ML19338G569
| ML19338G569 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/01/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| TASK-02-01.B, TASK-02-02.B, TASK-02-02.D, TASK-03-08.B, TASK-06-07.A2, TASK-06-08, TASK-10, TASK-15-08, TASK-15-11, TASK-15-18, TASK-2-2.B, TASK-RR NUDOCS 8010310185 | |
| Download: ML19338G569 (5) | |
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ja, UNITED STATES e
A NUCLEAR REGULATORY COMMISSION e
.rp WASHINGTON, D. C.,20555 g
October 1,1980 Docket No. 50-213
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Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
By 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 November 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 their disposition:
Tooic Catecorization Discosition II-2.8 Generic Compliance with Appendix E is being evaluated under the Emergency Prepardness Program Office (EPP0) effort.
Compliance with Appendix I is being evaluated as part of the NRC Aopendix I review effort.
II-2.D Generic Compliance is being evaluated under the EPP0 effort.
III-8.B Deleted This topic was criginally intended f or BUP,'s.
VI-2 Generic Will be reviewed by NRC as part of TMI Task Action Plan (t;UREG-0660) as specified in May 7,1980 letter to all operating reactor licensees.
XV-ll Deleted This item applies specifically to BWR's.
XV-13 Deleted This item applies specifically to BWR's.
The radiological consequences of steam line breaks for PUR's is part of Topic XV-2.
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4 October 1,1980 Mr. W. G. Counsil.
Catego'ization Discosition Topic r
VI-7 A.2 Deleted Not applicable to this unit's design.
The following two topics will not be reviewed by SEP in their entirety due to overlap with other NRC activities:
Tooic Discosition II-l.S Those portions dealing with plant emergency plans will be evaluated as part of the EPP0 effort.
X Those portions of the auxiliary systems being reviewed as part of Lessons Learned, the TMI Action Plan and IE Circular 80-04 will not be reviewed by SEP.
In addition, the original DBE review list indicated that Group VI events,
" Uncontrolled Rod Withdrawal at Power" and " Uncontrolled Rod Withdrawal -
Low Power Startup" were part of Topic XV-13 which does not apply to PWR's.
The actual topic reference should be Topic XV-8, " Control Rod Misoperation" which is applicable to PWR's. The new topic reference list for Topic XV-8 should include Standard Review Plans 15.4.1 and 15.4.2. to this letter includes a revised listing of the DBE Accident and Transient Groups applicable to PWR's. Of note should be the addition of Group XII, " Steam Generator Tube Failure and the inclusion of Fuel Handling Accidents in Group VIII.
Sincerely, A-k.
Dennis M. Crutchfield, C' ef Operating Reactors Branen #5 Division of Licensing
Enclosure:
As stated
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cc w/ enclosure:
See next page 1
I l
4 Mr. W. G. Counsil October 1,1980 cc w/ enclosure:
Day, Berry & Howard U. S. Environmental Protection Counselors at Law Agency One Constitution Plaza Region I Office Hartford, Connecticut 06103 ATTN: EIS COORDINATOR JFK Federal Building Superintendent Boston, Massachusetts 02203 Haddam Neck Plant RFD #1 Resident Inspector Post Office Box 127E Haddam Neck Nuclear Power Station East Ha@ ton, Connecticut 06424 c/o U. S. NRC East Haddam Post Office Mr. James R. Himmelwright East Haddam, Connecticut 06423 Northeast Utilities Service Cogany P. O. Box 270 Richard E. Schaffstall Hartford, Connecticut 06101 KMC, Incorporatad 1747 Pennsylvania Avenue, NW Russell Library Washington, D. C.
20006 119 Broad Street Middletown, Connecticut 06457 Board of Selectmen Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency ATTN: Assistant Director Research and Policy Development Department of Planning and Energy Policy 20 Grand Street Hartford, Connecticut 06106 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
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PWR DBE TOPIC LIST Accident and Transient Groucs RELATED TOPIC DESIGN BASIS EVENT SRP Group I XV-1 Decrease in feedwater temperature 15.1.1 (PWR)
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 15.4.6 decrease in baron concentration Grouc 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 flow 15.2.7 XV-6 Feedwater system pipe break 15.2.8 Grouc III XV-2 Steam line break inside containment 15.1.5 XV-2 Steam line break outside containment 15.1.5 Grouc IV XV-4 Loss of AC power to station 15.2.6 auxiliaries XV-24 Loss of all AC power Grouc V XV-7 Loss of forced coolant flow 15.3.1 X'i-7 Primary auma rotor seizure 15.3.3 XV-7 Primary pump shaft break 15.3.4 Grouc VI XV-8 Uncontrolled rod assembly with-15.4.2 drawal at power XV-8 Uncontrolled roc assembly with-15'.4.1 drawal low power start-up XV-8 Control rod misoperation 15.4.3 XV-12 Spectrum of rod ejection accidents 15.4.8 Grouc VII XV-19 Spectrum of loss of coolant accidents 15.5.5 Grouc VIII XV-21 Drop of cask or heavy ecuipment 15.7.5 XV-20 Radiological Consequences of Fuel 15.7.t Damaging Accidents (inside anc outside containment)
Grouc g XV-15 Inadvertent opening of ?WR 15.5.1 pressuri:er relief valve Grouc X XV-14 Inadvertent coeration of ECCS or 15.5.1 CVCS malfunc-ion tnat causes an 15.5.2 increase in coolant inventory
. RELATED TOPIC DESIGN BASIS EVENT SRP Grouc XI Not applicable to PWRs Grouc XII XV-17 Steam Generator Tube Failure 15.5.3 O