ML19309C553

App 1A to TMI-1 PSAR, Technical Qualifications. Includes Revisions 1-11

ML19309C553
Person / Time
Site:	Three Mile Island
Issue date:	05/01/1967
From:	JERSEY CENTRAL POWER & LIGHT CO., METROPOLITAN EDISON CO.
To:
References
NUDOCS 8004080758
Download: ML19309C553 (12)

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METROPOLITAN EDISON ObihPANY TH R EE M I LE IS LAN D """"' *"F*d NUCLEAR STATION UNIT 1 i

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TABLE OF CCNTENTS b

Section _Pa 1 INr ODUCTION AND

SUMMARY

. . Volume 1 . . . Tab 1 . . . l-

1.1 INTRODUCTION

. . . . . . . . . . . . . . . . l-1.2 DESIGN HIGHLIGHTS . . . . . . . -. . . . . . . . l-1.2.1 SITE CV.ARACTERISTICS . . . . . . . . . . . . . 1-1.2.2 PCWER LEVEL . . . . . . . . . . . . . . . l-1.2.3 FIJX SPECIFIC PCWER LEVEL . . . . . . . . . . l-1.2.h REACTOR BUILDING SYSTEM . . . . . . . . . . . . 1-1.2.5 ENGINEERED SAFEGUARDS . . . . . . . . . . . . . l-1.2.6 ELECTRICAL SYSTEMS AND EMERGENCY POWER . . . . . . . 1-1.2.7 ONCE-THROUGH STEAM GENERATORS . . . . . . . . . . 1-13 TAEULAR CHARACTERISTICS . . . . . . . . . . . . . 1-1.4 PRINCIPAL DESIGN CRITERIA . . . . . . . . . . . . l-1.h.1 CRITERION 1 . . . . . . . . . . . . . . . l-1.k.2 CRITERION 2 . . . . . . . . . . . . . . . l-1.h.3 CRITERION 3 . . . . . . . . . . . . . . . 1-1.k.4 CRITERION k . . . . . . . . . . . . . . . 1-1.h.5 CRITERICN 5 . . . . . . . . . . . . . . . 1-1.h.6 CRITERION 6 . . . . . . . . . . . . . . . 1-1.h.7 CRITERICN 7 . . . . . . . . . . . . . . . 1-1.h.8 CRITERION 8 . . . . . . . . . . . . . . . 1-1.k.9 CRITERION 9 . . . . . . . . . . . . . . . 1-1.h.10 CRITERION 10 . . . . . . . . . . . . . . . 1-1.h.11 CRITERION 11 . . . 1-O t ' 12 caltzale= 12 - . . .. - . - . - . . - - . - 1-1.k.13 CRITERION 13 . . . . . . . . . . . . . . . 1-  !

1.k.lk CRITERION 14 . . . . . . . . . . . . . . . 1-I 1.h.15 CRITERION 15 . . . . . . . . . . . . . . . 1-1.h.16 CRITERION 16 . . . . . . . . . . . . . . . 1-1.h.17 CRITERION 17 . . . . . . . . . . . . . . . 1- '

l.k.18 CRITERICN 18 . . . . . . . . . . . . . . . 1-1.4.19 CRITERION 19 . . . . . . . . . . . . . . . 1- l 1.h.20 CRITERION 20 . . . . . . . . . . . . . . . 1. i 1.h.21 CRITERION 21 . . . . . . . . . . . . . . . 1- I 1.h.22 CRITERION 22 . . . . . . . . . . . . . . . 1- l 1.h.23 CRITERION 23 . . . . . . . . . . . . . . . 1- l 1.h.24 CRITERICN 24 . . . . . . . . . . . . . . . 1- i 1.k.25 CRITERICN 25 . . . . . . . . . . . . . . . 1-: I 1.h.26 CRITERION 26 . . . . . . . . . . . . . . . 1-;

1.4.27 CRITERION 27 . . . . . . . . . . . . . . . 1-:

15 RESEARCH AND DEVELOPMENT REC.UIREMENTS . . . . . . . . 1-;

1.5.1 ONCE-THROUGH STEAM GENERATOR TEST . . . . . . . . . 1-;

1.5.2 CorROL ROD DRIVE LINE TEST . . . . . . . . . . . 1-;

1.5 3 SELF-PCWERED DETECTOR TESTS . . . . . . . . . . . 1-;

l.5.4 THERMAL AND HYDRAULIC PROGRAMS . . . . . . . . . . 1-;

1.6 IDENTIFICATION OF AGENTS AND CONTRAC"' ORS. . . . . . . . 1-;

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i 1.7 CCNCLUSIONS . . . . . . . < . . . . . . . . . 1-;

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2 SITE AND ENVIRONMENT

• Tab 2 Volume 1

• 4 2.1 GENERAL DESCRIP"' ION .. . . . . . . . . . . ...

