiles

1. Dresden Unit 1, Preliminary Hazards Summary Report, GEAP-1044 revised June 1, 1957

2. " Feasibility Analysis of Primary Containment Vessel" Sargent and Lundy 1977 i

III-4.B - Turbine Missiles

1. GEAP-1044, " Preliminary Hazards Summary Report for the Dresden Nuclear Power Station," Revised June 1957

2. GEAP-0878, " Final Hazards Summary Report for the Dresden Nuclear Power Station," January 1957, Revised 1970 III-4.D - Site Proximity Missiles

1. Proximity Missiles were not considered in the design of Dresden Unit 1.

III-8.C - Reactor Vessel Internals Integrity

1. Robert F.

Janecek letter of March 10, 1980 to D.L. Ziemann V-6

- Reactor Vessel Integrity

1. Dresde'n Unit 1 Final Hazards Summary Report

2. APED 3988, "Dresden Nuclear Power Station Reactor Vessel Steel Surveillance Program"

3. Dresden Unit 1 Equipment Manuals, Volume 2 l

Commonwealth Edison 4.

Letter, from D.K.

Davis (NRC) to R.L. Bolger (CECO), dated May 20, 1977

5. Letter, from M.S.

Turbak (CECO) to D.K. Davis (NRC), dated October 18, 1977

6. Letter, from M.S.

Turbak (CECO) to D.K. Davis (NRC), dated December 23, 1978

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7. NUREG 0569-Evaluation of the Integrity of SEP Reactor Vessels VI-7.C.1-Appendix K-Electrical Instrumentation and Control (EIC)

Re-review

1. This topic is covered by NRC order to modify the ECCS systems.

Work and NRC reviews are ongoing VI-8

- Control Room Habitability

1. Dresden Preliminary Hazard. Report, Amendment No. 3, Teole J-11

2. Dresden Unit 1 Final Hazards Summary Report, Section D, Description of Plant, Section 5 (Shielding Design Criteria),

page 27

3. Dresden Unit 1 Final Hazards Summary Report, Figure D-35, Control Room Layout 4.

Dresden Units 2 and 3 Final Safety Analysis Report, 4mendment No.

9, Question III.K-1

5. Dresden Units 2 and 3, Final Safety Analysis Heport, Volume I, Section 1, Introduction and Summary, page 1.3-3

6. Dresden Station Administrative Procedures, DGA-14,

7. Dresden Un'.t 1 Drawing No. M-273, Diagram of Control Room Office and Drywell Air Conditioning

8. Dresden Units 2 and 3, Final Safety Analysis Report, Volume I, Sect} ion 1, Introduction of Units 1, 2, and 3, page 1.5-4

9. Dresden Station Units 2 and 3 Special Report No. 37, Rev.1, Section 11.0, Habitability of the Control Room

10. Dresden Station Special Report No. 30, Evaluation of Steam and Feedwater Pipe Greaks Outside Containment, Volumes II and III, Dresden Unit 1

11. Emergency Plan Implementing Procedure, EPIP 2.6.7, Classification of an Incident involving Hazardous Materials i

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12. DDA 5750-4, Rev. O, Noxious Fumes in Control Room, January l

1978 l

Commonwealth Edison VIII-4

- Electrical Penetrations of Reactor Containment

1. R.F. Janecek letter of 3/14/79 to D.L. Ziemann

2. Specification No-2345-104, Spe'cification for test of three Typical Sphere Electrical Penetration Assembly Units for the Dresden Nuclear Power Station of the Commonwealth Edi on Company Chicago, Illinois dated July 31, 1957

3. Sphere Electrical Penetration Assembly Unit Report E-1 Covering the Design, Fabrication, Testing and Test Results of Typcial Sphere Penetrations for Insulated Wire and Cable, and Copper Tubes for Air Lines for the Dresden Nuclear Power Stations of the Commonwealth Edison Company, Chicago, Illinois dated July 7, 1958

4. M.S.

Turbak letter of December 9, 1977 to Edson G. Case Start up of an inactive loop or recirculation loop at an XV-9 incorrect temperature and flow controller malfunction causing an increase in BWR Core Flow Rate

1. Collett, W.I.,

"Dresden Control and Transient Analysis,"

GEAP 3198, Sections 2.3.1.3 and 2.3.1.4, pp. 34-36, July 1, 1979

2. Dresden Unit 1 Technical Specification, " Partial Loop Operation," page 54a XV-11 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position.

1. Normal reload analysis submittals cover this topic.

XV-13 Spectrum of Rod Drop Accidents (BWR)

1. Dresden Unit 1 Technical Specifications, pages 53 and 54.

2. Final Hazards Summary Report, Revised April 1, 1970

3. Dresden Statico Special Report No. 32 XV-19 Loss of Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks within the Reactor Coolant Pressure Boundary i

1. Dresden Unit 1 Nuclear Power Station Loss-of-Coolant I

Accident Analysis Conformance with 10CFR50, Appendix K/

Plant As Is (Non Jet-Pump Plant)," 1975 Enclosure 1 to 1etter, from R.L. Bolger (CECO) to B.C. Rusche (NRC), dated j

July 31, 1975 i

2. " Type XN-1 Heatup Analysis Supplement to Dresden Unit 1 Loss-of,-Coolant Accident Analysis Conformance wth 10CFR50, i

Appendix K/ Plant As Is (Non Jet-Pump Plant)," June 1977 (revised July 1977), Attachment III to letter, from R.L.

Bolger (CECO) to E.G. Case (NRC), dated August 3, 1977

Commonwealth Edison 5-

3. "Dresden Unit 1 Final Hazards Summary Heport," " Effects of a Major Accident, pp. 141-156, and Table J-ll, " Radiological Effects of Maximum Credible Accident" 4.

SEP Evaluation Report for Dresden Unit 1 for Topic II-2.C,

" Atmospheric Transport and Diffusion Characteristics for Accidents Analysis"

5. Supplement A, Proposed Change No. 17 to Operating License DPR-2, as amended, Docket 50-10, transmitted to the USAEC by letter, from H.E. Bliss to P.A. Morris, dated September 17, 1970.

6. Work on this topic is covered by a NRC order to modify the ECCS system. Work and NRC reviews are in progress One (1) signed original and thirty nine (39) copies of this letter have been provided for your review.

If you have any questions concerning this matter, please contact this c.'fice.

Yours very truly, W'

Robert F. Janecek Nuclear Licensing Administation Boiling Water Reactor NPS:mnh 2703A e

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