ML19308C119
| ML19308C119 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/20/1979 |
| From: | Mallory K ESSEX CORP. |
| To: | Pickleshimer M NRC - NRC THREE MILE ISLAND TASK FORCE |
| Shared Package | |
| ML19308C116 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001210416 | |
| Download: ML19308C119 (16) | |
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_sV ESSEX 1
i August 20, 1979 MEMORANDUM TO:
Marion Pickles imer Nuclear Regulatory Commission FROM:
Ken Mallory Essex Corporation
SUBJECT:
Request for Information from Metropolitan Edison Attached is a list of Metropolitan Edison and Burns & Roe documentation needed by Essex to com-plete Task A - Control Ro om Designiat TMI-2.
If you have questions or need clarification, please call (703) 548-4500.
8 001210 h.((
- ESSEX CORbORATION
- 333 North Fairfax Street, Alexandria Virginia 22314 * (703) 548-45(-
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A.
List of TMI-2 Operator Procndures o
EP 2202-1.1"'
Reactor Trip EP 2202-3.3v' Loss of
. Coolant / Coolant Sys. Press o
o EP 2202-1.4v' Loss of RC Flow /RC Pumptrip o
OP 2102-3.lF Unit Shutdown o
OP 2102-1.3 /
Unit Startup o
SP 2303-M4 Control Rod Movement Exercise o
SP 2303-M16 Diesel Testing o
Manual Overide Pro 7edures for ICS B.
Specification 2555-46 Control Boards, Control Systems and
'1In' strum'entati'on, Jersey Central Power and Light Company, Three Mile Island Nuclear Station, Unit No. 2 Burns and Roe, Inc. Engineers and Constructors.
o Part 14 Engineer's Drawings and Specifications of Section lA General Requirements-Delivery of Division 1 General Requirements and Special Conditions o
Part 26 Testing and Startup of Section lA, Division 1 o
Part 3.2 Instruction Manuals and Spare Parts Lists of Section 1B Special' Conditions of Division 1 General Requirements and Special Conditions o
Part 9.0 Conformance with Trade Practices of Section 1B, Division 1 o
Part 10.0' Federal OSHA Regulations of Section 1B, Division 1 The following parts of Section 2A Control Boards, Control o
Systems and Instrumentation of Division 2 Technical' Specifications:
2.1 Work to be Provided 2.3 Codes and Standards 2.4 Drawings 3.2 Seismic Conditions 3.5 Mimic Lines and Color Coding 3.6 Panel Finish and Painting 3.7 Electrica3 Requirements i
e 3.8 Pneumatic Requirements 3.14 Instrumentation and Control System 3.15 Thermowells 5.1 Acceptance Tests 5.4 Operational Tests 5.5 Calibrations 1
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ATTACHMENT B ESSEX TMI-2 DOCUMENT LOG 0
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TMI-2 DOCUMENT LOG AUGUST 10,1979 I
NUREG-0573, TMI-2 Lessons Learned Task Force Status Report and Short-Term Recornmendations 2
NUREG-0568, Title List Publicly Available Documents Three Mile Island Unit 2,
, Docket 50-320 (Cumulated to May 21, 1979) 3 TMI-2 Investigation Report (Draft) NRC (by IE investigation team) 4 Safety Evaluation by the Division of Reactor Licensing U.S. Atomic Energy
- Commission in the Matter of Met. Ed. Co. and 3ersey Central Power and Light
- Co. TMI-2, Docket No. 50-320, 1969 5
NUREG. 9094, NRC Operator Licensing Guide 6
Code of Federal Regulations 10 Energy, Parts 0-199, 1/1/79 7-10 Preliminary Safety Analysis Report, Volumes 1-4 11 IEEE //279,1963, Proposed IEEE Criteria for Nuclear Power Plant Protection Systems
-- 12 IEEE Std. 279-1971/ ANSI N42.7-1972 An American National Standard /IEEE Standard:
Criteria for Protection Systems for Nuclear Power Generating Stations 13 Attachment to Enclosure 3, IEEE-279, Regulatory Guides, TMI-2 PSAR 14 IEEE Std. 566-1977 IEEE Recommended Practice for the Design of Display and Control Facilities for Central Control Rooms of Nuclear Power Generating Stations 15 ANSI N13.1-1971 American National Standard Selection and Training of Nuclear Power Plant Personnel 16 ANS-3.4/ ANSI N546-1976 Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants 17 ANSI N13.7-1976/ANS-3.2 Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants 1S ANSI /ANS-3.1-1978 ANS for Selection and Training of Nuclear Power Plant Personnel
.19 ANSI /ANS-3.5-1979 ANS Nuclear Power Plant Simu!ators for Use in Operater Training
- 20-31 Final Safety Analysis Report TMi-2 (Met. Ed.) Dec
- :et No. 50-320, Vo:umes 1-XI!!