2.2 LOCATION, POPULATION,AND LAND USE . . . . . . ...

2.2.1 LOCATION . . . . . . . . . . . . . . ...

2.2.2 POPULATICN . . . . . . . . . . . . . ...

2.2 3 LAND USE . . . . . . . . . . . . . ...

2.3 METEOROLOGY . . . . . . . . . . . . . ...

2.3.1

SUMMARY

2.3.2 SEVERE WEATHER. . , . . . . . . . . . . ....

2 3.3 AVERAGE ATMOSPHERIC DISPERSION . . . . . . . ...

2 3.h ATMOSPHERIC DIF?USION FOR ASSESSING ACCIDENTS . . ....

2.4 HYDROLOGY AND GROUNWATER . . . . . . . . . ...

2.k.1 CHARACTERISTICS OF STREAMS IN VICINITY . . . . ...

2.h.2 OTHER POWER PROJECTS IN VICINITY . . . . . . ...

2.k.3 LOW FLOW STUDIES . . . . . . . . . . . ...

2.h.k FLOOD FLOW STUDIES . . . . . . . . . . . ...

2.k.5 DESIGN OF PROPOSED DAMS AND SPILLWAYS . . . . ...

2.4.6 GROUNDWATER . . . . . . . . . . . . . ....

2.5 GEOLOGY . . . . . . . . . . . . . . ....

2.6 SEISMICITY . . . . . . . . . . . . . . ....

2.6.1 SEISMICITY . . . . . . . . . . . ....

2.6.2 RESPONSE SPECTRA . . . . . . . . . . . ....

2.7 REFERENCES

3 REACTOR . . . . . . . . Volume 1 . . Tab 3 ...

31 DES 1GN uSES . . . . . . . . . . . . . ...

3.1.1 PERFORMANCE OBJECTIVES . . . . . . . . . ...

3.1.2 LIMITS . . . . . . . . . . . . . . ...

32 REACTOR DESIGN . . . . . . . . . . . . . ...

3 2.1 GENER'J.

SUMMARY

3 2.2 NUCLEAR DESIGN AND EVALUATION . . . . . . . ...

323 THERMAL AND HYDRAULIC DESIGN AND EVALUATION . . ...

3 2.4 MECHANICAL DESIGN LAYOUT . . . . . . . . . ...

33 TESTS AND INSPECTIONS . . . . . . . . . . ...

331 NUCLEAR TESTS AND INSPECTION . . . . . . . ...

332 THERMAL AND HYDRAULIC TESTS AND INSPECTION . . . ..,

3 3.3 JUEL ASSEMBLY, CONTROL ROD ASSEMBLY, AND CONTROL RCD DRIVE MECHANICAL TESTS AND INSPECTION . . . ...

3 3.h INTERNALS TESTS AND INSPECTIONS . . . . . . ...

3.k REFERENCES . . . . . . . . . . . . . ...

h REACTOP COOLANT SYSTEM Volume.1 . Tab.4 .

h.1 DESIGN BASES 4.1.1 PERFCRMAN6; OBJECTIVES . . . . . . . . . ...

h.l.2 DESIGN CHARACTERISTICS . . . . . . . . . ...-

k.l.3 EXPECTED OPERATING CONDITIONS . . . . . . . ....

h.1.k SERVICE LIFE . . . . .

