ML20076C944

Answers to Second Set of Interrogatories & Requests to Produce.Certificate of Svc Encl.Related Correspondence

ML20076C944
Person / Time
Site:	Robinson
Issue date:	08/18/1983
From:	Banks H, Bohannon J, Coats R CAROLINA POWER & LIGHT CO.
To:	HARTSVILLE GROUP
References
83-484-03LA, 83-484-3LA, ISSUANCES-OLA, NUDOCS 8308230229
Download: ML20076C944 (113)

Text

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UNITED STATES OF AMERICA USIf[C E

NUCLEAR REGULATORY COMMISSION

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In the Matter of

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BRANCH

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CAROLINA POWER & LIGilT COMPANY

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Docket No. 50-261-OLA

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(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

APPLICANTS ANSWERS TO TIIE IIARTSVILLE GROUP SECOND SET OF INTERROGATORIES AND REQUESTS TO PRODUCE A.

INTERROGATORIES RELATING TO IIARTSVILLE CONTENTION 1 (PARTS A & B) 1-1.

For each person identified with respect to Applicant's responses to General Interrogatory 1 (G-1) to "The Hartsville Group First Set of Interrogatories and Requests to Produce,' please describe that person's professional qualifications.

ANSWERl-1.

Ronnie M. Coats Education & Training A.

B.S. Degree in Chemical Engineering from North Carolina State University - 1967.

B.

Graduate School s.

North Carolina State University, one semester 1968.

Site Lecture Series of Westinghouse Training Program.

Professional Societies American Institute of Chemical Engineers.

Registered Professional Engineer - State of North Carolina.

Experience A.

June 1965, Research Assistant in Nuclear Engineering Depcrtment at North Carolina State University.

September 1967, Graduate Student Laboratory, Instructor at North Carolina State University.

B.

Carolina Power & Light Company 8308230229 830818 PDR ADOCK 05000261

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January 1968 - Employed as a Chemical Engineer in the Design and Construction Section.

February 1970 - Employed as a Radiochemical Engineer in the Technical Services Section.

July 1971 - Employed as a Senior Chemical Engineer in the Nuclear Design Section of the Power Plant Design and Construction Department.

April 1972 - Employed as a Principal Engineer in the Nuclear Plant Engineering Section of the Power Plant Engineering and Construction Department.

August 1973 - Employed as a Principal Engineer - Projects in the Nuclear Plant Engineering Section of the Power Plant Engineering and Construction Department.

Located at the Brunswick Plant.

August 1975 - Employed as Principal Engineer on the staff of the Assistant to Group Executive - Engineering, Construction, and Operating.

October 1976 - Employed as a Principal Engineer in the Staff Services Unit of the System Planning & Coordination Department.

January 1977 - Employed as Manager - Generation Services Section of the Generation Department.

November 1979 - Employed as Manager - Nuclear Operations Administration Section of the Nuclear Operations Department.

February 1981 - Employed as Manager - Nuclear Operations Administration Section of the Technical Services Department.

March 1982 - Employed as Assistant to the Group Executive Power Supply. Power Supply Staff.

R. L. Mayton, Jr.

Education & Training A.

B.S. Degree in Nuclear Engineering - N.C. State University - 1963.

B.

M.S. Degree in Nuclear Engineering - N.C. State University - 1965.

Professional Societies American Nuclear Society.

IIcalth Physics Society.

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Completed Part 1 of American Board of IIcalth Physics Certification - 1982.

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Experience Prior to Joining CP&L

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June 1962 - September 1962: Engineering Assistant, L. E. Wooten & Company.

June 1963 - September 1963:

Engineer, Nuclear Power Division, Charleston Naval Shipyard.

June 1964 - August 1965:

N.C. State University, Teaching nuclear physics laboratory while attending college.

August 1965 - June 1968: Engineer responsible for technical assistance to production department at Savannah River Project.

Experience with CP&L June 1968 - February 1971: Senior Engineer - Raleigh, NC.

February 1971 - November 1971: Principal Nuclear Licensing Engineer, Environmental &

Technical Services Section, Generation & System Operations Department, Raleigh, NC.

November 1971 - June 1976: Principal Nuclear Licensing Engineer, Environmental &

Technical Services Section, Special Services Department, Raleigh, NC.

June 1976 - December 1976: Manager - Corporate Ilealth Physics, Technical Services Department, Raleigh, NC.

December 1976 - November 1977: Manager - Corporate llealth Physics, System Planning

& Coordination Department, Raleigh, NC.

November 1977: Director - Corporate liealth Physics, System Planning & Coordination Department, Raleigh, NC.

August 1979:

Director - Corporate llealth Physics, Nuclear Safety & Research Department, Raleigh, NC.

June 1981: Director - Corporate liealth Physics Section, Corporate Nuclear Safety &

Research Department, Raleigh, NC.

August 1982: Manager - Corporate IIcalth Physics Section, Corporate Nuclear Safety &

Research Department, Raleigh, NC.

Harold R. Banks l

l Education & Training A.

Graduated from Indiana fligh School, Indiana, Pennsylvania - 1948.

B.

Class "C Instructor Training School - U. S. Navy - 1954.

C.

Basic Nuclear Power Engineering School-U. S. Navy - 7/59 - 1/60.

D.

Nuclear Power Training Unit - U. S. Navy - 1/60 - 6/60.

E.

Naval Officer's, Limited Duty, Candidate School-10/64 to 12/64.

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Member of American Society of Mechanical Engineers.

B.

Member of American Society of Nondestructive Testing.

C.

Member of North Carolina Society of Engineers.

D.

Member of American Nuclear Society.

E.

ASME Standards Committee on Personnel Qualification and Work Groups for N45.2.12 and N45.2.23.

F.

EEI QA Committee.

Experience A.

U. S. Navy 1.

June 1948 - June 1959 a.

Shipboard and shore base assignment in power plant operation, maintenance, instructor and supervision.

B.

Nuclear Power Engineering School and Prototype 1.

June 1959 - June 1960 a.

Student.

C.

Nuclear Submarine Prototype, Idaho Falls,ldaho 1.

June 1960 - June 1962 a.

Nuclear Power Training Unit - qualified EOOW.

D.

USS Andrew Jackson 1.

June 1962 - October 1964 a.

Leading Machinery Division Chief, supervisor in charge of the operation of the nuclear power plant - qualified EOOW.

E.

Naval Officer's Candidate School 1.

October 1964 - January 1965 a.

Student.

F.

San Francisco Bay Naval Shipyard 1.

January 1965 - August 1968 a.

Nuclear Ship Superintendent.

G.

Carolina Power & Light Company 1.

August 1968 - Present a.

August 1968 - Employed as a Resident Project Engineer at the H. B.

Robinson Plant in Hartsville, SC.

b.

July 1970 - Employed as a Resident Project Engineer in the Plant Design

& Construction Department at the Brunswick Plant in Southport, NC.

c.

August 1971 - Employed as Manager - Quality Assurance in the Power Plant Design & Construction Department in Raleigh, NC.

d.

February 1972 - Employed as Manager - Quality Assurance Audit in the Special Services Department in Raleigh, NC.

e.

July 1973 - Employed as Manager - Quality Assurance & Training Audit in the Special Services Department in Raleigh, NC.

f.

August 1975 - Employed as Manager - Corporate Quality Assurance Audit in the Special Services Department in Raleigh, NC.

g.

March 1976 - Employed as Manager - Nuclear Generation in the Generation Department in Raleigh, NC.

h.

November 1979 - Employed as General Manager - Harris in the Nuclear Operations Department in Raleigh, NC.

i.

February 1981 to present - Employed as Manager - Corporate Quality Assurance in the Corporate Quality Assurance Department. Located in the General Office, Raleigh, NC.

Guy P. Beatty, Jr.

Education & Training A.

Bachelor of Mechanical Engineering, Clemson University,1958.

Reactor Safety & Hazards Evaluation Course - 1966. Conducted by HEW, Rockville, Maryland.

Nuclear Power Reactor Safety Course - 1966. Conducted by MIT.

Basic Radiological Health Course - 1967. Conducted by HEW, Cincinnati, Ohio.

Nuclear Fuel Management Course - 1967. Conducted by NUS Corporation, Washington, D.C.

Westinghouse Reactor Operator Training ~ Program.

Conducted by Westinghouse, Hartsville, S.C.; Waltz Mill, PA; Saxton, PA; Pittsburgh, PA..

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Completed license requirements for a reactor operator on tne Saxton Nuclear Experiment Reactor, August 1969.

2)

Cornpleted " cold *' License Requirements for a Senior Reactor Operator's License, June 1970 (SOP-1932) for II. B. Robinson Unit No. 2.

Reactor Operator Retraining Program conducted by Westinghouse & CP&L - April 1972.

1)

Re-licensed as Senior Reactor Operator,11. B. Robinson Unit 2, June 1972.

Reactor Operators Training Program conducted by FPC operations personnel at Crystal River Site. Shift Technical Advisor Training, B&W/ Simulator, Lynchburg, VA.

Work Experience June 1958 February 1960

- Plant Engineer, H.

F.

Lee Plant, Carolina Power & Light Company i

Assignments included design

work, water purification system, automation of plant subsystems, training, plant performance, water

analysis, fuel analysis.

February 1960 - June 1960

- Plant Engineer, H. B. Robinson Plant, CP&L - responsible for organization of Fuel and Water Analysis Laboratories, programming instrument controls, etc.

June 1960 - July 1964

- Plant Maintenahce Supervisor, II. B.

Robinson Plant, CP&L - responsible for supervision of mechanical, electrical and instrument groups of pulverized coal unit.

Established preventive maintenance program; identified, managed and scheduled maintenance work for all the plant systems.

July 1964 - February 1966

- Operation Supervisor, II. F. Lee Plant, Carolina Power & Light Company.

Three-unit pulverized coal.

February 1966 - July 1972

- Plant Manager,11. B. Robinson Station, CP&L - responsible for the continued operation of the pulverized coal unit, pre-operational testing and start up of II. B. Robinson Unit #2 700 MW Electric Westinghouse PWR, July 1972 - August 1973

- Nuclear Staff Engineer, Florida Power Corporation - involved with the pre-operational training and licensing for gtal River Unit 3, 855 MW B & h s l

I I

i August 1973 - November 1974

- General Plant Manager - responsible for Crystal River Units 1 and 2, Crystal River Unit 3 and two other plants.

i November 1974 - December 1975

- Assistant Project Manager - for the j

final construction and pre-operational phase on Crystal River Unit 3.

i' December 1975 - November 1979 Plant Manager, Crystal River Unit 3 -

responsible for the development of the Operations Manual and for the management of Crystal River Unit 3 during the pre-operational testing, start i

i up and commercial operation phases.

November 1979 - October 1982 Functioned as Assistant to the Vice i

President of Nuclear Operations.

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Primarily concerned with an overview of the licensing and management techniques.

Was a member of the B&W Regulatory

Response

Group, The Engineering Advisory Committee of Nuclear Electric Insurance Ltd. (NEIL), member of the Executive Committee of the E. A.C., NEIL; member of Nuclear i

General Review Committee (Florida Power Corp.); and member eel Prime Movers Nuclear Power Operations Subcommittee. Performed as the EOF (Emergency Offsite Facility). Director for Florida Power Corporation.

Was delegated full signatory authority of my supervisor for personnel, material i

l and contracts.

Served as Capital Improvements Project Manager for major improvements including the Technical Support Center.

1 October 1982 - Present

- Employed as Manager, Special Projects by Carolina Power & Light Company.

Primary responsibility is Project Team j

Manager for the H. B. Robinson Unit 2

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Steam Generator Repair Project.

Robert E. Halliburton Education & Training l

A.

B.S. Degree in Mathematics, University of Tennessee, Knoxville, Tennessee,1970, i

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M.S. Degree in Health Physics, University of Tennessee, Knoxville, Tennessee,1970.

Professional Societies Health Physics Society.

Experience A.

August 1970 to March 1971 - Teacher - Clarksville-Montgomery County School System, Clarksville, TN.

March 1971 to December 1972 - Officer - United States Air Force.

July 1974 to August 1976 - Health Physics -Technician, Oak Ridge National Laboratory, Oak Ridge, TN.

August 1976 to December 1979, Health Physicist, Oak Ridge National Laboratory, Oak Ridge, TN.

January 1980 to April 1982 - Health Physics Supervisor, Oak Ridge National Laboratory, Oak Ridge, TN.

B.

May 1982 to Present - Project Specialist-Health Physics, CP&L.

Power Supply Group, Technical Services Department, Radiological and Chemical Support Section, New Hill, NC.

Sherwood R. Zimmerman Education & Training A.

B.S. Degree in Engineering - U. S. Naval Academy - 1963.

I B.

U. S. Naval Officers Advanced Nuclear Power School, Bainbridge, Maryland - July l

1963 to December 1963.

C.

U. S. Naval Officers Submarine School, New London, Connecticut - August 1964 to Feburary 1965.

D.

Fleet Ballistic Missile Submarine POLARIS Weapons Officer School-January 1967 l

to May 1967.

Professional Societies Registered Professional Engineer - State of North Carolina, February,1977.

Experience December 1963 to December 1969 - Lieutenant - U. S. Navy - Knowledge of all phases of nuclear power plant operations obtained through a 12-month training program culminating in qualification as Supervisor of the land-based prototype reactor, SIC (Combt.stion Engineering, Inc., Windsor, Connecticut).

Subsequent 6-month on-ship reactor supervisor qualification on Westinghouse nuclear reactor, S5W.

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December 1969 to June 1972 - Engineer in the Nuclear / Mechanical Group, Engineering Department of the Baltimore Gas and Electric Company.

Devote full time to engineering and licensing work in connection with Calvert Cliffs Nuclear Power Plant.

June 1972 to June 1973 - Senior Engineer - Environmental & Technical Services Section -

Special Services Department.

June 1973 - Project Engineer - Environmental & Technical Services $cetion'- Special Services Department.

June 1976 - Director - Nuclear Licensing Unit, Licensing & Siting Section, Technical Services Department.

January 1977 - Manager - Lie,onsing & Siting beetion, Technical Services Department, CP&L, Raleigh, NC.

December 1979 - Manager - Licensing

&-2 Permits Section,- Technical Services Department, CP&L - Raleigh, NC.

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Richard E. Lumsden Thirty (30) years' expeilence as an officer in the U.S. Navy, retiring as a Captain (0-6). The last 24 years of service were in the Navy Nuclear Propulsion Program with duties requiring the supervision of construction, maintenance, and operation of naval nuclear power plants, lie also has one year of CP&L ex;ierience as Acting Assistant to the Vice President _ Nuclear Operations Department, commencing in 1982.

J. IIenry Ochmann, III Education A.

A.B. Degree in economics from the University of North Carolina at Chapel Hill.

l B.

M.B.A. Degree from East Carolina University in Greenville, NC.

Professional Societics I

Accredited Personnel Manager.

~~

Member of the American Society of Personnel Administrators.

Experience Joined CP&L in 1972 as a residential marketing representative in Asheville, NC and also served in commercial marketing. Named senice customer service representative in 1974 and was promoted to assistant personnel representative in 1978. II 1980 - promoted to l

general office personnel director. In 1983 - promoted to manager of planning and N, -

administrative support at CP&L's General Office in Raleigh, NC.

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e James R. Bohannon, Jr.

Education B.S. & M.S. with Ilonors, Nuclear Engineering, NC State University, 1950-1953.

Diploma, Air Command & Staff School, Air University,1957.

Diploma, Air War College, Air University,1965.

2 Professional Societies Professional Engineers' Registrations in DC and NC.

Quality Assurance Consultant, Southern Mobile Concrete; Carolina Power & Light Company (Safety Committee); Duke Power Company; ISMMC; and Marvin Johnson Association.

Consultant, DOE, Hg. Operational Safety Division (through Dec.1979).

Consultant, NRC Hg. Reactor Operator Licensing Division (through Dec.1979).

Member of ANS-15 Standards Committee on Research Reactors.

Previously held NRC Senior Operator License on R-3 and PULSTAR reactors.

Member of American Nuclear Society.

Experience January 1980 to Date - Manager, Nuclear and Fossil Training, Carolina Power & Light Company, Raleigh, NC.

1966 - 1979 - Associate Professor of Nuclear Engineering and Nuclear Operations Administrator - NC State University, Department of Nuclear Engineering, and Nuclear Reactor Program, Raleigh, NC.

1964 - 1966 r Director of Nuclear Engineering Facility, U. S. Air Force, Institute of

(

Technology and Flight Dynamics Laboratory, Wright-Patterson Air Force Base, Ohio.

1961 - 1964 - Nuclear Projects Engineer, U. S. Air Force, IIq. USAF, Directorate of Civil Engineering, Washington, DC.

1954 - 1957 - Project Engineer, U. S. Air Force, Aircraft Nuclear Propulsion Office and Materials Laboratory, Wright-Patterson Air Force Base, Ohio.

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s 1954 - 1954 (six months) - Special Assignment, Oak Ridge National Laboratories, Oak

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Ridge, Tennessee.

"1953 - 1954 - Special Staff Member, NC State University, s

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e R. B. Starkey, Jr.

See answer to Interrogatory 1-3.

L. B. Wilson, Jr.

Educat'on & Training B.S. Degree in Civil Engineering, Virginia Military Instit Ate, Lexington, Virginia,1962.

Professional Societies American Society of Civil Engineers (National and N.C. Section) - Member National Society of Professional Engineers - Member North Carolina Society of Engineers -

Member Registered Professional Engineer in North and South Carolina.

Experience A.

Ebasco Services Incorporated February 1965 - March 1967 - Assistant Engineer, Concrete Hydraulic Design, New York, N Y.

