ML20065B047

Testimony of Gr Capodanno & Rj Chisholm Re ALAB-708,Issue 8 on safety-grade Status of Emergency Feedwater Sys.Status of safety-grade Classification of Sys Unchanged from Previous Submittal to ASLB & Aslab.Prof Qualifications Encl

ML20065B047
Person / Time
Site:	Three Mile Island
Issue date:	02/16/1983
From:	Capodanno G, Chisholm R METROPOLITAN EDISON CO.
To:
Shared Package
ML20065A980	List: ML20065A977 ML20065B010 ML20065B017 ML20065B025 ML20065B040 ML20065B047 ML20065B061 ML20065B079
References
ALAB-708, NUDOCS 8302220375
Download: ML20065B047 (10)

Text

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February 16, 1983 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL EOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

LICENSEE'S TESTIMONY OF GARY R. CAPODANNO AND RICHARD J. CHISHOLM IN RESPONSE TO ALAB-708 ISSUE NO. 8 (SAFETY-GRADE STATUS OF EMERGENCY FEEDWATER SYSTEM) l l

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8302220375 830216 PDR ADOCK 05000289 '

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SUMMARY

This testimony addresses the Appeal Board's request for clarification of the safety-grade classification of the

-emergency feedwater system components generally, and of the new manual control stations in particular. The testimony reports that there have been no changes in the status of the safety-grade classification of the EFW system from that previously submitted to the Licensing Board and the Appeal Board. The testimony also provides a detailed description of the new EFW manual control stations and concludes that,. while this modification is highly reliable, it cannot be considered safety-grade.

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I 1 INTRODUCTION 2

This testimony by Gary R. Capodanno, Fluid Systems 3

Director, GPU Nuclear Corporation, and Richard J. Chisholm, 4

Manager of Electric Power and Instrumentation, GPU Nuclear 5

Corporation, is addressed to Issue No. 8 of the Appeal Board's 6

Memorandum and Order of December 29, 1982 (ALAB-708), which 7

seeks:

6 8. Clarification of the apparent incon-9 sistencies and confusion concerning the safety-grade status of components 10 in the EFW system (from the licensee and the staff).

1 l

Mr. Capodanno was a witness earlier in these proceedings 12 l on the EFW system. He sponsored Licensee's Exhibit 15 which 13 i describes the ZFW system at the time TMI-1 last operated, the 14 modifications being made to the system prior to restart, and 15 long-term modifications planned for the future. The status of 16 modifications to the EFW system to be completed prior to 17 restart was also addressed by Licensee in submittals of August 18 12, 1982, and November 22, 1982, in response to Appeal Board 19 requests for information of July 14 and November 5, 1982, 20 respectively.

21 BY WITNESSES CAPODANNO AND CHISHOLM:

We have reviewed Licensee's Exhibit 15 as well as pages 9 through 13 of Licensee's August 12, 1982 response to the Appeal Board, a.ad pages 9 through 15 of Licensee's November 22, 1982 5

response to the Appeal Board. That review has been conducted to determine whether there are any inconsistencies or confusing

statements regarding the safety-grade status of equipment prior 1

to restart which should be corrected for the Appeal Board and 2

to determine whether there are any items projected to be 3

safety-grade prior to restart which may not actually be so, or 4

items not intended to be safety-grade by restart that may be 5

so. The review has considered the capability of equipment to 6 respond to either a loss of main feedwater or a small break 7

loss of coolant accident (SBLOCA).

8 Our review confirms that statements by Licensee regarding 9

the safety-grade status of equipment in the EFW system and 10 modifications to that system at the time of restart are 11 consistent and appear to he clear. At the time of restart, the 1 2 EFW system will be safety-grade for purposes of respendina to 13 either a loss of mai;. feedwater or SBLOOA. The present status 14 of EFW modifications to be completed prior to restart has not 15 been altered. Those items anticipated to be safety-grade prior 16 to restart will be safety-grade for the accidents under 17 consideration; those items expected not to be safety-grade will 18 not be so qualified prior to restart.

19 The review has also considered any known inconsistencies 20 or apparent inconsistencies between Licensee's and the Staff's 21 descriptions of the safety-grade status of equipment in the EFW 22 system. We are aware of only one such inconsistency -- the one l 23 pointed out by the Appeal Board in ALAB-708 related to the 24 manual control stationn.

25 l 26 BY WITNESS CHISHOLM:

1 An alternate manual control capability for the EFW flow 2

valves has been installed which is independent of the ICS. It 3

consists of manual control (loader) stations, one for each 4

steam generator, in the control room which the operator can 5

activate by means of selector switches to manually provide 6

control signals to the emergency feedwater control valves.

7 Operation of the selector switches also transfers the power 8

supplies for the remote voltage / pressure transducers from an 9

ICS derived power supply to an independent power supply. The 10 new manual control circuits are supplied from a battery-backed, 11 115 volt 60 hertz power supply. The power comes from an 12 inverter which is normally fed from the Red train lE AC power 13 system and backed up by the Red battery. If voltage from the 14 inverter is lost, an automatic transfer switch will switch to a 15 regulated voltage source which is derived from the Green lE AC 16 power system. The manual control circuits utilize highly 1

17 reliable industrial grade components and the design is such 18 that no single failure in the control circuits will result in a 19 loss of system function. This manual control feature by itself 20 is highly reliable but not " safety-grade" as we have applied 21 that term throughout our review.