O O h.l.5 CODES AND CLASS m CATIONS . . . . . . . . ...-

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~ REACTCR COOLANT SYSTEM (CONTINUED) . . Volume 1 . . Tab.h .

h.2 SYSTEM DESCRIPTION AND OPERATICN . . . . . . . . . . h h.2.1 GENERE DESCRIPTION . . . . . . . . . . . . . k ,

k.2.2 MAJOR CCMFONENTS . . . . . . . . . . . . . . h  !

k.2 3 PRESSURE-RELIEVING DEVICES . . . . . . . . . . . h k.2.h ENVIRONMENTE PROTECTION . . . . . . . . . . . . h 4.2.5 MATERIES OF CONSTRUCTION ~ . . . . . . . . . . . h h.2.6 MAXIMUM HEATING AND COOLING RATES . . . . . . . . . k l k.2 7 LEAK DETE ZION . . . . . . . . . . . . . . . k h.3 SYSTEM DESIGN EVALUATION . . . . . . . . . . . . k '

h.3 1 Sir m uCTORS . . . . . . . . . . . . . . . u l

h.3 2 RELIANCE ON INTERCONNECTED SYSTEMS . . . . . . . . k j h.3.3 SYSTEM INTEGRITY . . . . . . . . . . . . . . k '

h.3.4 PRESSURE PETm . . . . . . . . . . . . -. . . h h.3 5 REDUNDANCY . . . . . . . . . . . . . . . . h 4.3.6 SAFETY ANALYSIS . . . . . . . . . . . . . . h k.3 7 OPERATIONAL LIMITS . . . . . . . . . . . . . . k i

h.h TESTS AND INSPECTIONS . . . . . . . . . . . . . k l h.k.1 CCMPONENT IN-SERVICE INSPECTION . . . . . . . . '. k 4.h.2 REACTOR COOLANT SYSTEM TESTS AND INSPECTIONS . . . . . k 4.h.3 MATERIE IRRADIATION SURVEILLANCE . . . . . . . . . h k.5 REFERENCES . . . . . . . . . . . . . . . . . 4 l 5 CONTAINMENT SYSTEM . . . . Volume 1 . . . Tab 5 . . 5 51 REACTOR BUILDING . . . . . . . . . . . . . . . 5

' 5.1.1 DESIGN BASES . . . . . . . . . . . . . . . 5 5 1.2 STRUCTURE DESIGN . . . . . . . . . . . . . . 5 5.2 ISOLATION SYSTEM . . . . . . . . . . . . . . . 5 5 2.1 DESIGN BASES . . . . . .

. . . . . . . . . 5 i 5 2.2 SYSTEM DESIGN . . . . . . . . . . . . . . . 5  !

53 VENTILATION SYSTEM . . . . . . . . . . . . . . 5 531 DESIGN BASES . . . . . . . . . . . . . . . 5 532 SYSTEM DESIGN . . . . . . . . . . . . . . . 5 5.h LEAKAGE MONITORING SYSTEM . . . . . . . . . . . . 5 5.5 SYSTEM DESIGN EVALUATION . . . . . . . . . . . . 5 5.6 TESTS AND INSPECTION . . . . . . . . . . . . . . 5 5.6.1 FREOPERATIONAL TESTING AND INSPECTION . . . . . . . 5 5.6.2 POSTOPERATIONAL LEAK MONITORING . . . . . . . . . 5 6 ENGINEERED SAFEGUARDS . . . Volume 1 . . . Tab 6 . . . 6 6.1 EMERGENCY INJECTION . . . . . . . . . . . . . . 6 6.1.1 DESIGN BASES . . . . . . . . . . . . . . . 6 s.1.2 DESCRI m 0N . . . . . . . . . . . . . . . . e 6.1 3 DESIGN EVALUATION . . . . . . . . . . . . . . 6 6.1.4 TESTS AND INSPECTIONS . . . . . . . . . . . . . 6 6.2 REACTOR BUILDING ATM0 SPHERE COOLING AND WASHING . . . . 6 6.2.1 DESIGN BASES . . . . . . . . . . . . . . . . 6 g 6.2.2 '

DESCRIPTION . . . . . . . . . . . . . . . . 6 U '

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Ssetion 6 ENGINEERED SAFEGUARDS (CONTUUED) . . Volume 1 . . Tab 6 6.2.3 Dl: SIGN EVALUATION . . . . . . . . . .....

6.2.4 TESTS AND USPECHONS . . . . . . . . .....

6.3 ENGINEERED SAFEGUARDS LEAKAGE AND RADIATION CONSIDERATIONS . . . . . . . . . . .....

6.3.1 INTRODUCH ON . . . . . . . . . . .....

6.3.2

SUMMARY

OF POSTACCIDENT RECIRCULATION AND LEAKAGE CCNSIDERATIONS . . . . . . . .....