_ (Vol. XII missing) y p.
-er
32 Digital Control Technology Person-Machine Interface R6:D, Tenta:ive Func:icnd Requirements and Design Criteria f or Operator in:erfaces (Exxon) 33 Inf orma:ica Repor:s; SECY-79-330, SECY-79-33SA, 5, C & D.
Subjec: Ma:ter:
Training and Operator Licensing 34 NRC Regulatory Guides:
o 1.134, Medical Evaluation of Nuclear Power Plant Personne! Requiring l
Operator Licenses, 3/79 o
1.114, Guidance on Being Operator at the Controls of a Nuclear Power Plant, 11/76 o
1.S, Personnel Selection and Training,9/75 o Draf t and Value/ Impact Statement Task RSS07-5 Personnel Selection and Training (Proposed Revision of Reg. l.S),2/79 1.33, Quality Assurance Program Requirements (Operation),2/73 o
S.3, Info. Relevant to Ensuring that Occupational Radiation Exposures at o
Nuclear Power Stations will be as Low as is Reasonably Achievable,6/7S 35 Nuclear Safety Analysis Center Sequence of Events TMI-2 Accident - March 23, 1979, with Appendix Aux. Bldg.,6/79 36 Training and Certification of Med. Ed. Co. TMI-2 Licensed Personnel
-37 Report of TMI-2 Accident Assessment Documentation - Training Programs and Procedure Review,3/16/79 33 TMI Documents: TM-431, 3/13/79, Med. Ed. Co.; TM-473, TM-4S2, TM-0279, TM-0429 (Hand-written Documents of the sequence of events) 39 Transmitta! #W14S, 4/10/79, TMI Procedure 2" Evaluation of Unit !! Control Room - Emergency Procedure" 40 PSAR (excerpts) Reactor Bldg. design 41 Description of Human Factors Reports by Sandia Labs,5/73 42 NRC Memo: Minimum Requirernents for Con:rol Room Manning by Licensed Resctor Opera: ors h3 Commissioner Action, SECY79-330E, Qualifications of Reactor Operators 44 Standard Review Plan, NUREG-75/037, Section 13.2 - Training 45 Nuclear Safety Analysis Center Sequence of Events TMI-2 Accident, 3/2S/79, Rev. 2 6/2S/79 46 NSAC Summary Description of the TMI-2 Acciden:,6/S/79 L7 Procedure to prevent loss-of-core-cooline sccidents,1202.%
43 Long Term Dynamic Response of Power Systems:
An isnalysis of Major Disturbances, IEEE Transactions on Power Apparatus and Systems Vol. PAS-94,
- 3,3-6/75 49 Duke Power Company Oconee Nuclear Station Loss of Reactor Coolant, EP/0/-
A/IS00/4 50 Draf t Chronology of TMI-2 Accident - Task Force 2 51 Testimony of Dale G. Bridenbaugh, Richard B. Hubbard, Gregory C. Minor before the Joint Committee on Atomic Energy 2/1S/76 52 Section 5, Operator Motion Requirements in a Control Room (Hypothetical
, Accident) 53 Section 6, Special Topics (Reactor Safety Study) Human Reliability Analysis 54 NUREG/CR-0110, Licensee Performance Evaluation 55 NSMB SR-18, 5/31/79, Status Report of Projects Under the Nuclear Standards Management Board 56 NUREG-0006, Water Reactor Safety Research Program: A Description of Current and Planned Research 57 Phenomena, Comment and Notes (The Smithsonian Magazine)
!EEE Std. 4SS-1973, Standard Digita! Interface fo.- Programmable Instrumen-tation 59 IEEE Std. 566-1977, Recommended Practice for the Design of Display and Control Facilities for Central Control Rooms of Nuclear Power Generating Stations 60 ANS-3.2/ ANSI NIS.7-1976, Administrative controls and quality assurance for the operational phase of nuclear power plants 61 ANS-3.4/ ANSI N546-1976, Medical certification and monitoring of personnel requiring operator licenses f or nuclear power plants 62 ANSI /ANS-3.1-197S, For selection and training of nuclear power plant personnel 63 PS67/4H, Criteria for the Design of the Control Room Complex for a Nuclear Power Generating Station 64 HF Review of Nuclear Power Plant Cont.ol Room Design, EPRI NP-309,1976, (Lockheed) 65 HF Review of Nuclear Power Plant Control Room Design, EPRI NP-309-SY,1976 (Lockheed) 66 Human Engineering of Nuclear Power Plant Control Rooms rad its Effects en Operator Perf ormance, ATR-77(2S!5)-1,1977 (Aero pr.ce Corp.)