October 1966 - March 1967 - Eagineering Field Representative, Ilartsville, SC.

March 1967 - August 1970 -. Office Engineer, responsible to the Resident Engineer, n

Hartsville, T C.

August 3070 - February 1971 - Field-Office Engineer responsible to the Project Supeririteadent, llartsville, SC.

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B.

Carolitui Power & Light Company February 1971 - employed as a Senior Engineer in the Construction Section of the Powe~ Plant Design & Construction' Department.

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June 1972 - promoted to Principal Engineer in the Construction Section of the Power Plant Engineering & Construction Department.

February 1977 - promoted to Manager - Construction Engineering Section in the

/

Power Plant Construction Department.

December 1979 - promoted to Manager - Fossil Power Plant Engineering Department.

t January 1981 - named Manager - Fossil Plant Engineering & Construction Department.

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W. Parker Tomlinson Education B.S. Degree in Nuclear Engineering - North Carolina State University - 1972 4

Professional Societies A.

American Nuclear Society.

].

I B.

Registered Professional Engineer - North Carolina - February 1977.

1 Experience A.

Carolina Power & Light Company 1.

June 1972 - Employed as a Junior Engineer in the Nuclear Plant Engineering Section of the Power Plant Engineering & Construction Department, General Office, Raleigh, NC.

2.

November 1972 - Transferred to Brunswick Steam Electric Plant as a Junior Engineer, Nuclear Plant Engineering Section, Power Plant Engineering Department, Southport, NC.

3.

June 2,1973 - Promoted to Engineer, Nuclear Plant Engineering Section of Power Plant Engineering Department, located in Southport, NC.

j 4.

June 1975 - Promoted to Senior Engineer, Nuclear Plant Engineering Section of Power Plant Engineering Department, Raleigh, NC.

5.

January 1977 - Assigned to the Engineering Pool Section of the Power Plant Engineering Department as Senior Engineer at the Brunswick Plant, Southport, 4

N C.

6.

April 1,1977 - Tranderred to General Office, Raleigh, as a Senior Engineer, Engineering Pool Section, Power Plant Engineering Department.

7.

January 1979 - Promoted to Project Engineer, Engineering Pool Section, Power Plant Engineering Department.

8.

December 1,1979 - Transferred as Project Engineer to the liarris Plant Engineering Section of the Nuclear Power Plant Engineering Department.

9.

July 12,1980 - Promoted to Principal Engineer of the Mechanical Unit of the Harris Plant Engineering Section of the Nuclear Power Plant Engineering Department, New Hill, NC.

10.

October 31, 1981 - Transferred as Principal Engineer-Mechanical to the Engineering Support, Nuclear Plants Section, Nuclear Plant Engineering Department, General Office.

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e Mike McDowell Education & Training B.S. Degree in Chemical Engineering, North Carolina State University - 1970.

Professional Societies A.

Edison Electrical Institute Power St9*. ion Chemistry Committee - Chairman, Editorial Seetion.

B.

American Nuclear Society.

C.

Registered Professional Engineer in North Carolina (August 1975).

Experience A.

Carolina Power & Light Company June 1970, Junior Engineer in the Bulk Power Supply Deoartment.

May 1971, Chemical Engineer in the Fossil & Ilydro Generation Section of the Bulk Power Supply Department.

July 1975, Senior Engineer in the Fossil & Ilydro Generation Section of the Bulk Power Supply Department.

January 1977, Senior Engineer in the Generation Services Section of the Generation Department.

October _1977, Project Engineer - Chemistry in the Generation Services Section of the Generation Department.

May 1979, Project Engineer - Chemistry in the Generation Services - IIE&EC Section of the Generation Department.

November 1979, Principal Specialist - Chemistry in the Environmental & ltadiation ControlSection of the Nuclear Operations Department.

March 1981, Principal Specialist - Chemistry in the Environmental & Radiation Control Section of the Technical Services Department.

February 1982, Principal Specialist - Chemistry in the Radiological & Chemical Support Section of the Technical Services Department.

B. Mitchell Williams Education & Training B.S. Degree in Agricultural Engineering from N.C.S.U. - 1969.

• _ -_ = -

Professional Societies North Carolina Society of Engineers - member.

l Experience A.

Prior to Joining CP&L:

L June' 1969 August 1972 Engineer - Distribution Engineering -

Virginia Electric & Power Company -

a Williamston, NC.

i August 1972 - August 1973 Engineer - Transmission Line Engineering -

Virginia Electric & Power Company -

Richmond, Virginia.

B.

Carolina Power & Light Company:

August 1973 Agricultural Development Engineer - Henderson District Nashville Area Office - Northern Division Operations - Nashville, 4

N C.

April 1974 Transmission Line Coordinator - Transmission Location Unit -

Transmission Engineering & Construction Section - System Engineering & Construction Department - Raleigh, NC.

January 1977 Engineering & Construction Department - Raleigh, NC. Senior Industrial Power Engineer - Sumter District Office - Southern Division Operations - Sumter, SC.

January 1977 Senior Industrial Services Engineer - Industrial Services Unit -

Energy Services Section - Customer Service Operations Support Department - Raleigh, NC.

l August 1979 Project Staff Services Specialist - Administrative Unit - Staff Services Section - System Planning & Coordination Department -

l Raleigh, NC.

July 1981 Principal Engineer - Regulatory Unit - Staff Services Section -

l Planning & Coordination Department - Raleigh, NC.

i February 1982-Planning & Coordination Department - Raleigh, NC. Director-present Staff Services - Staff Services Section - Planning & Coordination Department - Raleigh, NC.

Manley A. Pope Twenty-eight (28) years experience with CP&L.

Initially worked in various accounting positions including Internal Auditor. Five (5) years experience as IIead Team

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Auditor for Materials & Supplies Auditing which included audit responsibilities for generating plants. Employee Relations experience includes one (1) year as Assistant Personnel Representative - General Office; eight (8) years Division Personnel Representative - Eastern Division which included the Brunswick Nuclear Plant; two (2) years as Manager - Personnel Relations for the Brunswick and Robinson Nuclear Plants, and presently Personnel Relations responsibilities for Brunswick, Robinson and liarris Nuclear Plants. Previously served three (3) terms as Regional Vice President and National Board Member and presently National Board Member At Large for the American Society for Personnel Administration (ASPA).

1-2. Describe in detail the administrative structure of each of the following CP & L departments.

The description should include the Table of Organization with the incumbent in each position identified and assignment of responsibilities for ensuring adherence to NRC operating procedures, rules and regulations, a) Corporate Quality Assurance b) Corporate Nuclear Safety and Research c) Nuclear Operations Department d) Nuclear Plant Engineering Department e) Nuclear Plantr [ sic] Construction Department ANSWER l-2.

a)

CORPORATE QUALITY ASSURANCE DEPARTMENT (Harold R. Banks)

The Corporate Quality Assurance Department has three sections and one unit. The sections are QA/QC Harris Plant Section, QA Services Section, and QA/QC Brunswick and Robinson Plants Section. The unit is the Office Services Unit. The management structure is depicted on an exhibit following this answer.

QA/QC liarris Plant Section (Nathaniel J. Chiangi) i The QA/QC liarris Plant Section is responsible for the development and implementation of the engineering, construction, operations and nondestructive testing quality assurance / quality control (QA/QC) programs that will assure nuclear generating facilities and other assigned projects are constructed, operated or modified in accordance with regulatory and Company requirements.

This responsibility entails l

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i directing the planning, development and implementation of Nuclear QA; Nonnuclear

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Balance of Plant (BOP) QA; and ASME N-Stamp QA programs to ensure compliance with 1

applicable codes, standards, specifications, drawings, regulatory requirements, and corporate policies and commitments. The Section consists of three Units: the QA/QC I

Harris Plant Unit; the Nondestructive Examination Unit; and the QA Engineering liarris

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Plant Unit.

Quality Assurance Services Section (Richard Lumsden - effective 9/3/83)

The Quality Assurance Services Section is responsible for assuring that the Corporate Quality Assurance Program is implemented, that Company policies are administered uniformly, that quality assurance activities are performed in accordance with the Corporate Safety Manual and OSHA requirements, and that a QA Program is maintained which identifies existing and potential problems in the engineering, construction, modification, and operation of nuclear plants. The Section consists of four t

Units:

the QA Engineering Unit; the Vendor Surveillance Unit; the Performance Evaluation Unit; and the Training and Administration Unit.

QA/QC Brunswick and Robinson Plants Section (C. H. Moseley)

The QA/QC Brunswick and Robinson Plants Section is responsible for implementing a QA/QC pcogram at each operating nuclear plant to ensure that requirements of the 4

Corporate QA Program, ASME QA Program, NRC and other regulatory agencies, and appropriate industry standards and specifications are met. It is responsible for promoting the safe operation of nuclear power plants by developing and implementing an effective plant surveillance program and by providing technical support for quality-related l

matters. - The Section consists of two Units: the QA/QC Brunswick Plant Unit (located at Brunswick Plant) and the QA/QC Robinson Plant Unit (located at Robinson Plant).

Each QA/QC Unit has the responsibility at their respective plant for assuring proper application of quality standards, practices, and procedures associated with nuclear 4

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plant oDeration, maintenance, and modification to ensure that the appropriate quality requirements of the Nuclear Regulatory Commission, the Corporate Quality Assurance Program, the plant operating license and technical specifications, and industry codes and standards are satisfied in all applicable phases of nuclear plant activity.

This responsibility is accomplished by planning and directing the activities of a qualified staff in the implementation of the Corporate QA Program in the electrical, mechanical, structural, material control, and nondestructive examination disciplines; by effective review of maintenance authorizations for inclusion of quality requirements; and conducting QA/QC surveillances of on-going plant activities and reporting results to responsible department and plant management; and evaluating the effectiveness of the plant QA program.

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' CORPORATE QUALITY ASSURANCE DEPARTMENT Executive Vice President i

Power Supply and Engineering & Construction k

E. E. Utley l

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Corporate Quality Assurance Department H. R. Bank 1

Manager 1

4 Administrative j

Of fice Services Assistant i

Unit 1

Supervisor i

I OA/QC j

Harris Plant Section OA Services Section QA/QC BSEP&HBR Section Manager 1

Manager Manager i

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b)

CORPORATE NUCLEAR SAFETY & RESEARCH The administrative structure of the Corporate Nuclear Safety and Research Department is as shown on the exhibit following this answer. The Department is headed by Dr. Thomas S. Elleman, Vice President, and is divided into three functional sections.

The sections are: Corporate Nuclear Safety, headed by Dr. J. D. E. Jeffries; Corporate Health Physics, headed by R. L. Mayton, Jr.; and Research, headed by Dr. A. G. Bullard.

The objective to the Corporate Nuclear Safety and Research Department is to work through the sections to insure that Company nuclear power plants are as safe as reasonably achievable through independent safety reviews; to keep abreast of research programs and investigations; and to insure that the health physics programs are professional and in compliance with the regulations.

The Corporate Nuclear Safety Section is responsible to corporate management for an independent review and assessment of nuclear safety primarily in the operation phase of the Company's nuclear power plants. Specifically, the Section performs reviews of operating nuclear plant system and procedure changes, licensing actions, unreviewed safety questions, plant operational occurrences, and regulatory violations. The Section maintains cognizance of nuclear industry situations and identifies nuclear safety concerns which might be applicable to CP&L plants.

The Corporate Nuclear Safety Section consists of an On-Site Nuclear Safety Unit at each of the operating nuclear plants, and a Corporate Nuclear Safety Unit located in Raleigh. The On-Site Nuclear Safety Units conduct direct surveillance as well as safety reviews of procedure changes, changes to technical specifications, special tests, plant modifications, and unusual events. The Units provide a safety review capability at the plants which allows for timely review of unusual incidents and events. Findings of the Units are conveyed to Operations for implementation and response. Tne Units also provide backup technical assistance to operations personnel on safety related questions as needea.

The on-site safety review responsibilities are consistent with NRC 1

requirements for the independent safety evaluation group as specified for nuclear plants licensed by the NRC.

f The Corporate Nuclear Safety Section provides specific expertise to plant units for analysis for safety related events. They conduct system analyses at the plants to establish maintenance histories of critical safety systems and identify areas of safety concern. The Section monitors operations experience information developed by INPO, NSAC, and NRC and makes recommendations to Operations for safety considerations derived from this information. The Corporate Nuclear Safety Unit located in Raleigh provides a backup to the On-Site Units and generally conducts those safety reviews which are generic in nature, while the plant units analyze events and documents that relate to specific plant operations.

The Corporate Health Physics Section is responsible for formulation and recommendation of corporate level health physics programs and policies, evaluating I

existing health physics programs and recommending improvements and modifications, serving as corporate spokesman on health physics and related matters, providing support to the licensing and Corporate Nuclear Safety activities of the Company, and serving as

' the corporate interface with regulatory agencies on matters of radiological safety.

The Corporate Health Physics Section performs formal assessments of the health i

physics programs at the operating nuclear plar to assess the effectiveness of the programs and to assist in identification of any areas which might not comply with NRC operating rules and regulations. The assessments are documented and recommendations i

made to appropriate plant management. The Manager of Corporate IIealth Physics evaluates the various health physics programs to assess compliance with the requirements of the Corporate IIealth Physics (CIIP) Policy. The CIIP policy requires I

that the health physics programs be structured to maintain radiation exposures of Company personnel, contractor personnel, and the general public at levels which are as low as reasonably achievable (ALARA). The Manager of CIIP assures that this policy is properly communicated to all affected organizations.

l - - -

The Corporate IIcalth Physics Section assesses the various ALARA programs which have been developed within the Company to assure that they are effective in minimizing exposure to radiation for people working in our nuclear facilities. The Section provides technical assistance in the areas of health physics to the various departments within the Company as requested. The Section continuously assesses our overall health physics activities to assure that appropriate resources are being committed to the health physics programs and that senior management of the Company is kept informed of the current status of the various health physics programs.

The Research Section is responsible for monitoring and evaluating active and proposed research and development projects related to the electric utility business.

Their responsibilities are not related to ensuring adherence to NRC operating procedures, 2

rules, and regulations.

In summary, the Corporate Nuclear Safety Section and the Corporate Ilealth Physics Section primarily support the Vice President of Corporate Nuclear Safety and Research in his overall mission to assure that the Company nuclear power plants are as safe as reasonably achievable. Efforts conducted by members of the department are of assistance in assuring that the Company's nuclear power plants are operated in a safe manner and that the health physics programs established are consistent with the Corporate llealth Physics Policy, NRC regulations, and good health physics practices.

l

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CORPORATE NUCLEAR SAFETY & RESEARCH DEPARTMENT Executive Vice President Power Supply and Engineering & Construction E. E. Utley

+

Corporate Nuclear Safety

& Research Department T. S. Elleman Vice President Office Services Unit Supervisor Corporate llealth Corporate Nuclear Physics Section Safety Section Research Section Manager ManaDer Manager a

D 1I s*

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c) NUCLEAR OPERATIONS DEPARTMENT The Nuclear Operations Department's management structure is depicted and the incumbents are identified on an exhibit following this answer. The structure consists of the Plant General Manager at the Robinson Plant, the Plant General Mancger at the Harris Plant, and the Assistant to the Vice President of Nuclear Operations reporting to the Vice President of Nuclear Operations.

The Vice President of Nuclear Operations reports to the Senior Vice President -

Power Supply and is responsible for operation and maintenance of the Robinson and Harris Nuclear Plants. He supervises:

1.

The Robinson Plant General Manager who is responsible for safe and efficient plant operation of the Robinson Plant in accordance with license, regulatory and Company requirements, and consistent with nuclear safety, environmental, and other considerations.

Reporting to this position are:

Manager - Environmental and Radiation Control Director - Planning and Scheduling Assistant to the General Manager Manager - Technical Support Manager - Operations and Maintenance 2.

The Harris Plant General Manager who is responsible for ensuring the safe and efficient startup and operation of the Harris Plant in compliance with license, regulatory, and Company requirements, and consistent with nuclear safety, environmental, and other considerations.

Reporting to this position are:

Manager - Plant Operations Director - Planning and Scheduling Assistant to the General Manager

• t

Manager - Technical Support 3.

The Assistant to the Vice President of Nuclear Operations who is responsible for providing administrative and technical assistance to the Vice President of Nuclear Operations.

4.

The Office Services Supervisor who is responsible for coordinating clerical services.

1 l

1 l

• J NUCLEAR OPERATIONS DEPARTMENT Nuclear Operations Department B. J. Furr Vice President Assistant to Vice Presicient -

Of fice Services Nuclear Operations Unit J. L. Ilarness "E*

11. R. Ilutchins liarris Plant Robinson Plant General Manager I

General Manager J* b* N11118 R.

B.

S ta rkey I

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d)

NUCLEAR PLANT ENGINEERING DEPARTMENT The Nuclear Plant Engineering Department is divided into two major sections: the Harris Plant Engineering Section, and the Engineering Support, Niielear Plants Section.

In ' addition, the Direcs - - Safety-Review, Nuclear Engineering is a part of this Department. There is also an Office Services Unit and a Staff Assistant who provide the Department Manager with staff support. The exhibit following this answer indicates these sections and incumbents therefor.

The responsibilities of these are briefly described below.

Harris Plant Engineering Section The Harris Plant Engineering Section is responsible for providing the design and i

engineering for the Shearon Harris Nuclear Power Plant project, including engineering support of site activities, and for accomplishing corporate, group, and departmental goals associated with the project. The Section fulfills these responsibilities by managing the contract for architeet/ engineer services; by providing technical direction for project design; by performing site engineering support to Construction and Operations, including specified design activities; and by managing the procurement of engineered equipment.

The Harris Plant Engineering Section is organized into four Units: Mechanical,

?'