6.3.3 LEAKAGE ASSUMPTIONS . . . . . . . . .....

6.3.4 DESIGN BASIS LEAKAGE . . . . . . . . .....

6.3.5 LEAKAGE ANALYSIS CONCLUSIONS . . . . . .....

7 INSTRUMENTATION AND CONTROL . Volume.2 . . . Tab 7 . . .

7.1 PROTECTION SYSTEMS . .. . . . . . . . .....

7.1.1 DESIGN BASES . . . . . . . . . . .....

7.1.2 SYSTEM DESIGN . . . . . . . . . . .....

7.1 3 SYSTEMS EVALUATION . . . . . . . . . .....

7.2 REGULATING SYSTEMS . . . . . . . . . .....

7.2.1 DESIGN BASES . . . . . . . . . . . .....

7.2.2 SYSTEM DESIGN . . . . . . . . . . .....

7.2.3 SYSTEM EVALUAU CN . . . . . . . . . .....

73 INSTRUMENTATION . . . . . . . . . . .....

7 3.1 NUCLEAR INSTRUMENTAHON . . . . . . . .....

732 NONNUCLEAR PROCESS INSTRUMENTATION . . . .....

7 3.3 O 7.h INCORE MONITORING SYSTEM .

OPERATING CONTROL STATIONS . .

7.h.1 Gu M LAYOUT . . . . . . . . . . .....

7.k.2 INFORMATION DISPLAY AND CONTROL WNCTION . .....

7.k.3

SUMMARY

OF ALARMS . . . . . . . . . .....

7.h.h COMMUNICATION . . . . . . . . . . .....

7.4.5 OCCUPANCY . . . . . . . . . . . .....

7.h.6 AUXILIARY CONTROL STAHONS . . . . . . ..... <

7.h.7 SAFETY FEATURES . . . . . . . . . . ..... I 8 ELECTRICAL SYSTEMS . . . . Volume 2 . . . Tab 8 . . .

8.1 DESIGN BASES .. . . . . . . . . . . .....

8.2 ELECTRICAL SYSTEM DESIGN . . . . . . . .....

8.2.1 NETWORK UTERCONNECTIONS . . . . . . . .....

8.2.2 STATION DISTRIBUTION SYSTEM . . . . . . .....

8.2 3 EMERGENCY PcwER . . . . . . . . . . .....

8.3 TESTS AND INSPECTICNS . . . . . . . . .....

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Section P 9 AUXILIARY AND EMERGENCY SYSTEMS . Volume 2 . . Tab 9 . . 9 91 MAKEUP AND PURIFICATICN SYSTEM . . . . . . . . . . 9 J 9 1.1 DESIGN BASES . . . . . . . . . . . . . . . 9 9 1.2 SYSTEM DESCRIPTION AND EVALUATICN . . . . . . . . . 9 I

92 CHEMICAL ADDITION AND SAMPLING SYSTEM . . . . . . . . 9 9.2.1 DESIGN Bt.SES . . . . . . . . . . . . . . . 9 ,

9 2.2 SYSTEM DESCRIPHON AND EVALUATION . . . . . . . . . 9 9.3 I7TERMEDIATE COOLING SYSTEM . . . . . . . . . . . 9 9.3.1 DESlGN BASES . . . . . . . . . . . . . . . 9 9.3.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9 9.h SPENT FUEL CCOLING SYSTEM . . . . . . . . . . . . 9 9.h.1 DESIGN BASES . . . . . . . . . . . . . . . 9 9.4.2 SYSTEM DESCRIPTION AND EVALUAUCN . . . . . . . . . 9 9.$ DECAY HEAT REMOVAL SYSTEM . . . . . . . . . . . . 9 9 5.1 DESIGN BASES . . . . . . . . . . . . . . . 9 9.5.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9  ;

9.6 COOLING WATER SYSTEMS . . . . . . . . . . . . . 9 9.6.1 DESIGN BASES . . . . . . . . . . . . . . . 9 9.6.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9 9.7 FUEL HANJLING SYSTEM . . . . . . . . . . . . . . 9 9 7.1 DESIGN BASES . . . . . . . . . . . . . . . 9 9 7.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9 9.8 STATICN VENU LATION SYSTEMS . . . . . . . . . . . 9 9.8.1 DESIGN BASES . . . . . . . . . . . . . . . 9 9.8.2 SYSTEM DESCRIPTION AND EVALUATION . . . . . . . . . 9

