ML20027B975
| ML20027B975 | |
| Person / Time | |
|---|---|
| Issue date: | 07/26/1982 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Udell R Public Citizen's Critical Mass Energy Project |
| References | |
| FOIA-82-261 NUDOCS 8210120090 | |
| Download: ML20027B975 (5) | |
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f July 26,1982 Mr. Richard A. Udell CRITICAL MASS ENERGY PROJECT 215 Pennsylvania Avenue, S.E.
IN RESPONSE REFER Washington, DC 20003 TO F0IA-82-261
Dear Mr. Udell:
r This supplements ut previous letters to you concerning the subject FOIA request.
l The enclosed undated document identified as "Sumary of Events Discussed i
At Operating Reactor Events Meetings During 1981" (1 page); "Most Significant Events of 1981" (1 page); and "Less Significant Events of 1981" (2 pages) is being provided to you pursuant to your verbal request tc the NRC's technical staff under the subject F0IA request.
Sincerely, I
. celton, Director ivision of Rules and Records Office of Administration
Enclosure:
As stated s
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.UDELL82-261 PDR
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SUMMARY
OF EVENTS DISCUSSED t
AT OPERATING REACTORS EVENTS MEETINGS i
DURING 1981
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The attached lists present background information used in developing the I
summary information presented at the December 16, 1981 Operating Reactors Events meeting.
The events discussed at all of the 1981 meetings were l
reviewed and the most significant, less significant and least significant were sorted out and assigned 3, 2 or 1 points respectively. A summary of the least significant events is not included here since it can be readily developed if needed from the total of all events discussed (already identified i
in the meeting minutes for 1981 meetings) minus the events identifv'd on the two attached lists.
l It should be noted that this information was developed in the normal course of preparing information for presentation at an internal NRC meeting con-cerning operating reactor events and that this information did not receive f
NRR nanagement review and appqoval either before or after the meeting.
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v Most Significant Events of 1981 f
1/2/81 M111stene 2 (CE) Loss of DC Power E 1/6/81 Palisades (CE) Lors of Both DC Batteries f
1/29/81 H.B. Robinson (1) CVCS Leak l
2/11/81 Sequoyah 1 (g) 100,000 gal of Reactor Coolant Sprayed into Containment 3/6/ 81 Beaver Valley (E) Loss of Decay Heat Removal 4
4/ 8/ 81 Arkansas Nuclear-0ne. Unit 1 -(BW) Overfeed of 0TSG ad / ra s
- 5/5/ 81 Brunswick 1 + t Inadequate Shutdown Cooling
- 6/6/81 Beaver Valley (1) Sabotage to ECCS/ Aux FW 6/16/81 Crystal River 3 (BW) Loss of AC & DG Failure 6/24/81 Davis Besse (88W) Loss of NNI 7/3/81 North Anna (E) Transformer Fire i
7/15/81 Palisades (CE) Loss of Decay Heat Removal 8/6/ 81 Sequoyah 2 (E) 9,000 gal RCS Drained to Sump
- 9/3/81 San Onofre 1 (E) ECCS Valve Failures l
r 11/30/81 H.B. Robinson (1) PORY Leak ar.d Block Valve Failure M11/29/81 Turkey Point Unit 4 g) Low Temperature 0verpressurization f
12/19/81 St.. Lucie Unit'l (CE) SV Failure, 2 RCS Blowdowns r
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i LESS SIGNIFICANT EVENTS OF 1981 r/zt/fl Browns Ferry 3 Leak Rate Exceeding T/S f
- *[# M Calvert Cliffs 2 Inadequate Shutdown Cooling
~ //fl Fitzpatrick Loss of Power 4/28/81 Ft. Calhoun Partial Loss of DC Power
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4/14/81 Ginna Loss -of Offsite Power r
5/20/81 Indian Point 3 Loss of Offsite Power
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Millstone 1 Pipe Crack
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4/27/81 Monticello Loss of Offsite Power i
4/1 4/81 Peach Bottom 3 Spill Outside Containment (Flooding)
