ML13330A146
| ML13330A146 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/01/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| TASK-02-01.B, TASK-02-02.B, TASK-02-02.D, TASK-03-08.B, TASK-06-08, TASK-10, TASK-15-11, TASK-15-18, TASK-2-1.B, TASK-2-2.B, TASK-2-2.D, TASK-3-8.B, TASK-6-8, TASK-RR NUDOCS 8011180205 | |
| Download: ML13330A146 (6) | |
Text
Docket No. 50-206 RN 2 42 OCOBER
.0_1 8
- ~ s ~
Mr. R. Dietch, Vice President.
Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California, 91770.
Dear Mr. Dietch:
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:
Topic Categorization Disposition 11-2.83
-Generic Compliance with Appendix E is being evaluated under the Emergency Prepardness Program Office (EPPO) effort.
Compliance with Appendix I is being evaluated as part of the NRC Appendix L review effort.
11-2.0 Generic Compliance is being evaluated under the EPPO effort.
111-8.8 Deleted This topic was originally intended for BWR's.
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.
XV-11 Deleted This item applies specifically to BWR's.
XV-18 Deleted This item applies specifically to B WR's The radiological consequences of steam line breaks for PWR's is part of Topic OFFICE s u mN E
DATE b_ 2265_._
..1.....
NFC FORM 318 (9-76) NRCM 0240 U.S. GOVERNMENT PRINTING OFFICE: 1979-289-369
Mr. K. utietcn OCTOBER 0 1 1980 The following two topics will not be reviewed by SEP in their entirety due to overlap with other NRC activities:
T Disposition II-1.8 Those portions dealing with plant emergency plans will be evaluated as part of the EPPO 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.
Enclosure I to this letter includes a revised listing of the.DUE 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, DISTRIBUTION oigina h
signedby DocOe Df sM. C-utchf ield NRC PDR Dennis M. Crutchfield, Chief Local PDR Operating Reactors Branch 5
ORB Reading Division of Licensing NRR Reading DEisenhut
Enclosure:
RPurple As stated TNouak JRoe cc w/enclosure:
GLainas See next page RTedesco DCrutchfield HSmith SNowicki OELD OI*E (3)
GCwalina
- OFFICE 4
oi SNow ic DCrc'fid SURNAME w
i hii DATE J 9/ /80 1/
/80 NRC FORM 318 (9-76) NRCM 0240
- U.S.
GOVERNMENT PRINTING OFFICE: 1979-289-369'
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 1, 1980 Docket No. 50-206 Mr. R. Dietch, Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
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:
To ic Categorization Disposition II-2.B Generic Compliance with Appendix E is being evaluated under the Emergency Prepardness Program Office (EPPO) effort..Compliance with Appendix I is being evaluated as part of the NRC Appendix I review effort.
II-2.D Generic Compliance is being evaluated under the EPPO effort.
III-8.B Deleted This topic was originally intended for BWR's.
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.
XV-11 Deleted This item applies specifically to BWR's.
XV-18 Deleted This item applies specifically to BWR's.
The radiological consequences of steam line breaks for PWR's is part of Topic XV-2.
Mr.
October 1, 1980 The following two topics will not be reviewed by SEP in their entirety due to overlap with other NRC activities:
Topic Disposition II-1.B Those portions dealing with plant emergency plans will be evaluated as part of the EPPO 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, nnis M. Cru chfleld, C ef Operating Reactors Brancn #5 Division of Licensing
Enclosure:
As stated cc w/enclosure:
See next page
Mr. ctober 1, 1980 cc w/enclosure:
Charles R. Kocher, Assistant Director, Technical Assessment General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (AW-459)
Rosemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Crystal Mall #2 SSamuel B. Casey Arlington, Virginia 20460 Chickering & Gregory Three Embarcadero Center U. S. Environmental Protection Twenty-Third Floor Agency San Francisco, California 94111 Region IX Office ATTN:
EIS COORDINATOR Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisco, California 94111 San Diego Gas & Electric Company P. 0. Box 1831 Mr. Richard E. Schaffstall San Diego, California 92112 KMC, Incorporated 1747 Pennsylvania Avenue, N. W.
Resident Inspector Washington, D. C. 20006 c/o U. S. NRC P. 0. Box AA Oceanside, California 92054 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814
PWR DBE TOPIC LIST Accident and Transient Groups 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 boron concentration Grouo 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 Group III XV-2 Steam line break inside containment 15.1.5 XV-2 Steam line break outside containment 15.1.5 Grouo 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 pump shaft break 15.3.4 Grouo VI XV-8 Uncontrolled rod assembly with-15.4.2 drawal at power XV-8 Uncontrolled rod 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 GrouD VII XV-19 Spectrum of loss of coolant accidents 15.6.5 Grouo 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 PWR 15.6.1 pressurizer relief valve Group X XV-14 Inadvertent operation of ECCS or 15.5.1 CVCS malfunction that causes an 15.5.2 increase in coolant inventory