Electrical, Civil, and Support. The technical Units are headed by Principal Engineers.

The Principal Engineers are responsible for ensuring that project work and decisions which are their responsibility are accomplished in such a manner that the Section's accountabilities are fulfilled.

Engineering Support, Nuclear Plants Section The Engineering Support, Nuclear Plants Section is responsible for providing engineering support for the Company's operating nuclear plants consistent with NRC operating procedures, rules, and regulations and for utilizing feedback received from the operating plants so as to prevent identified problems from recurring. This Section's objective is to provide engineering and procurement of engineered products on schedule i

.m with designs that are economical, safe, efficient, reliable, and compatible with the environment. The Engineering Support, Nuclear Plants Section is organized into three technical Units and an Engineering Administration Staff. The technical Units are Mechanical I (emphasis on major components and analytical support); Mechanical II (emphasis on process systems); and Electrical. The three Units are headed by Principal Engineers.

Director - Safety Review, Nuclear Engineering The primary responsibilities of the Director - Safety Review, Nuclear Engineering are to review documents generated by the Company's nuclear organization and A/ES to identify problems or potential problems in engineered safeguards systems and plant safety features; to assess activities and trends in the industry regarding design and operation of safety features; to provide feedback to preclude potential nuclear safety problems in ongoing plant designs and design of modifications; and to assure that ALARA concepts for radiation control are considered in engineered designs.

2 1

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_ 24 -

NUCLEAR PLANT ENGINEERING DEPARTMENT Vice President-Nuclear Plant Encineerinn A. B. Cutter Office Services Staff Assistant-NPPE Supervisor Carol S. Garrison Zelma T. Ausley Manager-Director-Manager-Engineering Engineering Safety Rewlew liarris Plant Support, Nuclear Plants Nuclear Engineering Leonard I. Loflin Sam McManus Ralph L. Sanders d

i Project Engineer-Nuclear 5

a e) NUCLEAR PLANT CONSTRUCTION DEPARTMENT The Nuclear Plant Construction Department consists of the Vice President; two administrative units-Office Services and Administrative Staff; the Robinson i

Construction Manager; the Project General Manager (Harris); and the Manager, Construction Procurement and Contracting. The Department's objective is to construct the Shearon Harris Nuclear Power Plant and perform additions and modifications to existing facilities at the H. B. Robinson Steam Electric Plant in such a manner as to ensure the Company maximum quality, safety, and economical benefits and to meet scheduled in-service dates.

Robir. son Construction Management Section The Robinson Construction Manager has the mar;agement responsibility for construction and engineering for the Robinson generating facility as required to complete project assignments in a manner which minimizes impact on plant operations, keeps management informed, and meets all requirements.

Harris Site Management Section 4

The Harris Site Management Section has the responsibility for construction management of the Shearon Harris Nuclear Power Plant and for control of the constructor and various contractors who work on the site. The Section is headed by the Project General Manager with five subordinate units; Assistant Project General Management, Construction Services, Project Costs and Accounting, Project Analysis, and i

i Electrical Construction.

Construction Procurement and Contracting Section The objective of the Construction Procurement and Contracting Section is to plan, schedule, and control costs of materials and equipment used during construction or modification of nuclear, fossil, hydro, and internal combustion generating facilities for l

the Company; and to provide contracting services for all assigned construction projects.

The Section includes five Units which are responsible for expediting, site procurement, construction equipment, warehousing and material control, and contracting.

. i i.

i i

NUCLEAR PLANT CONSTRUCTION DEPARTMENT Nuclear Plant Construction Department Sheldon D. Smith Vice President 4

Staff Assistant Office Services Unit

~

Supervisor 3

i 4

flobinson Construction Harris Site Management Construction Procurement i

Management Section Section

& Contracting Section 4

Robinson Construction Project General 4

Manager Manager Manager i

j M. J. Reid R. M. Parsons S. N. llamilton 1

1 N) t f.

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RESPONSIBILITY ASSIGNMENTS All personnel, whether employees of or contractors to CP&L, are responsible for adhering to applicable NRC operating and administrative prceedures, rules, and regulations.

Specific line management responsible for ensuring adherence to these requirements is delegated to the Plant General Managers. This delegation of authority flows from a chain of command beginning with the Chairman / President and CEO and from there to the Executive Vice President - Power Supply and Engineering and Construction, then to the Senior Vice President - Power Supply, and then to the Vice President - Nuclear Operations Department. In the case of the Brunswick Plant, the delegation of authority flows after said Executive Vice President to the Vice President -

Brunswick Nuclear Project. The Plant General Managers of Robinson and Harris Plants report to the Vice President - Nuclear Operations. The Plant General Manager of the Brunswick Plant reports to the Vice-President - Brunswick Nuclear Project.

1-3. For each person who has occupied the position of Plant Manager at Robinson, Brunswick or Harris since January 1,1978, please provide that person's name, current position and address, and a statement of professional qualifications.

ANSWER l-3.

Robinson Plant Mr. R. B. Starkey, Jr.

Box 790 Hartsville, SC 29550 Mr. Starkey has occupied the position of Plant Manager (upgraded to Plant General Manager) at the Robinson Plar.t since 1977.

Mr. Starkey joined CP&L in 1973 after completing nine years of nuclear-related service in the United States Navy. He has ten years of engineering and management experience with CP&L. He has a Bachelor of Science Degree in Physics from Miami l

University in Oxford, Ohio.

l j l

Brunswick Plant Mr. C. R. Dietz Box 10429 Southport,'NC 28461 Mr. Dietz has occupied the position of Plant General Manager at the Brunswick Plant since 1981.

Mr. Dietz has over 20 years of nuclear-related experience. His experience includes 12 years with the General Electric Company where he served as Operations Manager for Start-Up Test Operations on two BWR nuclear plants including the Brunswick Plant. He also served as the Manager of Operator Training Services with the General Electric Company. He has a Bachelor of Science Degree in Chemical Engineering from Montana State College.

Mr. A. C. Tollison, Jr.

Box 1551 Raleigh, NC 27602 Mr. Tollison occupied the position of Plant Manager at the Brunswick Plant from December of 1976 through November of 1979. This position was upgraded to Plant General Manager in November of 1979, and Mr. Tollison occupied this position through January of 1981. Mr. Tollison is currently serving CP&L as the Assistant to the Manager of Technical Services.

Mr. Tollison joined CP&L in 1970 after completing six years of nuclear-related service in the United States Navy. He has 13 years of engineering and management experience with CP&L and served as the CP&L Company representative to the Institute of Nuclear Power Operations.

Ile has a Bachelor of Science Degree in Chemical Engineering from the University of South Carolina..

l 3

I 1

Harris Plant Mr. J. L. Willis Box 165 New Hill, NC 27562 Mr. Willis has occupied the position of Plant General Manager at the Harris Plant since April of 1982.

Mr. Willis joined CP&L in 1981 after completing 28 years of nuclear-related service in the United States Navy and two years of managerial experience in industry.

He has a Bachelor of Science Degree in Electrical Engineering from the United States Naval Academy.

Mr. H. R. Banks Box 1551 Raleigh, NC 27602 Mr. Banks occupied the position of Plant General Manager at the Harris Plant from November of 1979 through January of 1981. Mr. Banks is currently serving CP&L as Manager of the Corporate Quality Assurance Department.

Mr. Banks joined CP&L in 1968 after completing 20 years of service in the United I

States Navy. See response to 1-1.

The position of Plant General Manager at the Harris Plant was not occupied prior j

to November of 1979 or in the period between Mr. Bank's tenure and Mr. Willis' assignment.

1-4. Why was the decision made to create a separate Vice Presidentiallevel position to oversee the Brunswick Nuclear Plant?

ANSWER l-4.

The decision to establish a Vice Presidential position at the Brunswick site was made in order to achieve more control and closer coordination of scheduled major projects and plant modifications. Prior to this organizational change in September 1982, a satisfactory structure had been in place at the site to manage power generation opere.tions and to provide the necessary engineering and construction effort to support and improve these operations. Under this arrangement, each of the three major

functions of operations, engineering and construction reported, and were controlled, through separate channels to management located off site. In view of the increasing number, complexity, and interdependence of major engineering and construction projects and plant modifications (retubing the condensers in both units, for example), it became apparent that, to achieve optimum responsiveness, timeliness, and flexibility of effort, the majority of coordination functions and control decisions should be reassigned to the site level. Accordingly, the position of Vice President, Brunswick Nuclear Project, to be located at the site, was established to consolidate all operating and maintenance, engineering, and construction activities at the Brunswick Plant in order to facilitate coordination among these major functions and to expedite the decision-making process.

1-5. Identify any and all correspondence, memoranda, notes or minutes of meetings or any other documents which describe, discuss or otherwise refer to the background to and decision to create the position of Vice President-Brunswick Nuclear Project.

ANSWER 1-5.

Memorandum from Mr. E. E. Utley, Executive Vice President, CP&L, dated July 30, 1982, on the subject: " Brunswick Steam Electric Plant Operations Improvement Progra m."

CP&L presentation at a meeting between CP&L and NRC (Region 11) in Atlanta, Georgia, on August 24,1982.

Presentation of Mr. E. E. Utley, Executive Vice President, CP&L, to CP&L Board of Directors meeting on September 15,1982.

Remarks of Mr. John P. Jackson, Group Vice President, Management Analysis Company, for the CP&L Board of Directors meeting on September 15,1982.

CP&L presentation to the NRC (Region II) in Atlanta, Georgia, on November 10, j

1982.

l Management Study of Carolina Power & Light Company, conducted by Cresap,

. McCormick, and Paget, Inc., for the State of North Carolina Utilities Commission (dated December 15, 1982).

Prefiled direct testimony of Mr. L. W. Eury, Senior Vice President, CP&L, before the North Carolina Utilities Commission, Docket No. E-2, Sub 461 (June 1983).

Letter from Mr. E. E. Utley, Executive Vice President, CP&L, to Mr. R. C.

DeYoung, Director of the Office of Inspection and Enforcement, U.S. Nuclear l

Regulatory Commission, dated May 2,1983.

1-6. Identify and provide statements of professional qualifications for the Robinson i

• i i

s

Steam Generatror [ sic] Repair Project Team Manager, Project Construction Manager, the Manager-Corporate Quality Assurance and the Senior Engineer noted at page 22 of

" Applicant's Answers to The Hartsville Group First Set of Interrogatories and Requests to Produce *'(Applicant's Answers).

ANSWER l-6 Guy P. Beatty, Jr.

Robinson Steam Generator Repair Project Team Manager (see professional qualifications as set forth in ANSWER l-1)

Matthew J. Reid i

Robinson Construction Manager Education BS Degree in Mechanical Engineering - University of Rhode Island,1948.

Experience A.

February 1948 - June 1965 1.

ITT Grinnell Corporation a.

February 1948 - October 1953 - Field Superintendent / Engineer at Hartwell Company, Inc., East Providence, Rhode Island, b.

October 1953 - February 1956 - Operations Manager at Portsmouth, Ohio, AEC Gaseous Diffusion Project.

February 1956 - November 1959 - Project Manager at T. II. Allen c.

Generation Station, Memphis, Tennessee.

d.

November 1957 - June 1965 - Construction Manager at Industrial Piping Division, Providence, Rhode Island.

B.

June 1965 - June.' 970 1.

Kaminer Construction Corporation, Atlanta, Georgia

a. Vice President.

C.

June 1970 to August 1982 1.

ITT Grinnell Corporation June 1970 - January 1972 - Assistant Division Manager of Industrial Piping a.

Division, Providence, Rhode Island.

A b.

January 1972 - January 1973 - President of Hartwell Company, East Providence, Rhode Island, c.

January 1973 - August 1982 - Vice President, Director of Construction at Industrial Piping Division in Kernersville, North Carolina.

D.

August 23,1982 - Present 1.

Carolina Power & Light Company a.

August 23, 1982 - Project Construction Manager (Robinson) in the Brunswick & Robinson Site Management Section of the Nuclear Plant Construction Department. Located at the Robinson site, Hartsville, SC.

b.

March 5,1983 - Promoted to Robinson Construction Manager in the Robinson Construction Management Section of the Nuclear Plant Construction Department. Located at the Robinson Plant, Hartsville, S C.

Harold R. Banks Manager - Corporate Quality Assurance (see professional qualifications as set forth in ANSWER l-1)

Richard L. Miller

" Senior Engineer *', now Project Engineer - Mechanical Education BS Degree in Mechanical Engineering from North Carolina State University - 1977 Experience A.

May 1977 - November 1977 1.

Goodyear Tire and Rubber Company, Akron, Ohio a.

Design engineer.

B.

November 1977 - November 1979 1.

Westinghouse Electric Corporation, Charlotte, North Carolina a.

Field service engineer, supervised and directed inspection of turbine

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a 3 N generators, boiler feed pumhturbines, and r9 actor coolant pump motors.

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C.

December 17,1979 - Present 1.

Carolina Power & Light Companys a.

December 17, 1979 - Employed as Engineer in the Harris Site Constructkbny Department.

Management Section of the Power Plant Located at liarris Site, New Hill, North Carolina.

b.

March 7,

1981 - Transferre4 ' to the Brunswick'd Itobinson Site Management Section of the Nuclear Plant Construction Department.

Located at the Robinson Site, Hartsville, SC.

c.

December 26, 1981 - Promoted to Senior Engineer in th'e Brunswick &

Robinson Site Management Section of;the Nuclear Plant Construction Department. Located at the H. H. Robinson site, Hartsville, SC.

d.

September 1982 to March 1983 - Loaned to FP&L, Turkey Point, to perform as a " Hands on'IArea Supervisor for the Turkey Polni Unit Noi 4 Steam Genera' tor I epair.

2 e.

July 7,

1983 - Promoted to Project Engineer in the sRobins6n q,.c Construction Management Section of the Nuclear Plant Construction Department. Located at the H. B. Robinson site, Hartsville, SC.

1-7. Describe in detail the procedure for the Corporate Health Physics assessments of the health physics programs identified in response to Interrogatory 1-11 of the Erior set of Intervenor's Interrogatories (Applicant's Answers, p. 25).

ANSWER 1-7. A Corporate Nuclear Safety & Research Department Procedure has-A been developed to detail the activities associated with Corporate Health _ Physics

~

assessments of the health physics programs at the operating nuclear plants.

The procedure, entitled " Procedure for Corporate Health Physics'Section Assessments of Health Physics Programs," describes the methods for performing assessments of nuclear plant health physics programs and special assessments of health physics related activities. Periodic assessments are made of the various aspects of the operating nuclear

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plant health physics programs to assbb the effectiveness of the programs in meeting NRC rules and regulations and good health physics practices.

s The assessments of the operating nuclear plants health physics programs are conducted periodically throughout the year based on a topical breakdown of key areas of the health physics programs.

The primary thrust of this effort is to assure the effectiveness of the health physics programs and to utilize information obtained in the assessments to make recommendations for improvements in the health physics programs.

1-8. Please provide a copy of the procedure referenced in Interrogatory 1-7, above.

ANSWER l-8.

A copy of.the Corporate Health Physics assessment procedure is available for inspection and copying by the Ilartsville Group at CP&L's General Office in j

Raleigh, N.C.

- e 1-9.

Please provide to Intervenors or make available for copying a copy of the Corporate Quality Assurance Program Manual, Revision 4 (Blue Book) or any more recent c,

, ' revision thereof.

ANSWER l-9. Applicant will make said manual available to the flartsville Group for A

copying at CP&L's General Office in Raleigh, N.C.

1-10. Describe in detail the General Employee Training program.

ANSWER l-10.

Currently in operation at the II.B. Robinson Plant is a general employee training (badging) course. This course is designed to provide each CP&L employee, contract empoyee, and visitor with the basic knowledge of safety, security, radiation protection, and appropriate emergency actions that each individualis expected to perform at CP&L's nuclear facilities. This course consists of 11 instructional modules and takes about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to complete. The instructional modules for this course are:

1.

Introduction to General Employee Training 2.

Types and Sources of Radiation r

3.

Biological Effects of Radiation 4.

'htdiation Dose Limits and Protection 5.

Personal Radiation Protection l

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6.

Workers' Rights 7.

Plant Security and Emergency Actions

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8.

Fire Protection, Clearance

Tegs, Independent Verification, Quality Performance, and Good liousekeeping 9.,

Plant Communications Systems i

~16.

Radiation Areas Contamination and RWPs I

11.

L otective Clothing and Radiation Monitoring Efforts are cure,cptly underway to restructure the current general employee

+

training (pdging) course and implement a General Employee Training Level I - Plant Indoctrinatio[n Course and a General Employee Training Level II - Radiation Protection y

t Course. The restructured General Employee Training Level ! Course will be designed to

~

provide basic knowledge of the nonradiation protection subjects such as plant description, l

industrial safety, quality assurance, quality control, and plant security. The General j

Employee Training Level II - Radiation Protection Course will be designed to provide basic knowledge and skills in the areas of radiation protection such as types and sources of radiation, biological effects of radiation, radiation dose limits / dosimetry, radiation protection, workers' rights, portable radiation detection instruments, radiation and contamination areas, radiation work permit, respiratory protection, emergency actions, protective clothing, and personnel monitoring. The General Employee Training LevelII-Radiation Protection Course is being structured to coincide with the Institute of Nuclear Power Operation's guidelines for general employee training. This restructure of General Employee Training is targeted to be completed in 1983.

A General Employee Training LevelIII-Radiation Protection Application Course is being taught at the II.B. Robinson Plant.