I 3/ /81 Quad Cities Valve Failure
-M3/12/81 Rancho Seco Service Water Problem I/ / 81 Robinson 2 Spill Inside Containment 4/8/ 81 Salem 2 SI/ECCS Actuation 3"
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l 2/8/81 Sequoyah Loss of Coolant Rod Annunciation sto,~
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l 2/11/81 Sequoyah Loss of CoeJant Rod Annunciation P. -
t 2/16/81 Sequoyah Loss of Coolant Rod Annunciation l
5/13/81 Sequoyah 1 SI/ECCS Actuation
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4/24/81 Sequoyah 1 SI/ECCS Actuation
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f 5/1/81 Sequoyah 1 SI/ECCS Actuation
_ f 2/a'7/81 Trojan Loss of Control Room Annunciators 5/7/81 Zion 2 Inverter Failure a
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- 10/21/81 Pilgrim RBC0i Heat Exchanger Failure 11/30/81 Robinson 2 RCS Leak, PORV Leak 6/ 81 & 7/ 81 Brunswick 2 MSIV Failures 7/16/81 Oconee 1 Loose Parts 9/14/81 McGuire 1 Overcooling Event 8/10/81
~ Millstone 1 High Reactor Vessel Level 7/ 31 / 81 Millstone 2 Turbine Trip and Single Failure I
7/8/81 Salen 2 Poor Startup Experience 11/14/81 Ginnna Actuation of Fire Suppression System L
9/81 Rancho Seco Desicant Found in Air System 7/7/81 Surry 1 Fire Line Orifice Failure 5/22 to 6/.5.
Farley 2 Poor Startup Experience 5/21 to 6/3 Indian Point 2 Poor Startup Experience
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5/20 to 6/3 Salen 2 Poor Startup Experience e
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- A Branch of Public Citizen, Inc.
O June 3, 1982 Mr. Joseph Felton FREEDOM OF INFORMATON Division of Rules and Records ACI REQUEST FOIA Office
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20555
Dear Mr. Felton:
Pursuant to the Freedom of Information Act 5 USC 6 9 (subpart A), the Critical Mass Energy Project hereby requests copies of the information detailed below.
The requested documents will be used in our annual study of nuclear reactor events and safety problems.
Because our study will be published in our monthly Critical Mass Energy Journal and distributed to the press,. and will therefore be used in the general public interest, we request a complete waiver of all costs you might incur in processing this information or in providing us access to it under provisions at 10 CFR E 9, 14a and the Freedom of Information Act.
Nothing in this request should be interpreted as a request for the private
- records of a specific individual.
Hence no provisions of the Privacy Act should be deemed applicable.
If all or any part of this request is denied,.please cite the specific exemption.(s) which you think justifies your refusal to release the informat.on and inform us of the appeal procedures available to us under law.
The materials and information sought are as follows:
1.
Any list or compilation of records which would show how many times the NRC Operat.lons center was utilized or put in standby mode during 1981.
t 2.
Any list or compilation of records which would include information about any site area or general emergency events occurring.in 1981.
3.
Any and all reports, memoranda, studies, SECY papers or other documents by AEOD, NRR, EDO, Division of Licensing, DEP, I&E or other NRC offices which report, analyze or evaluate events or mishaps occurring in 1981.
LERs and PNOs are not included in this request.
215 Pennsylvania Ave., SE a Washington,DC 20003 m (202) 546-4790 pp' n
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4.
Any review, study, report or memorandum by NRC (including but not limited to 'the following offices:
AEOD, NRR, Divlsion of Licensing, Lessons Learned Task Force, DEP, I&E, EDO) that, evaluate LER trends ear relatior. ship between LERs
-(or PNOs) and nuclear safety or economics.
Only documents written during or since 1980 are being requested.
