ML19339C283
| ML19339C283 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/26/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TASK-02-02.B, TASK-02-02.D, TASK-03-08.B, TASK-06-08, TASK-15-08, TASK-15-14, TASK-15-8, TASK-2-2.B, TASK-2-2.D, TASK-3-8.B, TASK-6-8, TASK-RR NUDOCS 8011180034 | |
| Download: ML19339C283 (5) | |
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UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION Ri i
.I WASHINGTON, D. C. 20555 D
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f September 26, 1950 os tin Docket No. 50-245
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m Mr. W. G. Counsil, Vice President Nuclear Engineering and Operation:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
6y letter dated November 16, 1979, we sent you the list of topics which would not be reviewed by your plant in the Systematic Evaluation Program (SEP).
These topics were deleted from the SEP review because they were not applicable to your plant or they were being reviewed as part of an ongoing generic issue outside the SEP. The following topics should be added to the Novenber 16 listing. Removal of these additional topics from the SEP review results from 1) related generic NRC activities and 2) non-applicability of topics to certain facilities.
The following is a list of such topics and indicates tne1r disposition:
Topic Categorization Disposition 11-2.C Generic Cor.pliance with Appendix E is being evaluated under the Emergency Prepardness Program Office (EPPO) effort.
Conpliance with Appendix I is being evaluated as part of the NRC Appendix I review effort.
11-2.D Generic Conpliance is being evaluated under the EPP0 effort.
III-8.B Deleted The review published as NUREG-0479,
" Report on BWR Control Rod Drive Failures" fulfills the intent of this topic.
e VI-8 Generic Will be reviewed by NRC as part of TMI Task Action Plan (NUREG-0660) as specified in May 7,1980 letter to all operating reactor licensees.
Those parts of Topic II-1.B " Population Distribution" relating to emergency plans will be evaluated by EPPO.
In addition, the original DBE review list indicated that DBE group VI events " Uncontrolled Rod Assen&ly Withdrawal at Power and " Uncontrolled Rod Assembly Withdrawal - Low Power Startup" are a 80111,8008 g
Mr. W. G. Counsil September 26, 1980 part of Topic XV-13. However, the topic of reference should be Topic XV-8,
" Control Rod Misoperation" and accordingly the references for Topic XV-8 should include Standard Review Plans 15.4.1 and 15.4.2.
Also, the November 16, 1979, letter states that DBE Group X, " Inadvertent Operation of ECCS or CVCS Malfunction that.Causes an Increase in Reactor Coolant Inventory" should be deleted as it applies only to PWR's.
However, Group X will be included in the SEP review since inadvertent operation of ECCS should be evaluated for BWR's. to this letter includes a revised listing of the DBE Accident and Transient Groups applicable to BWR's.
Of note should be the inclusion of Group XI, " Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position", revision to Group III to include " Radiological Conse-quences Of a Main Steam Line Failure Outside Containment", and the It clusion of Fuel Handling Accidents in Group VIII.
Sincerely, OperatingReactorsBran@ch#5 ennis
- 1. Crutcifield, ief Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 1
9 t
. September 26, 1980 Mr. W. G. Counsil cc William H. Cuddy, Esquire Connecticut Energy Agency Day, Berry & Howard ATTN: Assistant Director Counselors at Law Research and Policy One Constitution Plaza Development Hartford, Connecticut 06103 Department of Planning and Energy Policy Natural Resources Defense Council 20 Grand Street 917 15th Street, N. W.
Hartford, Connecticut 06106 Washington, D. C.
