ML19260C031

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Amend 9 to 790912 Startup Rept
ML19260C031
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/14/1979
From:
METROPOLITAN EDISON CO.
To:
Shared Package
ML19260C029 List:
References
NUDOCS 7912180257
Download: ML19260C031 (195)


Text

To provide further assurance that emergency feedwater can be delivered when required, the failure mode of control valves EF-V30 A/B is being changed. Currently these valves fail half open on loss of electrical control signal and fail "as-is" on loss of instrument air. The change consists of modification to the operator such that on loss of air, the valves will fail in the open position and remain in this position.

Control valves EF-V30 A/B are controlled by the Integrated Control System. The design of this sytem is described in chapter 7 of the TMI-l FSAR. Upon loss of all reactor coolant pumps, and/or both feedwater pumps, the IC positions the control valves to maintain steam generator water level. If reactor coolant pumps are available, the ICS controls are set to maintain a 30 inch water level on the start-up range level indicator. If reactor coolant pumps are not available, the ICS maintains steam gener-ator water level at 50% on the operating range level indicator.

The Integrated Control System is a control grade system. It does, however, receive power from the Class 1E power system. Specific-ally the ICS is supplied from Distribution Panal ATA. This panel can be powered from the station batteries thru inverter IA and Panel VBA or from ES Control Center lA through Panel TRA.

Manual Control of the emergency feedwater control valves can be taken from the control room. When manual control is selected all active components of the ICS are bypassed except for the raise /

lower voltage circuit. As further assurance that control of the emergency feedwater control valves are available to the operator, an additional manual control station is being provided for each valve. The controls will be located in the control room and will be totally separate from the ICS. Power from the edundant por- ,

tion of Class lE power system will be provided to the back-up controls. A functional diagram of the new manual controls is shown in Figure 2.1-3. A new manual loader station for each control valve will be mounted on the control room console. This will allow the operator to manually set a +10 volt control signal into the voltage / pneumatic converter in order to control the position of the EFW control valve. An adjacent selector switch connects the signal from the manual loader station to the voltage /

pneumatic converter and also replaces the ICS "EL" power supply with an independent 115 volt, 60 hz supply. Thus, if the EFW controls are disabled due to a failure in the ICS or failure of the "EL" power supply, the operator will have the ability to control flow to either steam generator entirely independent of the ICS.

Each of the emergency feedwater supply lines has also been pro-vided with two redundant flow sensing devices. These devices are a sonic flow device as manufactured by Controltron and will be installed downstream of the control valves before the lines enter the containment building. The flow devices are safety grade and have been seismically qualified. The output of the flow devices will transmit the signals to the main control room where meters will be installed to read flow directly with an accuracy of better than 5%. The equipment to be installed will be safety related.

Cabling will be routed as described in Section 7 of the TMI-l 2.1-22 Am. 9

' 7 91218 0 e 1613 064

FSAR. The power supply for the instruments will be derived from the vital 120 V power system. Redundant Power supplies will be used for redundant instruments.

A diverse means of monitoring emergency feedwater flow is provid-ed by the steam generator level indicators. These measurements are derived from Bailey type "BY" transmitters which, subsequent to their installation at TMI-1, have been seismically qualified and qualified for operation in a post-LOCA containment enviran-ment. One start-up range and one operating range transmitter have been raised higher above the reactor building floor to avoid flooding in a post-accident situation and have had their elec-trical connections protected to prevent degradation due to moisture. The level instruments are supplied from lE on-site power sources and their wiring is run in raceways which have been analyzed to assume heat. They will withstand a seismic event.

2.1.1.7.4 System Operation The TMI-l Auxiliary Feedwater System is a stand-by plant system which is not used during normal plant start-ups, shutdowns or operation. The system is maintained in stand-by during plant operations and is automatically actuated upon loss of both main feedwater pumps or loss of all four RC pumps. The following table gives actuation time for the system:

Event Turbine-Driven Motor-Driven a) Loss of Feedwater or Immediate 5 Sec.

Loss of RC Pumps b) Above with loss of Immediate 15 Sec.

off-site power (LOP) c) Above with ESAS but Immediate 20 Sec no LOP d) Above with ESAS and LOP Immediate 30 Sec Start-up and test data indicates that the turbine driven pump requires 18 seconds to reach full flow. The motor-driven pumps should be capable of accelerating to full speed in less than 10 seconds. Therefore under worst case conditions emergency feed-water flow should be established within approximately 40 seconds.

Control of auxiliary feedwater flow following initiation is accom-plished by the ICS. The ICS controls the injection of auxiliary feedwater to maintain water level in each steam generator to one of two setpoints depending on whether RC pumps are or are not available. Under forced cooling conditions, the ICS controls level to 30 inches on the start-up range since this is sufficient to provide core cooling. However upon loss of forced RCS cooling the ICS controls steam generator level to 50% on the operating range to promote natural circulation with the Reactor Coolant System.

Manual controls in the control room are available for the opera-tor to take control of the EFW flow to either steam generator when needed or in the event of ICS failure.

1613 065 2.1-23 Am. 9

5.2 STATION ORGANIZATION The Vice President utilizes the following management staff in carrying out his responsibilities:

. Manager Plant Engineering

. Manager Unit 1

. Manager Administration and Services

. Manager Training

. Manager Radiological Controls The Three Mile Island Nuclear Station organization as shown in Figure 5.2.1 will function in five main areas: Unit 1 operations and maintenance, engineering, training, administration and ser-vices, and radiological controls.

The Operations Group under the Manager Unit I will be responsible for the day-to-day operation of the unit. Unit I will have a Shift Supervisor directing the operations of each shift through the Shift Foreman, Control Room Operators, and Auxiliary Operators. A maintenance force supporting TMI-1 in the areas of electrical, mechanical and instrument control maintenance and surveillance will also report to the Manager Unit 1.

The Plant Engineering Group under the Manager Plant Engineering will consist of lead engineers in such disciplines as nuclear, mechanical, electrical, and instrument and control engineering to whom other engineers and analysts assigned to TMI-l will report.

Technicat Engineers will be assigned on each operating shift to maintain technical liaison and coordination between operating shift personnel and the technical support engineering staff. In addi-tion, a Supervisor Chemistry and a Technical Analyst (Fire Protec-tion) are assigned to support requirements of the unit in their particular area.

The Training Department will function primarily in the three main areas of operator training, technician training and career development training. The operator training section is organized to support both licensed operator and non-licensed operator train-ing. The technician training section will support training of technicians in both the maintenance and health physics areas. The career development section will support general employee training and RWP Training.

The Administration and Services group will function in the areas of facilities , of fice management , personnel and station security.

The Radiological controls group under the Manager Radiological Controls will function in the areas of Radiological Control Program design, support, and enforcement. The group will prepare and review the Radiological Protection Plan and implementing proce-dures, training plans and procedures,and the Bioassay and Respi-ratory Protection programs. Additionally, the group will conduct surveys and assessments related to protective controls in order to assure that work practices are accomplished in compliance with established practices, procedures and regulations.

5-2 Am. 9 1613 066

The following subsections detail the functions and responsibilities of various station supervisory personnel.

5.2.1 Vice President

a. Function The Vice President - in carrying out his management responsi-bility for day-to-day plant operations directs the management staff, identified in paragraph 5.2 Station Organization, in executing the following TMI-l operational functions.

Shift daily operations and surveillance in accordance with Technical Specification requirements.

Preventive and corrective maintenance on safety related systems and components.

Administrative controls related to Technical Specification compliance not specifically assigned elsewhere.

Radiological controls including compliance with Radiological Effluent Technical Specifications.

Primary and Secondary plant chemistry.

Radioactive waste processing and treatment including shipment.

Refueling operations and operational related shutdown sur-veillance requirements.

Training of licensed and non licensed operations personnel, Radiation / Chemistry technicians and maintenance personnel.

Planning of day-to-day maintenance, operations surveillance and refueling activities.

Plant engineering support of maintenance requirements and shift operations, including liaison with the offsite Technical Functions Group.

b. Responsibility The Vice President - in carrying out his responsibility for overall direction of day-to-day TMI-l operations is responsible for:

TMI-l Technical Specification and Regulatory Requirements compliance, (unless specifically assigned elsewhere, e.g.,

the Radiological Environmental Monitoring Program and non-Radiological Environmental Monitoring Program) through the direction of the managers identified in paragraph 5.2. ,

1613 067 5-3 Am. 9

Direction of the Manager TMI Unit 1 in the execution of his responsibilities which are set forth in paragraph 6.1 of the THI-1 Technical Specifications.

TMI-l compliance with all commitments made in the TMI-l restart report submitted in response to the TMI-1 shutdown order dated 9 August, 1979 unless specifically assigned elsewhere.

Developing and implementing the Security Plan, Fire Protection Plan and Radiation Emergency Plan.

Compliance with the company approved Quality Assurance program, the Security Plan, the Radiation Emergency Plan, the Fire Protection Plan and the Radiation Protection Plan.

Insuring that training programs for licensed operators ,

non-licensed operators, maintenance personnel, Shift Technical Advisors, Radiction Chemistry Technicians and the Security Force are implemented and maintained in accordance with regulatory and management requirements.

Direct Interface with the Directors identified in paragraph 5.3 to insure the necessary TMI-l support is provided in the areas of Engineering Change Modification coordinated review and approval, major corrective maintenance and construction, Nuclear Safety Analysis, quality assurance, licensing, environ-mental programs, Licensee Event Report Review, laboratory analysis and Generaton Review Committee support in acccordance with the TMI-1 Technical Specifications.

Insuring that appropriate management and administrative control systems and procedures are developed, implemented, and complied with as necessary to fulfill the other listed responsibilities.

Evaluation of the adequacy of the Station Staff in terms of number assigned and qualifications,

c. Authority The Vice President - has the authority to:

Laplement the Radiation Emergency Plan.

Order the shutdown and cooldown of TMI-1 whenever the health and safety of the public is endangered.

Initiate emergency procurement.

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d. Minimum Qualifications The Vice President - shall possess as a minimum the qualifi-cations outlined in ANSI 18.1, Section 4.2.1, Plant Manager.

The Vice President shal: have ten years of responsible power plant experience, of which a minimum of three years shall be nuclear power plant experience. A maximum of four years of the remaining seven years of experience may be fulfilled by aca-demic training on a one-for-one time basis. To be acceptable, this academic training shall be in an engineering or scientific field generally associated with power production. The Vice President shall have acquired the experience and training normally required for examination by the NRC for a Senior Reactor Operator's License whether or not the examination is taken,

e. Incumbent Qualifications The incumbent received a Bachelor of Science Degree in Marine Engineering in 1960 from the U.S. Naval Academy. From 1960 to 1967, he spent six years on conventional destroyer ships in various capacities including Weapons Officer and Chief Engineer. In addition to the shipboard assignment, he spent one year at the U.S. Naval Nuclear Power School and qualified as Engineering Of ficer of the Watch at the DIG Prototype at West Milton, New York. From May 1967 to September 1967 the incumbent was the Assistant to the Operations Supervisor at Yankee Atomic. In September 1967, he became Staff Engineer at the Saxton Nuclear Experimental Station where he remained until August 1968 when he assumed the position of Supervisor of Operations and test for Saxton. At that time he acquired a Senior Reactor Operator's License. In May 1970, he assumed the position of Supervisor of Reactor Plant Services at Saxton. In August 1970, the incumbent was transferred and assigned as Station Engineer at TMI. In that capacity, he was responsible for instrumentation, electrical, mechanical, nuclear, health physics and chemistry, site engineering and technical supervision. He remained in this position until January 1973, when he assumed the position of Assistant Superintendent of TMI. He acquired a Senior Reactor Operator's License in February, 1974. From January 1974, to June 1975, he held the position of Superintendent Nuclear Generating Station at TMI. In June 1975, he assumed the position of Manager - Generation Operations Nuclear in which he was responsible for day-to-day direction and Supervision of TMI.

In September 1976, he assumed the position of Manager -

Generation Operations in which he was responsible for nuclear, fossil and hydroelectric generation. In May 1977, he assumed the position of Vice President - Generation and in August 1979, he was assigned to TMI as Vice President - and is presently serving in that capacity.

1613 069 5-5 Am. 9

f. Interfaces The Vice President reports to and is held accountable for THI-l operations by the Met-Ed Senior Vice-President.

In carrying out his management responsibility for day-to-day TMI-l operations the Vice President interfaces and communicates with the Directors shown on Figure 5.2-1 who also report to the Met-Ed Senior Vice-President.

The offsite Directors who interface and communicate with the Vice President and their corresponding direct support responsi-bilities relative to TMI-l are identified in paragraph 5.3.

The Vic' President interfaces and communicates directly with the Director TMI-2 Recovery and the TMI-2 Site Operations / Waste Management Manager to insure the separation and independence of TMI-2 decontamination and restoration activities from TMI-1.

Additionally, this interface and related communications insures TMI-1 installed waste handling equipment which is required for operation as described in the TMI-l FSAR is not relied on by operations at TMI-2.

The Vice President has the ability to call upon various compo-nents of the Technical Functions and Quality Assurance Groups for assistance in the areas of process computers, Safety Analysis, fuel performance and fuel management.

5.2.2 Manager Unit 1

a. Function The Manager reports directly to the Vice President and assists him in the overall operation and maintenance of the unit.
b. Responsibility This position has direct responsibility for operating the unit in a safe, reliable and efficient manner; is responsible for off-site radioactive discharges and the protection of personnel from radiation exposures; bears the responsibility for compliance with the operating licenses and the rules and regulations of the Commonwealth of Pennsylvania; supervises the operations group and maintenance group,
c. Authority The authority of the Manager, delegated by the Vice President, is inherent in the position and commensurate with the assigned responsibilities. It includes the authority to issue procedures, orders, and other directives required in the execution of the assigned responsibilities. Necessarily included is the respon-sibi'lity for plant operation, compliance with Technical Specifi-cations, radioactive discharges and personnel protection from radiation exposure is the authority to assign and prioritize 5-6 Am. 9 1613 070

requirements to the Plant Engineering, Training and Adminis-tration and Services Groups. Similarly, the authority of the Manager includes the initiation and reprioritization of correct-ive maintenance, preventative maintenance or construction in the execution of his responsibilities. All personnel within the confines of Unit 1 protected area are subject to the authority and direction of the Manager. The Manager may delegate his authority and share his responsibilities with the Supervisor of Operations or Shift Supervisor during absences.

This delegation of authority extends to the issuance of standing orders and directives in support of the responsibilities assigned. In the absence or incapacitation of the Vice President, the Senior Unit Manager is delegated the authority of that office for the centralized control supervision, cocrdination and planning of all aspects of TMI Operations.

d. Minimum Qualifications The Manager shall have a minimum of eight years of responsible power plant experience of which at least three years will be in nuclear power plant design, construction, startup, operation, maintenance, or technical services. A maximum of two years of remaining five may be fulfilled by academic training. The Manager must hold a Senior Reactor Operator license.
e. Incumbent Qualifications Unit 1 High School graduate. U.S. Merchant Marine Academy, Kings Point, NY (1963)

(Marine Engrg) 1965-70 Newport New Shipbuilding (assigned to varicus new const. nuclear submarines).

1970-71 Newport News Shipbuilding (Asst. Project Mgr.) for completion of reactor plant).

1971-73 Newport News Shipbuilding & Dry Dock Co. (Senior Test Supervisor) 2/73 to 8/74 GPU Corp. Supt.-Test Design.

5 years experience Nuclear Power Plant Operation - TMI.

f. Interfaces
1. Offsite The' Manager interfaces with company, corporate, local commonwealth, and federal government organizations in fulfillment of responsibilities assigned, state and federal regulations, and directives received.

5.2.3 Supervisor of operations lfl} 7

a. Function The Supervisor of operations has the responsibility for directing the actual day-to-day operation of the unit.

He reports directly to the Manager Unit 1. The Supervisor of 5-7 A"* 9

Operations coordinates operations and related maintenance activities with the Superintendent of Maintenance,

b. Responsibility This position is responsible for the day-to-day administration and direction of the Operations personnel, ensuring that the conditions of the plant operat:.ng license are met, and ensuring compliance with the technical ;pacifications.
c. Authority The Supervisor of Operations Unit 1 has the authority and responsibility to order the plant shutdown when in his judgment the safety of the plant or public is being compromised.
d. Minimum Qualifications The Supervisor of Operations will have a minimum of six years of responsible power plant experience of which at least one year will be in nuclear power plant design, construction, startup, operations, maintenance, or technical services. A maximum of two years academic or related training may be included as part of the remaining five years of power plant experience. The Supervisor of Operations shall hold a Senior Reactor Operators License,
e. Incumbent Qualifications Education: High School Graduate 1960 Military Service: U.S. Navy - 1960-1968 Relevant Assignments / Training: U.S. Navy Nuclear Power School (26 weeks) - 1961 Nuclear Power Prototype School 1961 Reactor Operator - USS HADD0 -

1962-1965 Instructor - Nuclear Power Training Unit - 1965-1966 (Qualified as Engineering Officer)

AEC Field Representative at NPTU -

1966-1968 (Passed Nuclear Engineer Examination)

Operations Staff and Instructor -

Saxton Nuclear Experimental Corporation - 1968-1970 5-8 Am. 9 1613 072

Shift Foreman - TMI - Aug. 1970-July 1972 Shift Supervisor - July 1972-April 1978 Supervisor of Operations -

April 1978-Present

f. Interfaces
1. Onsite The Supervisor of Operations has onsite interfaces with the Superintendent of Maintenance and the Faergency Planning Coordinator.

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5.2.4 Emergency Planning - Coordinator

a. Function The Emergency Planning - Coordinator in carrying out his responsibility will perform the following functions.

. Ensure effective coordination of the TMI Emergency Plan with all applicable outside plans, such as State and County plans.

. Plans, organizes and controls all activities necessary to insure ongoing viability and effectiveness of the TMI Emergency Plan and Emergency Plan Lnplementing Procedures.

. Coordinates the annual review and update of the TMI Emer-gency Plan and Implementing Document.

. Coordinates and/or provides emergency planning related training.

. Plans and schedules the quarterly inventory and inspection of designated emergency equipment.

b. Responsibility The Emergency Planning - Coordinator in carrying out his responsibility for the overall coordination and implementation of the TMI Emergency Plan is responsible for the following:

. Annual review and update of the Emergency Plan.

. Coordination of the annual training.