. O 10 STEAM AND PCWER CONVEESION SYSTEM . Volume 2 . . Tab 10 . . 1 10.1 DESIGN BASES . . . . . . . . . . . . . . . . 1 10.1.1 OPERATING AND PERFORMANCE REQ,UIREMENTS . . . . . . . 1 10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS . . . . . . . . . 1 10.1.3 FUNCTIONAL LIMITATIONS . . . . . . . . . . . . 1 10.1.4 SECONDARY FUNCTIONS . . . . . . . . . . . . . 1 10.2 SYSTEM DESIGN AND OPERATION . . . . . . . . . . . 1 10.2.1 SCHEMATIC FLCW DIAGRAM . . . . . . . . . . . . 1 10.2.2 CODES AND STANDARDS . . . . . . . . . . . . . 1 10.2 3 DESIGN FEATURES . . . . . . . . . . . . . . 1 10.2.h SHIELDING . . . . . . . . . . . . . . . 1 10.2 5 CORROSION PROTECTION . . . . . . . . . . . . . 1 10.2.6 IMPURIHES CONTROL . . . . . . . . . . . . . . 1 10.2.7 RADI0ACH VITY . . . . . . . . . . . . . . .. 1 10 3 SYSTEM ANALYSIS . . . . . . . . . . . . . . . 1 10 3 1 TRIPS, AUTCMATIC CCNTROL ACTIONS, AND ALARMS . . . . . 1 10 3.2 TRANSIENT CONDITIONS . . . . . . . . . . . . . 1 10.3.3 MALIUNCTIONS . . . . . . . . . . . . . . . 1 10 3.k OVERPRESSURE PROTECU CN . . . . . . . . . . . . 1 10 3 5 INTERACTIONS . . . . . . . . . . . . . . . 1 10 3.6 OPERATIONAL LIMITS . . . . . . . . . . ... 1 10.h TESTS AND INSPECTIONS . . . . . . . . . . . . . 1 0

0002 058

Section _E 11 RADI0 ACTIVE WASTES AND RADIATICN PROTECTION _ - _ _ _. _ _. - . .. . . . . Volme 2 . . Tab 11 . . 1 11.1 RADIOACTIVE WASTES . . . . . . . . . . . . . . 1 11.1.1 DESIGN BASES . . . . . . . . . . . . . . . . 1 11.1.2 SYSTEM DESIGN . . . . . . . . . . . . . . . 1 11.1 3 TESTS AND INSPECTICNS . . . . . . . . . . . . . 1 11.2 RADIATION SHIELDING . . . . . . . . . . . . . . 1 11.2.1 PRIMARY, SECCNDARY, REACTOR BUILDING, AND AUXILIARY SEIELDING . . . . . . . . . . . . . 1 11.2.2 AREA RADIATION MONITORING SYSTEM . . . . . . . . . 1 11.2 3 HEETH PHYSICS . . . . . . . . . . . . . . . 1 11 3 REFERENCES . . . . . . .- . . . . . . . . . . 1 12 ,

CONDUCT OF OPERATIONS . . . . . Volme 2 . . Tab 12 . . 1 12.1 ORGANIZATICN AND' RESPONSIBILITY . . . . . . . . . . 1 12.1.1 FUNCTIONE DESCRIPTION . . . . . . . . . . . . 1 12.1.2 QUALIFICATIONS . . . . . . . . . . . . . . 1 12.1 3 ORGAN 12ATION DIAGRAM . . . . . . . . . . . . . 1 12.2 TRAINING . . . . . . . . . . . . . . . . . 1 12.2.1 STATICN STAFF . . . . . . . . . . . . . . . 1 12.2.2 REPLACEMENT PERSONNEL . . .. . . . . . . . . . . .1 12.2 3 CN-THE-JOB TRAINING . . . . . . . . . . . . . 1 12.2.4 ENERGENCY DRILLS . . . . . . . . . . . . . . 1 12.3 WRITTEN PROCEDURES . . . . . . . . . . . . . . 1 12.k RECORDS . . . . . . . . . . . . . . . . . 1 O~

12 5 ADMINISTRATIVE CONTROL . . . . . . . . . . . . . 1 13 INITIAL TESTS AND OPERATION . . . Volme.2 . . Tab 13 . . 1 13 1 TESTS PRIOR TO REACTOR EUELING . . . . . . . . . . 1 13 2 INITIE CRITICEITY . . . . . . . . . . . ..