This course, vthich exceeds regulatory requirements, is designed to provide additional knowledge of biological effects, radiation exposure, radiation dose limits and rules, radiation exposure control, radiation detection theory, radiation monitoring, survey and records requirements, radioactive waste disposal, respiratory protection, and basic nuclear power plant systems, emphasizing

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radiation protection. This course was implemented at the II.B. Robinson in July 1983 and is being offered to personnel in cupervisory and key-lead roles.

Efforts are continuing to be made to revise and upgrade general employee training at our nuclear plants to meet new regulate:'y requirements and the needs of personnel working at our nuclear facilities.

1-11. What is the documentary basis for your response to Interrogatory 1-10?

ANSWER l-11.

A.

Carolina Power & Light Company, Nuclear Training Section, General Employee Training Manual LevelI-Badging, Revision 3, April 27,1983.

B.

Memorandum to Mr. B. J. Furr and Mr. P. W. Ilowe from Mr. J. R. Boha: mon, Jr.

Serial:

NO-83-il924.

File:

NTS-4204(I).

Subject:

Concurrence on Restructured General Employee Training Levels.

C.

Memorandum to Mr. L. W. Eury from Mr. B. J. Furr dated July 13, 1983.

Subject:

GET Level III Training.

1-12.

Please provide to Intervenors or make available for copying the Nuclear Training Section General Employee Training Manual, lesson plans, textbooks, and any other materials employed in the General Employee Training program.

ANSWER l-12.

The General Employee Training materials are available for inspection and copying at CP&L's General Office in Raleigh, NC.

1-13.

Describe in detail the difference in job functions and qualifications of a Quality Assurance Technician and a Quality Assurance Specialist.

ANSWER l-13. The QA/QC Specialist is a professional or exempt classification.

The Specialist is a knowledgeable and experienced individual who performs a specifie quality assurance function such as surveillance, inspection and documentation. The Specialist, by virtue of professional classification, may be required to assist in resolution of highly technical or unique plant problems. This function requires frequent interfacing with personnel in other plo.t organizations.

The QA/QC Technician is a non-professional or non-exempt classification. The QA/QC Technician is a qualified inspector, by virtue of training and testing, in one or more of the following inspection disciplines: civil, mechanical, welding, nondestructive testing, electrical, material receiving, or documentation.

The technician receives inspection assignments from, and is monitored by, the QA/QC Specialist. The inspection t

work is performed according to prescribed codes and standards.

4 1-14. What records does CP & L maintain at a) the Corporate level and b) at the site level with respect to disciplinary actions taken wispect [ sic] to CP & L employees or contractor or subcontractor employees with regards to non-compliance with NRC operating and administrative rules, regulations and procedures?

ANSWER l-14. a) Records are not maintained at the corporate level relative for all disciplinary actions. b) Documentation of disciplinary actions involving significant NRC 4

non-compliances is normally maintained in personnel files on site for CP&L employees.

1-15. Identify by name and provide the professional qualifications of the following persons:

a) Site Personnel Director - Robinson b) Site Director of Quality Assurance - Robinson c) the " representative of the Manager of Construction" referenced at p. 34, Applicant's Answers 4

d) Site Personnel Director -Ilarris

~

e) Site Manager of Quality Assurance and Quality Control-Ilarris f) Construction Site General Manager - Harris g) Site Persionnel[ sic] Director - Brunswick h) Site Director of Quality Assurance and Quality Control-Brunswick.

ANSWER l-15.

a)

Magie E. Fishburne Dircetor Personnel Relations II. B. Robinson Nuclear Plant Eleven (11) years experience in the educational field, which included positions as Field Representative, English Teacher, Assistant Director of Admissions, and Director of l

Admissions. Ten (10) years experience with CP&L which includes four (4) years as Recruitment Representative, four (4) years as an Assistant Personnel Representative -

Northern Division, and two (2) years experience as Director - Personnel Relations, Robinson Nuclear Plant. B/S English and Masters Education Administration.

b) liarry Joseph Young Director - QA/QC - Robinson Plant Education & Training A.

University of South Carolina - One Year - 1964.

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B.

Nondestructive Testing Qualifications held:

1.

Liquid Penetrant - Level II 2.

Magnetic Particle - Level 11 3.

Radiography - Level II Experience l

A.

E. I. DuPont, Aiken, SC.

t 1.

February 1955 - March 1967 i

a.

Laboratory Technician / Chemist Assistant.

I i

B.

Walker Laboratories - Columbia, SC.

1.

May 1967 -September 1967 a.

Testing / Inspecting Engineer.

C.

Duke Power Compamy - Seneca, SC.

i

]

1.

September 1967 - July 1968 i

]

a.

A*' Inspec tor.

4 D.

Grinnell Company, Inc. - Providence, R.I.

4 l

1.

August 1968 - September 1969 a.

Radiographer / Quality Assurance Technician.

E.

B. F. Shaw Company - Laurens, SC.

1.

October 1969 - October 1971 a.

Chief Radiographer /NDT Lab Supervisor.

F.

Daniel Construction Company - Barnwell, SC.

i j

1.

November 1971 - March 1973 l.

a.

Lead Quality Control Welding Inspector.

G.

Carolina Power & Light Company i

1.

March 1973 employed as a Senior Quality Control Specialist-Construction in the Quality Assurance Section of the Power Plant Engineering & Construction Department, located at the Shearon liarris Nuclear Power Plant, New flill, N C.

a.

October 1973-transferred from Power Plant Engineering & Construction Departmer.t to Power Plant Construction Department, Quality Assurance Section, located at the liarris Plant.

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b.

November 1976-transferred to the Technical Services Department, Senior Quality Control Specialist, Engineering & Construction Quality Assurance Section, located at the Harris Plant.

c.

November 1978-promoted to Project QA Specialist in the Engineering &

Construction QA Section, Technical Scrvices Department, Mayo /Roxboro Construction QA, located at Person County, NC.

d.

March 1981-promoted to Director-Quality Assurance / Quality Control-Operating Nuclear Plants at the H. B. Robinson Steam Electric Plant in the Operations Quality Assurance Quality Control Section of the Corporate Quality Assurance Department at Hartsville, SC.

i e.

March 1983-title changed to Director - QA/QC - Robinson Plant in the QA/QC

- Brunswick and Robinson Plants Section of the Corporate Quality Assurance 2

l Department located at the Rabinson Plant, Hertsville, SC.

e c)

Debocah W. Martin Senior Clerk I

Approximately twelve (12) years office experience. One and one-half (1-1/2) years clerical experience with construction company working on-site at the H. B. Robinson Nuclear Plant. One and one-half (1-1/2) years experience with CP&L. Duties consist of clerical responsibilities in the Office of Manager - Construction, H. B. Robinson Nuclear Plant.

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d) John D. Ferguson l

Director Personnel Relations Harris Nuclear Plant Five (5) years military experience (U. S. Army-Captain). Approximately six (6) l 1

years experience with CP&L which includes four (4) years as a Technical Recruiter, two (2) years as Assistant Personnel Representative for the Central Division which included the liarris Nuclear Plant Site. B/S Degree in Engineering.

4 e

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Nathaniel J. Chiangi Manager - Quality Assurance / Quality Control Harris Plant Education & Training A.

Graduate of Norwich Free Academy, Norwich, Connecticut.

I

• B.

Special Schools: Nuclear Submarine Systems, Navyships 250-1500-1, Mil Std 271 D -

271A, Navyships 250-693-3 (Structural), IIcalth Physics Monitoring, Management Schools-Electric Boat Company, Electronics School-U.S. Navy, Welding School-EBC, Radiography School, Magnetic Particle Testing School-EBC, Liquid Penetrant Test School-EBC, Ultra Sonic Testing Classes-EBC, Eastman Kodak School for Automatic Film Processing Equipment, Job Cost Estimating-EBC.

C.

Qualified: AEC Licensed Radiographer and Radiographer Supervisor.

Professional Societies A.

ASNT - ASME.

B.

Qualified ANST - Level III - 2/4/77 Radiographic - Magnetic Particle - Liquid Penetrant.

C.

Professional Engineer - State of California - January 1977 Experience A.

U. S. Navy 1.

1947 - 1952 a.

Sonar Man - Radar Man.

B.

Electric Boat Company, Groton, CT 1.

1952 - 1967 a.

Welding-Field Work-Piping-Structural.

b.

1954-1967 - Lead Supervisor - Radiography Department.

C.

Ebasco Services, Inc., New York, NY 1.

1967 - 1973 a.

Quality Compliance-Quality Control Supervisor.

b.

1970-1972 - Site Quality Compliance Supervisor.

c.

1972 - October 1973 - Senior Quality Compliance Engineer.

D.

Carolina Power & Light Company 1.

October 1973 to Present a.

October 1973 - Employed as Quality Assurance Manager-Construction in the Quality Assurance Section of the Power Plant Construction Department. Located in the General Office.

b.

November 1976 - Transferred and promoted to Manager-Engineering &

Construction Quality Assurance Section of the Technical Services i

Department. Located in the General Office.

c.

March 1981 - Transferred and reclassified as Manager Engineering &

Construction Quality Assurance / Quality Control in the Engineering &

Construction Quality Assurance / Quality Control Section of the Corporate Quality Assurance Department.

Located in the General Office.

d.

March 1983 - Transferred as Manager - Quality Assurance Quality Control llarris Plant Section of the Corporate Quality Assurance Department located at the liarris site, New Ifill, NC.

f)

Roland M. Parsons Project General Manager - Ilarris Education BS Degree in Civil Engineering from Fresno State College,1959.

Professional Societies A.

American Society of Civil Engineers.

B.

Registered Professional Engineer in North Carolina - January 20,1977.

Exoerience A.

August 1964 to November 1966 1.

U. S. Forest Service, Neveda City, California a.

Forest service representative on hydroelectric developments built on forest service land by others.

B.

November 1966 to September 1973 1.

Ebasco Serveies, Inc., liartsville, South Carolina; and Jensen Beach, Florida a.

November 1966 - Field Engineer on construction of II. B. Robinson Unit No.2.

b.

November 1967 - Resident Engineer responsible for site engineering and quality control for construction of II. B. Robinson Unit 2.

c.

April 1971 - Senior Resident Engineer responsible for all site engineering for construction of St. Lucie Unit No.1. (810 MW combustion engineering PWR nuclear power plant).

C.

September 1973 to May 1974 1.

Daniel Construction, Jenkinsville, SC.

1 a.

Site Manager of Engineering responsible for all site engineering for construction of V. G. Summer Nuclear Power Plant.

D.

June 1974 to September 1976 1.

Ebasco Services, Elma, Washington s.

Senior Resident Engineer responsible for all site engineering on 1300 MW PWR nucleer power plant.

E.

September 20,1976 to Present 1.

Carolina Power & Light Company a.

September 20, 1976 - Employed as Site Manager in the Nuclear Construction Section of the Power Plant Construction Department.

Located at the Harris site, New liill, NC.

b.

April 27,1979 - Reclassified as Site Manager (Harris)in the Harris Site Management Section of the Power Plant Construction Department.

c.

May 3,1980 - Reclassified as Site Manager - Harris Plant Construction in the Harris Site Management Section of the Power Plant Construction Department.

d.

January 31, 1981 - Reorganization - Site Manager - Ilarris Plant in the Harris Site Management Section of the Nuclear Plant Construction Department.

e.

March 22,1982 -Title changed to Project General Manager.

g)

Marlie Steve Choplin Director Personnel Relations Brunswick Nuclear Plant Seven (7) years experience with CP&L, which includes three (3) years in office supervision, two (2) years Assistant Personnel Representative for the Eastern Division, and two (2) years as Personnel Representative for the Brunswick Nuclear Plant. B/A Degree in Accounting.

e r

h)

Larry Edward Jones Director - QA/QC - Brunswick Plant Education & Training BS Degree in Metallurgical Engineering from University of Missouri at Rolla,1967..

?

-n-e- - ~.

---r-en.-w.,-

,,--.,,,n,.,v.,.

n,

.-n,

,,~, - - -, -,

.,..---m--

,,-~,,,,.,,.. ~,., - - ~ -,..

Professional Societies A.

American Society for Nondestructive Testing (ASNT),

B.

Licensed Professional Engineer, State of California, August 1978 Experience A.

ITT Telecommunications 1.

1966 (summer) a.

Quality Control Lab Technician.

B.

Newport News Shipbuilding and Drydock Company 1.

1967 to 1972 a.

Quality Control Engineer, C.

Carolina Power & Light Company 1.

July 31,1972 to present a.

Employed as a Quality Surveillance Specialist - Engineering in the Quality Assurance Section of the Power Plant Engineering Department located in the General Office.

b.

February 2,1974 - Promoted to Senior Quality Assurance Engineer in the QA Section of the Power Plant Engineering Department located in the General Office.

c.

October 25, 1975 - Promoted to Project Quality Assurance Engineer in the Quality Assurance Section of the Power Plant Engineering Department located in the General Office.

d.

November 1976 - Transferred as a Project Quality Assurance Engineer in the Engineering & Construction Quality Assurance Section of the Technical Services Department located in the General Office.

e.

February 4,1977 - Promoted to Principal QA Engineer in the Engineering

& Construction QA Section of the Technical Services Department located in the General Office.

f.

March 7, 1981 - Transferred as a Principal QA Engineer in the Engineering & Construction Quality Assurance / Quality Control Section of the Corporate Quality Assurance Department located in the General Office.

g.

March 5,

1983 - Transferred and promoted to Director-Quality Assurance / Quality Control - Brunswick Plant in the QA/QC - Brunswick and Robinson Plants Section of the Corporate Quality Assurance Department located at the Brunswick Plant, Southport, NC.

l t

l B.

INTERROGATORIES RELATING TO HARTSVILLE CONTENTION 3 i

3-1.

How many Westinghouse Model 44 steam generators have experienced significant degradation of tubes resulting in tube leaks?

]

ANSWER 3-1. Steam generator leaks exceeding Tech Spee limits which necessitated j

a plant shutdown are listed in the NRC Grey Book statistics.

1 3-2.

Identify each reactor employing Westinghouse Model 44 steam generators which has experienced tube leaks.

ANSWER 3-2.

4 1

Ginna l

l Point Beach 1 and 2 Turkey Point 3 and 4 Indian Point 2 and 3 H. B. Robinson 3-3.

What data do you possess on the frequency and severity of tube leaks in reactors equipped with Westinghouse Model 44 steam generators?

3 ANSWER 3-3. None, other than that which CP&L possesses for H. B. Robinson 2 as shown in response to Interrogatory 3-10 of this set. See NRC Grey Book statistics and l

NUREG-0886 for further data on Model 44 steam generators.

3-4. What are the bases for your responses to Interrogatories 3-1 through 3-3?

l ANSWER 3-4.

NUREG-0886 " Steam Generator Tube Experience' NRC Grey Book Statistics thru November 1981 (NUREG-0020) j 3-5. How many tube ruptures have occured [ sic] at reactors employing Westinghouse i

Model 44 steam generators?

ANSWER 3-5. See NUREGs 0651 and 0909.

3-6. At which reactors employing Westinghouse Model 44 steam generators, have:

a) steam generator tubes been plugged;

• I I

=. - _ -.

4 b) steam generator tubes been sleeved; or, c) lower steam generator assemblies been replaced?

ANSWER 3-6. See NUREG-0886.

3-7.

Identify any additional reactors employing Westinghouse Model 44 steam generators where the operators or owners anticipate:

a) plugging steam generator tubes; b) sleeving steam generator tubes; or, c) replacing the lower steam generator assemblies.

4 ANSWER 3-7.

1 a)

All.

b)

Unknown.

c)

H. B. Robinson.

Point Beach 1.

3-8. What are the bases for your responses to Interrogatories 3-5 through 3-7?

ANSWER 3-8.

NUREG-0886 N UREG-0651 NUREG-0909 Steam Generator Sleeve Test Program, R. E. Ginna Nuclear Power Plant (Non-proprietary Report) prepared by Babcock and Wilcox.

3-9.

How many leaks have been experienced in the steam generator tubes in Robinson 2?

ANSWER 3-9. 22.

3-10. For each instance of leaking steam generator tubes at Robinson 2, identify the date of the occurence [ sic], the leakage rate, and the cause of the leakage.

ANSWER 3-10.

l l.

...,.,,_.-.-.-..,-,,g-,-+.n

,,,,w _ --

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i

-l Date Leak Rate No. of Leaking Tubes 5/14/72 12.00 GPM 1

11/22/73 4.18 GPM 1

.9/21/78 0.62 GPM 2

4/11/79 0.38 GPM 6

6/11/79 Assumed 7 0.35 GPM 1

3/14/80 0.15 GPM 3

4/13/80 0.50 GPM 1

7/7/80 0.32 GPM 1

7/30/81 0.30 GPM 3

11/20/81 1.50 GPM 1

4/83 0.31 GPM 2

All steam generator tube leaks are believed to be a result of corrosion related phenomena. A specific cause for each leakage instance cannot be determined without a metallographic examination of each affected tube.

3-11.

Is Applicant aware of any litigation in which its supplier Westinghouse is involved in which it has been alleged that there have been defects or deficiencies in the design, manufacture or operation of Westinghouse steam generators?

ANSWER 3-11. Yes.

3-12.

If the answer to Interrogatory 3-11 is affirmative, identify each such litigation, the parties involved, and the allegations made.

ANSWER 3-12. The only litigation that Applicant is aware of is an action filed in the U. S. District Court (Southern District of Florida). Case No.: 78-1896-Civ-CA entitled " Florida Power & Light Company v. Westinghouse Electric Corporation." The complaint sets forth the allegations made.

3-13.

What are the bases for your responses to Interrogatories 3-11 and 3-12?