. Planning and scheduling of the quarterly inventory of the designated emergency equipment.

c. Authori'y The Emergency Planning - Coordinator has the authority to:

. Implement changes to the TMI Emergency Plan to insure it remains effective and current,

d. Minimum Qualifications The Coordinator - Emergency Planning shall have a BS degree in a science related field or the equivalency in experience in the areas of Health Physics and nuclear generation,
e. Interfaces The Emergency Planning - Coordinator reports to and is held 5-10 Am. 9 1613 074

accountable for Emergency Planning to the Manager Unit 1 In carrying out his responsibilities, the Emergency Planning -

Coordinator interfaces and communicates with:

. Vice President - Met-Ed for TMI Emergency Plan Coordination +

. County, State and Federal Officials for their respective Emergency Coordination.

. Supervisor Security for the TMI Security Plan Coordination.

. Manager - TMI Communications for Met-Ed Emergency Communi-cations Plan.

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5.2.5 Supervisor - Radwaste, Nuclear

a. Function The Supervisor-Radwaste Nuclear in carrying out his supervisory responsibility in Radwaste Operations directs three (3) Rad-waste Foremen and radwaste Utility workers in executing the following TMI-1 functions:

. Packaging of solid radwaste including both compacting and solidification.

. On-site temporary storage of radwaste material.

. Coordination of all shipments of radioactive waste material from TMI-1.

. Operation of the waste solidification s, stem at TMI-1.

. Training of radwaste personnel in regulatory requirements.

. Minimizing the volume of radwaste generated and disposed of by the Unit,

b. Responsibility The Supervisor-Radwaste-Nuclear in carrying out his responsi-bility for overall radwaste operations is responsible for:

. NRC Packaging and DOT Packaging and Shipping Requirement Compliance.

. NRC and 10CFR20 Radioactive Material Storage Requirements through an interface with Radiation Protection personnel.

. Insuring that training programs for radwaste personnel developed, implemented and maintained in accordance with regulatory and management requit nents.

. Direct interface with Radiation Protection personnel and Operations personnel to insure that regulatory compli-ance is achieved and the generation of radwaste is con-trolled.

. Insuring that appropriate management and administrative control systems and procedures are developed, implemented and complied with as necessary to fulfill the other listed responsibilities.

c. Authority The Supervisor-Radwaste Nuclear has the authority to:

. Stop the shipment of any radioactive material which does not comply with regulatory or management requirements.

5-12 Am. 9 1613 076

. Stop any activity which unnecessarily generates rsdioactive waste.

d. Minimum Qualifications The Supervisor-Radwaste Nuclear shall possess as a minimum a Bachelor of Science Degree in an engineering or science disci-pline and four years of experience of which a minimum of two years shall be nuclear power plant experience. An additional four years of nuclear power plant experience may be substituted for the degree requirements,
e. The incumbent Supervisor Radwaste Nuclear has the following qualifications:

. BS Degree Chemicel Engineering, Drexel University, 1973.

. 6 1/2 years of utility experience in waste disoosal field.

. 31/2 years of that at TMI.

f. Interfaces The Supervisor-Radwaste Nuclear reports to and is held account-able for radwaste operations by the TMI-l Operations Supervisor.

In carrying out his supervisory responsibilities for radwaste operations the Supervisor-Radwaste Nuclear interfaces and communicates with:

. The Radiation Protection Supervisor for radiation and contamination surveys and radioisotope analysis to insure compliance with regulatory and management requirements.

. The Supervisor of Operations for systems operation and material control to minimize the volume of radioactive materials generated at TMI-1.

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5.2.6 Shift Supervisor

a. Function This position directs the activities on his shif t and is cognizant of operations, maintenance, construction and radio-logical control maintenance activities being performed while he is on duty. This function includes the approval and insurance that all activities involving Nuclear Safety related Systems and components are accomplished in accordance with properly approvaled procedures.
b. Responsibility The licensed Senior Reactor Operator assigned to the position of Shift Supervisor has the primery command and control respon-sibility for the management and direction of all operations and maintenance activities including the manipulation of any controls, equipment, or components in physical plant systems on his shift. The Shift Supervisor Command responsi-bilities are further defined in a management directive dated 11/28/79 signed by the acting Med-Ed President.
c. Authority The Shift Supervisor has the authority and obligation to shut down the unit if, in his own judgment , conditions warrant this action. The Shift Supervisor also has the authority to refuse, or halt any activity, requested or in process, on any plant system if in his discretion, the safety of plant systems, personnel in the manipulatin of plant controls and/the perfor-mance of their duties.
d. Minimum Qualifications Each Shift Supervisor shall have a high school diploma or an equivalent education. He shall have a minimum of 4 years power plant experience of which a minimum of one year will be nuclear power station operations or maintenance. A maximum of two years of academic or related education may be included as part of the remaining three years of required plant experience.

The Supervisors in this category should hold a Senior Reactor Operator's License.

e. Incumbent Qualifications Incumbent A Education: High School Graduate - 1954 Military Service: U.S. Army 1958-1959 5-14 Am. 9 1613 078

Relevant Assignments: Control Room Operator -

October 1969 - October 1976 Shift Foreman -

October 1976 - July 1979 Shift Supervisor -

July 1979 - Present Incumbent B Education: High School Graduate - 1961 Relevant Assignments: Auxiliary Operator -

October 1969 - December 1972 Control Operator -

December 1972 - July 1975 Shift Foreman -

July 1975 - July 1979 Shift Supervisor July 1979 - Present Incumbent C Education: High School Graduate - 1959 Military Service: U.S. Air Force - 1959-1963 Relevant Assignments: Control Room Operator -

October 1968 - August 1976 Shift Foreman -

August 1976 - April 1978 Shif t Supervisor -

April 1978 - Present Incumbent D Education: High School Graduate - 1965 Military Service: U.S. Navy - 1966-1971 Relevant Assignments /

Training: U.S. Navy Basic Nuclear Power School (26 weeks) 1966-1967 Nuclear Power Prototype School (26 weeks) - 1967 1613 079 5-15 Am. 9

Reactor Operator -

U.S. Navy - USS Bainbridge 1969-1971 Auxiliary Operator -

February 1972-October 1973 Shift Foreman -

October 1973-May 1976 Shift Supervisor -

May 1976-Present Incumbent E Education: High School Graduate - 1964 Military Service: U.S. Air Force - 1964-1969 Relevant Assignments: Auxiliary Operator -

March 1969 - July 1970 Control Room Operator -

July 1973 - October 1975 Shift Foreman -

October 1975 - October 1977 Shift Supervisor -

October 1977 - Present Incumbent F Education: High School Graduate - 1963 Utah State University - 2 years Military Service: U.S. Navy - 1966-1973 Relevant Assignments /

Training: U.S. Navy Basic Nuclear Power School (26 weeks) 1967 Nuclear Power Prototype School -

(26 weeks) - 1967 Reactor Coolant - USS Greenling -

1968-1973 Auxiliary Operator -

April 1973 - August 1975 Control Room Operator -

August 1975 - November 1976 1613 080 5-16 Am. 9

Shift Foreman -

November 1976 - March 1979 Shift Supervisor -

March 1979 - Present

f. Interfaces
1. Offsite The Shift Supervisor has no offsite interfaces or responsi-bilities during normal operation.
2. TMI-2 The Shift Supervisor has no technical responsibilities in Unit 2.

5.2.7 Shift Foreman

a. Function He reports directly to the Shift Supervisor. He directs the activities of the unit operators on his shift and is cognizant of all in plant activitics being performed while he is on duty.
b. Responsibility The Shif t Foreman is responsible for the actual operation of the unit during his assigned shift. He is also responsible for insuring all control room activities including Control panel monitoring, processing of RWP and tagging applications, oper-ational log and recording functions, and inter plant Communi-cations are executed in accordance with prescribed guidelines and correct operating practices.
c. Authority The Shif t Foreman on duty has both authority and the obligation to shut down the unit if, in his judgment, conditions warrant this action.
d. Minimum Qualifications Each Shift Foreman shall have a high school diploma or an equivalent education. He shall have a minimum of 4 years power plant experience of which a minimum of one year will be nuclear power station operations or maintenance. A maximum of two years of academic or related education may be included as part of the remaining three years of required plant experience.

The Foreman in this category should hold a Senior Reactor Operator's License.

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e. Incumbent Qualifications Incumbent A Education High School Graduate - 1963 Military Service: U.S. Air Force - 1963-1968 Relevant Assignments: Auxiliary Operator -

July 1968 - June 1975 Control Room Operator -

June 1975 - July 1978 Shift Foreman -

July 1918 - Present Incumbent B Education: High School Graduate - 1963 Military Service: U.S. Navy - 1964-1971 Relevant Assignments /

Training; IhS; N:cy Hugle_ar Power School -

(26 weeks) 1904-1305 Nuclear Power Prototype School -

(26 weeks) - 1965 Mechanical Operator -

USS Whale - 1968 Engine Room Supervisor - USS Theodore Roosevelt - 1969-1971 Auxiliary Operator -

Feburary 1971 - April 1975 Control Room Operator -

April 1975 - May 1978 Shift Foreman -

day 1978 - Present Incumbent C Education: High School Graduate - 1966 Military Service: U.S. Navy 1968-1974 Relevant Assignments /

Training: U.S. Navy Nuclear Power School -

(26 weeks) - 1968 13 082 5-18 Am. 9

Nuclear Power Prototype School -

(26 weeks) - 1968-1969 USS Sea Devil - Electrical System Opeator - 1959-1972 USS Bates - Sound and Vibration Analysis - 1972-1974 Auxiliary Operator -

February 1974 - October 1976 Control Room Operator -

October 1976 - July 1978 Shift Foreman -

July 1978 - Present Incumbent D Education: High School Graduate - 1967 Relecent Assignments: Auxiliary Operator -

January 1975 - October 1977 Control Room Operator -

October 1977 - August 1978 Shift Foreman -

August 1978 - Present Incumbent E Education: High School Graduate - 1957 Relevant Assignments: Auxiliary Operator -

October 1969 - July 1970 Control Room Operator -

July 1970 - June 1977 Shift Foreman -

June 1977 - Present Incumbent F Education: High School Graduate - 1962 Military Service: U . S . N avy - 1963-1970 Relevant Assignments /

Training: U.S. Navy Nuclear Power School -

(26 weeks) - 1965 5-;9 Am. 9 1613 083

Nuclear Power Prototype School -

(26 weeks) - 1965-1966 Reactor Operator - USS George C.

Marshall - October 1968-March 1970 Auxiliary Operator -

June.1970 - February 1974 Control Room Operator -

February 1974 - February 1978 Shift Foreman -

March 1978 - Present

f. Interfaces
1. Offsite The Shift Foreman has no offsite interfaces or responsi-bilities during normal operation.
2. TMI-2 The Shift Foreman has ac technical responsibilities in Unit 2.

5.2.8 Control Room Operator

a. Function Each Control Room Operator reports to the Shift Foreman and operates the reactor, turbine, generator, switchboards and all other equipment necessary to maintain continuous production with maximum safety and efficiency in accordance with the Operating License,
b. Responsibility The Control Room Operator is responsible for all the equipment assigned to him in the Unit, and the reporting of any unusual performance of this equipnment to the Shift Foreman.
c. Authority The Control Room Operator has the authority to shutdown the unit when conditions in the unit warrant such action. He also has the authority to direct the auxiliary operators in their performance of Company approved procedures.
d. Minimum Qualifications High School diploma or equivalent and two years experience in a power plant one of which is at e nuclear plant. The Control Room Operator must be licensed by the NRC.

5-20 A** 9 1613 084

5.2.9 Auxiliary Operator

a. Function The main function of each Auxiliary Operator is to operate and inspect equipment in the nuclear power station as required to support day-to-day operation from his position outside the Control Room. He will be directed in the performance of his duties by the Shif t Foreman or the Control Room Operator and will report any unusual performance of equipment.
b. Responsibility The Auxiliary Operator shall be responsible for the operation and inspection of plant equipment. He also performs the functions of radiation protection monitor on his shift as required and is responsible for notifying the appropriate supervisor if any portion of the unit exceeds established limits. He assists in the receipt, storage, loading and unloading of fuel, shipment of irradiated materials and dis-posal of radioactive wastes as directed.
c. Authority The Auxiliary Operator shall have the authority to execute Company approved procedures as directed by Control Room Operators or Shift Foreman,
d. Minimum Qualifications Each Auxiliary Operator should have a high school diploma or equivalent. The Auxiliary Operator shall be interviewed to verify that they exhibit mature judgement, testing will be used to aid in determining the individuals ability to progress to higher levels of responsibility and eventual NRC licensing.

1613 085 5-21 Am. 9

5.2.10 Superintendent of Maintenance

a. Function The Superintendent reports to the Manager Unit I and provides maintenance support for the unit.
b. Responsibility This position is responsible for planning, organizing, inte-grating and directing the maintenance effort of the TMI nuclear generating station in order to insure optimum equipment / systems availability and reliability.

This position is responsible for assuring the provision of adequate resources to carry out the Maintenance programs,

c. Authority The Superintendent of Maintenance has the authority to assign Maintenance work to company and contract resources identified by management.
d. Minimum Qualifications This position shall have seven (7) years of responsible power plant experience or applicable industrial experience, a minimum of one (1) year which shall be nuclear power plant experience.

An Associate Degree in an Engineering or Scientific field is preferred and may be credited to the remaining six (6) years of experience. The individual should have non-destructive testing familiarity, craft kn5wledge and an understanding of electrical, pressure vessel and piping codes,

e. Incumbent Qualifications The Superintendent of maintenance is a Navy veteran of twenty-seven years with experience in Marine and Power Plant operations, Maintenance and repair. He has served as Chief Engineer and Repair Officer on several large combatant Naval ships. He was a member of the Naval Board of Inspection and Survey as an engineering inspector. He attended engineering service schools as a prerequisite for qualification as Engineer Officer. He was appointed Supervisor of Maintenance at TMI in 1973.
f. Interfaces
1. Offsite 1613 086 Contractors, vendors representatives.

5.2.11 Supervisor - Corrective Maintenance

a. Function The Supervisor reports to the Superintendent of Maintenance and provides corrective maintenance support for the unit.

5-22 ^"* 9

b. Responsibility This position is responsible for planning, organizing, integra-ting and directing the corrective maintenance ef fort for Unit 1 in order to insure optimum equipment / systems availability and reliability.

This position is responsible for the identification, justifi-cation and utilization of resources requisite to the maintenance program,

c. Authority The Supervisor - Corrective Maintainance has the authority as delegated by the Superintendent - Maintenance to assign corrective maintenance tasks, to coupany and contractor resources identified by management.
d. Minimum Qualifications This position is required to have seven (7) years of respon-sible power plant experience or applicable industrial experi-ence, a minimum of one (1) year which shall be nuclear power plant experience. An Associate Degree in an Engineering or Scientific field is preferred and may be credited to the remaining six (6) years of experience. The individual should have non-destructive testing f amiliarity, craft knowledge, and an understanding of electrical, pressure vessel and piping codes.
e. Incumbent Qualifications Education: University of Missouri BSME - 1968 Relevant Assignments: U.S. Navy Training - Naval Nuclear Power School, six (6) months; Naval Nuclear Prototype, six (6) months.

Qualified - as Engineering Officer of the watch; Nuclear Engineer Officer.

Duties - Electrical Officer, Main Propulsion Assistant, Engineer Officer (2nd in command) on two (2) different nuclear submarines.

Supervised - Equipment overhaul, reactor defuelit.g - refueling, startup and testing during two (2) nuclear submarine overhauls 1968-1979.

5-23 ^** 9 1613 087

TMI - Maintenance Engineer Special Maintenance Projects March 1979 - October 1979

f. Interfaces
1. Offsite Contractors, vendors' representatives.

5.2.12 Supervisor - Preventive Maintenance

a. Function The Supervisor reports to the Superintendent of Maintenance and provides preventive maintenance support for the unit.
b. Responsibility The Supervisor is responsible for organizing, modifying, and conducting the preventive maintenance for the Unit.

The Supervisor - Preventive Maintenance has the responsibility

. to identify / justify resources requisite to accomplish the PM progren.

c. Authority The Supervisor - Preventive Maintenance has the authority as delegated by the Superintendent - Maintenance to assign pre-ventive maintenance tasks, not performed by the operations department, to company and contractor resources identified by management.

He has the authority to establish and/or modify the operation of the PM Program not required by Technical Specification Surveillance.

d. Minimum Qualifications The Supervisor of Preventive Maintenance shall have seven (7) years of responsible power plant experience or applicable nuclear power plant experience. An Associate Degree is an Engineering or Scientific field is preferred and may be credited to the remaining six (6) years of experience. The individual should have non-destructive testing familiarity, craft know-ledge, and an understanding of electrical, pressure vessel and piping codes,
e. Incumbent Qualificetions Education: High School graduate - 1957 1613 088 5-24 Am. 9

Relevent Assignment: U.S. Navy (1958-1962) as Electronics Technician. Final rate: E-5. Was Lead Petty Officer last 1 1/2 years of enlistment.

Saxton Nuclear Experimental Corp.

Instrument Technician July 1966 to August 1972.

TMI - Maintenance Foreman in Instrumentation August 1972 to November 1976 and June 1978 to December 1979.

Training - numerous training courses including at Penn State, a Management Development course, Electrical Theory course and Math course, and one (1) week of B&W simulator training.

~

f. Interfaces
1. Offsite Contractors, Vendors' representatives.

5.2.13 Maintenance Foreman

a. Function Maintenance Foreman report to the Supervisor of Preventive Maintenance and provide support in the area of their descipline.
b. Responsibility Maintenance Foremen are responsible for directing the work of assigned personnel in the performance of preventive mainten-ance.
c. Authority Assigns production personnel to tasks. Resolves departmental interface problems at production level.
d. Minimum Qualifications Each Foreman shall hav_ a high school diploma or equivalent and four (4) years of experience in the craft or discipline supervised and shall have supervisory skills necessary to coordinate the activities of a crew or crews consisting of technical and/or non-technical personnel in the performance of their function.

1613 089 5-25 Am. 9

5.2.14 Lead Maintenance Foreman

a. Function Lead Maintenance Foreman reports to the Unit Supervisor of Maintenance and directs the day to day activities of the department for which they are responsible.
b. Responsibility The Lead Maintenance Foremen prioritize and assign the duties to be carried out by the Foremen who report to them.
c. Authority Assigns tasks to Foremen and production personnel.
d. Minimum Qualifications Each Foreman shall have a high school diploma or equivalent and four (4) years of experience in the craf t or discipline supervised and shall have supervisory skills hecessary to coordinate the activities of a crew or crews consisting of technical and/or non-technical personnel in the performance of their function.