We are particular:ly interested in any study similar to NUREG-0572, if such materials exist.
5.
Any NRC review or critique (including but not limited to Commissioner's. briefing papers) of
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NRC's SALP report made public in September.
If NRC
- bas in its files letters or reviews of SALP from other agencies or organizations, these are also requested.
6.
Any review or critique of Critical Mass' 1980 LER study:
" Nuclear Power Plant Safety Scoreboard 1980:
3,800+ Mishaps."
7.
Any update of C.G. Long's July 30, 1979 memorandum for R.J. Matson, or any similar document or studies, which reviews LER's or power plant aishaps for loss of safety function due to personnel error and/or defective procedures.
8.
Any NRC or industry studies which analyze LERs (or PNOs or other significant events) and note what if any relationship they have to vendor, capacity, performance record, plant management or economic iRBicators (e.g., bond rating).
Only documents written during or since 1980 are requested.
9.
Any and all documents, including but not limited I
to computer printouts and AEOD studies, that detail what if any relationship LERs (or PNOs or other significant events) have with unresolved and generic safety problems (including USIs)
- 10. ' A copy of all 1981 LERs (or those available) which includes AEOD's A,B,C,D,E, letter grade.
(See last year's FOIA-81-llS.
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I 11.
Any and all studies, memoranda,' reports, letters, articles or other documents by
-NRC and/or its contractoxs or industry of capacity factors and/or optage times for plants written, received or routed during or since 1980.
12.
Any and all studies, memoranda, reports, letters, articles or other documents by NRC, its contractors, industry or others
- that analyze, critique, estimate or evaluate i
the accuracy or reliability of LER cause codes.
13.
Any and all studies, memoranda, reports, letters or other documents (including but not limited to internal memoranda between NRC staff, SECY papers, and memoranda or brief-ing papers for NRC Commissioners) which discuss, evaluate, analyze or explain the causes of' i
steam generator problems at TMI I.
only documents written during or since 1980 are being requested.
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14.
Any cost benefit or value impact analysis by NRC and/or its contractors on industry of resolving or eliminating unresolved safety issues or generic requirements.
Only documents written during or since 1980 are being' requested.
15.
Any and all proposals since 1979 to eliminate generic requigements or unresolved safety issues written by or routed through CRGR, NRR.
Division of Licensing, EDO, Commissioners' offices, or other NRC offices.
16.
Any documents that identify which NRC office (s),
branch (es), division (s) or individual (s) are assigned responsibility for reviewing and/or analyzing LERs and significant operating reactor events.
17.
Summaries of all Operating Reactor Events Meetings'an'd all memoranda, reports, studies or other documents arising out of those meetings or written between meeting attendeec previous-
.to the_ meetings.
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Specifically included in this request are minutes
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or memos from each week 1f.; meeting, I&E's " Items of Interest", and the rating system (1-low safety sig-nigicance, 2-moderate safety significance, 3-high safety significance) attached to each operating reactor event.
Also included in this request is
" Summary of Operating Experience for the Six Months June 1981 through December 1981 18.
A list of population estimates for the 10 and i
50 mile radius around each nucicar plant or construction project.
If no such list exists, then please inform us about what documents do exist.
NUREG/CR.-1856 vol.1 and 2 is not complete in this regard.
19.
If NRC has a list of evacuation time estimates for the 10 mile radius around each nuclear plant or construction project that is either more recent or accurate than NUREG/CR-1856 Vol, 1 and 2,
then we would appreciate access to it.
Specifically we would like to know if there are new evacuation time estimates using the CLEAR model described in NUREG/CR-2504.
While your office has been most cooperative in the past, it has not always been the most prompt.
We ask to receive a substantive reply to this request within ten (10) working days as is required by law.
If your office will not be able to complete this request in that amount of time, then we would appreciate receiving in writing an estimate on when you think it will be complete.
e Thank you so much for your attention to this matter.
Sincer ly, r
Rich rd A. Udell 1
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