Identify all documents, testimony or oral statements by any person upon which you rely in support of your position.

l l

ANSWER 3-13. A copy of the Complaint for Damages filed in the litigation referred l

to in response 3-12 above.

i 3-14. Has CP & L made any written or verbal complaints to Westinghouse regarding the adequacy of the design, manufacture or operation of any steam generators provided to or currently on order by CP & L from Westinghouse?

ANSWER 3-14. Yes.

3-15. If the answer to Interrogatory 3-14 is affirmative, describe in detail each such complaint..

6

-~

ANSWER 3-15. (1)

Nonconformance report for not following procedures and errors on mill test report.

(2)

Nonconformance report on errors in weld procedure.

(3)

Nonconformance report for not following specific procedure and dropping tubesheet.

(4)

Nonconformance report on steam generator tubing.

(5)

Nonconformance report on mill test reports.

(6)

Nonconformance report on UT machine out of calibration.

NOTE: The SHNPP steam generators are Model D4, one of three Westinghouse "counterflow" steam generator models. Sincts February 1982, CP&L management and engineering personnel have worked closely with Westinghouse during the resolution of flow induced tube vibration problems identified first in " split flow" and later in "counterflow" steam generators. CP&L's activities have included:

Participation in Westinghouse's Customer Working Group Meetings.

Participation with five other utilities, in the counterflow Steam Generator Owners Review Group in an independent evaluation of Westinghouse's proposed modifications to counterflow steam generators.

Review of technical issues through presentations by Westinghouse to CP&L management and engineering personnel.

CP&L requested Westinghouse's formal recommendation for proposed modifications to the SHNPP steam generators in May 1983; received the recommendation in June 1983; endorsed the Oy:ners Review Group evaluation of the proposed modifications presented to the NRC in July 1983 and formally accepted the proposed modification in Augun 1983.

3-16.

What are the bases for your responses to Interrogatories 3-15 and 3-16?

Identify all documents, testimony or oral statements by any person upon which you rely in support of your position.

ANSWER 3-16. Letters from CP&L to Westinghouse (1)

CP&L letter EO-00892 dated 2/7/83 (2)

CP&L letter EO-Oll83 dated 4/25/83

• l

d (3)

CP&L letter EW-3 dated S/4/83 (4)

CP&L letter EW-9 dated 5/23/83 (5)

CP&L letter EW-25 dated 7/26/83 (6)

CP&L letter EW-28 dated 8/5/83 3-17. Has CP & L filed suit against Westinghouse with respect to the operation, non-operation, or recovery of costs for defects, deficiencies, or failures of Westinghouse steam generators?

I ANSWER 3-17. No.

3-18.

Does CP & L contemplate suing Westinghouse with respect to any matter related to steam generators?

ANSWER 3-18. Not at this time.

3-19. What are the bases for your responses to Interrogatories 3-17 and 3-18?

ANSWER 3-19. No answer required.

3-20. Please provide a copy of the " estimated / cash flow" referred to in response to l

Interrogatory 3-95 of Intervenor's first set of interrogatories.

ANSWER 3-20. The budget documents from which the " estimate / cash flow" referred to in response to Interrogatory 3-95 of the first set of interrogatories was taken are a

)

part of the Company's work papers requested in this second set of intecrogatories. These work papers will be made available to the Hartsville Gropp for inspection and copying in CP&L's General Office in Raleigh, NC. The data provided on these budget documents are reflected on Attachment 3-89 of the first set.

3-21. Please provide a copy of the 1983 construction budget, as approved, referred to in Applicant's Answer to Interrogatory 3-95.

i ANSWER 3-21. As stated in response to the preceding Interrogatory (3-20) of the second set, CP&L's 1983 construction budget documents regarding the Robinson 2 steam generator replacement, as referred to in CP&L's response to Interrogatory 3-95 of the t

first set, are part of the work papers which will be made available to the Hartsville Group for inspection and copying.

The following questions refer to Applicant Responses to NRC staff requests 1-10, i

supplied by S. R. Zimmerman under a cover letter dated July 14, 1983.

l

• l

_. ~., -,,.. _

3-22. With respect to Staff Request 1, the cost of replacing the Robinson 2 steam generator lower assemblies (SLG A's) is estimated as follows:

Labor.

37,485,000 Equipment 37,161,000 Other 31,027,000 Total 105,673,000 It is also stated that because of (a) contractual agreements and (b) support modifications already performed, "a

commitment has already been made for approximately $67 million of the $105,673,000 total cost.'

a)

Please disaggregate the estimate of "other costs' into overheads, contingency funds, AFUDC, and miscellaneous, b) Please disaggregate the $105,673,000 according to the following table:

Contractually Performed Not Committed Modifications Committed Total Labor x

x x

x Equipment x

x x

x Overheads x

x x

x Contingency x

x x

x AFUDC x

x x

x Miscellaneous x

x x

x Total x

x x

$ 105,673,000 If the table cannot be accurately completed, please provide best current estimates and indicate which entries are so estimated.

d l

ANSWER 3-22. Standard definitions for all of the breakdown categories requested do not exist and CP&L does not use all of these categories. However, for purposes of l

responding to this interrogatory, CP&L has made the following breakdowns of the cost estimates, a) The following table provides the breakdown of "other costs"into overheads, I

l contingency funds, AFUDC, and miscellaneous costs:

l Cost ($)

Overhead 12,681,000 Contingency Fund 8,932,000 AFUDC 9,010,000 Miscellaneous 404,000 l

Total 31,027,000 b)

The following table provides a breakdown of the $105,673,000 cost l '

estimate.

The assumed decision date for determining whether to proceed with the proposed replacement plan or to retire the unit at the end of 1984 was January 1,1984.

Therefore, the following breakdown is provided with respect to that date.

ESTIMATED BREAKDOWN AS OF 1/1/84(I)

(BASED ON 1983 CONSTRUCTION BUDGET)

(C00's $)

Performed Contractually Not Modifications Committed Committed Thru As Of As 01) 1/1/849 Total 1/1/84 1/1/84 Labor 15,229 1,954 20,302 37,485 Equipment 34,676 2,100 385 37,161 Overheads 4,640 8,041 12,681 Contingency 4,735 4,197 8,932 AFUDC 3,116 5,894 9,010 Miscellaneous 404 404 Total 62,800 4,054 38,819 105,673 (1)

All of the above expenditures are projected estimates as of January 1, 1984.

(2)

If work is stopped January 1,1984, a portion of this noncommitted cost will be incurred in the demobilization of the jobsite.

3-23. With respect to Staff Request 1, please supply all workpapers, including bbut

[ sic] not limited to the inputs and outputs of production costing models, used in developing the $41 million estimate of replacement power costs.

ANSWER 3-23.

The workpapers used as the basis for calculating the $41 million estimate of replacement power costs will be made available to the llartsville Group for inspection and copying at the CP&L General Office in Raleigh, NC.

3-24.

With respect to Staff Request 2, the cost comparison of sleeving and the proposed plan appears to consider only capital costs.

a)

Is this true?

b) is it accurate to assume that any non-capital costs savings under the sleeving plan would not be sufficient to offset the greater replacement power costs?

c)

Please provide workpapers showing the development of both the nominal and present value cost comparison.

ANSWER 3-24. See objections of counsel.

3-25. With respect to Staff Request 3, explain why a fifteen year study period (1984 through 1998) was chosea.

ANSWER 3-25. The 15-year study period (1984 through 1998) was chosen for two basic reasons: 1) that time period was considered long enough to reflect the effect of the steam generator repairs and payback period and to show the effects of retiring Robinson 2 on December 31,1984, and 2) the use of any longer period would require increasingly speculative assumptions regarding costs and other data necessary for such calculations. It is not anticipated that the cost trends or conclusions resulting from the 15-year study would change if a longer study period were used.

3-26. With respect to Staff Request 3, is Robinson 2 to be retired in 1998?

ANSWER 3-26. No. CP&L currently has no plans to retire Robinson 2. The current operating license does not expire until 2007, and it is anticipated that the unit will operate at least until that time.

3-27. If the answer to Interrogatory 3-26 is negative, please provide estimates of the following plant-related costs from 1998 to retirement:

a) Fuel b) Spent fuel disposal c) Operation and Maintenance d) Additional capital costs e) Decommissioning cost f) Nuclear insurance cost g) Property taxes h) Other costs (explain)

ANSWER 3-27. No estimates have been made of the data requested for the period i

1998 to retirement. As stated in respose to the proceeding Interrogatory (3-26) of this set, CP&L currently has no plans to retire the Unit.

3-28. With respect to Staff Request 3, please provide outputs of the production cost simulations for Alternatives (1) and (2) on an annual basis.

ANSWER 3-28. In response to Interrogatory 3-127 of the first set, CP&L provided annual outputs of the production cost simulation for Alternative (1). Attached hereto is -28 of this set which provides similar outputs for Alternative (2).

3-29. With respect to Staff Request 3, please provide copies of allinput assumptions for the simulations referred to in Interrogatory 3-28 above.

ANSWER 3-29. In response to Interrogatories 3-126 and 3-127 of the first set, CP&L provided basic input information to the production cost simulation model for Alternative (1). Most of the inputs for Alternatives (1) and (2) are essentially the same except for the status of Robinson 2 in Alternative (2).

Chsinges in the input information as necessary for Alternate (2) are provided in the attached Attachment 3-29 of this set.

Some types of input assumptions (such as maintenance schedules and capacity factors) can be found on the output reports, as provided in CP&L's response to Interrogatories 3-127 of the first set and 3-28 of this set.

• i

3-30.

With respect to Staff Request 3, please provide operating capacity factor, scheduled outage periods, actual capacity factor, and energy generation for Robinson Unit 2:

a) Annually, based on historic experience from commercial operation through 1982; b) Annually, based on projections, from 1984 until decommissioning.

ANSWER 3-30.

a) Data for the above request is provided in the following table. Robinson Unit 2 was declared commercial on March 7,1971. Scheduled outage periods for 1971-1975 are not readily available; therefore, we have included only those from 1976-1982.

Also, operating capacity factors reflect forced outages only and do not include the effect of scheduled outages. CP&L uses operating capacity factors primarily as a planning tool and, therefore, such numbers are not calculated on a historical basis.

l 1

i i

• IIISTORICAL OPERATING DATA FOR ROBINSON 2 Scheduled Outages Annual Energy Duration Capacity Factor Generation Year Dates (liours: Minutes)

(percent)

(GWii) l 1971 46.9%*

2,233.5**

1972 80.2 %

4,828.6 1973 60,1 %

3,763.6 1974 82.6 %

4,813.2 1975 71.5%

4,167.5 1976 7/9 7/12 49:02 83.4 %

4,871.6 8/7 8/7 08:04 10/2 10/2 14:25 10/30 - 12/12 1039:49 12/18 - 12/19 22.23 1977 3/25 3/27 26:03 72.6 %

4,230.4 6/17 6/18 21:16 9/29 9/30 09:54 1978 2/1 4/23 1941:24 68.2%

3,973.7 1979 4/18 7/21 2277:21 F8.5%

3,992.4 9/4 9/5 23:48 11/2 11/3 11:47 1980 3/14 3/28 321:32 54.6 %

3,191.1 8/8 - 10/25 1850:42 10/25 10/25 02:19 11/10 18:33 11/15 1981 5/16 -

6/11 641:01 60.1 %

3,503.8 9/28 -

9/28 02:28 11/16 - 11/19 309:47 12/6 -

12/6 11:01 1982 2/26 8/15 4070:42 38.7 %

2,251.8 8/22 -

8/24 32:111 8/25 -

8/25 00:14 10/22 10/24 30:08

• 1971 Capacity factor was calculated from a figure based on net generation since date of commercial operation. Test generation is not included.

• • The 1971 generation figure includes net generation since actual date of commercial operation (March 7,1971). Test generation is not included.

b) This information is taken from the computer output made for Alternative (1) as provided in CP&L's response to Interrogatory 3-127 of the first set. This i

informstion is not available through decommissioning for reasons stated in response to Interrogatory 3-26 of this second set.

PROJECTED DATA FOR ROBINSON 2 BASED ON PROPOSED REPLACEMENT PLAN Operating

• Annual **

Energy Capacity Capacity Generation Year Factor (Percent)

Scheduled Outages Factor (Percent)

(GWil) 1984 85 1/21 - 11/16 15 878.7 1985 85 10/19 - 12/31 69 4045.0 1986 85 1/1 - 1/31 80 4660.0 1987 85 1/31 - 5/15 62 3611.4 1988 85 7/16 - 10/28 63 3671.7 1989 85 88 5103.3 1990 85 1/1 - 4/1 65 3804.5 1991 85 6/3 -

9/1 66 3866.3 1992 85 11/2 - 12/31 73 4259.9 1993 85 1/1 - 1/31 80 4660.6 1994 85 4/4 -

7/7 66 3850.4 1995 85 9/4 - 12/3 66 3824.4 1996 85 88 5117.6 1997 85 2/3 -

5/4 65 3806.7 1998 85 7/6 - 10/4 66 3867.0

• Operating capacity factor reflects forced outages only, not scheduled outages. These capacity factors are based on a 665 MW summer and a 700 MW winter rating for Robinson 2.

• • Based on a 665 MW rating for Robinson 2 and projected annual energy generation.

3-31. With reference to Staff Request 3, please provide the following information concerning Alternate (1), Replacement of Steam Generator Lower Assemblies in 1984.

• a) Please define the first column shown on page 8, i.e. total annual revenue requirements under alternative (1).

b) For capital costs included under alternative 1, please provide annual capital expenditures, the impact of those expenditures on annual revenue requirements, and any and all workpapers and/or computer printouts used to translate investments into revenue requirements.

c) Please provide all data and assumptions used to make the above-cited translation. This should include assumptions concerning cost of capital (by component) capital structure, investment tax credits, deferred income taxes, depreciation for tax and book purposes; calculation of the rate base contribution of the investment, federal income tax, state income tax, revenue tax, amortization of different taxes and investment tax credits, property tax, other tax, other tax [ sic], and any other items not

]

specifically mentioned above.

d)

Please indicate whether capital costs other than those of SGLA's are included in the analysis. If so, please indicate those separately, show their impact on annual revenue requirements in each year, and discuss any differences in the fixed charge factor used here and those used for the SGLA's costs.

e) Please indicate what costs, if any, are assumed under Alternate A to correct Pressurized Thermal Shock (embrittlement) at the Robinson 2 unit. If such costs were assumed, please provide estimates of costs and down-time associated with assessing and correcting the problem.

Interrogatories 3-32 through 3-46 all have reference to Applicant's responses to Staff Request 3.

ANSWER 3-31. a) As stated on page 8 of CP&L's July 14, 1983 submittal to the NRC, the estimated annual charges as shown in the first column include " capital, production, decommissioning, nuclear insurance, and replacement power costs." The capital costs include the revenue requirements related to capital expenditures at Robinson 2 and the cost of the fuelinventory through the study pnriod. The production cost includes system fuel cost, Robinson 2 O&M cost and purchase power cost. The decommissioning cost reflects the method for collecting this cost, as approved by the North Carolina Utilities Commission and the South Carolina Public Service Commission.

The nuclear liability insurance cost reflects our most recent estimate. Replacement power costs apply only to Alternative 2 (shown in the second column) and are the additional production costs (including purchased power costs) necessary because of the assumed retirement of Robinson 2. l i

b)

See Applicant's response to Interrogatory 3-35.

c) The annual revenue requirement factors were computed separately for each vintage (annual capital expenditure) with the following assumptions:

1)

Capital Structure and Cost of Capital:

49.5% Debt at 9.59%

12.5% Preferred Stock at 8.96%

38.0% Common Equity at 15.5%

2)

Investment Tax Credits (ITC) a) The following ITC rates were assumed:

Nuclear Production Vintages 1971-1974 4%

Vintages 1975-1998 10 %

Nuclear Fuel All Vintages 10 %

b)

All ITC is normalized with amortization on a straight line basis over the book life of the asset.

3)

Deferred Income Taxes Differences between book and tax depreciation due to depreciation method and life were normalized. Basis differences fellinto one of two categories, either AFUDC or Other Basis Difference. AFUDC was calculated using a net of tax rate which is self normalizing. Other Basis Differences for post 1975 expenditures were normalized. Other Basis Differences for 1975 and prior expenditures were flowed through.

4)

Depreciation for Tax and Book Purposes a) The book depreciation rate used was 4.014% for nuclear production plant and 25% per year for nuclear fuel. Book depreciation was not included in the revenue requirements factors for nuclear fuel but was used in determining deferred income taxes.

b)

Tax depreciation was computed using the following assumptions:

Tax Life Nuclear Production Vintages 1971-1980 16 years Nuclear Production Vintages 1981-1998 10 years Nuclear Fuel 5 years Tax Depreciation Method Nuclear Production Vintages 1971-1972 Sum of the years digits Nuclear Production Vintages 1973-1980 Double declining balance for the first two years changing to sum of the years digits in the third year Nuclear Production Vintage 1981 ERTA rates Nuclear Production Vintages 1982-1998 TEFRA rates Nuclear Fuel TEFRA rates Tax Basis for 1982-1998 vintages was reduced by 50% of the ITC taken.

c) For conservatism in this alternative, it was assumed that all prior years additions would continue to depreciate as if they remained in use.

5)

Calculation of the Rate Base Contribution of the Investment The revenue requirements for the cost of capital were determined from the cost of capital rates and the net investment. Net investment was original cost less accumulated depreciation and accumulated deferred taxes.

6)

Federal Income Tax:

Federal income tax was determined using a 46% tax rate.

7)

State Income Tax:

State income tax was determined using a 6% tax rate.

