ML17250A770
| ML17250A770 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/01/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| 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 8011180008 | |
| Download: ML17250A770 (9) | |
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"=-< IMP DlSTAIQUTiPX S~RVIC~S UXtT Docket Ho.60-244 OCTOBfR 0 1 1980 f930 NOV 6 PI',f P gP
~S XRC ST;zI 1pX SERVERS NAXCH Hr. Leon D. White, Jr.
Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Hr. Nhite:
By letter dated November 16, 1979, we sent "you the list of'opics 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 ari ongoing gener ic 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) r elated generic NRG activities and 2) non-applicability of topics to certain facilities.
The folio>ling is a li'st of such, topics and indicates their disposition:
Tii~~ait tH:~~~oil i i 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 III-8.B VI-8 XV-11 XV-18
~86'>x 80xF OFFICE P s' SURNAME
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Generic Deleted Generic Deleted Deleted Compliance is being evaluated under the EPPO effort.
This topic was-originally intended for BMR's.
i<ill be reviewed by 5RC as part of TNI Task Action Plan (HUREG-0660) as specified in Nay 7, 1980 letter to all operating reactor licensees.
This item applies specifically to B>81s.
This item applies specifically to B1/R's.
The radiological consequences of steam line breaks for PHR's is part of Topic NRC FORM 318 {9 76I NRCM 0240 AU.S. GOVERNMENT PRINTING OFFICE: 1979 289 369
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OCTOBER 0 1 198O The following two topics will not be reviewed by SEP in their entirety due to overlap with other NRC activities:
~To Ic IN II-1.B Those portions dealing with plant emergency plans will be evaluated as part of the EPPO effort-ld Those portions of the auxiliary systems being reviewed as part of Lessons
- Learned, the THI 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 l/ithdrav>al at Power" and "Uncontrolled Rod Hithdrawal-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 fiisoperation" which is applicable to PHR's.
The new topic reference list for Topic XV-'8 I
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ud Sta da d Revi P
ns 15.4.1 and 5.4.2.
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Enclosure 1 to this letter includes a revised listing of the DBE Accident and Transient Groups applicable to PMR's.
Of note should be the addition of Group XII, "Steam Generator Tube Failure and the inclusion of Fuel Handling Accidents in Group VIII.
Enclosure:
As stated DISTRIBUTION Docket NRC PDR Local PDR ORB Reading NRR Reading DEisenhut RPurple RTEdesco GLainas cc w/enclosure:
TNo>>k See next page HJeltemes, AEOD DCrutchfield HSmith SNowicki OELD 8I&E (3)
GCwalina Sincerely, Ozi~~na> sXaned b
,Dennis M.
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. Crutchg geld Dennis N. Crutchfield, Chief Operating Reactors Branch fi5 Division of Licensing
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SURNAME DATE$
NRC FORM 318 (9-76) NRCM 0240 DL 5
.DC.. chf.iel.d Ie/.(./.80 AV.S. GOVERNMEN7 PRINTING OFFICE: 1979 289Q69
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Docket No. 50-244 UNiTED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 1, 1980 Mr. Leon D. White, Jr.
Yice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. White:
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 revi ew 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.di spositi on:
~To ic I I-2. B II-2.D Cate orization Generic 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 qf the NRC Appendix I revi ew effort.
Compliance is being evaluated under the EPPO effort.
I II-8. 8 Deleted This topic was originally intended for BWR's.
VI-8 XV-11 XY-18 Generic Del eted Deleted Will be reviewed by NRC as part of TMI Task Action Plan (iiIJREG-0660) as specified in May 7, 1980 letter to all operating reactor licensees.
Thi s item appl ies speci fi ca 1 ly to BWR'.
This item applies specifically to BWR's.
The radiological consequences of steam line breaks for PWR's is part of Topic XV-2.
~hr'eon D-White The following two topics will not be reviewed by SEP in their entirety due to overlap with other NRC activities:
~TQ 1C II-1 ~ 8
~tli
(
Those portions dealing with plant emer'gency plans will be evaluated as part of the EPPO effort.