1613 090 5-26 Am. 9

5.2.15 Manager Plant Engineering

a. Function The Manager Plant Engineering reports to the Vice President and is responsible for the coordination of the technical engi-neering staff including the Nuclear Engineering, Mechanical Engineering, Electrical Engineering, Instrument and Control Engineering, Shift Technical Advisor and Chemistry.
b. Responsibility The position is responsible for assisting the Unit Manager in the technical engineering for TMI Unit 1 in order to ensure safe, efficient and continuous generation. The incumbent ensures overall safety of Unit Operations through the review and evaluation of changes to procedures, systems and equipment in the light of their effect upon the FSAR, the CFR, etc. This position is responsible for the effective direction of lead engineers and their functional areas, ensuring that technical support is provided in decisions involving all aspects of the Unit's operation, scheduling and coordination of all aspects -

involved with and during plant refueling, supervising budget preparation and controlling expenditures to crnform to the unit budget, recommending various personnel actions, and effectively assists in the coordination of communications between TMI and corporate and System Engineering groups,

c. Authority The Manager has the authority to approve minor plant design and modification work. He has the authority to approve Purchase Requisitions for material, equipment, supplies and services in the Engineering Area at TMI. He has the authority to effect procedure changes through the Plant Operating Review Committee.

Additionally, he shall provide engineering support for the maintenance group.

d. Minimum Qualifications The Manager shall have 8 years in responsible positions related to power generation, of which one year shall be nuclear power plant experience. A Bachelor of Science Degree in an Enginee-ring or Scientific field is preferred and may be credited to the remaining 7 years of experience. The individual should have non-destructive testing familiarity, craft knowledge,and an understanding of electrical, pressure vessel and piping codes.

1613 091 5-27 Am. 9

e. Incumbent Qualifications B.S. Mechanical Engineering - Villanova University, 1963.

1963 - Cadet Eng. - Reading.

1965 2 years Crawford Station - Plant Eng, and then Mech.

Maintenance Form.

1967 - 1 1/4 year Saxton Nuclear - obtaineo NRC Operator License. 8 years TMI Unit 1 - Supervisor Operations 8/1/68, Plant Engineer 1/1/73, Unit Superintendent 8/1/74 to May 77, obtained SRO License.

f. Interface
1. Offsite The Manager will primarily interface with the GPUSC off-site technical support group in creas requiring specialized engineering assistance w'aich cannot be performed by the on-site staff. He will also interface with other enginee-ring firms where design assistance is required. He will interface with Materials Management on procurement / contract problems. He will interface with Regulatory Bodies such as the NRC on technical areas involved with the Technical Specifications.
2. Other TMI Staff Supervisor Maintenance - coordination of work

- allocation of resources

- feedback on program effectiveness Suparvisor - Operations - scheduling of work Manager Plant program technical support / evaluations 1613 092 5-28 Am. 9

5.2.16 Chairman, Plant Operation Review Committee

a. Function The Plant Operation Review Committee Chairman conducts the Committee meetings and manages the meeting records and activities,
b. Responsibility This position is responsible the for conduct of Plant Operation Review Committee activities in accordance with the TMI Unit 1 Technical Specifications.

These activities include review of procedure change, review of reportable events, and review of violations of regulations and procedures having nuclear safety significance,

c. Authority The Chairman has the authority to conduct Plant Operations Review Committee Meetings in accordance with Technical Speci-fication requirements and and relate the findings and formal recommendations to the Manager of TMI Unit 1.
d. Minimum Qualifications The Chairman shall have a Bachelor of Science degree in an engineering or scientific related field and at least four years of nuclear power plant experience. The academic training may be replaced on a one-for-one time basis by power plant or other suitable industrial experience.
e. Incumbent Qualifications Education: Pennsylvania State University Dubois Campus Associate Degree - Electrical 1963-1965 s

Pennsylvania State University Capitol Campus

. Bachelor of Engineering Technology -

Electrical 1968-1970 Relevant Assignments: Summer Student - Engineering Assistant -

TMI - June 1969 - September 1969 Project Engineer - TMI June 1970 - November 1973 Lead Engineer - TMI November 1973 - President 5-29 Am. 9 1613 093

Holds Senior Reactor Operator License on TMI-1.

f. Interface The Plant Operation Review Committee Chairman reports to the Manager Plant Engineering and interfaces with the Onsite and Offsite Engineering Groups, the Nuclear Regulatory Commission, and the Supervisor of Licensing in the execution of the PORC responsibilities set forth in the technical specifications.

1613 094 5-30 Am. 9

5.2.17 Lead Engineer Nuclear

a. Function The Lead Nuclear Engineer functions to provide technical assistance to the plant operations and maintenance departments as directed by the Manager Plant Engineering,
b. Responsibility This position is responsible for the support of plant apera-tions activities related to Nuclear physics testing to verify core design parameters and the evaluation and interpretation of periodic surveillances related to the reactor core, including the review of safety related operating, test and maintenance procedures and procedure changes.

The responsibilities of the Lead Nuclear Engineer include membership in the Plant Operations Review Committee as dafined by the Technical specificaticns.

The Lead Nuclear Engineer also has the responsibility for the direct supervision of physics testing and the evaluation of nuclear parameters are within the bounds permitted by the technical specifications.

Areas of plant operations and maintenance activity technical support include such areas as maintaining-Special Nuclear Material inventory records required by 10 CFR 70 and the coordination of all nuclear fuel movements including fuel receipt.

c. Authority The Lead Nuclear Engineer has the authority to coordinate activities which involve handling of fuel assemblies according to approved procedures. He has the authority to supervise and make the initial determination regarding the acceptability of testing involving nuclear fuel and related fuel handling equipment.

He has the authority to recommend procedure changes and design changes and may perform the initial nuclear safety evaluation on design and procedure changes. ,

d. Minimum Qualifications The lead Nuclear Engineer shall meet the minimum qualification requirements of ANSI 18.1.

1613 095 5-31 Am. 9

T eA Incumbent Qualifications Education: Rensselaer Polytechnic Institute BS Nuclear Engineering - 1976 Relevant Assignments: Nuclear Engineering and Plant Per-formance Corporate Division Engineer I - Nuclear September 1976 - December 1976

f. Interfaces The Lead Nuclear Engineer reports to the Manager Plant Engineering. In performing his duties the Lead Nuclear Engineer interfaces with other lead engineers, the Plant Operations Review Committee , of f site engineering support ,

Nuclear Regulatory Commission inspectors and maintenance operations and radiological control department personnel.

1613 096 5-32 Am. 9

5.2.18 Lead Electrical Engineer

a. Function The Lead Electrical Engineer functions to provide technical assistance to the plant operations and maintenance departments as directed by the Manager-Plant Engineering.
b. Responsibility This position is responsible for the support of plant operations and maintenance activities relating to electrical systems and components , including the review of safety related operating ,

test and maintenance procedures and procedure changes. The responsibilities of the Lead Electrical Engineer include membership in the Plant Operations Review Committee as defined in the Technical Specifications.

Areas of plant operations and maintenance technical support activities include such components and systems as Control Rod Drive, Pressurizer Heater Control, Engineering Safeguards Actuation, Diesel Generators, Main and Auxiliary Transformers, Heat Trace, Main Generator Temperature Monitoring, Electrical Distribution, Grounding and Lightining Protection, Battery and Battery chargers, Inverters and Vital Busses, and Substation equipment.

c. Authority The Lead Electrical Engineer has the authority to recommend procedure changes and design changes. He also has the authority to perform the initial nuclear safety evaluation on design and procedure changes,
d. Minimum Qualifications The Lead Electrical Engineer shall meet the minimum qualification requirements of ANSI 18.1.
e. Incumbent Qualifications Education: Pennsylvania State University Dubois Campus Associate Degree - Electrical 1963 - 1965 Pennsylvania State University Capitol Campus Bachelor of Engineering Technology -

Electrical 1968 - 1970 Relevant Assignments: Summer Srndent - Engineering Assistant -

TMI - J e 1969 - September 1969 5-33 ^** 9 1613 097

Project Engineer - TMI June 1970 - November 1973 Lead Engineer - TMI November 1973 - Present Holds Senior Reactor Operator License on THI-l

f. Inter f ac e The Lead Electrical Engineer reports to the Manager Plant Engineering. In performing his duties the Lead Electrical Engineer interfaces with the other lead engineers, the Plant Operations Review Committee, Offsite Engineering Support Nuclear Regulatory Commission Inspectors, and maintenance, operations and radiological control department personnel.

1 098 5-34 Am. 9

5.2.19 Lead Instrument and Control Engineer

a. Function The Lead Instrument and Control Engineer functions to provide technical assistance to the plant operations and maintenance departments as directed by the Manager Plant Engineering.
b. Responsibility This position is responsible for the support of plant operations and maintenance activities relating to Instrument and Control Systems and components including the review of safety related operating, test and maintenance procedures and procedure chat.ges. The responsibilities of the Lead Instrument and Control Engineer include membership in the Plant Operations Review Committee as defined by the Technical Specifications.

Areas of plant operations and maintenance activity technical support include such components and systems as the Reactor Protection System, Intergrated Control System, Non-Nuclear Instrumentation, Incore Monitoring System, Loose Parts Monitor-ing System, Pneumatic control valves and components, and the Turbine Electro-Hydraulic Control System,

c. Authority The Lead Instrument and Control Engineer has the authority to recommend procedure change and design changes. He also has the authority to perform the initial nuclear safety evaluation on design and procedure changes.
d. Minimum Qualificatiors The Lead I&C Engineer shall meet the minimum qualification requirements of ANSI 18.1.
e. Incumbent Qualifications Education: University of Louisville BSEE - 1966 University of South Carolina MSEE - 1968 Relevant Assignments: NSAEC Division of Naval Reactors (U.S. Navy - 03) - Nuclear Propulsion Engineer, I&C Section Training - Bettis Reactor Engineering School: Reactor 6 months Design; 3 weeks Prototype; 3 weeks - Shipyard-1968 - 1973.

5-35 Am. 9 1613 099

Virg.'.nia Research, Inc. - Engineer 1973 - 1974 TMI - Lead I&C Engineer Training - Several Inst. Vendor Courses I week B&W Simulator 1974 - Present

f. Interfaces The Lead Instrument and control engineer reports to the Manager Plant Engineering. In performing his duties the Lead I&C Engineer interfaces with other lead engineers, the Plant Operations Review Committee, offsite engineering support, Nuclear Regulatory Commission Inspectors and maintenance, operations and radiological controls department personnel.

100 5-36 Am. 9

5.2.20 Lead Mechanical Engineer

a. Function The lead mechanical engineer functions to provide technical assitance to the plant operations and maintenace departments as directed by the Manager - Plant Engineering.
b. Responsibility This position is responsible for the support of plant operations and maintenance activities relating to mechanical systems and components including the review of safety related operating test and maintenance procedures and procedure chandes. The responsibilities of the lead mechanical eengineer include membership in the Plant Operations Review Committee as defined by the Technical Specifications.

Areas of plant operations and maintenance activities, technical support include such components and systems as Steam Generators, Reactor Coolant Pumps, pipe hangers, supports and snubbers, heat exchangers and coolers, Reactor Building structural integrity, Reactor Building containment isolation valve leak tightness, Emergency Diesels, ventilation systems, piping systems, pumps, valves, and filters.

c. Authority This position has the authority as defined in Technical Specifi-cations to advise the Manager - Unit 1 on nuclear safety as a member of the Plant Operations Review Committee.

The lead mechanical engineer has the authority to recommend procedure changes and design changes. lie also has the authority to perform the initial nuclear safety evaluation on design and procedure changes.

d. Minimum Qualifications The Lead Mechanical Engineer shall meet the minimum qualification requirements of ANSI 18.1.
e. Incumbent Qualifications Education: Pennsylvania State University BS Chemistry Military Service: U.S. Navy 1969 - 1974 1613 101 5-37 Am. 9
e. Incumbent Qualifications (continued)

Relevant Assign-ments/ Training: U.S. Naval Nuclear Power School and Prototype Training - 1969 - 1970 Qualified for Supervison of Operations and Maintenance of Naval Nuclear Propulsion Plant 1970 - 1974 Two years experience as TMI-l Operations Department Engineering during first two years commercial operation of Unit and first refueling outage.

Three years experience as TMI-l Lead Mechanical Engineer during commercial operation of Unit including three refueling outages.

f. Interface The Lead Mechanical Engineer reports to the Manager - Plant Engineering. In performing his duties, the Lead Mechanical Engineer interfaces with other lead engineers, the Plant Operations Review Committee, off-site engineering support, Nuclear Regulatory Commission inspectors and Maintenance.

1613 102 5-38 Am. 9

5.2.21 Shift Technical Advisor

a. Function The Shift Technical Advisor will provide direct technical oversight of the plant reactor performance and associated safety systems in order to insure the safety of unit oper-ations.
b. Responsibility The Shift Technical Advisor (NUREG 0579-Section 2.2.1.b) reports to the Manager Plant Engineering. He is responsible for providing on Shift, technical support to the Shift Supervisor in the accident and operating experience assessment functions. The Shift Technical Engineer also has the responsibility for:

. monitoring the readiness of engineered safety features to perform their design function, including the evalu-ation of the need for and initiation of corrective action on such components and systems.

. advising the Shift Supervisor of any condition that may compromise the performance of Safety Systems of components, in the event of an emergency:

. providing technical liason with the Plant Engineering Department regarding matters pertaining to Nuclear Safety.

. providing technical advice to the Shif t Supervisor during plant transients, abnormal events and emergencies.

c. Authority The Shif t Technical Advisor acts in a monitoring / advisory capacity to the Operations Shift Supervisor and Shift Foreman.

He will advise and assist the Shi f t Supervisor in matters of reactor safety. He will also advise the Shift Supervisor whenever he believes it necessary to call for outside technical support,

d. Minimum Qualifications The Shif t Technical Advisor shall have a Bachelor of Science Degree in an Engineering or Scientific related field. A minimum of two years of related experience sin power generation.

In addition to the academic education, the Shif t Advisor shall possess a thorough knowledge of plant systems and components.

In addition, it is intended that the Shift Technical Engineer obtain the training necessary to be licensed as an SRO or on as soon as practicable basis but need not be licensed.

5-39 Am. 9 1613 103

e. Incumbent Qualifications Incumbent A High School Graduate. University of Missouri - B.S. Mechanical Engineering - 1972.

1972-76 Field Engineer, General Electric Co. Installation &

Service Div.

1976-Present - Metropolitan Edison Company 1976 - Eng. II Nuclear T!;I 1978 - Eng. III - Generation - Reading 1979 - Shift Engineer III - TMI 6/66 to 4/70 U.S. Air Force - Inventory Management Specialist, Dyess Air Force Base, Abilene, Texas.

Incumbent B High School Graduate. North Carolina State University - B.S.

Nuclear Engineering - 1976.

4/70 to 4/76 National Guard special schools in Accounting and Radar techniques .

1970-1971 - HP Tech. with Westinghouse Nuclear Fuel Div.

1971-1973 - Service Representative 3M Corp. - Instrumentation Technician.

1976 - Present - Metropolitan Edison Company - Engineer I -

Generation.

1979 - Engineer II - Generation 1979 - Shift Engineer II - TMI.

Incumbent C High School Graduate. 1976 - B.S. Physics Albright College and MSE Towne School of Engineering and Applied Science, University of PA.

1976 - Metropolitan Edison Company - Engineer I - Generation.

1979 - Metropolitan Edison Company - Engineer II - Generation.

Incumbent D High School Graduate. B.S. Nuclear Engineering - Rensselaer Polytechnic Institute, Troy, NY - 1976.

Master of Engineering - Nuclear Engineering - Penn State University 1979.

6/78 to 9/79 - Metropolitan Edison Company.

6/78 - Engineer I - Generation 9/79 - Shift Engineer I - TMI Incumbent E High School Graduate. BSEE, Penn State University 1977.

U.S. Navy 7/68 to 7/72 - Aviation Electricians Mate-Class A.

Flight Electrician and ECM Operator.

11/77 - Present - Metropolitan Edison Company - TMI.

5-40 Am. 9 1613 104

11/77 - Eng. I - Nuclear 8/79 - Eng. II - Nuclear 9/79 - Shift Engineering Incumbent F High School Graduate. B.S. Nuclear Engineering - Penn State University 1977.

6/77 - Present - Metropolitan Edison Company - TMI.

6/77 - Eng. I - TMI 9/79 - Shif t Technical Eng. - TMI.

f. Interfaces
1. Offsite The Shif t Technical Advisor will not normally have any offsite interface. He may, however, at times seek assis-tance from support organizations such as B&W, GPUSC, throught the manager of plant Engineering. He will also assist in the overall interface required during an emergency with the various outside agencies.

1613 105 5-41 Am. 9

5;2.22 Supervisor Chemis,ty

a. Function The Supervisor Chemistry functions to implement and sup-port the total plant chemistry program, which involves labora-tory chemical analysis, primary and secondary system chemistry control, wat*r treatment, waste treatment and radiochemistry to ensure safe, reliable plant operations which meet the require-ments of state and federal regulatory agencies.
b. Responsibility The Chemistry Supervisor in carrying out his responsibility for overall direction of the day-to-day TMI-l chemistry program is responsible for:
1. Proper operation and calibration of all chemical and radio-chemical analytical and counting instruments.
2. Selection, set-up and calibration of new laboratory equipment necessary to maintain quality laboratory analysis concurrent with systems and discharge limitations.
3. Selection and development of chemical and radio chemical analytical procedures.
4. Insuring through appropriate analysis compliance with chemical sections of plant technical specifications, manufacturers specifications and discharge permits.
5. Preparation and/or review of chemically oriented operating procedures.
6. Providing technical supervision and assistance for the operation of the water treatment systems, chemical addition systems and waste treatment facilities.
7. Maintaining adequate chemistry records and preparing any necessary reports to various state and federal agencies.
8. Providing technical guidance for the selection, setup calibration and operation of on-line chemical analyzers.
c. Authority The Chemistry Supervisor has the authority to specify required chemical additions to plant systems based on analysis and required chemistry parameter limits.

1613 106 5-42 Am. 9

d. Minimum Qualifications The Chemistry Supervisor shall meet the minimum qualification requirements of ANSI /ANS 3.1-1978, Section 4.4.3, Chemistry and Radio:hemistry.
e. Incumbent Qualifications Education: BS Animei Science - Pennsylvania State University - 1967 Relevant Assignments: Chemist - Saxton Nuclear Experimental Corporation - July 1968 - August 1972 Chemist - TMI - August 1972 - April 1974 Chemistry Foreman - TMI -

April 1974 - Present

f. Interfaces The Chemistry Supervisor reports to and is held accountable for TMI-1 Chemistry by the Met-Ed Manager - Plant Engineer-ing. The Chemistry Supervisor interfaces and communicates with the General Public Utilities System Chemical Labs and others, such as manuf acturer's representatives or consul-tants in order to maintain the technical liaison necessary in the chemistry area.