8)

Revenue Tax:

l No revenue tax was included in the revenue requirements factors.

l 9)

Amortization of Different Taxes and Investment Tax Credits This is explained above in items 2 and 3.

l.

l

10)

Property Tax:

A property tax rate of.629% was assumed, 11)

Other Tax:

No other tax was included 12)

Any Other Items not Specifically Mentioned Above a) A property insurance rate of.363% was assumed.

b) An administrative and general expense rate of 2.327% was assumed.

d)

Capital costs other than those for replacement of the SGLA's were included in the analysis. These costs were provided in CP&L's response to Interrogatory 3-107 of the fir.;t set. These costs were not considered separately, but were included in the total costs which were used to determine the revenue requirements, flowever, their impact on annual revenue requirements can be determined from the information provided in the Cc my's response to Interrogatory 3-35 of this set. It should be noted, as discussed in the response to Interrogatory 3-45 of this set, that CP&L's analysis for Alternative 2 did not include the capital cost of accelerating proposed new generating units.

e)

CP&L has modified certain fuel bundles to be used in Robinson 2 to reduce the potential for PTS. The modified fuel bundles will be placed in the core beginning with the next refueling. The following table provides the estimated additional cost over normal fuel prices for the modifications.

[

s 6

~

u s'

d,

~.

/

ESTIMATED ADDITIONAI/ COSTS ~

.e

-s f c\\\\

OVER NORMAL FUEL COSTS FOR PT3 f40DIFIED FUEL BUNDLES' (000'S $, NOMlNAL3 T

s

}

YEAR U,On + CONVERSION ENRICIIMENT FABRICATION ANALYSIS TOTAL COST.

U s

237 I

1982 237 1983

,. 258 2000 880 3138

-52 D

1984

-52 1985

-223

-223 1986

-67

-239 g,-306

~~'

1987 499 499 1988 385 3050 7 3435

, [-

^

-292

- D '

-429 1989

-137 1990

-175 Q

-175

-333 1991

-333 1992 1505 472 1977 I

1993

-259 4620 4361

.+

1994

-381

-381 y

1995

-288

-432

-720 1996 1985' 1985 1997

-335 691 6450 6806

~

1998

-518

-518 w

The negative cost values indicate estimated fuel savings which are anticipat'ed to result from the modifications.

3-32. Please supply a complete list of all differences between Alternatives A and B.

ANSWER 3-32. Note: In our responses to Interrogatory 3-32 through Interrogatory 3-46, CP&L assumes Alternatives A and B correspond to Alternatives (1) and (2) w_

4\\

t respectively.

t.,

~*

\\v s

Alternative;(1) reflects the proposed plan of replacing the steam generator lower

. +

g

, Jssemblies (SGLA's) in a 43 week outage in 1984. Upon completion of that outage, the

(

unit would return to service and operate at an 85% operating capacity factor, with a 15 week refueling and maintenance outage every 12 effective full power months (EFPM).

Alternative (2) reflects early retirement of Robinson 2 on December 31, 1984. In this case Robinson 2 would be refueled in a 6 week outage and would operate during 1984 at a 3

70% operfitirig capacity factor with a steam generator inspection outage every 3 EFPM's.

Alternative (1), as stated in our response to Interrogatory 3-31a), includes capital, L

production, decommissioning, and nuclear liability insurance costs.

As appropriate, Alternative (2) includes these same costs, plus the write-off of uncollected costs resulting from early retirement. The following table shows the types of costs included in each alternative.

s Data Items AltArnative (1)

Alternative (2)

\\

l'? venue Requirement le to Capital Expenditures

• yes yes (through 1984)

Revenue Requirement Related to FuelInventory yes yes (through 1984)

Write-off Related to Fuel

• no yes

e Write-off Related to*

A Capital Investment no yes Decommissioning Revenue

• yes yes (through 1997)

(through 1984)

Nuclear Liability Insurance yes yes Difference in System O&M Costs yes yes Purchased Power Cost i

yes yes CP&1 System Fuel Cost

?

yes yes c

(

• For Robinson 2 only.

3-33. Please indicate every data item which differs between Alternatives A and B.

ANSWER 3-33. Because of the significant differences between the two alternatives, all data items listed in the table in CP&L's response to Interrogatory 3-32 of this set differ between Alternatives (1) and (2).

3-34. Please provide copies of all workpapers and other supporting documentation employed in estimating costs under alternatives A and B.

ANSWER 3-34. CP&L's workpapers used in estimating costs for Alternatives (1) and (2) will be made available to the Hartsville Group for review at CP&L's General Office in Raleigh, NC.

3-35. Please provide all fixed charge factors employed in the analysis, indicate for what years and capital costs each factor applies, and provide worksheets which show the development of each fixed charge factor.

ANSWER 3-35. The capital costs, the fuelinventory costs and their associated fixed charge rates used in CP&L's analysis are previded on Attachment 3-35 of this set. Also, the results of applying the fixed charge rates to the capital costs, as requested in Interrogatory 3-31b) and d) of this set, are included in the attached Attachment 3-35.

The workpapers associated with these components will be made available for inspection at CP&L's General Office in Raleigh, NC.

• 3-36. Please provide the rationale for employing a discount rate of 9.42 percent.

ANSWER 3-36.

The calculatio.n from which the discount rate is derived is as follows:

Ratio Cost Tax Effect Weighted Cost

(%)

(%)

(%)

Long Term Debt 49.5 9.59 (1-0.4924) 2.41 Preferred Stock 12.5 8.96 1.12 Common Equity 38.0 15.50 5.89 Discount Rate 9.42 Tax Rate 49.24%

The above capital structure and cost of capital were used because they reflect CP&L's request in the 1983 North Carolina retail rate case, and are considered appropriate for the study.

3-37.

Please provide any workpapers or calculations used in developing the 9.42 percent discount figure.

ANSWER 3-37. See Applicant's response to Interrogatory 3-36 of this second set.

3-38. Please supply all escalation rates employed.

ANSWER 3-38. The following is a description of the escalation rates used in the study:

Capital-9 percent per year Fuel - Existing coal and nuclear fuel contracts are escalated individually based upon indices stated in the contract, for base-escalated type contracts. The source of the forecasts for appropriate indices is Data Resource?,

Incorporated (DRI).

CP&L subscribes to DRI's Macroeconomic, Coal, and Costs Forecasting Services.

A common source of forecasted indices for both fossil and nuclear costs assures that relative price forecasts are as accurate as possible.

In forecasting prices for periods beyond our existing contracts, a forecasted market price is used. The forecasted market price is also used whcn a specific contract price is related to a market price. The

• 1

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market forecasts for coal are generated from DRI's Coal Mode. Uranium forecasts are generated from the Eureka model developed by Colorado Nuclear Corporation. Market price projections for U 03 8 conversion and nuclear fuel fabrication are obtained from the nuclear consulting firm of Pickard, Lowe, and Garrick. Oil price projections are provided by DRI.

Beckend nuclear fuel costs are set by the Department of Energy at 1.0 mil /kwh in 1983. These costs are assumed to escalate with inflation.

DRI's forecasted GNP deflator is used as an estimate for general inflation.

O&M - The basic rate for O&M costs is 7.7 percent per year.

Decommissioning - 9 percent per year through 1990 and 6 percent per year after was used.

Nuclear Insurance - 5 percent per year.

3-39. Please supply annual estimates of Robinson 2 fuel costs. In each year, please indicate what amount, if any, is included for spent fuel disposal.

ANSWER 3-39. The following table provides the annual estimates of Robinson 2 fuel and spent fuel disposal costs, as used for Alternative (1).

• ~

Total

• Spent Fuel Fuel Disposal Cost Cost Years

($/MWH)

($/MWH) 1984 4.7 1.1 1985 5.0 1.2 1986 6.5 1.3 1987 7.1 1.4 1988 7.5 1.5 1989 8.3 1.6 1990 9.2 1.7 1991 10.0 1.8 1992 11.0 1.9 1993 12.7 2.0 1994 13.7 2.1 1995 14.4 2.2 1996 15.6 2.3 1997 16.9 2.5 1998 17.7 2.7

• Includes spent fuel disposal costs.

3-40. Please explain why purchase power costs incresse during the study period by over 300% (page 9) while replacement power increases by about 90% (page 10).

ANSWER 3-40.

Purchase power and replacement power are different items.

Purchase power is comprised of purchased energy and capacity; whereas, replacement power reflects a mix of increased generation from other, more expensive generating sources on CP&L's system plus purchase power.

As noted in Applicant's response to Staff Request #3, the purchased power cost ranges from $30/MWH to $130/MWH with an average of $59/MWH. The $130/MWH purchased power cost occurs in 1989 and is primarily a function of two factors: 1) increasing purchase capacity charges, and 2) a large capacity shortage in 1989.

Regarding the purchase capacity charges, applicants expect most of the capacity now available for purchase to be unavailable in the late 1980s. Thus, the purchase capacity charge in 1989, and thereafter, reflects the costs of newly constructed coal capacity, which are significantly higher than those of existing coal enpacity. Also,1989 is the year just prior to the in-service of Harris Unit 2.

Without Robinson 2, a large amount of purchase capacity is needed to maintain reliability.

__.-rh 4-_

The increase in replacement power costs is generally a function of increasing substitution fuel costs and purchase power costs. With more of the replacement power l

generally being provided from other units on the system than from purchase power, the lesser increase of the substitution fuel cost outweighs the higher cost of purchase power and, therefore, reflects a lower overallincrease for replacement power than for purchase power.

3-41.

Please define and explain the difference between the costs referenced in Interrogatory 3-40 above.

ANSWER 3-41. See Applicant's response to Interrogatory 3-40.

3-42. Please provide actual historic O & M costs for Robinson for each year of its life.

ANSWER 3-42.

The following is a list of the yearly historical O&M costs for Robinson Unit 2.

Robinson )

1 O&M Costil

(

_ $)

Year 1971 1,918,000 1972 1,780,000 1973 4,609,121 1974 4,780,000 1975 6,361,000 1976 5,902,728 1977 6,859,964 1978 14,354,990 1979 15,142,000 1980 22,142,000 1981 21,788,972 1982 47,293,853 (1) The O&M costs do not inclede fuel cost.

3-43.

Please provide annual estimates of decommissioning costs under each alternative. Include workpapers showing the development of each alternative.

ANSWER 3-43. It is assumed that the " decommissioning costs requested are the annual revenue requirements to be collected over the study period, the necessary funds for decommissioning the unit at the assumed time.

The decommissioning revenue requirements for Alternatives (1) and (2) are as follows:

~

Robinson 2 Decommissioning) Revenue Requirements (000's $

Year Alternative (1)

Alternative (2) 1984 4,827 38,114 1985 5,268 0

1986 5,750 0

1987 6,275 0

1988 6,849 0

1989 7,475 0

1990 8,158 0

1991 8,904 0

1992 9,717 0

1993 10,606 0

1994 11,575 0

1995 12,633 0

1996 13,788 0

1997 4,110 0

1998 0

0 The workpapers used in deriving these estimates will be made available to the Hartsville Group for review at the CP&L General Office in Raleigh, NC.

3-44. Please indicate what extra decommissioning costs, if any, would be incurred under Alternate A due to the higher level of radioactivity at the Robinson 2 unit.

ANSWER 3-44.

The same base decommissioning cost estimates were used for estimating the revenue requirements under each Alternative.

3-45.

Please provide estimates and workpapers showing the cost and in-service dstes for newly constructed units under Alternate B.

ANSWER 3-45. The following table provides the estimated cost and in-service dates for units for which construction schedules were accelerated because of inadequate reserves under Alternative (2).

I i

l

Estimated Assumed Accelerated Accelerated Construction Unit In4ervice Date Cost (000's $1 Mayo 2 1991 800,692 Undesignated 1*

1994 2,014,925 Undesignated 2*

1996 1,482,591 Undesignated 3*

1998 1,961,443

• the term "Undesignated' is used because CP&L has not made commitments to a particular design, unit size, or location. This capacity is shown strictly for long-range planning purposes to indicate that additional capacity will be needed in this time frame (based on minimum 20% reserves) should loads develop as indicated.

It should be noted that for production cost calculation, the above units were included on their accelerated schedule. However, the capital cost of these units and the impact they would have on CP&L's financial position were not considered in the analysis.

3-46.

Please provide Load and Resource Tables for Alternatives A and B. This should include annual peak loads, required reserves, capacity sales and purchases, and new and existing capacity.

ANSWER 3-46. Load and Resource Tables for Alternatives (1) and (2) follow:

ALTERNATIVE 1 Prev!ous Year's Firm New Total Peak Capacity Purchases Capacity Resources Load Reserves Percent

• Year (MW)

(MW)

(MW)

(MW)

(MW)

(MW)

Reserves 1984 8725 75 8800 7043 1757 24.9 1985 8725 75 8800 7346 1454 19.8 1986 8725 75 900 9700 7557 2143 28.4 1987 9625 75 9700 7674 2026 26.4 1988 9625 75 9700 7852 1848 23.5 1989 9625 75 9700 8043 1657 20.6 1990 9625 75 900 10600 8224 2376 28.9 1991 10525 75 10600 8461 2139 25.3 1992 10525 75 720 11320 8605 2715 31.6 1993 11245 75 11320 8854 2466 27.9 1994 11245 75 11320 9094 2226 24.5 1995 11245 75 11320 9386 1934 20.6 1996 11245 75 690 12010 9696 2314 23.9 1997 11935 75 12010 9998 2012 20.1 1998 11935 75 690 12700 10300 2400 23.3

• CP&L's planning criteria is to maintain a minimum 20% reserve margin.

• ALTERN ATIVE 2 Previous Year's Firm New Total Peak Capacity Purchases Capacity Resources Load Reserves Percent

• Year (MW)

(MW)

(MW)

(MW)

(MW)

(MW)

Reserves 1984 8725 75 8800 7043 1757 24.9 1985 8060 740 8800 7346 1454 19.8 1986 8060 93 900 9053 7557 1496 19.8 1987 8960 234 9194 7674 1520 19.8 1988 8960 447 9407 7852 1555 19.8 1989 8960 677 9637 8043 1594 19.8 1990 8960 75 900 9935 8224 1711 20.8 1991 9860 75 720 10655 8461 2194 25.9 1992 10580 75 10655 8605 2050 23.8 1993 10580 75 10655 8854 1801 20.3 1994 10580 75 690 11345 9094 2251 24.8 1995 11270 75 11345 9386 1959 20.9 1996 11270 75 690 12035 9696 2339 24.1 1997 11960 75 12035 9998 2037 20.4 1998 11960 75 690 12725 10300 2425 23.5 l

• CP&L's planning criteria is to maintain a minimum 20% reserve margin.

3-47.

Please provide estimates of the annual costs of analyzing and correcting Pressurized Thermal Shock (embrittlement) problems at Robinson 2.

ANSWER 3-47. See Applicant's response to Interrogatory 3-31e) of this set.

3-48.

Please indicate whether the costs referred to in Interrogatory 3-47 are included in the estimate of " Net Construction Cost supplied in response to Hartsville Interrogatory 3-107 in its first set of interrogatories.

ANSWER 3-48. The additional capital expenditures provided in CP&L's response to Interrogatory 3-107 of the first set do not include estimates of the annual costs of addressing the Pressurized Thermal Shock problem. CP&L is modifying certain fuel

bundles to reduce the potential for embrittlemer:t problems. The mst of the fuel bundle modifications as provided in the Company's response to Interrogatory 3-31e) of this set are reflected in the fuel costs used in the study, with the exception of the $880,000 analysis cost in 1983.

3-49. Please supply all documentation and support for your response to Hartsville Interrogatory 3-107 in its first set of interrogatories.

ANSWER 3-49. The workpapers and support for the additional capital expenditures listed under Interrogatory 3-107 of the first set of interrogatories will be made available to the Hartsville Group for inspection and copying at CP&L's General Office in Raleigh, N C.

3-50. Has the Company investigated a conservation program as an alternative to construction of generating facilities?

ANSWER 3-50. Yes. A corporate Conservation and Load Management (CLM) Policy Committee directed a comprehensive six-month study in 1981 to analyze each customer sector to identify the major CLM opportunities available. Once feasible program ideas were identified, their load and energy impacts, cost and benefits, and customer acceptance levels were analyzed. To select programs that would receive broad customer support, significant market research was conducted. Based on this comprehensive study, a strategy consisting of 37 programs was developed, resulting in a goal of reducing the forecasted 1995 peak demand by 1750 MW below what would otherwise be.

3-51. If the answer to Interrogatory 3-50 is affirmative, please provide any studies or documents which analyzes [ sic] this alternative.

ANSWER 3-51. A study entitled Conservation and Load Management Strategy for Ensuring Reliable Electric Supply in the 1990's was the basis of CP&L's decision to pursue cost effective conservation and Icad management alternatives. This study will be made available to the Hartsville Group for inspection and copying at CP&L's General Office in Raleigh, NC.

3-52. Please provide a copy of the Applicant's most recent load forecast.

ANSWER 3-52. As previously requested, a copy of CP&L's most recent load forecast was provided as an Attachment to CP&L's response to Interrogatory 3-124 of the first set of interrogatories.

3-53.

For each Company forecast beginning in 1973, please provide the forecast

'.990 peak load.

ANSWER 3-53. The following is a list of the forecasted 1990 peak and the date the I

forecast was made.

Forecast Forecasted 1990 Date Peak Load 5-73 19784 6-74 18177 10-75 14811 11-77 11549 11-78 10859 2-79 10715 4-79 10427 11-79 9543 12-80 8727 12-81 8228 12-82 8224 4

4

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4 4

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ATTACIDfENT 3-28 ROBINSON 2 RETIREMENT SCENARIO OUTPUT FROM 1984-1998 PROJECTIONS i

i s

The_,-

--wm---.Nwee -

m.-mg m

.m.

..T M*M M'

-~-

~~.