20005 Director, Technical Assessment Division Northeast Nuclear Energy Company Office of Radiation Programs ATTN: Superintendent (AW-459)
Millstone Plant U. S. Environmental Protection P. O. Box 128 Agency Waterford, Connecticut 06385 Crystal Mall #2 Arlington, Virginia 20460 Mr. James R. Himmelwright Northeast Utilities Service Coapany U. S. Environmental Protection P. O. Box 270 Agency Hartford, Connecticut 06101 Region 1 Office ATTN:
EIS COORDINATOR Resident inspector JFK Federal Building c/o V. S. NRC Boston, Massachusetts 02203 P. O. Box Drawer KK Niantic, Connecticut 06357 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 First Selectman of the Town of Waterford Hall of Records 200 Boston Post Road Waterford, Connecticut 06385 John F. Opeka Systems Superintendent Northeast Utilities Service Company l
P. O. Box 270 Hartford, Connecticut 06101 i
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BWR OBE TOPIC LIST Accident and Transient Groups RELATED-TOPIC DESIGM SASIS EVENT SRP
~ Group I XV-1
' Decrease in feedwater tamperature 15.1.1 1,
(BWR)
XV-1 Increase in feedwater flow 15.1.2 XV-1 Increase in steam flow 15.1.3 XV-9' Start-up of inactive loop and flow 15.4.4, 5-controller malfunction XV-3 Inadvertent closure of main steam 15.2.4 isolation valve Group II XV-3 Loss of external load 15.2.1 i
l XV-3 Turbine trip 15.2.2 l
XV Loss of condenser vacuum 15.2.3 l
XV-3 Steam pressure regulatory failure 15.2.5 l
XV-5 Loss of feedwater flow 15.2.7 Group III XV-18 Radiological Consequences of a 15.6.4 Main Steam Line Failure Outside Containment i
Group IV XV-4 Loss of AC power to station 15.2.6 auxiliaries XV-24 Loss of all AC power Group V XV-7 Loss of forced coolant flow 15.3.1 XV-7 Primary pump rotor seizure 15.3.3 XV-7 Primary puns shaft break 15.3.4 Group VI XV-8 Uncontrolled rod assembly withdrawal 15.4.2 l
at power XV Uncontrolled rod assembly withdrawal 15.4.1 low power start-up XV-8 Control rod misoperation 15.4.3 XV-13 Spectrum of rod drop accidents 15.4.9 Group VII XV-19 Spectrum of loss of coolant accidents 15.6.5 l
Group VIII XV-21 Drop of cask or heavy equipment 15.7.5 i
XV-20 Radiological Consequences of Fuel 15.7.4 Damaging Accidents (inside and outside containment)
Group IX XV-15 Inadvertent opening of BWR safety /
15.6.1 relief valve-broup X XV-14 Inadvertent operation of ECCS 15.5.1 Group XI XV-ll-Inadvertent loading and operation of 15.4.7 a fuel ' assembly in an improper l
position-Group XII Not applicable to BWRs u.
O' 2-BWR DBE LIST (continued) i SRP RELATED GROUP SEP TOPIC
. DESIGN BASIS EVENT SECTION s
.V I' XV-8 Uncontrolled rod assembly withdrawal 15.4.2 at power Uncontrolled rod assembly withdrawal 15.4.1 XV-8 low power start-up XV-8 Control rod misoperation 15.4.3 15.4.9 XV-13 Spectrum of rod drop accidents 15.6.5 VII XV-19 Spectrum of rod drop acciaents VIII XV-20 Radiological consequences of fuel 15.7.4 damaging accidents (inside and outsiae containment)
XV-21 Drop of cask or heavy equipment 15.7.5 IX XV-15 Ir. advertent opening of BSR safety /
15.6.1 relief valve X
XV-14 Inadvertent operation of ECCS 15.5.1 XI XV-11 Inadvertent loading and operation of 15.4.7 a fuel assembly in an improper position Not applicable to BWR's XII PWR DBE LIST GROUP RELATED SRP SEP TOPIC DftIGN BASIS EVEtiT SECTION I
XV-1 Decrease in feedwater temperature 15.1.1 XV-1 Increase in feedwater flow 15.1.2 XV-1 Increase in steam flow
~15.1.3 XV-1
. Inadvertent opening of steam 15.1.4 generator relief / safety valve XV-9 Start-up of inactive loop 15.4.4 XV-10 System malfunction causing a 15.4.6 decrease in boron concentration II XV-3 Loss of external load 15.2.1 XV-3 Turbine trip-15.2.2 XV-3 Loss of condenser vacuum 15.2.3 XV-3 Steam pressure regulatory failure 15.2.5 XV-5 Loss of feedwater ficw-15.2.7 XV-6
.Feedwater system pipe break 15.2.8 C