I613 107 5-43 Am. 9

5.2.23 Technical Analyst - Fire Protection.

a. Function The Technical Analyst - Fire Protection functions to coordinate the implementation of the Fire Protection Program at Three Mile Island,
b. Responsibility / Authority The Technical Analyst - Fire Protection is responsible for the overall readiness of all fire service and fire protection systems at Three Mile Island. The position is further respon-sible for evaluating related station fire protection activities to ensure satisfactory fire protection / prevention practices and conformance to required codes. This responsibility in:1udes frequent station inspection, operation and mair.tenance (both corrective and preventative) assistance, and fire protection procedure review and development. This position is responsible for coordinating, developing ansd assisting the training department in the implementation of training programs for the Station's fire brigades and local fire companies,
c. Authority The Technical Analyst - Fire Protection has the authority to make recommendations to improve the overall station Fire Protection program, including the areas of training, fire prevention, fire system and component material readiness and technical specification compliance.
d. Minimum Qualifications The Technical Analyst - Fire Protection shall have a high school diploma or equivalent and shall have at least one year of practical experience in the protection field,
e. Incombent Qualifications Education : High School Graduate - 1966 Completed 40 credit hours in Fire Service. Presently enrolled at Harrisburg Area Coimnunity College.

Military Service: U. S. Navy 1968 - 1977 Relevant Assign-ments/ Training: Power School (26 weeks) - 1969 U. S. Navy Prototype Instructor - 1970 - 1973 Quality Control Assistant -

TM1 - 197 7 - 1978 5-44 Am. 9 1613 108

Tech. Analyst / Fire Protection TMI - 1978 - Present

f. Interface This position interfaces with the engineering disciplines in both units and with the Company's fire protection engineer, the fire protection engineers in the architect-engineering firms, and with the Company's insurance and claims department.

The position further interfaces with the plant operations, utility, maintenance, and safety departments in the imple-mentation of the Fire Protection Program.

1613 109 5-45 Am. 9

5.2.24 Manager Administration and Services

a. Function The Manager of Support Services and Logistics reports to the Vice President and is responsible to plan, organize, and direct the day to day activities of the Personnel, Budgets and Reports, Security, Facilities, Document Control, Of fice Management, and Safety functions.
b. Responsibilities This position assures that ef fective programs are implemented in Personnel Administration, Personnel Recruiting and Employ-ment, Personnel Wages and Salary Administration; that an ef fective Operations and Maintenance and Capital Budget pre-paration, review and appr? val process is in effect, that the TMI Security Plan is implemented in accordance with r.ll applicable regulations; that an efficient Office Management program is in effect; and that the Industrial Safety Program is developed, organized, ano implemented to insure that a safe working atmosphere exists for all employees and that all applicable safety regulations are met.
c. Authorities Consistent with the responsibilities of this position, the Manager Administration and Services is authorized to institute procedures required to implement programs which improve or enhance the degree of Support Services provided to the plant operating staff. Additionally, consistent with the level of signature authority established, this Managw can extend job offere and approve other personnel transactions, authorize and approve expenditures and authorize facility changes.
d. Minimum Qualifications This position is required to support the Met-Ed organization and shall have appropriate qualifications.
e. Incumbent Qualifications The (acting) incumbent received a' Bachelor of Science Degree in Civil Engineering in 1957 from the Pennsylvania State University. From 1957 to 1959 he served as a Navy Officer on an Amphibious Ship. He was employed by Met-Ed in 1959 and has held positions in the. Transmiss'on Engineering function for fourteen years, the Distribution Operations function for one year, the Operations Analysis function for four years, and is currently Manaa,er - Generation Administration, having been named to that position on April 1,1978. He has attended the Public Utility Executive Program at the Graduate School of Business Administration, University of Michigan.

5-46 Am. 9 1613 110

f. Interfaces
1. Off-site A functional line of communication exists with the GPUSC Manager - Management Services to coordinate int e rc ompany actions in the functional areas of responsibilities assigned to this position.
2. TMI-2 All functional areas of responsibility assigned to this position are common between TMI Unit 1 and TMI Unit 2; therefore, the employees in this organization unit routinely divide their time evenly between both units, fll 5-47 Am. 9

5.2.25 Manager Training

a. Function The Manager - Training reports to the Metropolitan Edison Vice President. In this position he is responsible for the operator training, technician training and accelerated operator retraining. The technical training section will include training for maintenance and readiological control technicians. The operator accelerated retraining program is a broad program based upon changes and lessons learned as a result of the TMI-2 accident. The training department will be augmented by outside consultants as necessary.
b. Responsibility This position is respo.asible for the training of all personnel at TMI. This responsibility is discharged through an organiza-tional structure devised to address training consistent with established functional disciplines. In addition, the organiza-tion provides its owr. administrative support and any temporary personnel necessary to conduct the major programs. The principle reponsibilities of this position are:
1. To assure the content and conduct of training for Reactor Operators, Radiological Control and Maintenance Technicians, and to insure Professional personnel and Management person-nel meet Federal, State, and Local regulatory requirements and conform to establish industry standards.
2. Oversee the development and maintenance of a viable station training philosophy.
3. To select and develop competent training staff.
c. Authority The Manager - Training has the authority to schedule and imple-ment approved TMI training programs. He has the authority to recommend SRO and CR0 candidates for NRC license examinations.
d. Minimum Qualificati s This position is required to support the Met-Ed orginization and shall have appropriate qualifications,
e. Incumbent Qualifications B.S. Degree in Physics - Ill. Institute of Technology.

Employed - U. S. Navy 1948 Reactor Operator, Nuclear Power School Instructor.

Met-Ed - 1973-Present - Head of Licensing, QA Program, Manager Generation Operations.

Argonne National Laboratory 6/58-7/58 - Instructor and Reactor Operator.

Vermont Yankee Nuclear Power Corp. 7/68-7/73 1613 112 5-48 Am. 9

f. Interfaces
1. Offsite The position, Manager-Training, interfaces with Licens-ing in the areas of regulatory training and LER in-corporation into the operator training program. Inter-face with Eng. insures the utilization of knowledgeable and qualifed engineers to develop trainin3 materials and provide instruction in accordance with approved training programs.

1613 113 5-49 Am. 9

5.2.26 Supervisor Operator Training

a. Function The Supervisor Operator Training reports to the Manager Training. In this position he is responsible for the planning, preparation and conduct of the licensed and non-licensed operator training and requalification programs. Included is the operator accelerated re-training progran which is based upon the changes and lessons learned as a result of the TMI-2 accident,
b. Responsibility This position is responsible for the training of all licensed and non-licensed operators and senior reactor operators at TMI.

This responsibility is discharged through an operator training organizations structure devised to address the trainee among functional discipline lines. Principle accountabilities of this position are:

1. Formulation, administration and implementation of approved operator training programs for exempt and non-exempt per-sonnel at the Three Mile Island Nuclear Station. This includes curriculum development, training material prepar-ation and presentation, scheduling, examination preparation and administration, e.nd program evaluation.
2. The implementation of specialized nuclear initial training programs for auxiliary operators, Control Room Operators, shift supervisors sad foreman, and plant engineers.
3. The development and implementation of the TMI Operator Requalification Program (10 CFR 55 requirement) for continued NRC licensed operator certification and continued station operations.
4. The development cf procedures necessary to implement an effective SED, CR0 and Auxiliary Operator training pro-gram,
c. Authority The Supervisor of Operator Training has the authority to schedule and implement approved training programs.
d. Minimum Qualification At the time of assuming the position, the Supervisor of Training shall have a high school diploma or equivalent and four years of experience in the educational or training discipline.

At least one year of this experience should be nuclear.

5-50 Am. 9 1613 114

e. Incumbent Qualifications
1. High School Graduate - Reading Senior-High School, Reading, PA.
2. Employed - Western Electric Co. 1959-1961, Senior Electronic technician
3. Employed - Penn State University Nuclear Engineering Dept. 1963-1969, Reactor Operator Training Supervisor.
4. Employed - Met-Ed, 1969-1973, Training Specialist.

1973-1976, Administrator Nuc/ Tech Training.

1976-1978, Group Supervisor Tech. Training.

5. Attended Penn-State University 1961-1969, Full and part-time accumulated 83 credits.
6. Held Senior Reactor Operator License-Penn State University Nuclear Reactor Facility.
7. Graduate - Babcock and Wilcox Nuclear Steam Supply School and Simulator Startup Certification Program.
8. Fifteen years experience in operator training.
f. Interface The Supervisor Operator Training, interfaces with the TMI Operations Department to insure continaity and compliance with training program requirements. Interface with the Nuclear Regulatory Commission Licensing Branch for the scheduling of NRC operator examinations. Interface with the Babcock and Wilcox Corp. for the scheduling of Nuclear Steam Supply System and Simulator Training.

1613 115 5-51 Am. 9

5.2.27 Supervisor-Technician Training Section

a. Fur.ction The Supervisor-Technician Training reports to the Manager-Training in performance of his duties. He is responsible for supervising the performance of personnel assigned to the training department in the following groups:
1. Maintenance
2. Radiological Controls
3. Chemistry
4. Security
b. Responsibility The Supervisor-Technician Training is responsible for developing and conducting training in the following areas:
1. Maintenance Technician Training
2. Radiological Controls Training
3. Chemistry Training
4. Security Training
5. Emergency Plan Training In addition he is responsible for providing support training in the following areas:
1. General Employee Radiological Controls Training
2. General Employee Security Training
3. Operator Radiological Controls Training
c. Authority The Supervisor-Technician Training has the authority to develop and conduct approved training programs in his areas of respnsi-bility. In addition, he has the authority to meet directly with other Station Department Heads in order to develop specific technical training program needs and related requirements.

1613 116 5-52

d. Minimum Qualificaticas At the time of assuming the position, the Supervisor-Technician Training shall have a high school diploma or equivalent and four years of experience in the related educational or training discipline.
e. Incumbent's Qualifications B.S. Degree in Engineering -- U.S. Naval Academy Employed -- U.S. Navy, 1945-1970, various positions from hospital corpsman to commanding officer, nuclear submarine 1972-1977 Supervisor Training -- Nuclear Power Station. Held SRO license -- PWR
f. Interface The Supervisor-Technician Training interfaces with the other training sections in the Training Department and with GPUSC engineering personnel for technical assistance. In addition, direct liaison is authorized with other station Department Heads and off-site training contractors in performance of his duties.

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5.2.28 Supervisor-Career Development Training

a. Function The Supervisor-Career Development Training reports to the Manager Training. His functions are General Employee Training, Support Training and Supervisory Development Training. The General Em ployee Training group will include general training and retraining for TMI employees, Basic Radiological Control and Intermediate Radiological Controls training for contractor and vendor personnel and orientation training for newly hired personnel. The super visory development groups will identify, develop and conduct those specific training courses and pro-grams for supervisory and manage ment personnel at the TMI station. These include Shift Technical Advisor training and Decision Analysis training for shift super vision and manage-ment personnel.
b. Responsibility This position is responsible for training general station personnel and station supervision and managenent. This re-sponsibility is discharged through a training section organ-ization structured along functional lines. Principle responsi-bilities of this position are: 1. To implement training directives from the Manager-Training for the areas of general employee training, support training, and supervisory develop-ment training.
1. To implement training directives from the Manager-Training for the areas of general employee training, support train-ing and supervisory development training.
2. To direct, coordinate and administer the training and retraining programs and activities of the subordinate career development training groups.
3. To interface with other training sections and TMI Station departments to identify, develop and implement general, supervisory, and support training programs.
4. To assure that training program content and conduct meet applicable Federal, State and Local regulatory requirements and conform to industry standards.
5. To oversee the dissemination and implementation of appropriate training procedures and practices.
6. To assist the Manager-Training in the evaluation of training program effectiveness.
7. To administer and implement the department training philosophy and assure transmittal of the philosophy to subordinate groups.

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c. Authority The position is delegated the authority from the Manager-Train-ing to discharge the necessary duties and responsibilities of the Career Development training section. He has the authority to develop and implement approved programs in the areas of his responsibility,
d. Minimum Qualifications The Supervisor-Career Development Training will possess the education, training, expertise, and experience necessary to discharge the functioning of the training section, and shall have four years experience in education or training or equivalent.
e. Incumbent Qualifications B.S. Electrical Engineering M.S. Electrical Engineering 1961-1967: Electrical Engineer - RCA 1967-1978: Associate Professor / Department Chairman Engineering Technology - Luzerne Community College 1978-1979: Systems Engineer - Bell Telephone Laboratories Present: Supervisor, Generation Training - Metropolitan Edison Co.
f. Interface
1. Offsite The position interfaces with the Met-Ed Employee Education and Development department in the areas of supervisory development training programs. Also interfaces with academic institutions and industry training organizations.

Additional interface with regulatory agencies to further define requirements of training programs.

2. Onsite The position interfaces with other training sections and TMI Station departments to develop and implement the training and retraining programs for general employees, support training, and supervisory development.

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5.2.29 Manager Radiological Controls

a. Function The Manager Radiological Controls - reports to the Vice Presi-dent Met-Ed on all matters related to the implementation of the Radiological Control Program design, support and enforcement functions in the ongoing operation, maintenance and construction activities associated with TMI-1.
b. Responsibility The Manager Radiological Controls is responsible for:

. The development and implementation of a Radiological Control Program which meets or exceeds those requirements specified in the Radiation Controls Plan, Technical Specifications, Code of Federal Regulations as related to the NRC or other Regulatory directives.

. The coordination of the Radiological Controls Department with the maintenance, operation and construction activities of other Unit 1 Departments.

. The direction of the technical review of all matters addressed to the Radiological Controls Department which involve personnel exposure to external or internal radi-ation.

. The technical review of all operations which release radioactivity to the environment.

. The monitoring and proper documentation of all radioactive material received, transferred or shipped offsite by Unit 1.

. The maintenance of records reflecting the results of all inspections and surveys pertinent to the Radiological Controls Program in Unit 1.

. The technical review and approval of all courses of training which may affect the Radiological Control Program including the approval of all examinations which measure the effective-ness of such training for both radiological control tech-nicians, operations, maintenance and craft trades personnel.

. The certification of qualification of all personnel who perform radiation monitoring or survey functions directly affecting the radiological safety of other personnel.

. The support of Manger Unit I through the technical review of radio-chemical analyses and an independent monitoring of the performance of the conduct of such analyses by the Chemistry Department.

5-56 Am. 9 l613 l20

. The reporting to proper station authority all unusual operating conditions likely to affect personnel radiological safety.

. Support of the Operations Department in Radioactive waste processing and treatment activities ,

c. Authority The Manager Radiological Controls - has the authority to direct the termination of any operation, maintenance, or construction which is not being accomplished in accordance with radiological control practices and procedures.
d. Qualifications The Manager Radiological Controls - shall have a Bachelor of Science Degree in Engineering or Scientific field and have 5 years of Nuclear Power Plant experience.
e. Incumbent Qualifications Education: BSEE Iennsylvania State University - 1970 Military Service: U. S. Navy - 1960-1966 Relevent Assignments / Test Engineer - Saxton Nuclear Training: Experimental Corporation Mar. 1970 - Aug. 1970 Supervisor Reactor Plant Services -

Saxton - Aug . 1970 - Aug . 1972 Supervisor - Quality Control TMI Unit 1 - Aug. 1972 - July 1976 Supervisor - Licensing Met-Ed - July 1976 - Jan. 1979 Superintendent - Technical Support Unit 1 - Jan. 1979 - Nov. 1979

f. Interfaces A separate organization under the TMI-2 Manager Radiological Controls reporting to the Senior Vice President, Met-Ed, in addition to providing direct services to Unit 2, provides contract functions to Unit 1 through the TMI-1 Radiological Controls Manager. These functions provided include personnel dosimetry, respiratory protection technical support, maintenance and calibration of survey instruuentation, and technical support related to the shipment of solid radioactive wastes.

5-57 Am. 9 1613 121

The Manager Radiological Controls - interfaces with the Mana-gers of, Plant Engineering, Training, and Administration and Services for Radiological Control Program related activities in chemistry, maintenance, operations, construction, radwaste treatment and processing, technician training, and security.

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. 4 5-58 Am. 9

5.2.30 Supervisor Radiological Controls

a. Function The Supervisor Radiological Control reports directly to the Manager Radiological Control for the coordination and perfor-mance of Radiological Control support and enforcement functions accomplished by Radiological Control Technicians including contract technicians assigned to the Radiological Control Technicians Group.
b. Responsibility The Supervisor Radiological Control is responsible for ensuring that radiological control functions thru the Supervision of the Radiological Control Foreman, are accomplished in full compliance with Title 10, Code of Federal hagulations, Part 20 (and other such regulations as applicable) and approved radiological control procedures and practices. Specific responsibilities include such items as:

. The execution of radiological surveys, including their scheduling and review, for radiation, airborne radioactivity, and surface contamination to assess radiological conditions in work areas.

. Coordinating and approving the training given to personnel assigned to perform foreman and technician radiological control activities.

. The evaluation and approval of the qualifications of personnel assigned to perform radiological control foreman and technician functions.

c. Authority The Supervisor Radiological Control has the authority to direct the termination of an operation or activity which is not being accomplished in accordance with regulations and radiological control practices and procedures.
d. Qualifications The Supervisor Radiological Control shall have a minimum of five years of Nuclear power plant radiological control work experience,
e. Incubent Qualifications

. High School graduate - 1963

. Navy GED Correspondence

. College - 1 year - Navy GED Correspondence 5-59 ^"* 9 1613 123

. United States Navy Nuclear Power Program - 6 1/2 years 1964-1971

. Mechanical Operator - Engineering Lab Technician -

Nuclear powered submarine.

. Nuclear power submarine

. Radiological Control Supervisor - Nuclear Submarine Tender

. Metropolitan Edison Company (Three Mile Island) 9 years 1971 present

. Auxiliary Operator "A" - 3 years

. Radiation-Chemistry Technician - 3 years

. Radiation Protection Foreman - 3 years

f. Interfaces This position interfaces with all TMI departments including Contractors to enforce compliance with approved radiological control and practices.