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 08E review list indicated that Group YI 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 XY-8, "Control Rod t'lisoperation" 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.
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Enclosure 1 to this letter includes a revised listing of the D8E 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.
Si ncerely, Division of Licensing
Enclosure:
As stated cc w/enclosure:
See next page
Mr. Leon D. White, Jr. October 1, 1980 cc w/enclosure:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and HacRae 1333 New Hampshire Avenue, N.
W.
Suite 1100 Washington, D. C.
20036 Hr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Committee for Sci ent ific Informat i on Robert E. Lee, Ph.D.
P. 0.
Box 5236 River Campus Station Rochester, New York 14627 J effrey Cohen New York State Energy Office
'wan Street Building Core 1, Second Floor Eoqire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 E~ire State Plaza
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontari o 107 Ridge Road West
- Ontario, New York 14519 Resident Inspector R. E. Ginna Plant
.c/o U. S.
NRC 1503 Lake Road
- Ontario, New York 14519 Director, Techni cal Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Hall t2 Arlington, Yirginia 20460 U. S. Environmental Protection Agency Region II Office ATTN:
EIS COORDINATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Saf ety and Licensing Board U. S. Nuclear Regulatory Comission Washington, D. C.
20555
'r.
Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Mr. Thomas B. Cochran Natural Resources Defense Counci.l, Inc.
1725 I Street, N.
W.
Suite 600 Washington, D. C.
20006 Richard E. Schaffstall KMC, Incorporated 1747 Pennsylvania Avenue, N.'.
Washington, D.
C.
20006
0 PWR DBE TOPIC LIST Accident and Trans ient Grou s
Group I
~(PWR Grouo II
~Grou I II Grouo IY Grouo V
RELATED TOPIC XV-1 XV-1 XV-1 XV-1 XV-9 XV-10 XV-3 XV-3 XV-3 XV-3 XV-5 XV-6 XV-2 XY-2 XV-4 XV-24 XV-7 XV-7 XV-7 DESIGN BASIS EVENT Decrease in feedwater temperature Increase in feedwater flow Increase in steam flow Inadvertent opening of steam generator relief/safety valve Start-up of inactive loop System malfunction causing rlP rrease in boron concentration Loss of external load Turbine trip Loss of condenser vacuum Steam pressure regulatory failure Loss of feedwater flow Feedwater system pipe break Steam line break inside containment S team 1 i ne break outs ide containment Loss of AC power to station auxi 1 iaries Loss of all AC power Loss o
forced coolant flow Primary pump rotor seizure Primary pump sha t break SRP 15.1.1 15.1.2 15'.1.3 15.1.4 15.4.4 15.4.6 15.2.1 15.2.2 15.2.3 15.2.5 15.2.7 15.2.8 15.1.5 15.1.5
- 15. 2.6 15.3.1 15.3.3 15.3.4 Grouo VI Grouo VII Grouo VIII XV-8 XV-8 XV-8 XY-12 XV-19 XY-21 XY-20 Uncontrolled rod assembly with-drawal at power Uncontrolled rod assembly with-drawal low power start-up Control rod misoperation Spec rum of rod ejection accidents 15.4.2 15.4.1 15.4.3 15.4.8 Drop of cask or heavy eq0i pmen Radiological Consequences of Fuel Damaging Accidents (inside and outside containment) 15.7. 5 15.7.4 Spectrum of loss of coolant accidents 15.6.5 Grouo IX Grouo X
XY-15 XY-14 Inadvertent opening of PWR pressurizer relief valve Inadvertent operation of ECCS or CYCS malfunction that causes an increase in coolant inventory 15.6.1 15.5.1 15.5.2
Enclosure 6
~Grou XI
~Grou XII RELATED TOPIC XV-17 DESIGN BASIS EVENT Not applicable to PMRs Steam Generator Tube Failure, SRP
- 15. 6. 3