ML19339C379
| ML19339C379 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/26/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-02-02.B, TASK-02-02.D, TASK-03-08.B, TASK-06-08, TASK-2-2.B, TASK-2-2.D, TASK-3-8.B, TASK-6-8, TASK-RR NUDOCS 8011180251 | |
| Download: ML19339C379 (5) | |
Text
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- i GT!!OUTION September 26, 1980 hi25 GT Docket No. 50-219 T40 Mi 6 RI 2 44
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I, 'l.',C Mr. I. R. Finfrock, Jr.
~ $$ERVICES Vice President - Generation Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road i
Morristown, New Jersey 07960 4
Dear Mr. Finfrock:
Dy letter dated November 16, 1979, we sent you the list of topics which would not be reviewed by your plant in the Systcoatic Evaluation Prograr (SEP).
These topics werc 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 addit %nal 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:
1 Topic Categorization Disposition 11-2.B Generic Conpliance with Appendix E is being evaluated under the Emergency Prepardness Program Of fice (EPPO) effort.
Compliance with Appendix I is being evaluated as part of the NRC Appendix I review effort.
11-2.0 Generic Conpliance is being evaluated under the EPPO effort.
III-8.B Deleted The review published as NUREG-0479,
" Report on BWR Control Rod Drive Failures" fulfills the intent of this topic.
VI-8 Generic Wi 1 Se reviewed by NRC as part of TMI ask Action Plan (NUREG-0660) as specified in May 7, 1980 letter to all operating reactor licensecs.
z Those parts of Topic 11-1.8 " 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 Assembly Withdrawal at Power and " Uncontrolled Rod Assembly Withdrawal - Low Power Startup" are a Boinsox i
Mr. I. R. Finf rock 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 B'N'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 Inclusion of Fuel Handling Accidents in Group VIII.
Sincerely, "M U pennisM.CrutchfieldQ,iief Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page e
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Mr. I. R. Fi nf rock, J r. September 26, 1980 cc G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road Trenton, New Jersey 08628 GPU Service Corporation ATTN: Mr. E. G. Wallace Connissioner Licensing Manager New Jersey Department of Energy 260 Cherry Hill Road 101 Commerce Street Parsippany, New Jersey 07054 Newark, New Jersey 07102 Natural Resources Defense Council Plant Superintendent 917 15th Street, N. W.
Oyster Creek Nuclear Generating Washington, D. C.
20006 Station P. O. Box 388 Forked River, New Jersey 08731 Steven P. Russo, Esquire 248 Washington Street Resident Inspector P. O. Box 1060 c/o U. S. NRC Tons River, New Jersey 08753 P. O. Box 128 Forked River, New Jersey 08731 Joseph W. Ferraro, Jr., Esquire Deputy Attorney General Director, Technical Assessment Div.
State of New Jersey Office of Radiation Programs Department of Law and Public Safety (AW-459) 1100 Raymond Boulevard U. S. Environmental Protection Newark, New Jersey 07012 Agency Crystal Mall #2 Ocean County Library Arlington, Virginia 20460 Brick Township Branch 401 Chambers Bridge Road U. S. Environmental Protection l
Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS COORDINATOR Lacey Township 26 Federal Plaza P. O. Box 475 New York, New York 10007 Forked River, New Jersey 08731 Commissioner Department of Public Utilities i
State of New Jersey l
101 Commerce Street Newark, New Jersey 07102 l
BWR DBE TOPIC LIST Accident and Transient Groups RELATED TOPIC DESIGN 9 ASIS EVENT SRP Group I XV-1 Decrease in feedwater temperature 15.1.1 (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.d.4, 5 controller malfunction XV-3 Inadvertent closure of main steam 15.2.4 isolation valve Group 11 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 Group III XV-18 Radiological Consequences of a 15.6.4 Main Steam Line Failure Outside Containment Group 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 XV-7 Primary pump rotor seizure 15.3.3 XV-7 Primary purp shaft break 15.3.4 Group VI XV-8 Uncontrolled rod assembly withdrawal 15.4.2 at power XV-8 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 Group VIII XV-21 Drop of cask or heavy equipment 15.7.5 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 6
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 position Group XII Not applicable to BWRs
I
~2-BWR DBE LIST _ (continued) i SRP RELATED SECTION GROUP SEP TOPIC DESIGN BASIS EVENT Uncontrolled rod assembly withdrawal 15.4.2 P
VI XV-8 at power Uncontrolled rod assembly withdrawal 15.4.1 XV-B 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 accicents VIII XV-20 Radiclogical consequences of fuel 15.7.4 damaging accidents (inside and outside containment) 15.7.5 XV-21 Drop of cask or heavy equipment IX XV-15 Inadvertent opening of BSR safety /
15.6.1 relief valve X
XV-14 Inadvertent operation of ECCS 15.5.1 XI XY-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 SRP GROUP RELATED SEP TOPIC, DESIGN BASIS EVENT 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 1
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 i