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5.2.31 Radiological Controls Foremen

a. Function This position reports to the Supervisor of Radiological Con-trols on assigned areas of responsibility to implement and enforce the Radiation Protection Program.
b. Responsibility This position is responsible for the implementation of the Radiation Protection Program by the Radiation Control Techn-icians. This includes insuring that all procedures involving Radiological Surveys, Radioactive Material Control and radia-tion exposure control and assessment are fully implemented.

This position is also responsible to review the practices of other personnel working within restricted areas to provide additioral assurance that all personnel are performing work in accordance with good radiological practices,

c. Authority This position has the authority to direct the activities of the Radiological Controls Technicians in the performance of their duties as well as to determine the radiological controls measures to be included in all work involving exposure of personnel to radiation or radioactive material. This position has the authority to stop any work being performed which is not in accordance with good radiological practices.
d. Minimum Qualifications High School graduate or equivalent and have at least three years experience as a technician qualified to ANSI /ANS-3.1-1978 paragraph 4.5.2.
e. Incumbent Qualifications Incumbent A

. High School Graduate 1968

. RCA Institute 1966-1968

. United States Navy Nuclear Power Program - 6 years 1968-1974

. Metropolitan Edison Company (Three Mile Island) 5 years 1974 present

. Radiation-Chemistry Technician 3 years

. Radiation Protection Foreman 2 years i25 5-61 Am. 9

Incumbent B

. High School Graduete 1968

. College - 2 ye:rs - 1968 - 1970

. Metropolitan Edison Company (Three Mile Island) 9 years 1970 present

. Lineman 3 years

. Radiation-Chemistry Technician 5 1/2 years

. Radiation Protection Foreman 1 1/2 months Incumbent C

. High School Graduate 1969

. University of Pittsburgh - B.S. in Biology - 1969-1973

. PA Dept of Transportation - Lab Technician 4 months

. PA Dept of Environmental Resources-Maintenance 4 months

. PA Dept of Agriculturee - Assistant Entomologist 6 months

. Metropolitan Edison Company (Three Mile Island) 1973 present

. Radiation-Chemistry Technician 6 yeras

.. Radiation Protection Foreman 1 month

f. Interface The position interfaces with every department and contractor organization which has need to enter the restricted area of the Unit to ensure the enforcement of approved radiological work practices and procedures. The interface includes interaction with regulatory agency inspectors in the review of the Radia-tion Protection Program.

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5.2.32 Radiological Controls Technicians

a. Function Under the direction of a Foreman, radiological controls Technicians support and enforce the implementations of the Radiological Control Program to insure that all procedures involving radiological surveys, radioactive material control, and radiation exposure control and assessment are fully ob-served; and, that work being performed with in restricted areas is in accordance with good radiological practices.
b. Responsibility The Radiological Controls Technicians are responsible for the accomplishment of tasks related to the radiological support of plant operations, maintenance, and construction activities.

Additionally, the Technicians are responsible to functionally enforce the field use of correct radiological control wcrk practices.

c. Authority Under the direction of a Foreman, the Technicir.ns assure that radiological control measures are included in all work activities involving exposure of personnel to radiation or radioactive material. This position has the authority to stop any work which is not being performed in accordance with good radiological practices.
d. Minimum Qualifications High School graduate or equivalent and meet or exceed the qualifications of ANSI /ANS-3.1-1978, para 4.5.2. All Techni-cians will be qualified by training and examination on each area or specific task related to their radiological control function prior to the performance of those tasks.
e. Interfaces The position interfaces with every department and contractor organization which has need to enter the restricted area of the unit to ensure the enforcement of approved radiological work practices and procedures.

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5.2.33 Supervisor Radiological Engineering

a. Function The Supervisor Radiological Engineering reports directly to the Masnager Radiological Control on all matters involving the Radiological Control program design and the technical aspects related to implementation of the program support functions including ALARA, Bioassay and Respiratory Protection.
b. Responsibility The Supervisor Radiological Engineering is responsible thru the supervision of the technical staff for the accomplishment of:

. Design reviews for proposed facilities, systems, and equipment that potentially affect radiation exposures.

. Accomplishing ALARA through: periodic review of work conditions; review of procedures; preplanning of work to include briefings; and developing and maintaining standard work practice and procedures.

. The calibration and maintenance of survey and laboratory instruments used in Unit 1.

. Maintaining technical liaison with the Radwaste Disposal group for the handling, storage, and shipping of radioactive material from Unit 1.

. The preparation and/or revision of radiological control program implementing procedures to meet current regulatory requirements / standards.

. The maintenance of required survey and exposure records.

. The timely submission of required reports and notifications.

. Respiratory protection.

. Dosimetry and bioassay.

. The review and approval of radioactive releases.

c. Authority The Supervisor Radiological Engineering has the authority to direct the termination of any operation or activity which is not being accomplished in accordance with regulations and radiological control practices and procedures,
d. Qualifications lhj} j

The Supervisor Radiological Engineering shall be qualified per paragraph 4.4.4 ANSI /ANS-3.1-1978 and further shall possess the qualifications prescribed in Regulatory Guide 1.8. 5-64 Am. 9

e. Incumbent Qualifications Education: BS Physics - Fairfield University -

1970 MS Nuclear Engineering - Georgia Tech - 1971 Military Service: U. S. Navy - 1972-1974 Relevent Assignments: Radiation Health Officer - Nuclear Submarine Tender - 1972-1973 Radiation Physicist - Naval Regional Medical Center - 1973-1974 Radiological Engineer - TMI - 1974-1976 Radiation Protection Supervisor - TMI - 1976-1977 Supervisor Radiation Protection & Chemistry - TMI - 1977-1979

f. Interfaces The Supervisor Radiological Engineering interfaces with other engineering groups, training, maintenance, operations, Nuclear Regulatory Commission, and other regulatory bodies necessary to perform his function.

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5.2.34 Radiological Engineers

a. Function As directed by the Supervisor-Radiological Engineering this position functions to provide engineering support for the Radiological Control Program.
b. Responsibility This position is responsible for providing technical support to the Radiological Control Program in the areas of general program design, respiratory protection, dosimetry program design, and ALARA program design. This position is responsible to insure that various aspects of the Radiological Control Program are in accordance with regulatory requirements, guides and standards as well as correct radiation protection practices.

The position is also responsible for the review of plant modifi-cations and design changes to insure that they are in accordance with ALARK considerations.

c. Authority Radiological Engineers have the authority to recommend changes to the Radiological Control Program to insure continued compli-ance with regulatory requirements. They have the authority to define procedural requirements necessary for implementation of approved program changes by the Radiological Controls Group.
d. Minimum Qualification A Bachelors Degree in Health Physics, a Physical Science, Engineering or equivalent.

I

e. Incumbent's Qualifications Education: BS - Radiological Health Physics Lowell University - 1974 Relevant Assignments : New England Nuclear - Cyclotron Operator and Health Physics Support 1973 - 1974 Morrison Knudsen Co. (Knolls Atomic Powr Lab) - Associate Health Physicist 1974 - 1976 Yale University - Associate Health Physicist 1976 -1977 Metropolitan Edison Co. (Three Mile Island) - Radiological Engineer 1977 - 1979 5-66 ^**

1613 130

f. Interfaces This position interfaces with the Radiological Controls group, Operations Department, Maintenance Department and Engineering personnel as well as consulting engineers and Health Physicists in the normal performance of duties. This position also interfaces with regulatory personnel to insure adequate program design.

1613 131 5-67 Am. 9

5.3 STATION SUPPORT ORGANIZATION The facility organization is supplemented by the resources of General Public Utilities. The GPU Station Support Organization, shown in Fugure 5.3-1, will function in the five main areas of: corrective maintenance, IMI-2 recovery, technical functions, environmental health and safetiy and reliability engineering. The Director of Maintenance reports to the Senior Vice President-Met-Ed-Vice President - GPU and is responsible for corrective maintenance and construction at Three Mile Island including coordination with outside contractors as necessary. The Superintendent of Maintenance reports to the Director of Maintenance and is responsible for Met-Ed and contractor cor-rective maintenance on IMI-1 and 2. Operations related cor-rective maintenance activities are coordinated through the respective supervf sors of maintenance with the unit supervisors of operations. A Supervisor of Maintenance on each unit reports to the Superin-tendent of Maintenance and is re.sponsible for Met-Ed corrective maintenance in the mechanical, electrical, and instrument and control areas for the respective units. Lead foreman on each unit in the various maintenance areas report to the supervisors of maintenance as shown in Figure 5.3-1. The Director of 1MI-2 Recovery reports to the Senior Vice Presi-dent Met-Ed-Vice President GPU and is responsible for the licens-ing and environmental safety of generating stations. The Director - Environmental Health and Safety reports to the Senior Vice President Met-Ed-Vice President GPU and is respon-sible for the licensing and environmental safety of generating stations. The Director Technical Functions reports to the Senior Vice President-Met-Ed, Vice President GPU. gthispositionhewill be responsible to provide a centralized technical capablity to support generating facilities. This capability will include general mechanical, civil, electrical and instrumentation and engineering mechanics areas to assist in the solution of plant operating problems. In addition, this position will be respon-sible for supporting GPU nuclear plants in the areas of nuclear fuel management, process computer, control and safety analysis, and plant operational analysis. In addition, IMI Engineering Management section has been organized to be the focal point for the coordination of all out of plant technical support for TMI operations. 1613 132 5-68 Am.9

The Director of Reliability Engineering reports to the Senior Vice Presidet-Met-Ed Vice President GPU. In this position, he is responsible for the activities of the systems laboratories and the quality assurance functions including the quality control support on site. 5.3.1 GPUSC Technical Functions Group The GPUSC Technical Functions Group consists of four engineering departments, namely Systems Engineering, Engineering & Design, Technical Management and IMI-2 Recovery Engineering. This group provides offsite support for TMI-1 as specified below: All staff, except as noted, includes only GPUSC permanent person-nel. Support from outside contractors is not included but is available on short notice to supplement the GPUSC staff as necessary. This may be used to accommodate short term manpower intensive needs or accommodate temporary vacancies. The Technical Functions Group management personnel e~ach have at least a B.S. degree in engineering or science and the following experience. Years of Eng. Years of Nuc. Title Experience Experience Director, Technical Functsons 26 24 Manager, Systems Engineering 22 22 Manager, Engineering & Design 20 14 Manager, IMI-2 Recovery Engineering 14 14

a. Systems Engineering Department is responsible for providing support in the areas of nuclear fuel management, process computer, control and safety analysis and plant operational analysis. More detailed responsibilities are:
1. Nuclear Analysis & Fuels - Responsible for analytical and other activities related to core reloads, fuel management and the physics performance evaluation, including shield-ing analysis.
2. Process Computers - Responsible for all process computer systems including both computer hardware (main frame and auxiliary memory units, input / output equipment and CRT display devices) and computer sof tware.
3. Control & Safety Analysis - Responsible for plant control systems engineering. Plant subsystem dynamic simulation and safety analysis.
4. Plant Analysis - Responsible for analyzing overall plant performance and the behavior of individual systems and components.

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The current department staff is 30, with a total staff of 51 planned (includes 7 Met-Ed personnel for Process Computers).

b. The Engineering & Design Department provides a centralized capability in the general mechanical, civil, electrical and instrumentation, and engineering mechanics areas. Other services include civil engineering and engineering standares and procedures. More detailed responsibilities are:
1. Engineering Mechanics - Technical expertise for the analysis of all structural and fluid mechanics problems, including piping, stress analysis and supports, general vibration and dynamics of mechanical equipment, acoustic noise, and fluid dynamics such as water and steam hammer, cavitation and related problems.
2. Mechanical Systems - Primary responsibilities for the analysis, engineering and design of all fluid and ma-terials handling systems.
3. Mechanical Components - Provides technical expertise in the application of specialized mechanical components including pumps, fans, valves, heat exchangers and power conversion equipment. Also responsible for the general area of water tr.atment and industrial waste management systems.
4. Electrical Power & Instrumentation - Responsible for analysis and design of plant main and auxiliary electrical power distribution systems, protective relaying, light-ing, communications, and grounding and cathodic protec-tion and design capability for instrumentation application and I&C circuits.
5. Design & Drafting - Responsible for providing generalized design and drafting support, including piping systems, electrical power and instrumentation, plant arrangements and equipment installation.

The current department staff is 53; with a total staff of 74 planned.

c. The Technical Management Group is responsible for coordinat-ing and directing of assigned projects including all out of plant technical support for TMI operations.

The current group staff is 8 with a total staff of 12 planned.

d. The TMI-2 Recovery Engineering Department is responsible for coordinating and directing assigned projects dealing with 1MI-2 recovery, including radwaste reactor systems and containment and in-containment restoration projects. This department also provides onsite engineering support in the following areas:

5-70 Am. 9 1613 134

Fluid and electrical systems, radiation and radiochemistry analysis, and process and waste management systems. The current department staff is 4 with a total staff of 20 planned. 1613 135 5-71 Am. 9

5.4 Quality Assurance Program and Procedural Control the TMI-1 Restart 5.4.1 The TMI-2 accident has required major readjustments in the organization and management of the TMI Nuclear Station. The organizational structure of the General Public Utilities Service Corporation (GPUSC) and the Quality Assurance Program for con-trolling the operational activities, at mI Nuclear Staton are contained in the Operational Quality Assurance Plan for TMI Units 1 and 2. This Plan establishes the organization and the manage-ment controls and Quality Assurance Program necessary to assure that the' operational phase activities at the Nuclear Station are performed and controlled in a manner that will not endanger the health and safety of the public or the employees or contractors of Metropolitan Edison Company (Met-Ed) or the GPUSC. Inherent in the oeprations of the Nuclear station are those day-to-day activities which are direcity associated with keeping Unit 1 on the line and Unit 2 in a safe configuration while the decontami-nation and/or restoration activities are being performed until such time as Unit 2 becomes operational. These activities are performed by the Operations personnel and those supporting activities such as radiation protection, surveillance testing, environmental monitoring, refueling, inservice inspection, modification, etc. which are required to assure continued opera-tion in a safe and economical manner. Inherent also in the operations of the Nuclear Station are those activities associated with the verification of the completeness and adequacy of the work perfromed and the provision of independent safety review and operational advice. This Operational Quality Assurance Plan is applicable to (1) the operation of MI Unit 1; (2) the maintenance of those E I Unit 2 items which have not been affected by the accident; (3) the maintenance of those TMI Unit 2 items which upon satisfactory completion of decontamination and recovery are turned over to and accepted by Nuclear Operations; and, finally, (4) the operation of M I Unit 2. The overall responsibility for the establishment and implementa-tion of the Operational Quality Assurance Frogram and for assur-ing proper and complete interfacing of the organizations having responsibilities for performing the work rests with the M I Generation Group. This group is nanaged by the Senior VP Met-Ed/ VP GPUSC. The MI Generation Group consists of one Vice Presi-dent and five Directors, as illustrated on Figure 5.4-1. The responsibilities of these departments relative to operations will be detailed separately in the Operational Quality Assurance Plan. 5.4.2 Ouality Assurance Department The S I Generation Group Quality Assurance Department under.the direction of the Manager of Quality Assurance reports to the 5-72 Am. 9 161C

Director of Reliability Engineering. The Manager of Quality Assurance and the Director of Reliability Engineering are inde-pendent of design, procurement, manufacturing, construction, operations, or maintenance and report at a sufficiently high enough level to provide an independent assessment and evaluation of the effectiveness of the implementation of the QA Program. The Manager of Quality Assurance has the overall authority and organizational freedom to identify quality or management control problems and provide recommended solutions. This authority and responsibility includes the stoppage of work or the recommenda" tion that an operating nuclear unit be shut down, the Manager of Quality Assurance has direct reporting authority to the Senior VP GPUSC/VP Met-Ed and shall use this path when differences of opinion with the Generatf.on Group regarding quality arise. The re-organized Quality Assurance Department consists of five major sections as shown in Figure 5.4-2. Listed below is a descriptiono f the responsibilities of each section together with a discussion of the major differences from the pre-accident Metropolitan Edison - Operational Quality Assurance Department. Changes depicted result in part from the analysis following the IMI-2 accident: (1) Design and Procurement Assurance Section - This section with a quality engineering staff located both in the corporate head-quarters and at IMI constitute the main technical support sections establishing quality programs, and inspection requirements in support of design and procurement activities. The same gorup reviews quality related materials and product specifications and procurement requisitions to asaure that the committed to require-ments have been established. Additionally, this group is involved with evaluation of specific vendors (contractors) and their programmatic controls against established requirements. An element of the on site Design and Procurement Assurance Section has the responsibility for reporting quality trending and performing final verification and acceptance of installation / modification documentation packages before turnover to Records Storage. The major change, organizationally, from the previous Quality Assurance Organization is the formation of the on-site quality assurance / design element to input quality related information and perform reviews in support of design and procurement. (2) Manufacturing Assurance Section - The prime responsibilities of this section are to perform those necessary post award quality related activities required to assure that vendor's product is designed, manufactured, and tested in accordance with those specified quality requirements. Trend information supplied by this group weighs heavily in the maintenance of the Vendor's Classification List. 5-73 Am. 9 1613 137

The major change organizationally is that this is now a separate organization section. (3) Modifications / Operations Section - This section consists of two major sub groups, Quality Control and Operation Quality Assurance. Quality Control is responsible for receiving inspection and the inspection and/or surveillance activities related to corrective maintenance, modifications, installation or new construction. The group has specialists who are qualified to the appropriate levels of ANSI N45.2.6 and SNT-TC-1A. Additionally, the group has a welding engineering section which reviews contractors procedures and surveils control of special processes. Operational Quality Assurance is responsible for monitoring functional testing and performing surveillance of all operations activities. The latter includes monitoring and surveillance of plant operations, preventative maintenance, radiation protection and the processing, packaging and shipping of contaminated products, and radioactive wastes. The Oparational Quality Assurance group is also responsible for in-service inspection and monitoring performance and results of pump and valve testing to the applicable requirements of ASME Section XI. The major difference from the previous organization is in the formation of the separate operational QA group for surveilling compliance with the technical specification requirements. The other revision is the inclusion of in-service inspection require-ments under QA Department scope. (4) Methods, Operations ar.d Audit Sectien - This section is responsible for QA Department program development. It is, therefore, responsible for coordinating activities associated with department procedures and indoctrination and training. Additionally, the group conducts independent evaluation and assessment of the program's implementation thru Quality Assurance Audit Program. The latter includes an evaluation of effectiveness of the pro-grammatic aspects of the QA Program. This program satisfied the requirements of ANSI N45.2.12 and utilizes auditors cualified to ANSI N45.2.23. . Assisting in this assessment is a full-time site audit group reporting independently to the Manager of Quality Assurance and the Director-Engineering Reliability through the Section Head thus providing management assessment of the effectiveness of the pro-gram. Additionally, both ections are available to provide timely close out and verification of identified problems. 5-74 Am. 9 1613 138

(5) Haterials Technology Section - This is an off-site section which has the responsibility of supporting design in establish-ment and/or review of requirements. Additionally the group is available as a staff group to support Manufacturing, Construction and Operations in assessment and/or evaluation of identified materials technology problems. To help affect the implementation of this responsibility are the services of the off-site laboratory which now reports to the Director-Reliability Engineering. The specific services provided by the Materials Technology section include: Non-destructive Examination In-Service Inspection Materials Engineering Welding Engineering Whereas, other sections have full-time technical expertise in these areas, this centralized gorup will provide technical direction. The Materials Technology Group did not exist in the Met-Ed Organization although elements of materials technology function existed throughout the Het-Ed/GPUSC Organizations. 5.4.3 Program The QA Program is in the process of undergoing major revisions and as previously identified to the NRC on October 8,1979 (GQL-1233), this revision is scheduled for submittal on January 15, 1980. The revision was necessitated for the following reasons :

a. To describe the newly formed THI Generation Group Organiza-tion and identify the management controls and Quality Assurance Program for this Organization. Many of the or-ganizational changes depicted are reflections of careful analysis resulting from the TMI-2 accident and our desire to provide a more effective and responsible management control over operations having an affect on nuclear safety.
b. To provide a workable QA program plan that describes the functional manner in which activities affecting safety are managed. Included but not limited to those activities are start-up, shutdown, normal operation, emergency actions, surveillance, maintenance, repairs, radwaste processing, and modifications.