1 CAROLIria POWER & l.1 3fti COMPANs Gif1E RA t tuti NEPORI IOR'1984 PAGE 3

2 Ruta DAT E : 08/10/83 3

BACK-EtJO TOTAL

• FUEL TOTAL

• CAP HEAT 4

GWit FUEL (K$) F UE L (Ct $ )_ FUEL J K$)_$/MWH_ $/MWit _ _ F AC_

RATE _,,_PLAW4ED_O.U_TAGES**

5 i

6 INPUI FOR CP&L LnAD 35985 7

PEAK FOR CPf.L LOAD 7043MW a

SLPA WilEE LItJG 128.O 431.4 9

in FIRM PURCHASES 128.0 481.4 3.8 4

st NON-FIRM PURCHASES 332.0 tG255.9 49.C 12 13 IDIAL PURCllASED POWER 4GO.O 1G737.3 36.4 j

14 is CPSL SYSTEM IIVDRO 720.1 38 i

1 ASHEVILLE 1

1317.7 25988.2 25988.2 19.3 19.3 77 9988.1 0423-0506 I

1m 2

912.G 10G77.0 18677.0 20.5 20.5 54 10544.8 1015-1125 to CAPE FEAR 5

318.2 8167.7 8167.7 25.7 25.7 25 10131.0 041G-OS27 20 6

601.4 14882.4 14882.4 24.6 24.6 40 9731.4 032G-0408 4

2:

LEE 1

75.3 2309.5 2309.5 30.7 30.7 11 11945.0 0102-0513 2

22 2

84.9 2599.G 2599.G 30.G 30.G 13 11870.3 0319-0101 23 3

G77.4 17242.0 17242.0 25.5 25.5 31 10012.8 1112-1125

]

24 MAYO 1

4385.2 99031.7 99001.7 22.6 22.G 71 10040.6 032G-0122 a

g 26 ROGlHCON t

333.7 8712.1 8712.1 2G.1 26.1 22 10291.9 1001-1014 i

27 T'1FGORO 1

2307.3 48993.5 48893.5 21.2 21.2 G8 10374.8 0507-0507 2

2n 2

3520.2 75GG4.0 756G1.0 21.5 28.5 GO 104G9.5 1008-1028 i

23 3 4017.7 85570.4 85570.4 21.1 21.1 65 10356.2 0102-0429 Jo 4

4046.7 95228.9 95228.9 23.5 23.5 GG 99G9.G 0910-1007 3:

SUilDN I

124,2 3GG1.7 3G61.7 29.5 29.5 15 -

11539.7 0227-0318

+

32 2

1G7.4 4G52.7 4G52.7 27.8 27.8 18 10987.2 1105-1125 j

33 3

1130.1 27792.1 27792.1 24.6 24.G 33 9712.2 0319-0513 14 Ur!DESIGNATfD T O S",I l 1 35 2

l 3

x 3;

WfA1HFRSP00ff 1

42.3 1379.3 1379.3 32.G 32.G 10 12897.3 032G-0429 JR 2

40.3 132G 4 132G.4 32.9 32.9 9

13005.9 0521-0527 i

31 3

114.1 3199.9 3999.9 28.0 28.0 17 11055.5 1029-1202 do q

4 10fAL FOSSIL SIF AM 24280 54503G.7 545037 22.4 22.4 53 10213.4 4

42 j

43 IC TURDINES 154.3 13851.3 13857.3 89.8 89.8 2

15635.4 i

44 l

45 T O I Al. FOSSit 24434 508898.1 558894 22.9 22.9 44 10247.6 i

4 r, j

41 CRur1SWICK 1

3613.1 13832.2 4082.9 17915.0 3.8 5.0 52 10148.7 0225-0302 0728-1109

}

es HARRIS __,,

2 3682.5 13851.G 41Gl.2 18012.8 3.8 4.9 53 10148.7 0101-031G 1201-1238 41 1

'j

$n 2

l 51 ROBI'NSON 2

3077.1 11457.1 3177.1 14934.1 3.7 4.9 53 10803.7 0121-0302 OG01-f0E7

~~ ~ ~ ^

~T f5L NUCLIhd

~' ~ ~~~i 373 ~ 35i30.9'IEf2iII ~5 852.0

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54 1

55 TOT AL CP&L GEtJFRATION 35527 598035.0 11721.1 609756 tG.8 17.2 46 10061.5 5

TOTAL INPUT 35987 G26493 17.4 sn OSM COSIS ARE INCLUDED IN ANOTHER SCilEDULE.

59 OU1 AGE SCitf DULF S ARE SUBdFC T T(1 CilAf!GE.

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[J CAROLINA POWER A LIGH1 C0t.1P ANY GEf4EMAi!ON REPORT FOR 1993 PAGE 12 2

RUN DATE: 08/10/83 1

UACK-END TOIAL*

TUEL 10TAL*

CAP HEAT 4

_ GWil_ _,F UE L. ( KS ) _FUELIK$) _ F UE L_, ( K $ ) _ $/$1 Wit _ $/MWH,

_FAC___ RATE.

PLANtJED DUT AGE S* *, _,,,,

5 6

INPUT FOR CPAI LOAD 47427 7

PEAK FOR CP&L LOAD 8851MW 8

SEPA WHfELING 120.0 480.0 9

to FIRM PURCHASES 128.0 480.0 3.7 11 NON-FIRM PURCHASES 757.0 74221.5 98.0 12 13 IOTAL PURCHASED POWER 885.0 14701.5 84.4 11 is CP&L SYSTEM livDRO 720.1 38 16 17 ASHEv!LLE I

1373 1 5954G.4 5954G.4 43.4 43.4 79 9988.4 0329-0411 88 2

1230.4 5G130.8 56130.8 45.6 45.6 72 1049G.5 1018-1031 19 CAPE FEAR 5

316.7 20883.0 20983.8 G5.9 G5.9 25 10127.7 0503-05tG 20 G

523.8 33183.0 33183.0 G3.4 63.4 35 9742.8 0322-0404 21 LEE 1

49.3 3871.6 3871.6-78.6 78.6 7

11923.8 0308-0321 22 2

54.4 4272.G 4272.6 78.5 78.5 8

11816.4 0503-05tG 23 3

630.7 41271.7 41271.7 G5.4 65.4 29 10023.7 0927-1010 24 MAYO 1

4324.5 205221.4 205221 47.5 47.5 70 9741.2 0301-0328 25 2

4262.4 195832.8 195833 45.9 45.9 68 9154.2 0329-0425 20 ROBINSON 1

340.9 2284G.1 2 2 P.4 6.1 67.0 67.0 22 10274.9 1011-1024 27 R0xCORD 1

1G40.4 80613.5 80613.5 49.1 49.1 49 10420.9 0426-042G 28 2 2966.9 14814 G. 8 148447 50.0 50.0 51 10519.6 1011-1031 23 3

338G.5 166109.8 1G6410 49.1 49.1 55 10410.5 0329-0425 30 4

3801.7 176286.9 176286 46.4 46.4 62 10008.3 0913-1010 31 SU T TutJ t

76.2 5753.8 5753.8 75.5 75.5 9

It510.G 0300-0321 32 2

1G5.5 11762.3 11762.3 71.1 71.1 18 10933.6 0927-1017 31 3

1043.3 GGilt.9 GG111.9 63.4 63.4 31 9738.7 0405-0425 3s UNDESIGNATED T OSSIL 1 92.4 2

11283.2 c,

y, y

l l

37 wtATHERSPOON.

3 1a t

29.5 24G9.9 2 1'*39. 9 83.G B3.6 7

12877.3 0419-0420 12934.G 0510-0516 t

31 2

26.6 2243.9 2243.9 84.4 81.4

+

l 31 3

92.0 6619.4 GG19.4 71.9 71.9 13 11043.7 1011-1017 An 4

TOTAL FOSSIL SIEAM 2G427 1309174.0 1309774 49.6 49.6 46 10100.5 t

42 l

41 IC TURCINES 328.2 85033.9 8503S.9 259.1 259.1 4

15dO8.7 45 as TOTAL FOSSIL 20755 1394808.0 1394808 52.1 52.1 40 10170.5 46 47 BRUtJSWICK 1

389G.1 45486.4

-7761.1 53247.5 11.7 13.7 5G 10448.5 O201-0502 49 2

4614.8 55325.4 9252.4 64577.8 11.9 13.9 67 10448.5 0101-0207 j

49 HARRIS 1

4G31.5 SG881.7 9225.9 GG107.6 12.3 14.3 59 10928.0 0517-0815 sn 2

5896.2 74157.5 81745.3 85302.8 12.G 14.6 75 10936.G 51 RCRINSOtt 2

l 52 j

53 10TAL NUCLEAR 19069 231851.0 379R4.G 269836 12.3~~~14.2 G4 10715.9 j

54 55 TOT AL CPSL GENERA 1!OtJ 45541 162GG59.0 37984.G 1GG4G44 34.9 35.8 47 10125.1

~

10IAL'ItMUI 47429 1739345 33.7 l

58

• DAM COSTS ARE INCLUDED IN AtJOTHER SCHEDULE.

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CAROLINA POWER & LIGHT COMPANY GENERATION RErf'RT FOR 1995 PAGE 14 2

Rt:N DATE: 08/10/83 3

PACK-END 101AL' FUEL TOTAL

• CAP HEAT 5

_GWH ___ F.U E L (KS).. FUEL (KS) FUEL (K1) $/MWil $/MWH FAC-

. RATE PLANNED OUTAGES *f, 4

s INPUT FOR CPSL LOAD 50290 7

PEAK r0R CPSL LOAD 938GMW 8

SEPA WHEELING 128.0 480.0 9

H)

FIRM PURCHASES 128.0 480.0 3.7 1

NON-FIRM PURCHASES 1844.4 151631 82.2 12 13 TOTAL PURCHASED POWER 1972.4 152111 77.1 11 s

15 CPAL SYSTFM HVDRO 720.1 38 ASHEVILLE 1

1423.4 7tO92.G 71092.6 49.9 49.9 82 9987.3 0417-0130 it 2

1296.7 G8113.9 68113.9 52.5 5 5 76 10496.9 1016-1029 M

CAPE FEAR 5

163.4 12223.3 12223.3 74.8 74.8 13 10126.6 0424-0507 2n 6

52G.5 37720.3 37720.8 71.7 71.7 35 9722.1 0320-0402 21 LEE 1

43.8 3903.0 3903.0 89.2 89.2 6

11922.7 0306-0319 22 2

46.0 4095.3 4095.3 89.1 89.1 7

ff839.G 0327-0507 23 1

344.4 25548.9 25548.9 74.2 74.2 16 10011.6 1002-1015 24 MAYO I

4381.3 230593.5 230594 53.1 53.1 70 9743.5 0220-0319 25 2 3796.0 198744.6 198745 52.4 52.4 GO 9744.6 0320-0528 26 ROBINSON 1

173.6 13204.1 13204.1 76.1 7G.1 11 10277.2 1002-1015 27 ROX80R0 1

2108.7 118941.1 118941 56.4 56.4 63 10409.1 0508-0508 28 2

3430.2 19GO73.2 19GO73 57.2 57.2 58 10491.6 0925-1015 2a 3 3703.1 208218.8 208219 56.2 56.2 60 10385.3 0403-0430 30 4

337G.9 176914.0 176914 52.4 52.4 55 10014.6 0724-1001 31 SUTTON 1

62.0 5312.8 5312.8 85.7 85.7 7

11513.0 0213-0326 32 2

88.8 7192.7 7192.7 81.0 81.0 10 10987.8 1009-1029 33 3

1082.4 77530.2 77530.2 71.6 71.G 32 9705.0 0327-0416 34 UNDESIGNATED FOSSIL 1 942.9 60890.6 60890.6 64.6 64.G 1G 10516.3 0327-0423 n

2 92.4 G247.0 6247.0 67.6 67.G 2

11283.2

, ' ' ~ ~"~ ~ Q[KitirkFf-iWyd

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12970.1 0424-0430 l

31 3

G2.8 5118.9 5118.9 81.6 81.6 9

11037.4 101G-1022 40 41 10l AL FOSSIL SIEAM 27155 153239G.O 153239G 56.4 SG.4 42 108?3.0 42 41 IC fuRCINES 306.9 93455.1 93455.1 304.5 304.5 3

15766.7 41 45 10TAL F f1551 L 27462 1625851.0 162b851 59.2 59.2 37 10186.1 l

46 i

47 DRUNSWICK 1 5187.1 72625 5 11531.0 8415G.5 14 0 16.2 75 10148.6 as 2 5185.3 73141.1 11526.8 84667.9 14.1 16.3 75 10848.6 49 HARRIS 1