67 EPRI AF-1041, The Role of Personnel Errors in Power Plant Equipment Reliability' 63 Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendix Ili and IV: Failure Data,1975 (NRC) 69 NUREG-0438, Plan for Research to Improve the Safety of Light-Water Nuclear Power Plants,4/12/73 (Report to U.S. Congress) 70 NUREG-0496, 1978, Review and Evaluation of the Nuclear Regulatory Com-mission Safety Research Program (report to U.S. Congress) 71 Investigation of Charges Relating to Nuclear Reactor Safety, Hearings Before
, the Joint Committee on Atomic Energy (U.S. Congress) Vol. I: Hearings and Appendices 1-11 72 Conference Proceedings: Power Plant Operator Selection Methods, EPRI SR28, 1976 73 On-Line Power Plant Alarm and Disturbance Analysis System, EPRI NP-613, 1978 74 Duke Power Company Oconee Nuclear Station Loss of Reactor Coolant 75 NUREG-0006, Water Reactor Safety Research Program 76 Draf t Chronology of TMI-2 Accident - Task Force 2
77 Human Factors Work Plan and Response to Questions, Hurnan Factors Task Force - NRC/TM! Special Inquiry Group,1979, parts IS2.
78 Three Mile Island Nuclear Station Unit 2 - Technical Specifications, NUREC-0432, Appendix "A", License No. DPR-73.
79 NSAC-1,1979, Analysis of Three Mile Island - Unit 2 Accident, Nuclear Safety Analysis Center SO Report Outline,1979, NRC, TMI Special Inquiry SI LER Output on Events at TMI 1 and 2 from 1969 to the present output sorted by Facility and Event Date,1979.
S2 LER Monthly Report,1979, July.
83 NUREG-0600, Investigation into the March 28,1979, Three Mile Island Accident by Office of Inspection and Enforcement - Investigative Report No. 50-320/79-10.
84 Title 10 - Chapter 1,1967, part 40, CFR.
SS Handout for " Technical Specifications," Given at RP!,1979, July 18.
86 Safety Evaluation by the Division of Reactor Licensing - U.S. Atomic Energy Commission,1969, September.
87 NUREG-0107, Safety Evaluation Report-related to Operation of Three Mile Island Nuclear Station, Unit 2, September 1976.
SS Operation of TMI Nuclear Station, Unit 2, Metropolitan Edison Company, Jersey Central Power and Light Company, PB-277192, February 1979.
89 Operation of Three Mile Island Nuclear Station, Unit 2, PB-265-67, February 1977.
90 NRC/TMI Special Inquiry Item 1 of July 1979, Request.
91 NFPA No. 801, Facilities Handling Radioactive Materials,1975.
92 ANSI N278.1-1975, Self-Operated and Power-Operated Safety-Related Valves Functional Specification Standard-American National Standard Reactor Plants and Their Maintenance.
93 ANSI N41.6/IEEE Std. 382-1972, IEEE, Trail-Use Guide for Type Test of Class !
Electric Valve Operators for Nuclear Power Generating Stations, Draft American National Standard 94 ANSI N41.26/IEEE Std. 497-1977; IEEE, Trail-Use Standard Criteria for Pvst Accident Monitoring Instrumentation fer Nuclear Power Generating Stations, Draf t American Nations! Standard.
95 ANSI NI.I.2S-1976/IEEE, Std. 494-1974. IEE' Standard Method for Identificatio,
of Documents Related to Class IE Equipment and Systems Ic.- Nu:! car Powe.-
Generating Stations, An American National Standard.
e 96 ANSI /IEEE, Std. 333-1975, IEEE, Standard Modular Instrumentation and Digita' Interf ace System (CAMAC*), An American National Standard.
97 ANSI N41.9-1976/IEEE, Std. 334-1974, IEEE, Standard for Type Tests of Continuous Duty Class IE Motors for Nuclear Power Generating Stations, An American National Standard.
98 IEEE Std. 323-1974, IEEE, Standard for Qualif ying Class IE Equipment for Nuclear Power Generating Stations.
99 IEEE, Std. 317-1976, IEEE, Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations.
100 ANSI N13.1-1969, Guide to Sampling Airborne radioactive materials in Nuclear f acilities, American National Standard.