I613 l39 5-75 Am. 9

c. To upgrade the committment to Regulatory Guides and ANSI Standards previously provided under the current revision of the Operations QA Plan. This list is currently under evaluation and will be finalized in the near future and submitted as a revision to this section and the Operations QA Program.

The extent of QA coverage for each item, component, system is to be separately evcluated and graded with due considera-tion given for the following: a) the importance of a malfunction or failure of the item to safety b) the design and fabrication complexity or uniqueness of the item c) the need for special controls and surveillance over process and equipment d) the degree to which functional compliance can be demon-strated by inspection or test, and e) the quality history and degree of standarization of the item. The TMI Generation Group is committed to a comprehensive quality assurance program consisting of a three level approach to assure satisfactory and complete implementation of the program commen-surate with its requirements for safety and performance. The program's foremost considerations are the protection of the general public's health and safety. The three level approach is defined below: Level 1 - activities at this level include independent inspections, checks and tests. This level of activity may be performed by the Operations Department such as surveillance tests, calibration of instruments, radiation surveys, analy-ses of samples, etc., the Quality Control Section such as receipt inspection or inspections of modification or correc-tive maintenance activities, or by contractors as part of their scope of work. In all cases, the activity is performed by individuals knowledgeable of the activity being performed and qualified to perform the work. Checklists or data sheets are also used for documenting the results of activity and for providing a permanent plant record of the performance of the activity. In all cases where the first level activities involve inspec-tion for purposes of acceptance and/or verification of modi-fications to safety systems, the activity will be performed by personnel who are independent of those performing the work. Level II - The activities at this level are primarily those of surveillance or monitoring and are perforned as deemed 5-76 ha.9 i613 140

necessary by the Operational QA, Quality Centrol, or Manuf ac-turing !.ssurance departments. The level of surveillance / monitoring applied is consistent with the importance of the item to safety. For activities, whereby QC is performing first level inspection, no second level activity wis2 be required. At this level procedures and instructions are established and surveillance records will be completed and maintained. Such surveillance / monitoring normally includes observation of quality control tests and inspections, observation of signi-ficant operations, review of records, verifications of test reports, and direct over inspection on a spot check basis. The organizations performing this activity have these levels of authority, the lines of internal and external communica-tion for management direction and the properly trained personnel for implementation of these activities. Le.el III - The purpose of this level of activity is to assure through a comprehensive program of review and auditing that the first and second levels of the program are properly f unc tioning. The 'surpose of the program is also to establish that all other orgal'.sations including Operations, Mainte-nance, Engineering, Materials Management, etc. are properly satisfying all the requirements of the Operational QA Program. At this level procedures and instructions are established including the use of comprehensive checklists for documen-tation of the audit or third level activity. The program requirements of ANSI N45.2.12 art satisfied. Qualified audit personnel are included that satisfy the requirements of ANSI N45.2.23. Additional technical experts from areas with administrative reporting outside the function that is being audited will be included as the Audit Team Leader desas necessary. The organization performing this activity has sufficient authority and lines of internal and external communications for obtaining the necest,ary management direc-tion. In addition to the Quality Assurance Department's actiities associated with verification of the completeness and adequacy of the work performed there also tre several independent review groups whose responsibilirit.s are to provide independent safety review and operational advice. These groups each have the technical expertise in the areas of licensing, operations, and radiation protection. The groups include the following: General Office Review Board (GORB) - This group is an advisory group to the President of GPU and whose responsibilities are to foresee potentially significant nuclear and safety problems and to recommend to the President how they may be avoided. Generation Review Committee (GRC) - This group is assigned the responsibility to provide independent review of desig-nated areas of operations, nuclear engineering, chemistry and radiochemistry, metallurgy, instrumentation and control, 1613 141 5-77 Am. 9

radiological safety, mechanical and elsetrical engineering and quality assurance practices. The GRC reviews safety evaluations, significant operating abnormalities, viola-tions of codes, Tech Specs, etc. and deficiencies. A member of the QA Department sits on this committee. Plant Operations Review Committee (PORC) - This committee functions as an advisory group to the Unit Superintendent on all matters related to nuclear safety. A member of the QA Department - Operational QA section sits on this committee. Radwaste Review Committee (RRC) - This committee functions to provide independent review of designated activities in the areas of radioactive waste management, chemistry and radio-chemistry, metallurgy, instrumentation and control, radio-logical safety, mechanical and electrical engineering and quality assurance practices associated with radioactive waste materials control and management. The scope of the quality program while defined in detail in TMI procedures in Beneral includes materials, components, systems, and structures identified by Engineering as falling under the following areas of concern:

a. Nuclear safety related
b. Fire safety related
c. Rad / Waste as 'faquired by RG 1.143
d. Rad / Waste shipments as required by 10CFR70 Appendix E
e. Quality Control augmented For new designs, QA scope coverage is expanded to include items which are "important to safety" as listed in Appendix A of 10 CFR 50. Again a graded approach will be used to determine the extent of QA coverage that is meaningful to apply.

As always, classifications of systems, components, and struc-tures is an Engineering responsibility subject to audit. Es-tablishment of the programmatic and inspection requirements is also an Engineering responsibility with input and review by Quality Assurance Department - Design and Procurement Section. QA surveillance coverage for Operations will include all items within the secondary system which are Lnportant to safety as well as present scope items. The extent to which the program is applied is detailed in the Operatienal QA Program. The Operational QA Program includes provisions for controlling, and identifying the in process, final inspection, examination, 1613 142 5-78 Am. 9

test and operating status of all equipment, structures, compo-nents and systems throughout the plant. This control will include provisions which preclude the final use of structures, systems, and components which are non-conforming or removed from service for purposes of maintenance, modification, inspection or te s t . 5.4.4 Procedures A documented QA review and concurrence of select procedures af-facting Operations, surveillance, in service inspection, main-tenaace, modifications, engineering, etc. to assure that they have been prepared, reviewed and approved in accordance with established policy and program controls; they contain the neces-sary policy and program requirements including the inspection and verification requirements; and they contain clear descriptions relative to the extent of documenting results of completed actions. A " graded" approach will be used as to which procedures are reviewed, so as not to involve QA in reviuw of procedures not having a significant impact or affect on items which are important to safety. Separate or redundant QA reviews are not required or encouraged. Procedures, instructions, drawings, etc. will be controlled to the point of use to the extent ' deemed necessary with due con-sideration for their impact on their importance to safety. To as?ure adequate compliance to requirements, these activities f as others affecting quality will be programmatically surveilled and/or audited. 5.5 STATION ORGANIZATION UNDER ACCIDENT CONDITIONS The THI-l Emergency Plan (See Section 4.5.1.3) incorporates all the current requirements in the area of emergency planning. It is anticipated that it will be revised once comments from the NRC Task Force on Emergency Planning are received. The Emergency Plan is to be implemented 60 days prior to the restart of IHI-1. Upon final plan approval, specific personnel assignments will be made to fill the emergency organization positions. It should be noted that the Emergency Plan provides for manning the on site emergency organization within one hour and the off site emergency organization in a two to four hour time frame. 1613 143 5-79 Am. 9

1 Senior Vice Pres. Me t-Ed Vice-Pres. CPt!SC 1

   .                                                                      Vice-President ir t-fit 1

Manager !1 Plant Engineering Manager thlt I htrationg "*9'T ad Ogitti services I II"'"9 fa m h Escrgency Planning supervisor g PORC Chairman Coordinalnr Security 3"pv. operator TraininR Radiological irnntroit Q) M Lead Nuclear g Superintetident racilities Radiological sep,. Technt-Engineer Maintenance office Managesient ,g,, gr, ,g"E Cnntrols Persnnnel Foreman Q Lead Electrica Supw. Career kadiological

%       Engineer                Supervisir                Supervisor                                                            DeveleP. Trng           Controls Supervisor of                                                       lechnician

@ P y t n , p f,[,], p rations E ' Lead 18C g Supervisor Engineer Radiological Mechanical lead [ngineering Tomman C*I 3, , , , , g , ,, ,

  • a.t Wa a t e p Lead E

Mechanical Engineer tead Shif1 5taff Electrical - Electrical ioreman rnn=un Supervisor g shift

         '       '      d 3d, sors 18C Forema n              lead 110                          shift ro rman                           inrem.in           pil Supervinor Chentatry          s Control Rawna y                                                               Operate >r s                                                                                  y Te r fs Analynt (Fire Prntertie    n) u                                                                   - -] -                                           LEGEND Auxillary
                            "                                                               ip rator Q   (dwa g gen, 4                                                                                                                                M   licente y                                  F10tre 5 2-1
                              .                                                                                                    11

handle the waste generated from a single operating unit and TdI-1 operated successfully in the single unit mode in excess of three years during TMI-2 construction. The TMI-2 design utilized the conservation of the TMI-1 system to provide radwaste treatment capabilities for liquid radwaste generated from its operation. Therefore, all TMI-2 liquid radwaste had to be transferred to TMI-1 for treatment. Therefore isolation of the units will increase the TMI-l liquid radwaste capability relative to that available during the pre-accident period. The Miscellaneous Waste Evaporation is the primary process equipment used to treat liquid raowaste. The evaporator has been used successfully in the past for a single unit waste treatment requirements. Because of interferences in TMI-1 caused by the storage of TMI-2 waste waters, the evapora-tion is not currently in use. At the time of startup of TMI-l (or within the month previous to starting) the evaporation will be shown to be operational or replacement equipment shall be available to supplement evaporation operation. Although, TMI-l radwaste processing capabilities are currently limited by the presence of TMI-2 liquid radwaste stored in TMI-l process vessels, this limitation will be completely removed by transferring and flushing all TMI-2 waste stored in TMI-l to TMI-2 facilities prior to startup. TMI-2 miscellaneous liquid radwaste will be processed in systems installed (or to be installed) in accordance with the recovery effort. The systems include Epicor 2, the submerged demineralizer system and an evaporator / solidification system. '~ A complete description of the TMI-l radwaste treatment system capability is provided in section 7.3.1.1.1 of this report. 7.2.4 Solid Waste Disposal Prior to the accident, TMI-2 radwaste system was completely depencent on TMI-1 facilities for solid waste processing and disposal of evaporation concentrates, spent resin and compactible trash. Isolation of the two units will enhance the ability of TMI to process solid radwaste. TMI-2 had installed separate trash compact-ing equipment and will obtain the equipment to solidify liquia and wet solid waste as part of the recovery program. THI-1 capabilities are not required for the TMI-2 recovery program. TMI-1 currently has an opeating trash compactor used exclusively for THI-l trash. Solicification facilities will be available through the use of a contractor for the short term and subsequently through the use of a

            - ~~                                                                    ~
        ~

pemanentlpTs'tTIlefsf's~tiem discussed more thoroughly in Supplement 1, Part 2, response to Question 53 and Section 7 3.1.3._ _ _ __ _ _ . _. __ _[~ 7.2.5 Sanitary Facility Drains By de, sign, sewage and sanitary drains from TMI-2 would join those from TMI-1 at the sewage pumping station and then be treated in a common sewage treatment plant. Operationally, the sewage from the individual unit currently remain separate 1613 145 7-4 Am._9 _

7.3.2 Plant Shielding 7.3.2.1 General: The purpose of this section is to identify the necessary action to be taken for providing additional shielding, procedures or plant modifications in vital areas and to equipment in which personnel occupancy may be unduly degraded by the large raciation fields in operating these systems in a post-accident environment. Systems, components, and areas considered subject to post-accident large radiation fields include: decay heat removal, reactor building spray recirculation, make-up and let-down, waste gas, Rad Waste Control Center, and Liquid and Gas Waste Panel. 7.3.2.2 Design Review: In order to determine which areas and systems require additional shield-in or plant modifications, a review of existing design will be completed which will identify and recommend the cor-rective actions needed in vital areas throughout the Unit. The review will encompass the accessibility and operability of the above stated systems and area in a post-accident environment. Bases to be used in comparing present design to post-acciaent environment. Bases to be used in comparing present design to post-accident radiation levels will be the fission product release as described in Regulatory Guices 1.3 and 1.4. The design review will be completed by January 1,1980. (Also see Section 2.1.2.3). 7.3.2.3 Near Term Modifications: Those near term modifications, identified by the design review, will be completed prior to startup of Unit 1. 7.3.2.4 Long Term Modifications: Over the longer term modifications not completed before startup of Unit I will be completed by January 1, 1981. 7.3.3 Auxiliary Building Ventilation System 7.3.3.1 General The Unit-1 Auxiliary Building Ventilation System is combinea with the Fuel Handling Building Ventilation System prior to filtration 1613 146 7-12 Am. ' 9 -~

d. Af ter each complete or partial replacement of charcoal adsorber bank by verifying that the charcoal adsorbers remove 199% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975.

7.3.3.3 Implementation Schedule The testing schedule as previously described will be in place prior to the restart of Unit-1. 7.3.4 Nuclear Sampling 7.3.5 Nuclear Sampling Capabilities 7.3.5.1 Post-Accident Sampling 7.3.5.1.1 General Purpose of this section is to identify the necessary action to be taken to facilitate the capability to perform timely sampling of Reactor Coolant and Containment Atmosphere in a post-accident environment. Action to provide the capability to perform timely (within 1 hour) sampling of reactor coolant and containment atmosphere include: a design review of existing systems and component location, near term and long term modifications. 7.3.5.1.2 Design Review: To determine what modifications are required, a design review of the existing systems and components will be completed. This design review will identify and recommend the corrective actions necessary to provide the capability to sample in a post-accident environment. The design review will encompass the accessability and operability of the reactor coolant sampling and containment atmosphere sampling sampling systems in a post-accident environment. The design bases to be used for this review will be the fission product release in an accident as assumed in Regulatory Guides 1.3 and 1.4. The design review will be completen by January 1,1980. (See Sect. 2.1.2.4). 7.3.5.1.3 Near Term Modifications: Those near term modifications, identified by the design review, will be completed prior to startup of Unit I. 7.3.5.1.4 Long Term Modifications: Over the longer term modifications not completed before startup of Unit I will be completed by January 1,1981. 1613 147 7-14

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                       'J L. ,

e APPENDIX 7A 1613 148 Am. 9

Revision 0 12/12/79 THREE MILE ISLAND NUCLEAR STATIuri UNIT I RADIATION PROTECTION PLAN

           .                                                                                        ~

i /_ n/a hn W. E. Potts ' Manager - Radiological Controls

                                                              /                       s
                                                                       ~

J. G. Herbein Q /2) /79 V ce President, Met-Ed Changes to this document require approval by these positions. 1613 149 7A-1 Am. 9

Revision 0 12/12/79 TABLE OF CONTENTS Page No. Article 1 Foundation of the TMI-I Radiological Control 2.0 Program Article 2 Responsibilities of Workers 4.0

     .           Article 3   Audits and Reports on the TMI-I Radiological         6.0 Control Program Article 4   Radiological Control Training                        9.0 Article 5   Control of External Exposure                        11.0 Article 6   Control of Internal Exposure                        13.0 Article 7   Control of Radioactive Contamination                15.0 Article 8   Centrol of Radioactive Materials                    16.0 Article 9   Organization for Radiological Controls              17.0 Figure 1    THI-I Radiological Controls Organization            18.0 1613 150 7A-2                        Am. 9                   '

Revision 0 12/12/70 Article 1 - Foundation for the TMI-I Radiological Controls Program This document, the Three Mile Island Unit I Radiation Protection Plan, sets forth the philosophies and basic policies of Metropolitan Edison Company and General Public Utilities Corporation concerning their TMI-I Radiological Controls Program. These philosophies and policies are based on and stem from the regulations of the Nuclear Regulatory Commission (NRC) as contained in

 . Title 10 of the Code of Federal Regulations, Parts 19, 20, 50, and 71, and appropriate Regulatory Guides. The TMI-I Radiation Protection Plan is based on these references, therefore they are not repeated throughout the remainder of this document.