1 13 3 POSTCRITICALITY TESTS . . . . . . . . . . . . . 1 lk SAFETY ANALYSIS

. . . . Vol me 2 . . Tab 14 . 1 lb.1 CCRE AND COOLANT BOUNDARY PROTECTION ANEYSIS . . . . . 1 1h.1.1 ABNCRMALITIES . . . . . . . . . . . . . . . 1 14.1.2 ANALYSIS OF EFFECTS AND CON 3EQUENCES . . . . . . . . 1 lb.2 STANDBY SAFEGUARDS ANALYSIS . . . . . . . . . . . 1 lk.2.1 SITUATIONS ANEYZED AND CAUSES . . . . . . . . . . 1 lb.2.2 ACCIDENT ANEYSES . . . . . . . . . . . . . . 1 lb.3 REFERENCES . . . . . . . . . . . . . . . . . 1 15 TECHNICE SPECIFICATIONS . . . . Volme 2 . . Tab 15 . 1 O

0002 059

TABLE OF APPENDICES A;;endix 1A TECHNICAL QUALIFICATICNS . . . . . . . Volu=e 3 . . . Tab 1A 2A ENGINEERING GECLOGY AND FOUNDATION CONSIDERATIONS . . . . . . .. .. . Volume 3 . . . Tab 2A 23 SEISMOLOGY AND METEOROLOGY , . . . . . Volu=e 3 . . . Tab 23 2C GROUND-WATER HYDROLCGY . . . . . . . . Volu=e 3 . . . Tab 2C 2D GEOLOGY . . . . . . . . . . . . . . . Volu=e 3 , . . Tab 2D 5A STRUCTURAL DESIGN 3ASES. . . .. . . . Volu=e 3 . . . Tab 5A 53 DESIGN PROGRAM FON REAC*CR BUILDING. . Volu=e 3 . . . Tab 5B 3C DESIGN CRITERIA FOR REACTOR SUILDING . Volume 3 . . . Tab 5C 5D QUALITY CONTROL. . . . . . . . . . . . Volu=e 3 . . . Tab 5D SE LINER PLATE SPECIFICATION . . . . . . Volu=e 3 . . . Tab SE 5F REACTOR SUILDING INS *RUMENTATION . . . Volu=e 3 . . . Tab 5F Supole=ent

1. . . . . . . . . . . . . . .. . . . . Volume h . . Supplement No. 1

2. . . . . . . . . . . . . . . .. . . . Volu=e k . . Supplement No. 2

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s 3 . . . . . . . . . . . . . . . . . . . . Volu=e 5 . . S uppleme nt No . 3 k . . . . . . . . . . . . . . . . . . . . Volume 5 . . S upplement No . h 5 . . . . . . . . . . . . . . . . . . . . Volu=e 5 . . S upple=e nt No . 5 o

V vii (Revised 6-23-68) 0002 060

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APPENDIX 1A TECHNICAL QUALIFICATIONS 1 METROPOLITAN EDISON COMPANY TECHNICAL QUALIFICATIONS 1.1 GENEPE Metropolitan Edison Capany has 8h years' experience in the operation of electric generating stations.

Met-Ed operates four steam electric generating plants with a total of 12 units and a total net capability of 8h5,300 kv. Also, one hydroelectric station with an average capability of 1h,000 kw is operated by Met-Ed.

The ecmpany has a total plant investment of $361,990,000 and employes over 2,300 people.

The ccmpany is a subsidiar/ of the General Public Utilities Corporation.

1.2 NUCLEAR PARTICIPATION Met-Ed is a partner with other GPU subsidiaries in Saxton Nuclear Experimenta:

Corporation. This Corporation, fomed in 1959, operates the Saxton Station, a 23,500 kw nuclear steam electric generating station for research, operating.

and engineering experience. Many Met-Ed empicyees who will be involved in the operation of 'Ihree Mile Island Nuclear Station vill have received training and experience at the Saxton Station.