5008.2 78379.3 11133.2 89512.4 15.7 17.9 64 10944.2 O*01-0305 so 2

4757.6 70295.6 1057G.1 80871.6 14.8 17.0 60 10914.8 1016-1231 51 RORINSON 2

ICIAL NUCt. EAR 20138 291141.4 317G7.1 339209 18.6 16.8 68 10G89.1

~~~~~"'~~~

54 55 TOTAL CPSL GENERATION 48320 1920292.0 41767.1 1965059 39.7 40.7 46 10143.8 TuiAL INPUI 50292 2117170 42.t v

OSH COSIS ARE INCLUDT D IN AN0 iller SCitEDULE.

ss

• • DUTAGE SCHEDtlLFS ARE SUBJECT 10 CilANGE.

en ronM on ei m2ran 9S m

. ~ _ - ~

l CAROLINA POWER & Llr.HI COMPANt GENERA 110N REPORI IOR 1996 PAGE 15 2

3 RUN DATE: 08/10/83 BACK-END TOTAL

• FUEL TOTAL

• CAP HEAT 4

5

_ CWH_ F UE L (K$)_ TUEL(K$)_ FUEL,(K$)_, $ /,MW1.l_ $ /MWil FAC RATE PLAf4NED OUTAGES **

l 6

INPUT FOR CP8L LOAD 518Gd 7

PEAK TOR CPT.L LOAD 9696MW a

SEPA WifEEL!rJG 128.0 481.4 4

9 to FIRM PURCl'ASFS 128.0 4Rt.4 3.8 1

NON-r!Pt1 PURCHASES 2709.0 208252 76.9 12 13 10!AL PURCliASED POWER 2837.1 208733 73.G t4 is CP&L SYSTEr1IlyDRO 720.1 to 38 17 ASHEVILLE 1

1457.2 78123.9 7Pl23.9 53 G 53.6 84 9982.9 0408-0121 18 2

1331.6 74958.1 74958.4 56.3 5G.3 78 10477.9 0930-1013 19 CAPE FEAR 5

162.4 13011.3 13011.3 80.1 80.1 13 10123.7 0101-0111 20 G

SOG.6 30015.2 39015.2 77.0 77.0 33 9741.9 0308-0317 2i LEE 1

43 9 4192.4 4192.4 95.G 95.6 G

11922.8 0226-0310 27 2

48.4 4618.7 4G18.7 95.4 95.4 7

1183G.3 0513-OS2G 23 3

321.5 25GG3.6 25GG3.6 79.8 79.8 t$

10021.1 0930-1121 24 MAVO 1

4453.4 249969.7 249970 56.1 56.1 72 9724.4 0226-0324

+

25 2

4416.3 253146.1 253146 57.3 57.3 70 9730.1 0325-0421 M

R001tJSof 3 1

173.3 14116.0 14116.0 81.5 81.5 11 1027G.7 0930-1924 77 R0xCORO 1

2158.4 130045.8 130016 GO.3 60.3 G4 1038G.2 0527-0527 i

23 2

3G12.4 219368.6 2193G9 GO.7 GO.7 G1 10152.7 1007-1027 29 7 3345.5 201230.8 201231 60.2 60.2 54 10372.2 0318-0526 30 4

3933.4 219174.1 219174 53.7 55.7 G1 9983.8 0909-1006 si SUT10N 1

67.9 G238.9 G238.9 91.9 91.9 8

11514.6 0401-0421 12 2

90.2 7820.9 7a20.9 8G.7 8G.7 10 1099G.4 0930-1110 3i 3

1049.5 80283.4 80283.4 7G.5 7G.5 31 9693.9 0422-0512 i

14 UfJOESIGt!AT E D roSSIL 1 1076.3 73G15.6 7?G15 C GB.4 GR.4 18 10181.0 0401-0428 35 2

1171.5 80235.8 80235.8 G8.5 G8.5 19 10470.2 36 3

37 WEATHERSPootJ 1

26.5 2G94.2 2694.2 101.9 101.9 G

12896.8 0415-0421 1

.19 2

23.4 2398.7 2398.7 102.G 102.G 5

12990.4 0422-0526 I

39 3

G4.4 SG2G.t SG2G.1 87.4 87.4 9

11012.0 1014-1020 4

40 j

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TOT AL TOSS!L Sif Att 29534 178551G.0 1785586 60.5 GO.5 46 10105.4 42

]

41 IC TURRItJES 307.7 101513.8 101544 330.0 330.0 3

15846.9 41 j

4s total FOSSIL 29841 1H87090.0 1887090 G3.2 63.2 41 10164.6 j

46 1

4; RRUNSWICK 1

3910.7 59112.1 9182.3 G8291.3 15.1 17.5 56 10448.7 0422-0721 48 2 3911.1 G2874.8 0183.3 72058.1 16.1 18.4 56 10448.7 0129-0428 4

' HARRIS 1

4748.6 77851.1 11189.8 88600.9 16.3 18.7 GO 10906.8 OE24-0922 43 3

50 2

5901.5 99102.1 1385G.8 113259 16.8 19.2 75 10937.3 0101-0114 si RORINSOf1 2

I 52 51 TOTAL FJUCLEAR 18472 298840.0 43372.1 342212 16.2 18.5 62 10722.5

- ~ ~ ~ ~ ~ ~

4 51 TOTAL CPSL GENERATIOt1 49033 2185930.0 43372.1 2229302 44.G 45.5 47 10126.0 J

56 i

57 TOTAL I f 4PU T 51870 2430035 47.O

- - - ^

ts 59 OSM COSTS ARE INCLUDED IN ANOTHER SCHEDULE.

on DUTAGE SCHEDULES ARE SUCdFCT TO CHANGF.

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f ATTACIDIENT 3-29 CHANGES IN PRODUCTION COST INPUT INFORMATION FOR ALTERNATE (2) s

m 4

CAROLINA POWER & LIGHT g PANY PROJECTED 0&M COSTS (000's $)

Other(2)

Fossil Other( }

Total Total Year Steam Nuclear IC Turbines Hydro Brunswick #1 Brunswick #2 Roxboro #4 Mayo #1 Mayo #2 Harris #1 Harris #2 l

1984 63,632 37,769 8,701 2,870 50,448 48,882 6,244 5,609 1985 68,584 9,074 3,086 33,724 39,879 6,725 6,641 j

1986 73,920 9,475 3,319 45,520 43,720 7,243 6,506 28,847

{

1987 79,671 9,907 3,570 37,228 37,872 7,801 7,007 46,635 1988 85,869 10,373 3,840 47,718 47,028 8,401 7,547 50,820 1989 92,552 10,875 4,131 45,241 49,677 9,048 8,128 42,653 1990 99,751 11,415 4,444 47,697 42,943 9,745 8,753 50,302 32.382 1991 107,769 11,997 4,781 57,072 57,072 10,496 9,427 6,6 77 44,223 55,241 1992 116,430 12,624 5,144 49,357 55,732 11,304 8,884 8,630 46,483 59,232 1993 125,787 13,299 5.535 65,581 58,749 12,174 9,295 9,295 60,549 47,862 1994 181,656 14,026 5,956 70,326 70,326 13,111 10,010 10,010 62,837 64,930 1995 205,916 14,809 6,410 60,785 60,785 14,121 10,781 10,781 57,246 67,340 i

1996 257,739 15,652 6,899 80,798 80,798 15,208 11,611 11,611 74,598 61,372 1997 292,061 16,560 7,425 75,021 86,623 16,379 12,505 12,505 78,687 79,976 i

1998 343,700 17,538 7,992 87,314 74,880 17,641 13,468 13,468 69,138 82,954

~

NOTES:

$N EE (1) These projected OAM costs do not include fuel costs.

(2) "Other Fossil Steam" includes the following plants: Asheville; Cape Fear; Lee; Robinson Unit 1; Roxboro Units 1,283; Sutton, Weatherspoon, and Undesignated Units 1, 2, and 3.

Y U$

(3) "Other Nuclear" includes Robinson Unit 2.

I 1

.~.

i l

1 FOSSIL STEAM DISPATCH FUEL PRICES All Data Are Cents /MBTU Plant 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998-Asheville 193 212 234 258 285 313 343 374 403 434 467 500 537 578 621 Cape Fear 227 253 281 311 347 382 422 466 502 541 582 625 672 725 783 Lee 227 253 281 311 347 382 422 466 502 541 582 625 672 725 783 Mayo 1 193 213 237 262 292 321 354 389 420 453 488 524 564 605 652 Mayo 2 354 389 420 453 488 524 564 605 652 i

Robinson 1 228 252 280 310 346 381 421 466 502 541 582 625 672 725 783 Roxboro 1-3 193 213 237 262 291 321 354 388 418 451 486 522 561 605 652 Roxboro 4 193 213 237 262 292 321 354 389 420 453 488 524 564 605 652 il i

Sutton 227 253 281 311 347 382 422 466 502 541 582 625 672 725 783 i

Ucatherspoon 227 253 281 311 347 382 422 466 502 541 582 625 672 725 783 Undesignated 563 599 641 685 732 (k

6 EI l

8/12/82

.g N"

Y a

9 ATTACHMENT 3-35 WORKSliEETS USED TO DEVELOP REVENUE REQUIRE}ENTS RELATED TO CAPITAL AND FUEL COSTS I

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1 CA/WAL REVENUE REQUIRetENT C3tPtNENTS SY YEAR (888'S $)

YEAR 1984 1985 1984 1987 1988 1989 1998 1991 1992 1993 1994 1995 1996 1997 1998 1971 9348.17 8917.81 8528.12 8179.83 7872.22 7544.41 7257.30 6958.!! 6442.58 6334.89 4027.28 5928.08 8

8 I

1973 514.471 487.787 4 3.768 442.497 424.452 489.!!7 393.739 378.404 343.827 347.491 332.314 316.978 316.844 I

I 1973 14.1747 13.3299 12.4373 12.I244 11.4819 !!.1113 18.4116 18.2889 9.84818 9.4875 9.89682 8.dId'4 8.28546 8.16518 I

1974 134.999 126.483 !!8.753 !!!.972 104.859 111.814 94.8254 93.4945 99.1744 84.8543 83.5233 80.2832 74.8831 73.563 74.4372 1975 383.883 288.474 274.849 268.447 248.218 234.774 226.318 214.843 288.343199.882191.382182.932174.C1165.946157.448 1974 34.1700 33.1962 38.5841 28.1997 25.9799 24.1438 22.5944 21.3287 20.3444 19.6512 18.9558 18.2444 17.5458 16.8445 16.171 1977 25.3572 24.2273 23.1475 22.!!79 21.1398 21.211519.332718.5951 17.727617.888316.3231 15.d47314.9781 14.293813.6171 1978 647.624 628.321 591.476 557.09 525.163 495.733 4 8.724 444.174 422.121 482.488 385.314 378.628 355.961 341.2 4 326.57 19791448.181382.361381.141225.231154.351988.521927.75 971.944 921.271875.578 834.922 799.324 768.7/8 738.232 787.d47 1988 1747.48 1445.98 1558.12 1459.88 1375.12 1295.98 1222.38 888.880 1892.11 1835.32 984.175 938.576 898.522 844.192 829.683 1981 885.944 759.999 712.255 645./.48 421.758 578.851 534.39 490.491 475.244 459.879 444.453 429.928 413.441 398.215 382.828 1982 2752.47 2584.99 2434.98 2288.81 2148.72 2002.42 1844.12 1725.83 1587.53 1537.48 1487.55 1437.62 1387.78 1337.65 1287.72 1983 1857.96 1748.57 1635.42 1542.53 1449.63 1354.65 1269.92 !!83.10 1I96.29 1989.48 977.819 944.182 914.423 882.687 858.958 1984 38788.9 29537.2 27734.6 26115.2 2 4 88.2 23244.1 21889.1 28444.5 19121.1 17777.7 16433.1 15916.6 15398.7 14888.9 14343.1 1985 I 4137.97 5884.87 5524.38 5193.97 4918.62 4622.53 4334.19 48d4.71 3794.99 3525.51 3255.78 3153.43 3851.23 3814.97 1986 8

0 8898.38 8548.41 8845.58 7598.98 7291.14 6802.94 4485.18 6831.47 5457.48 5283.85 4918.22 4754.88 4599.38 1987 0

0 8 549.652 527.188 494.529 4 5.279 439.387 413.495 387.682 343.384 339.144 314.947 299.729 281.574 1988 I

I 8

0 481.981 574.351 548.720 588.749 488.439 452.129 423.819 397.314 370.834 344.354 317.376 1989 I

8 I

I I 453.339 62d.542 587.888 553.954 522.278 491.583 444.781 431.916 483.138 374.344 1990 8

8 8

8 0

1 715.284 685.948 443.541 445.491 571.797 538.176 584.382 472.847 441.352 1991 0

I e

I 8

8 I 777.422 745.534 699.449 658.15 421.427 584.804 548.188 513.894 1992 I

I 8

I I

8 I

8 849.189 814.354 744.885 718.926 678.829 438.315 598.899 1993 5

8 8

8 8

8 I

8 9 924.3 4 884.434 831.438 782.457 738.914 695.335 1994 8

I I

I I

I I

9 I

I 1889.22 967.820 907.988 854.288 884.743 1995

- 8 8

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I !!88.82 1955.47 998.484 931.843 1996 I

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I 4

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I 8

8 8

0 !!98.87 !!49.79 1978.42 1997 I

I 9

0 8

8 0

8 8

8 4

8 8 1304.57 1252.98 1998 8

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8 1424.18 TORS 58444 54397 48199 57526 55029 52642 58394 47186 4 223 44345 42577 41994 35/48 35264 35342 e

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF HAROLD R. BANKS WAKE COUNTY

)

)

- NORTH CAROLINA

)

i Harold R. Banks, being duly sworn according to law, deposes and says that he is Manager-Corporate Quality Assurance with Carolina Power &

Light Company; that Answer to Interrogatories 1-1(Banks), 1-2a), 1-9, 1-13 and 1-15b),e) and h) in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

7/

,Ybbk Harold R. Banks Sworn to and subscribed before me this /f b day of August, 1983.

tbO

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[ j' $0IASif c'ipnksion expires: //-/ [ d 7 j ' 5

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r UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF J. R. B0HANNON WAKE COUNTY

)

)

NORTH CAROLINA

)

J. R. Bohannor., being duly sworn according to law, deposes end says that he is Manager-Nuclear Training Section with Carolina Power &

Light Company; that the Answers to Interrogatories 1-1(Bohannon), 1-10, 1-11 and 1-12 in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

l On k % A

_-.J.

j J. R. Bohannon Q

Sworn to and subscribed before me this \\"}

day o' August, 1983.

%\\ \\

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'OLf) 0 Nota (yTublic D

My commission expires:

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

~ AFFIDAVIT'0F RONNIE M. COATS WAKE COUNTY

)

)

NORTH CAROLINA

)

Ronnie M. Coats, being duly sworn according to law, deposes and says that he is Assistant to Group Executive with Carolina Power & Light Campany; that the Answers to Interrogatories 1-1(Coats), 1-4 and 1-5 contained in Applicant's Answers to 'Ihe Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

AE cb u;

Ronnie M. Coats Sworn to and subscribed before me this /7Nday of August, 1983.

'/ MhY/W

...'.'.'...I,,

ya6 Pub 1ic 0

! [ \\$QIfID'omm*(ssg' n expires: //!/J!87 5

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF CHARLIE B. HARDEE, JR.

WAKE COUNTY

)

)

NORTH CAROLINA

)

Charlie B. Hardee, Jr., being duly sworn according to law, deposes and says that he is Project Engineer-Nuclear Operations with Carolina Power & Light Company; that Answers to Interrogatories 3-11 through 3-19 contained in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

A Ib D'

J' L

Charlie B. Hardee, 3r. O Sworn to and subscribed before 4 ay of August, 1983.

me this /f d

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4, Notary Public j /' f()UR)ty E mm sion expires: // / 3'd 2 5!

i 5

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!%,PU300/7%$7

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF RICHARD E. LUMSDEN WAKE COUNTY

)

)

NORTH CAROLINA

)

Richard E. Lumsden, being duly sworn according to law, deposes and says that he is Acting Assistant to Vice President-Nuclear Operations with Carolina Power & Light Company; that Answers to Interrogatories 1-1(Lumsden),

1-2c) and 1-3 contained in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

I p

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Sw Richard E. Lumsden Sworn to and subscribed before me this / 9%ay of August, 1983.

i Os.bs) yt i

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4 Notary Public l

((

k cosmihion expires: //// E[8*7

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'l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

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CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF R. L. MAYTON, JR.

WAKE COUNTY

)

)

NORTH CAROLINA

)

R. L. Mayton, Jr., being duly sworn according to law, deposes and says that he is Manager-Corporate Health Physics with Carolina Power & Light Company; that the Answers to Interrogatories 1-1(Mayton),1-2b),1-7 and 1-8 contained in Applicant's Answers to The Hartsville Group Second Sct of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

R.L.MatopiJr.

)

Sworn to and subscribed before me this / W C day of August, 1983.

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE'THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF MIKE McDOWELL WAKE COUNTY

)

)

NORTH CAROLINA

)

Mike McDowell, being duly sworn according to law, deposes and says that he is Principal Specialist-Chemistry with Carolina Power & Light Company; that the Answer to Interrogatory 1-1(McDowell) contained in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief.

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Mike McDowell Sworn to and subscribed before e this I l Day of August, 1983.

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Notary Public O

My commission expires:,*l SE** u,, r< n Oddtils,103

r UNITED STATES OF AMERICA NUCLEAR REGULATORY CO)DiISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

' AFFIDAVIT OF J.' HENRY OEHMANN,'III WAKE COUNTY

)

)

NORTH CAROLINA

)

J. Henry Oehmann, III, being duly sworn according to law, deposes and says that he is Manager of Planning and Administrative Support with Carolina Power & Light Company; that the Answer to Interrogatory 1-1(Oehmann) contained in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief.

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J. Henry'0ehmann, III Sworn to and subscribed before me this /7 day of August, 1983.

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

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)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF MANLEY A. POPE WAKE COUtnT

)

)

NORTH CAROLINA

)

Manley A. Pope, being duly sworn according to law, deposes and says that he is Manager-Personnel Relations-Nuclear Plants with Carolina Power & Light Company; that the Answers to Interrogatories 1-1(Pope),

1-14 and 1-15a),c),d), and g) contained in Applicant's Aaswers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

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Jah t/Yu ManldlyA/P4pe' Sworn to and subscribed before methis/[

day of August, 1983.

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UNITED STATES OF AMERICA NUCLEAR REGULATORY C0FDiISSION BEFORE THE ATOMIC SAFETY AMD LICENSING BOARD In the Matter of

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CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF J. M. RUSS WAKE COUNTY

)

)

NORTH CAROLINA

)

J. M. Russ, being duly sworn according to law, deposes and says that he is Staf f Assistant-Nuclear Plant Construction with Carolina Power &

Light Company; that the Answers to Interrogatories 1-2e) and 1-15f) contained in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

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J.' M. Russ Sworn to and subscribed before

/'JN ay of August, 1983.

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r UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

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CAROLINA POWER & LIGHT COMPANY-

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF W. PARKER TOMLINSON WAKE COUNTY

)

)

NORTH CAROLINA )

W. Parker Tomlinson, being duly sworn according to law, deposes and says that he is Principal Engineer-Mechanical with Carolina Power & Light Company; that Answers to Interrogatories 1-1(Tomlinson), 1-2d), 3-1 through 3-8 contained in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

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W. Parker Tomlinson Sworn to and subscribed before N ay of August, 1983.

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P UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

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)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF B. M. WILLIAMS WAKE COUNTY

)

)

NORTH CAROLINA

)

B. M. Williams, being duly sworn according to law, deposes and says that he is Director-Staff Services with Carolina Power & Light Company; that Answers to Interrogatories 3-20 through 3-23, and 3-25 through 3-53, contained in Applicant's Answers to the Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief, and that the sources of his information are officers, employees, agents and contractors of Carolina Power & Light Company.

Answer to Interrogatory 1-1(Williams) is true.

B. M. Williams Sworn to and subscribed before me this /2K day of August, 1983.

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r UNITED STATES OF AMERICA NUCLEAR REGULATORY C0} MISSION BEFORE THE' ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

AFFIDAVIT OF SHERWOOD R. ZI3MEPJ4AN WAKE COUNTY

)

)

NORTH CAROLINA

)

Sherwood R. Zimmerman, being duly sworn according to law, deposes and says that he is Manager - Licensing and Permits Section, Technical Services Department with Carolina Power & Light Company; that the Answer to Interrogatory 1-1(Zimmerman) contained in Applicant's Answers to The Hartsville Group Second Set of Interrogatories to Applicant, Carolina Power & Light Company, are true and correct to the best of his knowledge, information and belief.

Sherwood R. Zi n

Sworn to and subscribed before

/1I day of August, -1985.; ' '

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Notary Tublic My commission expires:

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m UNITED STATES OF AMERICA NUCLEAR REGULATORY C019 FISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docket No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

CERTIFICATE OF~ SERVICE I hereby certify that copies of APPLICANT'S ANSWERS TO THE HARTSVILLE GROUP SECOND SET OF INTERROGATORIES AND REQUEST TO PRODUCE were served this 18th day of August, 1983 by depositing in the United States mail, first class, postage prepaid, to the parties on the attached SERVICE LIST. Affidavits of G. T. Beatty, Jr., ANSWER l-1 (Beatty) and 1-6; Robert E. Halliburton, ANSWER l-1 (Hailliburton); L. B. Wilson, Jr.,

ANSWER l-1 (Wilson); and R. B. Starkey, Jr., ANSWER 3-9 and 3-10 are not attached to said ANSWERS and will be provided.

swd bE27na Andrew McDaniel An Attorney for Applicant 2

m UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of

)

)

CAROLINA POWER & LIGHT COMPANY

)

Docekt No. 50-261-OLA

)

(H. B. Robinson Steam Electric

)

ASLBP No. 83-484-03LA Plant, Unit 2)

)

' SERVICE LIST Administrative Judge Morton B. Margulies Atomic Safety and Licensing Board Chairman, Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Washington, D.C.

20555 Administrative Judge Jerry R. Kline Atomic Safety and Licensing Appeal Atomic Safety and Licensing Board Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C.

20555 Administrative Judge David L. Hetrick B. A. Matthews Atomic Safety and Licensing Board Hartsville Group Professor of Nuclear Engineering P. O. Box 1089 University of Arizona Hartsville, South Carolina 29550 Tucson, Arizona 85721 Dr. John C. Ruoff Docketing & Service Section (3)

P.O. Box 96 Office of the Secretary Jenkinsville, South Carolina 29065 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Myron Karman, Esquire Office of Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D. C. 20555

,