Specific details as to how the TMI-I Radiation Protection Plan is implemented shall be promulgated in the TMI-I Radiological Controls Procedures Manual (RCPM), further references to the TMI-I RCPM are not repeated throughout this document. The TMI-I RCPM wil.1 consist of revisions of procedures which existed in the previous HPP 1600 and 1700 series with additional procedures deemed necessary. 'The procedures have direct applicability only to TMI Unit I. This TMI-I Radiological Controls Plan is the first part of the TMI-I RCPM. Requirements governing release of radioactive liquids and gases to the environ- _ ment and the disposal of solid radioactive waste are addressed in Unit I Technical Specifications. Verbatim compliance with the TMI-I RCPM is mandatory. In the event a procedure cannot be followed exactly, work under that procedure shall be stopped and shall not comence again until the procedure.has been corrected. This TMI-I Radiation Protection Plan and the new TMI-I RCPM are being written primarily to increase the effectiveness of The Radiological Control Program at TMI Unit I. The TMI-I Radiological Controls Program is to be fully integrated into each and every pbsse of the activities at TMI Unit I. The TMI-I Radiological Controls Program when carried out as specified will assure _ 7A-3 Am. 9 1613 151

Revision 0 12/12/79 that the activities of Unit I will be completed with personnel who work at the site incurring radiation exposure as low as can reasonably be achieved. In order to meet this objective, the program must be carried out by each person involved in the TMI-I activities. There is no element, group, or person involved in the THI-I activity who does not have some degree of responsibility for the Radiological Controls Program. Failure of any person to recognize this responsibility or to comply with issued procedures will not be tolerated. A radiologically safe activity will be achieved if each individual carries out his or her responsibility. The performance of each manager and supervisor must demonstrate support for the commitment by top management of General Public Utilities Corporation and Metropolitan Edison Company to a strong, effective Radiological Controls Program. 1613 152 7A-4 Am. 9 -

Revision 0 12/12/79 Article 2 - Responsibilities of Workers Although personnel specially trained in radiological controls normally oversee radioactive work, each individual involved in this work must constantly remain aware of the potential radiological problems. Each individual's actions directly affect his exposure, contamination, and overall radiological problems associated with the work. The following rules shall be

   , followed by individuals to minimize radiological problems:
1. Obey promptly "stop-work" and " evacuate" orders of radiological control personnel.
2. Obey posted, oral and written radiological control instructions, including instructions on Radiation Work Permits.
3. Wear TLD and self reading dosimeter where required by signs or .
               . by radiological control personnel.
4. Keep track of personal radiation exposure status and avoid exceeding exposure limits.
5. Remain in as low a radiation area as practicable to accomplish work.
6. Do not loiter in radiation areas. _
7. Do not smoke, eat, or chew in contaminated areas.
8. Wear anticontamination clothing and respiratory protection properly and wherever required by signs or radiological control personnel.
9. Remove anticontamination clothing and respiratory protection properly to minimize spread of contamination.
10. Frisk or be frisked for contamination when leaving a contaminated area or a radiological control point.
11. For a known or possible radioactive spill, minimize its spread an.1 notify radiological control personnel promptly.
12. Do not unnecessarily touch a contaminated surface or allow clothing, tools, or other equipment to do so. 1613 153 -
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                   ..        .m_w-    __- - .       - - - - .-    % ._       -.

Revision 0 12/12/79

13. Place contaminated tools, equipment and solid waste on disposable surfaces (for example, sheet plastic) when not in use and inside plastic bags when work is finished.
14. Limit the amount of material that has to be decontaminated or disposed of as radioactive waste.
15. Report the presence of open wounds to radiological control and medical personnel prior to work in areas where radioactive contamina-tion exists and immediately if a wound occurs while in such an area.
16. Assure a mentally alert and physically sound condition for performing assigned work.
17. En ure that your activities do not create radiological problems for others and be alert for the possibilities that the activities of others may change the radiological conditions to which you are exposed.

1613 154

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   .          -p..   ...wwe4    - =          ---w- ww-m             6-aw--   -= -

Revision 0 12/12/79 Article 3 - Audits, Reviews and Reports on the TMI-1 Radiological Controls Program-As indicated in Article 2, each individual is responsible for maintaining his or her radiation exposure as low as reasonably achievable while completing the scope of work they are required to perform. Each will be required to comply with the applicable procedures of the TMI-l RCPM and the specific radiological controls prescribed for work in which they are engaged. In order to ensure that these requirements are being met and to assist all site personnel in understanding and complying with these requirements, the following audit and review procedures shall be used:

1. Radiological control technicians shall monitor and aid the performance of each individual insofar as radiological work practices are concerned.
2. The radiological engineering staff shall review on a regular basis the performance of the radiological control technicians. This review includes shift coverage on those jobs which are considered likely to have a high potential for radiological difficulties.
3. Radiological audits shall be conducted throughout the Radiological Controls Program on a continuous basis. This. audit function shall report directly to the highest level of management in the TMI-l organization and shall be outside the Radiological Controls Department.

A written report of the findings of this audit shall be prepared and f ssued at least monthly.

4. Periodic technical reviews shall be conducted of the TMI-1 Radiological Conu ols Program by technic.'lly qualified persons from outside the Radiological Controls Department. These reviews shall cover everything in the TMI-l Radiation Protection Plan and all procedures in the TMI-l RCPM on at least an annual basis.
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7A-7_. Am. 9 1613 155

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5. The Plant Operations Review Committee shall review and coment on the TMI-1 Radiation Protectior. Plan and any changes thereto. They also have the responsibility to review those procedures requested by the Manager Radiolcgical Controls.
6. Periodically, the services of an outside consultant will be retained to provide evaluation and guidance on ways to improve the TMI-l Radiological Controls Program. ,,
7. In addition to these reviews and audits, a system shall be employed to identify radiological control deficiencies. A radiological control deficiency is defined as either a violation of an established procedure or a practice which could and should be improved. Such deficiencies are recorded in a Radiological Deficiency Report. This system shall be specified in the TMI-l RCPM embodying the following concepts. A Radiological Deficiency Report may be initiated by any individual who observes a deviation from good radiological practices.

These reports shall be evaluated by Radiological Engineering for desirable or necessary corrective action. The purpose of this system is to identify all deficiencies, regardless of how small or. inconsequential, correction of which will result in an improved Radiological Controls Program. Radiological Engineering shall prepare a monthly report sumarizing the Radiological Deficiency Report findings and corrective action taken.

8. The Nuclear Regulatory Comission (NRC) also inspects and reviews the TMI-1 Radiological Controls Program. The THI-l Radiation Protection Plan and any changes thereto shall be submitted to the NRC for approval.

1613 156

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9. In the event all the preceding measures fail to prevent a radiological incident, an investigation shall be conducted to determine the causes of the incident and to determine the corrective actions and improvements needed.

1613 157 7A-9 Am. 9

    - - - - - . . * -  e.        _- -       _ - . . .               . _ _ _ ,       _ _ _ .   , , . . . . . .

Revision 0 12/12/79 Article 4 - Radiological Control Training

1. Periodic radiological control training shall be given to ensure each person understands the radiological conditions to which he is exposed, understands his responsibility to minimize his own exposure to radiation, and understands his own responsibilities for complying with radiological control procedures. Personnel occupationally exposed to radiation shall receive instruction on the effects of radiation and the risks associated with radiation exposure.
2. General radiological indoctrination shall be given to those not directly involved with radiation so.that they understand not to enter areas requiring TLDs and not to cross radiation barriers.

The indoctrination shall include explanation of the radiological environment in which they work.

3. Radiological control training shall be given to personnel who require TLDs. These personnel shall be required to pass a written examination, and they shall requalify by written examination at least annually.
4. In addition to the training and written examinations of paragraph 3, those who require access to areas controlled by Radiation Work Pennits shall receive more extensive tr&ining and shall be required to pass a radiological examination on their practical abilities, including use of _ dosimetry, frisking, anticontamination clothing, respirators, and response to unusual situations. Retraining, and both written and practical examinations shall be conducted at least annually. In addition spot checks shall be made that they retain the required w . - - -

7A-10 Am. 9 _ - __ _ _ 161.3_l58 __

Revision 0 12/12/79 knowledge during the period between examinations. Special briefings and extra training including use of mockups where applicable, shall be conducted for work involving higher than usual exposures to radiation and radioactivity.

5. Radiological control technicians and their foremen shall receive theoretical and practical training and training for unusual
       ,      situations. They shall pass both written and oral examinations, in which the passing grade for foremen shall be higher than the passing grade for technicians. Periodic practical drills and oral drills shall be required for each technician and foreman. Annual requalifica-tion shall be required including both written and oral examinations.

Radiological control technician assistants shall perform specific functions under direction of a qualified technician or foreman and only after being qualified for the specific function. 1613 159 EI-11 Am. 9 ,

Revision 0 12/12/79 Article 5 - Control of External Exposure Control of radiation exposure is based on the assumption that any exposure no matter how small involves some risk; however, exposure within the accepted limits represents a risk small compared with normal hazards of life. Therefore the policy of Metropoliten Edison Company and General Public Utilities Corporation is to maintain exposures to

 , individuals and total manrems as low as reasonably achievable (ALARA).

Line management from all departments as well as each individual worker shall take an active role in radiation exposure reduction. To aid in exposure reduction, administrative radiation exposure control levels shall be established. Radiation exposure goals shall be established for each outage and for each year. Work involving radiation exposure shall be preplanned. Major exposure jobs shall require that radiological controls be incorpcrated into the work procedure and that pre-job briefing and rehearsals be conducted prior to commencing work. Work involving significant exposure to radiation shall be controlled by a Radiation Work Permit. Restricted areas used to control personnel access to radiation and . radioactive materials shall be defined, access controlled, and posted in accordance with 10 CFR 20.203 with the following modifications:

1. Each High Radiation Area shall be barricaded and conspicuously posted as a High Radiation Area, and personnel desiring entrance shall obtain a Radiation Work Permit (RWP). Any individual entering a High Radiation Area shall (a) use a dose rate monitoring device or (b) use a radiation dose rate integrating device which alarms at a preset dose level, or (c) assure that a radiological control technician provides periodic radiation surveillance with a dose rate monitoring instrument.

7A-12 __ Am. 9

  • 1613 160

Revision 0 12/12/79

2. Any area accessible to personnel where a major portion of the body could receive in any one hour a dose in excess of one thousand mrem, shall be locked to prevent unauthorized entry.

The keys to these locked barricades shall be maintained under the administrative control of the Radiological Controls Foreman on duty in accordance with the RCPM.

         -        Radiological Controls personnel shall be exempt from the RWP issuance   ,

requirements during the performance of their assigned radiation protection duties providing they are following radiological control procedures for entry into High Radiation Areas. To evaluate radiological conditions, radiation surveys shall be conducted for air activity, removable surface contamination and external radiation at regular intervals. Unsusual conditions detected in the per-fonnance of either a routine or special survey shall imediately be brought to the attention of Radiological Controls Management. The instruments required to conduct the surveys shall be maintained and periodically calibrated to assure a consistent, reliable and predictable response to radiation levels. Records of surveys shall be maintained on file. 1613 161 7^=13 E Am. 9

Revision 0 12/12/79 Article 6 - Control of Internal Exposure The policy of Metropolitan Edison Company and General Public Utilities Corporation is not to have any significant internal exposure to personnel from radioactivity associated with Three Mile Island Unit 1. For personnel exposed to radioactivity during their work, this means that no one should receive from internal radioactivity more than one tenth of their permitted annual radiation exposure. Controls ir. other parts of this TMI-l Radiation Protection Plan to minimize internal radioactivity, such as control of surface contamination and control of wounds, are not repeated in this article. The following , controls are to minimize internal exposure from airborne radioactivity:

1. Engineering controls and controls on personnel access shall be applied to the maximum extent practicable so that radioactive work does not increase the amounts of airborne radioactivity inhaled.

~ When no other controls are practicable, respirators shall be used. Those who may need to use respirators shall be medically qualified, trained, tested for respirator efficiency, and requalified in this respirator program at least annually.

2. Airborne radioactivity shall be measured regularly in areas where personnel may be exposed. Continuous monitoring shall be performed to supplement periodic measurements during. work which has the potential to cause a worker to receive measurable internal radioactivity.

Internal radioactivity shall be measured at least annually in each person who works in an area requiring a Radiation Work Permit; this includes each person who wears respiratory protection. Internal radioactivity shall be measured promptly in each person who receives radioactive contamination on his

e. ee.-.O- e e.mm 7A-14 Am. 9 d 613 1.62

Revision 0 12/12/79 skin, and in each person who is suspected of inhaling sufficient radioactivity to cause measurable internal radioactivity. Each measurement of internal radioactivity above a level near background shall be reviewed to detemine the cause and to assist in minimizing internal exposures. 1613 163

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7A-15 Am. 9

Revision 0 12/12/79 Article 7 - Control of Radioactive Contamination Radioactive surface contamination shall be controlled in order to minimize possible inhalation or ingestion of radioactivity and to minimize buildup of radioactivity in the environment. Measures to contain radioactivity and to minimize the number and extent of areas contaminated shall be taken in order to minimize personnel radiation exposure, to simplify subsequent decontamination, and to minimize the need te rely on ant 1 contamination , clothing. Emphasis in planning, training and working shall be placed on minimizing the numbers of occurrences and amounts of radioactivity involved in occurrences in which radioactive surface contamination exceeds the limits of the TMI-l RCPM on a person's skin or in areas not controlled for radioactive surface contamination. Each such occurrence shall be reviewed in detail to determine how to correct deficiencies and improve control of radioactivity. 1613 164 7A-16 Am. 9

Revision 0 12/12/79 Article 8 - Control of Radioactive Materials A radioactive material control system shall be established to ensure radioactive material is not lost or misplaced in a location where personnel could unknowingly be exposed and to prevent tM uncontrolled spread of radio-activity to areas where the public might be a'fected. This system shall include the following requirements:

    .         1. The number of areas in which radioactive materials are stored       .

shall be minimized.

2. Any new radioactive material storage area shall be approved before use by the Manager Radiological Controls.
3. The numbers of radioactive items and the amount of radioactivity in storage shall be minimized.
4. Radioactive items shall be identified as radioactive before removing them from a restricted area.
5. Radioactive materials removed from the Protected Security Area or removed from a restricted area outside the Protected Security Area shall be controlled in accordance with an accountability procedure which ensures the materials are not lost or improperly handled during transfer. This accountability procedure shall require periodic inventory of radioactive materials which remain outside such areas.
6. Each incoming or outgoing shipment of radioactive material shall be handled in strict compliance with detailed written procedures.

Each case in which radioactive material is lost or unaccounted for shall be reviewed in detail to determine the potential radiation exposure personnel might unknowingly receive, to correct deficiencies, and to improve control of radioactive materials. T-  : 1613 165 7A-17 Am. 9 e

                                                         ..,e

Revision 0 12/12/79 Article 9 - Organization for Radiological Controls A radiological control program cannot be strong and effective if left solely to the Radiological Controls Department. Each worker and supervisor has responsibility for radiological control; consequently, the organization for the entire Three Mile Island Unit 1 represents the organization for radiological control. , However the Manager Radiological Controls is responsible for ensuring , that a high quality radiological controls program is established and maintained. To assist him, a Radiological Controls Department is organized as shown in Figure 1. At times when demands upon the Radiological Control Department are sufficiently heavy to require a temporary increase in staff qualified contractor personnel will be used. These personnel will be fully integrated into the department under the direction of the Manager - Radiological Controls. Qualifications for the key radiological managers in NRC Regulatory Guide 1.8, Rev.1-R, (1975) will be met as far as practicable. Where the combination of strcng manager and experience in radiological controls cannot practicably be obtained in the same person, the combination of the qualifications of the Manager - Radiological Controls and his supervisors will meet Regulatory Guide 1.8,Rev1-R(1975). One portion of the TMI-1 radiological controls program is the ALARA program for personnel radiation exposures to be as low as reasonably achievable. To accomplish this each individual who provides work instructions, procedures and directions has to have constant awareness of radiological conditions as part of his assignment. Thus, most efforts to reduce radiation exposure are perfonned by individuals other than those in the Radiological Controls Department. The overall coordination of the TMI-1 ALARA program, however, is assigned to Radiological Engineering in the Radiological Controls Department. 7A-18 ~ ~ Am. 9

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RESPONSE TO SUPPLEMENT 1, PART 1,

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SUPPLEMENT 1, PART 1 QUESTION:

62. Bulletin 05C Item 1 Your reopense did not include Section B of this item.

State your intention to provide two licensed operators in the control room at all times during operation.

RESPONSE

Met-Ed will require two licensed reactor operators in the Control Room at all times when the reactor is critical. 1613 170 Am. 9

SUPPLEMENT 1, PART 1 QUESTION:

63. Your submittal states that you will provide an automated switchover to recirculation on the emergency core cooling system. Provide a detailed description and associated drawings related to this modification.

RESPONSE

Automatic switchover to recirculation for the emergency core cooling system is a long term modification that may not be completed prior to restart. The criteria, conceptual design and a schedule for the detailed design work will be provided by January 1,1980 as part of Section 2.1.3. 1613 171 Am. 9

SUPPLEMENT 1, PART 1 QUESTION:

64. Your submittal states that you intend to modify the reactor building spray system. Provide the detailed description and associated drawings related to this modification.

RESPONSE

The reactor building spray system changes are long term modifications that may not be completed prior to restart. The criteria, conceptual design and a schedule for the detailed design work will be provided by February 1, 1980. In addition, this modification will require NRC approval prior to implementation in accordance with 10 CFR 50.59. A Technical Specification Change Request will be provided by February 1,1980 to facilitate NRC review. 1613 172 Am. 9

SUPPLEMENT 1, PART I QUESTION:

67. The licensee has not described the proposed radiation protection program plan. It will require a detailed description, analogous to recent FSAR submittals, taking into account lessons learned and other additional considerations reflecting problem areas raised by the accident. Areas to be covered are characterized in Appendix C.

RESPONSE

See Appendix 7A. 1613 173 Am. 9

SUPPLEMENT 1, PART 2 QUESTION

4. Your response to Question 4 is not complete. Provide "as-built" drawings and qualification documentation for the existing steam generator level instrumentation.

RESPONSE

The "as-built" drawings for the existing steam generator level instrumentation will be submitted under separate cover. The original purchase orders for the steam generator water level instruments did not specify qualification requirements. These instruments use Bailey BY-3B40X-A transmitters which have been qualified in other applications. The applicable documents are: (1) Franklin Report F-C2574-01; (2) BCCo Report 2482; (3) BSW Report 58-0081-00; and (4) BAW-10003A, Rev. 4, Section 5. 1613 174 Am. 9

SUPPLEMENT 1, PART 2 QUESTION

25. Your submittal on the Lessons Learned requirements on Shift Supervisor Responsibilities (NUREG-0578), Section 2.2.1.a, as clarified in our letter of October 30, 1979, is not complete since only Position 2 is addressed. Provide the details of the management directive (Position 1),

training program (Position 3), and review policy (Position 4) used to implement this item.