2 THE 3ABCCCK & WILCOX COMPANY - TECHNICAL QUALIFICATIONS 2.1 GENERAL The Babcock & Wilcox Company was founded as a partnership in 1867 and organize as a corporation in 1881. B&W is a videly diversified empany serving the electric utility, transportation, steel, petroleum, chemical, pulp and paper, and nachiner/ industries , as well as one of the world's ' leading suppliers of specialty steels. B&W is a =ajor supplier of ecmponents for the nuclear Navy.

The Ccmpany ranks as one of the larger American industrial enterprises with corporate total current assets of over $262,000,000 at the end of 1966. Orders received in 1966 exceeded $8ho,000,000, and 1966 income before 1 taxes and minority interests was over $62,h00,000. The back1cg at the end of 1966 vas more than $915,500,000. Current orders for nuclear ccuponents systems, and fuel exceed $300,000,000.

B&W employs over 30,000 persons in facilities throughout the United States ,

Canada, Great Britain, and Sweden. Of this total, over 1,000 are technical and scientific personnel working in the nuclear power activities.

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As the world's largest manufacturer of steam generating equip =ent, B&W is a reccgnized leader in the American industrial family. The Cc=pany has contributed materially to the development of fundamental materials '

data, heat transfer data, manufacturing and erection processes , and inspection techniques used in the steam generating equip =ent industry.

2.2 DIVISIONS AITD SUBSIDIARIES The major Divisions and Subsidiaries of the Ccepany located in the United States , and their products , include: ,

a. Boiler Division The Boiler Division designs, manufactures, installs, and services nuclear and conventional steam generating systems and equipment and heavy pressure. vessel equipment for the utility, petrochemical, and other indnstries. 'Ihe Division designs and manufactures reactor vessels , steam generators ,

and pressurizers for the nuclear Navy, for the USAEC, and for cer::=ercial nuclear pcuer plants. The Division also manufactures reactor cores for cor::=ercial nuclear power plants.

b. Tubular Preducts Division The Tubular Products Division is one of the world's leading suppliers of specialty steel tubing, extrusions , and fittings.

c. Refractories Division The Refractories Division mines raw material and manufactures a ccuplete line of refractory =aterials and high temperature insulation for use in the utility, glassmaking, metals manu-facturing, and space industries,

d. Autcmated Machine Division The Automated Machine Division furnishes the autcmotive and related industries with highly automated production machinery.

e. Atomic Enerey Division The Atomic Energy Division conducts development programs on advanced nuclear power plant concepts , systems designs , and nuclear fuel management pregrams.

f. Research and Develetment Division The Research and Development Division conducts research , develop-ment, and testing pregrsms for the other Divisions and Subsidiaries of the Company. Development programs are also conducted under contract in the areas of heat transfer, metallurgy, nuclear fuels developnent, critical experiments, and radiochemistry pregrams. g The Division's test reactor (BAWTR) and hot cell facilities are W utill:ed for irrad:.ation testing, isotope production, and irradi-ation encapsulatien services.

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g. Bailey Meter Cmpany -

kiley Meter Ccmpany designs and =anufactures instruments ,

controls , and ccuputers for power generation, industrial processes , and naval and =erchant vessels. Bailey also produces a full line of nuclear instrumentation, incore instrumentation, safety systems , and process instru=enta-tion for use in nuclear power plants.

h. Diamond Power Specialty Ccrn:any Diamond Power designs and manufactures boiler cleaning equipment, special gauges , industrial television systems ,

stud tensioners, and reactor control red drive mechsuisms.

i. Babcock-Wilcox and Goldie-McCulloch Li=ited This organization is a =ajor Canadian supplier of steam generators , pumps , and process equipment for a variety of uses in the utility, pulp and paper, and chemical indus-tries. It is also a major Canadian supplier of stesm generators for nuclear power plants.

2.3 NUCLEAR EXPERIENCE B&W's participation in the development of nuclear power dates from the Manhattan project. B&W's nuclear activities are broad and include applied research to develop fundamental data, design and manufacture Os of nuclear systems ccmponents , and design and manufacture of ccuplete nuclear steam generating systems.

The major activities and accomplishments in the water-cooled and moder-ated reactor field are sunmarized below,

a. Indian Point No.1 (Censolidated Edison Ccmpany of New York, Inc.)

In 1955, B&W contracted for the development, design, and supply of the nuclear steam supply system, reactor core, and related control system for Consolidated Edison's Indian Point No.1 Unit. Indian Point No.1 ia a light-water-cooled and moderated pressurized vater reactor system rated at 585,000 thermal kilowatts. The unit includes a separately fired superheater which heats steam from the reactor system before introduction into a 275,000 kilowatt electric generator. Indian Point No.