101 TMI-2, Control Room, Manning Assignments, Public Document 7905190032.
102 Current Status of NRC Chronology of Events During the TMI-2 Accident, Public Document 7905140013, April 25,1979.
103 Action Plan for Developing Regulatory Options on Sister Babcock & Wilcox Operating Reactors - Public Document 7905160081,P.
104 Hart Testimony, NRC, April 9,1979, Public Document 790509023,G.
105 Letter from Congressman Preyer - ACRS Subcommittee Meeting on Three Mile Island, April 3,1979, NRC Public Document 7905140lSS,H.
106 Preliminary Recommendations for Additional Operational Safety Research,, April 16,1979, Public Document 7905110330,P.
l 107 Witness List for Second Hart Hearing on Three Mile Island - Unit 2, April IS, 1979, Public Document 7905160023,H.
103 Interim Report on Recent Accident at the Three Mile Island Nuclear Station Unit 2, April 7,1979, Public Document 7904170042.
109 Telephone Call from Don C. Beatty, Manager, Nuclea.- Construction and Maintenance, Catalytic, Inc., April 12,1979, Public Document 7905210034,P.
11C.
Special Operating Procedures Notes and Information, March 31 - April 11, 1979 Public Document 79052100 79, P 111.
TMI-2 Reactor Core Status Instrumentation Data Package, April 11, 1979, Public Document 7905190230 112.
Information Provided by GPU on TMI-2 Shutdown Procedures and on Sequence of Events of TMI-2 Accident, April'28, 1979, Public Document 7905140023 113.
Three Mile Island Accident, April 4,
1979, Public Document 7905140031 114.
Research Needs and Three Mile Island, April 26, 1979, Public Document 790514001 115.
Sequence of Events Following Loss of RC Pump ZA, April 18, 1979, Public Document 7905190089, P 116.
Loss of Pressure Control Procedure, Public Document 7905190241, P 117.
IE Bulletin No. 79-06, Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incident.
April 11, 1979, Public Documents 79051101-7 118.
ISA S67.04/ ANSI N719, Setpoints for Nuclear Safety-Related Instrumentation Used in Nuclear Power Plants, Oraft E, 11/15/78 119.
IEEE Std. 603 - 1977, IEEE Trial-Use Standard Criteria for Safet:
Systems for Nuclear Generating Stations, August 15, 1977 120.
ANSI /IEEE Std. 577 - 1976, IEEE Standard Requirements for Re-liability Analysis in the Design & Operation of Safety Systems for Nuclear Power Generating' Stations, 11/15/76 121.
ANSI /IEEE Std. 338 - 1977, IEEE Standard Criteria for the per-iodic Testing of Nuclear Power Generating Station Safety Systems October 28, 1977 122.
ANSI N41.28 - 1976/IEEE Std. 494 1974, IEEE Standard Method for Identification of Documents Related to Class 1E Equipment and Systems for Nuclear Power Generating Stations, Sept. 19, 19; 123.
ANSI N41.4 - 1976/IEEE Std. 352-1975, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems, April 14, 1975 12*.
ANSI /IEEE Std. 379 - 1977, IEEE Standard Application of the Single Failure Criterion to Nuclear Power Generatine Station Class 1E Systems, June 30, 1977 l
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125.
IEEE Std. 336 - 1977, IEEE Standard Installation, Inspection, and Testing Requirements for Instrumentation and Elcetric Equipment During the Construction of Nuclear Power Generating Stations, August 31, 1977 126.
ANSI N320 - 1979, Performance Specifications for Reactor Energency Radiological Monitoring Instrumentation, July 20, 1970 127.
ANSI /N18.17 - 1973, Std. ANS3.3 Industrial Security for Nuclear Power Plants 128.
ANSI /N 18. 2 - 1973, Std. ANS 51.1 Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants (an Amer-ican daticani Standard) 129.
ANS-8.10/ ANSI /N16.8 - 1975, Std. Criteria for Nuclear Criticalit Safety Controls in Operations where Shielding Protects Personnel 130.
ANS-51.8/ ANSI /N18.2a - 1975, Std. Revision and Addendum to Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants / ANSI /N18.2 - 1973 131.
ANS-28/ ANSI /N170 - 1976, Std. Standards for Determining Design Basis Flooding at Power Reactor Sites 132.
ANS-56.2/ ANSI /N271 - 1976, Std. Containment Isolation Provisions for Fluid Systems 133.
N/18-20/ ANSI /N524 - 1976, Std. Nuclear Plant Reliability Data Collection and Reporting System 134 ANS-51.7/ ANSI /N658 - 1976, Std. Siegle Failure Criteria for PWR Fluid Systems 135.