22 23 24 25 26 BY WITNESSES CAPODANNO AND CHISHOLM:

1 The functional objective of the EFW system for SBLOCA or 2

loss of main feedwater events is to provide adequate flow to 3 either of the steam generators. The function can be termed 4 safety-grade if it has the following attributes:

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1. Capable of performing in the accident or transient 6 environment.

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2. Capable of performing its function following a loss 8 of off-site power.

9 3 Satisfies the necessary provisions of the approved QA 10 program.

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4. Can perform its function following the worst single j' a failure in active mechinical or active or passive electrical 13 components.

14 5. Adequate time is available for manual control 15 functions.

16 The components of the EFW system can collectively meet 17 these criteria.

18 The manual control station is highly reliable but can fail l

19 as a result of certain single power supply distribution com-l l 20 ponent failures. A single failure in one of these components 21 will not disable the system function, however, since the l

22 operator dispatched to the vicinity of the EFW control valves 23 in the intermediate building on each EFW demand can manually 24 manipulate the valves with the local hand wheel. Since there 25 is adequate time for this operator action, system function is 26 l

achieved. Thus there are no single failures which can prevent 1

the accomplishment of the safety function.

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8 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 GARY R. CAPODANNO Business Address: GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Education: B.S., Mechanical Engineering, Fairleigh Dickinson University, 1967.

M.S., Mechanical Engineering, Newark College of Engineering, 1974.

Experience: Fluid Systems Director, GPU Nuclear Corporation, 1982 to present. Responsible for technical and administrative direction of the mechanical and radwaste engineering sections of the Engineering and Design Department with responsibility for

' secondary plant, reactor plant and radwaste systems and components within GPU Nuclear plants.

Directs, through the Mechanical Systems, Mechanical Components, and Radwaste Systems section managers, the engineering for fluid system designs, modifi-cation of existing plant systems, operations and maintenance review and troubleshooting for plant systems, and preparation and review of responses to inquiries of regulatory agencies. Directs the reviews and approvals of work done by outside engineering firms to assure conformance to GPU Nuclear criteria and standards. Directs the review of engineering standards and procedures, plant operating and emergency procedures and technical support to the plants during plant outages.

Manager of Mechanical Systems Engineering, GPU -

Service Corporation /GPU Nuclear Corporation,1978 to 1982. Responsible fo.r technical and admini-strative direction of the activities of company mechanical and nuclear engineers in the design of new power plants and major modifications to existing power plants for the three operating companies that comprise the GPU Sytem. Also responsible for directing these engineers in the review of work being done for GPU and the operating companies by architect-engineering firms.

Lead Systems Engineer, Ebasco Services, Inc.,

l April 1978 to July, 1978. Work on the Synthesis Gas Demonstration Plant Program for W. R. Grace Company and the United States Department of Energy.

Responsible for plant arrangements and system design work. Directed mechanical engineers in the l

design of steam, cooling water and materials ,

handling systems for a plant that was to use coal as a feedstock for the preparation of anhydrous ammonia and the production of elemental sulfur l or sulfuric acid as a by-product.

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GARY R. CAPODANNO Continued l

Mechanical Group Supervisor,' Burns and Roe, Inc.,

1974 to 1978. Engineering supervisor responsible for the technical and administrative direction of project engineers in the development od: plant general arrangements, system flow diagrams, engineering calculations, equipment specifications, bid evaluations, construction liaison, and licensing activities for nuclear power plants.

Mechanical Engineer, Burns and Roe, Inc., 1971 to i 1974. Responsible for design engineering of nuclear and conventional mechanical equipment and systems for nuclear power stmeions. This included preparation of specifications and system flow diagrams, evaluation of equipment pro'posals, performance of design calculations, construction liaison activities and activities related to governmental licensing of nuclear power plants.

Design Engineer, Foster Wheeler Corporation, 1969 to 1971. Responsible for design and development engineering of fossil fuel firing equipment and systems for electric generating plant steam gene-rators, preparation of engineering standards, evaluation of rendor equipment, and engineering assistance to company project site personnel.

Mechanical Engineer, Consolidated Edison Company, 1967 to 1969. Responsible for design and appli-cations engineering of mechanical equipment and s'rstems for nuclear and conventional electric generating stations.

ProfesJional Affiliations: Licensed Professional-Engineer -- New York, New Jersey and Pennsylvania

! Member -- American Nuclear Society l

Member -- National Society of Professional Engineers Publications: "New Approach to Optimization of the Multistage Flash Desalination Process", Summer Simulation Conference, San Diego, 1972.

RICHARD J. CHISHOLM Business Address: GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Education: B.E.E., Manhattan College, 1948 M.B. A. , Fairleigh Dickinson University,1971.

Post graduate courses in Electrical Engineering, 1 l

New York University and New Jersey Institute of Technology.

i Experience:

Manager, Electrical Power and Instrumentation, l GPU Nuclear Corporation /GPU Service Corporation, 1980 to present. Manager of engineering section responsible for design activities for plant systems )

related to electrical power and instrumentation.

Senior Electrical Engineer, GPU Service Corporation, 1971 to 1980. Lead engineer for all instrumenta-tion and control design activities for nuclear and fossil plants.

Manager of Electrical Design, Curtus-Wright Cor-poration, Electronics Division, 1966 to 1971.

Responsible for engineering group involved in design of instrumentation and control equipment for Navy nuclear program.

Chief Engineer of a small company engaged in the manufacturing of I&C equipment for industrial and shipboard applications. 1958 to 1966.

Project Engineer with manufacturer of control equipment. 1951 to 1958.

Consolidated Edison Company. Design of instrumen-tation and control systems for power plants and substations. 1948 to 1951.

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