RESPONSE

Position 1 Management Directive The management directive addressing the command responsibilities of Shift Supervisors in THI-1 is included as Enclosure 1. This directive will be reissued annually. Position 3 Training Program A five day decision analysis training program for Shift Supervisors which emphasized and reinforces their responsibility for safe operation and the Shift Supervisors management function for assuring operational safety will be conducted. The training program objectives are: A. To emphasize the Command role of Shift Supervisors in applying the Command responsibilities to operating problems. B. To assure an understanding of how to apply basic decision analysis techniques to operating problems. Additionally, the operator accelerated requalification program includes spacific training which will also emphasize and reinforce the Shift Super-visor's responsibility for safe operation and the management function to assure safety. Examples of this are: A. Use of Procedures The shift supervisors' role in the use of procedures is defined and discussed. B. Procedures Review The shift supervisors, as well as the operators, are instructed in the content of emergency procedures. C. Technical Specifications The responsibility of the shift supervisor and shift personnel with respect to Technical Specifications is stressed. D. Safety Analysis Work Shop 1613 175 The team response to casualty situations is stressed. Am. 9

SUPPLEMENT 1, PART 2 QUESTION

35. Provide the basis for selecting 20% and 10% reactor power as the bypass setpoints for main turbine and main feedwater pump anticipatory reactor trip, respectively.

RESPONSE

A bypass of the turbine trip signal is automatically provided below 20% reactor power in order to provide for normal starting and shut-down of the main turbine. There is adequate steam bypass capacity to accommodate a turbine trip at 20% power without challenging the over-pressure trip function. A bypass of the Fh' Pump trip signal has been provided in the design with a tentative set point at 10% reactor power. Further investigation is being made to determine whether this latter bypass is required and what the set point should be. If it is determined that the bypass is not required it will be removed or the set point will be set to zero power. Also see response to Question 15 of Supplement 1, Part 2. b l[h Am. 9

PAGE 3 OF RESPONSE TO QUESTION 52, SUPPLEMENT 1, PART 2 In addition to the modifications described above, a ventilation system to mitigate the consequences of a postulated fuel handling accident in the FHB will be installed. This new system will meet the requirements of Regulatory Guide 1.52, Revision 2. This system will be installed prior to the first refueling following restart. 1613 177 Am. 9

SUPPLEMENT 1, PART 2 QUESTION

63. Expand Figure S.2-1 to show details down to the technician level.

Include qualification requirements for all functional blocks except those in the Manager Support Services and Logistics.

RESPONSE

See revised Figure S.2-1 and the response to Question 64 of Supplement 1, Part 2. 1613 178 Am. 9

SUPPLEMENT 1. PART 2, QUESTION 2 RESPONSE TO PARTS C Ah9 D Auxiliary Feedwater Overfill The function of the auxiliary feedwater (AFW) system is to provide a source of water to the steam generators to assure decay heat removal whenever main feedwater is unavailable. Once initiated for decay heat removal, the AFW system is automatically controlled to establish and maintain a preset water level in the steam generators. The control system for auxiliary feedwater is thus designed to limit the amount of feedwater added to the generators. The control power and motive power supplies and the control valve for supplies have power provided by the normal plant systems with an authomatic backup of the emergency diesel. This design ensures decay heat removal and controllability for plant conditions with or without offsite power. Failures which will permit excessive feedwater addition are limited to the control valves, the signal inputs, and control power and air support systems. A failure of one of these components is required to allow excessive feedwater addition. Excessive feedwater can result in overfill of the generator and allow liquid to enter the steam lines if manual termination does not occur. Operating experience has shown that demands on the AFW system occur with moderate frequency. The AFW system and associated controls and instrumentation are relatively simple designs, thus the probability of failures leading to excessive feedwater occurring during infrequent demands is quite low. In the unlikely event that AFW begins to overfill one or both OTSG's, several indications are available to the operator and adequate time exists to allow manual termination of AFW to the affected steam generator (s). In order to assess the time available for operator action to prevent AFW overfill (i.e. , prevent the introducticn of water into the steam lines), several manual calculations were performed based on the TMI-1 design. Overfill is defined as that amount of feedwater that would fill the generator and permit liquid spillage into the steam lines. The results show that from 10 to 17 minutes

  • are available before the level in the OTSG reaches the top of the steam generator. The most limiting calculation conservatively assumed that all decay heat went into heating the cold AFW to saturation conditions thus producing maximum swell in the OTSG inventory. This assumption is conservative because decay heat will boil a portion of the feedwater. Even with the con-servative assumptions described in Attachment 1, the resultant minimum time is considered adequate for manual termination of AFW flow.

The operator can detect excessive feedwater addition by observing any deviation from the level control setpoint, and the response of the primary system temperature. Other indications such as high OTSG 1evel alarms and low OTSG pressure alarms are available to alert the operator to the abnormal conditions. TMI-I plans to incorporate explicit procedures and training excercises to sensitize the operator to excessive feedwater addition and to its mitigation. In summary: (1) (2) The AFW system operates infrequently The AFW system is designed to control fecdwater bf3 l[9

  • These fill times have been confirmed using the B5W plant simulator.

Am. 9

(3) A failure of the controls must occur te permit excessive feedwater addition (4) The plant has indicators which will note that abnormal feedwater addition exists (5) The operators will be trained to recognize an overfill situation and take corrective action The consequences of AFW overfill have been evaluated to determine adverse effects on the reactor coolant system and plant safety. The results of this evaluation are summarized as follows: (1) Uncontrolled AFW addition can lead to overcooling of the primary system. The effects of overcooling can be: (a) Thermal stresses in excess of design stresses for primary system components (b) Possible loss of pressurizer level indication (c) Possible draining of the pressurizer (2) AFW overfill can eventually lead to water spillage into the main steam lines, and may cause stresses in excess of the design stress. Thermal stresses of NSSS components due to overcooling have been evaluated and are included as a part of the Plant Design Basis. Excessive feedwater addition is a less severe transient than other overcooling events and stress analyses have been performed for those more severe transients (rapid primary system depressurization, steam line breaks, etc.). Based on these stress evaluations, AFW overfill will result in acceptable stresses on the NSSS components. Should the magnitude and rapidity of the primary system cooldown exceed the capability of the makeup system and result in draining the pressurizer, high pressure injection would be initiated by low RCS pressure. This sequence does not pose a reactor safety problem because refill by HPI will restore the plant to a stable condition. Throughout all portions of the transient, the core will remain covered and cooled and no core thermal transient will result. Again, other overcooling transients have been examined that are more rapid and severe and core cooling is maintained. A stress analysis has been performed on the consequences of flooding the TMI Unit 1 Main Steam line. The results of deadweight internal pressure and thermal expansion analysis show that the main steam piping can withstand these affects. An AFW overfill event occurred at the Rancho Seco plant on March 20, 1978 (Figure 1). Auxiliary feedwater was initiated by ESFAS to both generators (at the time of the transient the SMUD design did not provide automatic 1613 180 Am. 9

control of AFW when initiated by ESFAS). The resulting coolding was 310' in about an hour; this overcooling was due to loss of steam pressure because of open turbine bypass valves as well as injection of uncontrolled AFW. Some empirical evidence can be obtained from this event that indicate the results of overfill.

1. The fill times for the generators were about 15 minutes for A and 30 minutes for B (pump flow was greater than design because of the depressurized steam generator).

AFW pump design capacity for TMI-1 and Rancho Seco are roughly comparable.

2. The severe overcooling effects on the NSSS components were evaluated and the results were acceptable.
3. Pressurizer draining did not occur because HPI injection controlled inventory.
4. Post event inspection showed no steam line support deformation due to water in the steam lines. The quantity of water in the steam lines is not known.
5. Operator actions during the early portions of the event were directed toward management of the RCS inventory for core cooling. At a later time the operator controlled AFW.

Based on the flow instrumentation and level instrumentation available co the operator, the back-up controls and instrument air supplies that have been provided for the auxiliary feedwater control valves and key components, and the reasons discussed below, reliance on operator action to prevent steam generator overfill conditions is considered warranted. For the long term, the emergency feedwater system will be upgraded to meet safety grade criteria and further reduce the probability of steam generator overfill. The conceptual design for our long-term design changes and our schedule for accomplishing these changes will be provided by January 4, 1980. Due to the extent of the changes required, it is not expected that these changes can be completed prior to start-up. The TNI Unit 1 Integrated Control System (ICS) is hsigned to control auxiliary feedwater flow to preset steam generator levels. If Reactor Coolant pumps are available the ICS will control steam generator level to 30 inches on the start-up. If RC pumps are not available, the ICS will then control steam generator level to 50% of the operating range level. If automatic level control is not achieved or if overcooling conditions start to occur, operator will take manual control of the emergency feedwater control valves, EF-V30 ASB, using either the ICS manual controls or the back-up manual control station provided in the control room. 1613 181 Am. 9

In the extremely unlikly event that control of EF-V30 A/B cannot be obtained from the control room, the operator has several other means to control auxiliary feedwater flow and steam generator level from the control room. These are as follows:

1) The motor driven emergency feedwater pumps can be started and stopped from the control room.
2) The flow of auxiliary water from the turbine driven pump can be controlled using motor operated EFW valves EF-V-2 A/B. These valves are powered from 480V Engineered Safeguards Control Centers and the controls available in the control room.
3) If necessary, the turbine driven emergency feedwater pump can be stopped using Main Steam valves MS-V13 A/B. The controls for these valves are available in the control room. MS-V13 A/B are powered using instrument air and control power from 125 volt vital power sources. Valves MS-V13 A/B also receive instrument from the back-up instrument air system.

At the time it is determined that remote control of EF-V30 A/B is not available, an auxiliary operator will also be dispatched to the inter-mediate building to take local control of the emergency feedwater control , valves. The TMI Unit #1 operating procedures will be modified prior to restart to reflect the overfill potential and actions to be taken to present over-filling the steam generator. E. The procedure revisions for preventing steam generator overfill conditions are in the draft stage and have not completed the review and approval process required by Mministrative Procedure #1001. The draft procedure revisions instruct the operatora to:

1) Take manual control of EF-V30A/B from the control room as appropriate on high OTSG level to prevent overfill.
2) If control of EF-V30A/B is not available due to loss of control power on instrument air, then an attriliary operator, in communica-tion with the control room, takes manual handwheel control of EF-V30A/B to prevent overfill.
3) If sufficient time does not exist for the auxiliary operator alone to prevent overfill, the control room operator takes immediate action to stop EFW flow to the high OTSGs by shuting the EF-V2A/B valves, as appropriate, or by stopping the appropriate EFW pumps from the control rcom until local manual control of the EF-V30A/B and OTSG levels can be established.

When the procedure revisions are approved, adequate operator training in these procedures will be completed. 1613 182 Am. 9

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                          '                                                                             ' Metropolitan Edison Company                 -

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                ' ~T                                                                                      Post Office Box 542                        -i
                                                                                                         'Readng Pennsylvania 19640                      J 215 929 3001                                y 4

MiaWs Direct Dial Number h 215-921-65k2 3! December 3, 1979 GEL 1h72

                                                                                                                                                     )

5 Mr. G..T. Fairburn

              . Bateock & Wilcox Power Generation Group 06898--e                            $a P. O. Box 1260                                                                                                                  ~~j Ignchburg, Virginia              24505                                                                                             3 T
                                                                                                                                                      -4

Dear Mr. Fairburn:

                                                                             .,                                b
                                                'DtI-1 Emergency Feedwater Rystem
                                                                                                                                                      'j On November 27, it was agreed that B&W vould deterr.ine the mini =um length of time required to flood the TMI Unit #1 Steam Generators with auxilia:7 feed-vater. The analysis was to be perforned similar to that done for the B&W 205 FA plants and was to be submitted to the NRC.in support of the T!C-1 re-start efforts. The costs associated with this effort was to be charged under.

Haster Service' Task 94. . . .

                                                                                                                                                       .)

In supporti of this effort, B&W requested that the auxiliary feedvater flow- ) rates at lo25.psis, 900 psig, 700 psig, and 200 psig steam pressure be ~' provided. In dete: tining the aboye flow rates all auxiliary feedwater pu=ps . . vere assu=ed operating and no bypass flow vas assumed. With both steam generators operable, the flow to each steam generator has been deter =ined to . be TT5, 910,1080, and 1410 sps at each of the respective steam generater . pressures. When only one stea= generator is operable and all feed is to the operable steam generator, the amiliary system flow rates were determined to be 965,1150,1h00, and 1863 spm at each of the respective CTso pressures. '

                                                                                                                                                   ..j If you h&ve any questions regarding the above, please do not hesitate to call.

M. Sincerely,

                                                                                                                       . . .                   '.. .J,J
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3 TMI-1 Engineering 16l3 197 3g Management 4 I JFF:bv , 0 T. F. 1 cc: D. C. Slear J. J. Colitz C. W. S=yth OEC 051979 R. O. Barley 3 Z C. Lanese M. R. Dendler *

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f. . . . =- . ; --. . . =. _ c r.c - . . _.z *- .=-- _ .:. =- =- =

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      ~

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                                      -rn ce s =    LI 91oey Ibm                    (m ern sL4s -;- n -n o
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(hD= & Adi, v/na. U d,nu = ( mOsu)( /. /4) if = (s.76t,sx,o9 if Bh n,+ ~ AM G.m -A Rt" LLt. d ' nu.A % A.t o m a s c. + & 64h._ mm a su. (dou)

2. . 4o oliJaie me, u abb k n,^ +o mL &

us s - n dsuj, 4-o d.s m da.o.t (% ). ' No-te : hitfm' zn o tMai- - ( P>. Q hDQ 3 Yb5N0 b. NSS$Y 5 00 f k - Mut } ( bo m ) b nu = { TA) (I.L/C,04 X 40 ) Bfr N

                                 &        #l0o=    lrcthseu       &_.).nu N*r d       nhout, V~              U                 i
,-a c

w!: [ M */ - / *eCP NC FIL E NO

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          -no       11sd m              n         L                   onaata                 "

O 4% rur = llenf WA76 . Ibm e = S+" 4 //m,. ~~ n__i \ mia _ L'aJ ' ')frFW g_ f"[ i bm ho&Umu TAfw = 00 f 900 A Pss A IbbC ssu~ - [ Pt m uat M w v y

                                                                                                                                   */ mINb Fm          fwom Tasuss (ows0

(-R,

                           ~      ,)Av_w
                                   /

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                                                                                                    ,. B+u-Q caluta. -l n.pu ._, =
                                                                                                                                        ~~
                                         "fa w =            f+ (e 1of) = . otboG*                                                                 Uor.
                                        .56         Omo;           =   6c.4.69 4t'                  (04 42,< c52.')
                                                                 =     L}3. Sa b' W                (lsc.>32.0 W                    M= /5'00_ q                                            N ')O P Fx = 6a o o4.,h              A    =
                                                                            %> .-Aa - ~Zo3 7 Bf4 //4m
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                                                                                                                                     ~

1500 i. ownx so ' Q-( 7. Y8) ( 6 6. 6 4,9 ) 4 9P. (o fr 4_L2, La - u&

                                     =        3. Do 9                  -
                                                                                             ~
2. n s s 2 i xio ' O. -

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ik 5= Btw/-m,J FoeL >32' ux.,

                                               .S c,,        A=           43. s s e ht' L.su              =-       (x L.u.. h               &L.cc9 732                        '3+/            43,33 g-                                                           ,

L.e n s. = '+.b2923 ~

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= *' *?~ GeOU, NO C l' OATE 80*I' SMfgt NO h

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             . sal aJn           hem.

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jp)

                                    =      E. 4128 xio" 8+a.
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w i A.anam.my 4Ad M . k p.+ httviu:d.e d en&.

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  • 4 : '/-3. 5 3 8' W 9

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                                         / (1W)(.oskoS)                                                /

s a 1500 (? 4?N . 0 /405)

                                   = {l2\

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v>t. -Aaes e 4 oo n ---b- hmL faca' 9 9 dwz N

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                              Don' ieom So% alvf f a top el fid &= 3R.344-- 20. to61 = l2.177 '

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5 M* 12 80 som e 700 mte (/ ' I *

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                                -$e =   //98.11 B+a //h,,,                      e io<is,m s ee o , , , =         1000         -

6b (.elbos~) h.41) ' (114.2. + - sd - 2000 -

1. O s 991A so'Q l 9. */ k,i 44#, by 4 / 2.
                                                                    / to 6.1,6 9,I b>uo, y >          2. o f         -

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                                                             //1979 - 33)

{ 7 48) { la .t*49) Jf)C_y3 ? 5 JSS0/31 bbbI 43J52

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                                          .        v-                            -     -

E 3 /E,60 4 p m 6 u

                                                                     $00 m    '

fAM I* M 9100 0 pin C / C 0 0 ,D at.e Ess 544.5C B+~/lhe } _ / Ehalo4%f BI-n/lb r.s L ASr42 .6-fenen 7 o.6le

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14 = . o zi L Lis~ N)lb~ J (' s h a.) L ( 544.15 - 5%) = 4. 2 2)? y a o" E tk-

                                                 =         1000              =
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(2 4kM.oisos) mou M*0 9pm ' 1000 - P *b Q 4. 6 16 e nor (74tY.orsosD M M A>(dL esol o Lmgg = PE244 - ( & - cl.natixso') l ._catsur Z om.s .3 66.66,

                                               ~

2.9 - 5. 014 / yto ' ( $ - 4.w k t so

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1000 4 s2. ' [' ococ i n. ) f l b. fs b 9 ) R3.a n e ) i . . . , . ,

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                              $n.a.1_n , s            /000       tTAo                             --          l 2 4.9 4 -7Yi.-
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                                      ~~-
2. *.

b0 = 12 &'O ct n >m 6' e 200 Ys

  • hb= Siz.si.f Bfu}/b,,,

fis = 6 5 6. Sh~ Bfu //b m 1%= .o1o98 J+S/ Ibn

                           >%,3g =                      /2,5.o           ( 6/24t/ - 3fr ) s                6 . OJ7r*/ 3'o " B f a.

hv0 (.orun tri,a

                        /Ebo "spm =             1750               -    10 & bt. 9 lbm             a        no f (24r)l.ossos)                               m s.)
                                   .            .                                                                                         m b      __b__ _ _         E UCZ]/C,60 9

5

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            .               .                                    .      ms.m >                  .                   .               .

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A n h bj . $

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  • fl5$= $E' YLL a b S' Yb \

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                           % $      TTT
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JLc5'O) 3.0w &. Jtw dolio w & llu 4 YoblLu L ] - 7Aeos Ab& ('.aihe.t 1 - Near Lono Due to %, H ea r (o-*7.) L Rcs coog owa (o- top %,,) Mou A Ptf Rea*b Yo Mn TL H A6edG AeRT Lonos (ie, ao raceense to .u Leves) z sh 4 cLn 1 dL k.R^ ~ ~ essd u isooe a , & Ouo a .c con s-r n , i-Hwy ke_stp> " A saw>wap tat. m at. W f s/ Steam, Ja. pheed . O

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