ANSI /ANS-3.5 - 1979, Std. Nuclear Power Plant Simulators for Use in Operator Training (an American National Standard) 136.
ANSI /ANS-55.4 1979, Std. Gaseous Radioactive Waste Processing Syste=s for Light Water Reactor Plants (an American !!a tional Standard) 137.
ANSI /ANS-56.3 - 1977, Std. (N193) Overpressure of/0W Pressure Systems Connected to the Reactor Coolant Pressure Boundary i
138.
ANSI /ANS-56.5 - 1978, Std. Pressurized Water Reactor Containment Ventilation Systems (an American Nationa Standard) 139.
ANSI /ANS-58.3 - 1977, Std. (N-182) Physical Protection for Systems and Components Important to Safety 110.
ANSI /ANS-3.7.2 - 1979, Std. Emergency Control Centers for'Nucie Power Plants (an Anerican National Standard) l l
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. '6 140-a.
AKS-51.9/52.5/ Draft 1, Revision. 1/ January 1978, Std. Draft /
l 1
Caution Notice this Standard is being Prepared or Reviewed and b.s not been approved by ANSI.
It is subject to revision or wishdrawal before issue.
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ANS-51.9/52.5/ Draft 1, Revision 1/ January 1978, Std. Draft /Cauti.
Notice - this Standard is being Prepared or Reviewed and has been Aeproved g ANSI.
It is Subj ec t to Revision or With-not drawal before Issue.
141.
Third Interim 1R$ port on the TMI-2 July 16, 1979 (Metropolitan Edison Co) 142..
President's Commission on the Accident at Three Mile Island Third Meeting May 31, 1979 Afternoon Session 143.
_NRC Interview, TMI Tape #55 (Frederick J.
Scheimann, Jr.)
144.
TMI Tape #95 145.
TMI Tape #56 (Ed Frederick) 146 TMI Tape #57 147.
TMI Tape #94 148.
TMI Tape #277 149.
TMI Tape #35 (Craig Faust) 150.
TMI Tape #36 151.
TMI Tape f37 152.
TMI Tape #128-138 153.
TMI Tape #145 154.
TMI Tape #269 155.
TMI Tape #270 156.
TMI Tape #279 157.
TMI Tape #319 158.
TMI Tape #321 159.
TMI Tape #6 (Bill Zowe) 160.
TMI Tape #7 161.
TMI Tape #60 162.
TMI Tape #61 163.
TMI Tape #96 164.
TMI Tape #273 165.
TMI Tape #83 (George Kunder) 166.
TMI Tape 584 t
. 167.
NRC Interview, TMI Tapa #246 (George Kunder) 168.
TMI Tape #247 169.
TMI Tape #256 170.
TMI Tape #257 171.
TMI Tapes #81 & 82 (Michael Ross) 172.
TMI Tape #226 173.
TMI Tape #1 (Gary Miller & Joe Logan)
.174.
TMI Tape il Part 2 175.
TMI Tape #182 176.
TMI Tape #183 177.
TMI Tape #184 178.
TMI Tape #99 (Dick Dubiel, John Hilbish, and Gary Miller) 179.
TMI Tape #158 180.
TMI Tape #159 181.
TMI Tape #160 182.
TMI Tape #213
,(Brian Mehler) 183.
TMI Tape #276 184.
TMI Tape #91 (James R.
Floyd) 185.
TMI Tape #274 186.
TMI Tape #285 137.
NRC Advisory Committee on Reactor Safeguards 230th General Meeting, 14 June 1979, Pa'ges 1-261 187a..
NRC Advisory Committee on Reactor Safeguards 230th General Meeting, 14 June 1979, Pages 262-576 188.
NRC Advisory Committee on Reactor Safeguards Subcommittee on
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i the Three Mile Island Nuclear Station, Unit 2, 6 June 1979, Pages-1-192.
188a.
NRC Advisory Committee on Reactor Safeguards Subecmmittee on the Three Mile Island Nuclear Station, Unit 2, 6 June 1979, Pages 193-405 4
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' 189.-
President's Commiscion on the Accident at TMI, Third Meeting Public Hearings, First Day, May 30, 1979 190..
Third Meeting of the President's Commission on the Accident at TMI, May 31, 1979, Morning Session.
191.
ANSI /ANS 55.6-1979, Liquid Radioactive Waste Processing System for Light-Water Reactor Plants, April 24, 1979.
192.
List of Transcripts of Taped Interviews.
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