1 vent into ectmercial operation in January 1963.

b. NS Savannah (USAEC)

B&W was awarded a contract in 1957 to develop, design, and supply the entire propulsion plant for the NS Savannah. B&W's initial contract scope included, in addition to the design and supply of equipment and reector core, the responsibility for safety analysis work, supervision of propulsion plant equipment O.. .... .

erection, crew training, and advice in fuel lorsding, testing, 8

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and operation. Through later ancillary contracts , B&W personnel developed and directed the propulsion testing, start-up, and initial operational programs.

B&W has continued to supply services in the areas of crew training, upgrading, and operation.

The NS Savannah vent into ecz:mercial operation in May of 1962 and has been in continuous service since except for a one-year enforced outage resulting frcm a labor dispute.

The Savannah nuclear steam supply system is a light-water-cooled and moderated pressurized water plant rated at 80,000 thermal kilowatts.

c. Advanced Test Reactor (Ebasco/USAEC)

B&W vas retained in 1960 as the nuclear subcontractor to Ebasco Services, Inc., for the design of the Advanced Test

, Reactor. B&W's final scope of work included the design of the nuclear portion of the reactor ccmplex including the reactor core, critical experiments, control rod drives, reactor vessel internals , and fuel handling tools. In addition, B&W was responsible for supervising the research and developnent pregrs=s including corrosion testing, fuel assembly development and heat transfer testing, and the supply of the reactor control rod drive system, as well as the design of inpile test loops. The advunced Test Reactor is a light-vater-cooled and moderated high flux test reactor rated at 250,000 themal kilevatts ,

d. Otto Hahn Power Plant B&W received in 1960, through its Geman licensee , Deutsche Babcock & Wilcox, a contract to provide technical and design consultation and assistance on the nuclear steam supply system and reactor core for the Geman Nu.: lear Ship, " Otto Hahn."

Tne reactor is an advanced light-water-cooled and moderated pressurized water reactor in which the core, stes= generator, primary pumps , and piping are integrated into a single pressure vessel similar to B&W's Consolidated Nuclear Sterm Generator (CNSG). The reactor is rated at 38,000 themal kilevatts.

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e. Oconee Nuclear Station Units 1 and 2 (Duke Power Comagny) l B&W has a contract to supply two pressurized water nuclear I

steam supply systems. Each system is rated at 2,h52 MWt for a net electrical output of 839 MW. The first unit is scheduled for service in May 1971 and the second in May 1972. Each

, reactor uses chemical shim and control rods for reactivity l control and generates steam with a small amount of superheat in once-through steam generators .

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f. Jersey Central Power and Light Ccutany ~

B&W will supply one pressurized water nuclear steam supply system for instnllation at an undisclosed site. Initial operation is scheduled for 1973. The unit is rated at apprcximately 600 MWe net and vill be a near-duplicate of-the units being supplied to the Duke Power Ccmpany and the Metropolitan Edison Ccepany.

g. Florida Power Cortoration B&W vill supply one pressurized water nuclear steam supply system for installation at the Crystal River Station (near Tampa, Florida). Initial operation is scheduled for 1972.

The unit is rated at approximately 820 MWe (net) and vill be a near-duplicate of the units to be supplied for Duke Power Capany, Metropolitan Edison Company, and Jersey Central Power and Light Ccmpany.

h. Research Reactors B&W has designed and supplied seven research and test reagtors ranging in size frem 1,000 to 6,000 themal kilowatts.

1. Research and Develotment B&W's research and developent and study efforts are significant and range from developent of basic physics and materials data

~, O through the developent of ccuplete reactor systems including a substantial effort in advanced converter and breeder reactor systems. I 2.4 ORGANIZATION 1

B&W's Boiler Division vill execute the Metropolitan Edison Ccmpany contract with active participation by the other Divisions and Subsidiaries. )

3 GILBERT ASSOCIATES - TECHNICAL QUALIFICATIONS 3.1 GENERAL Gilbert Associates , Inc. , engineers and consultants , was organized in 1906 and has its main office at Reading, Pennsylvania. Principal offices are ,

l also located at Philadelphia, Pittsburgh, and New York City. Originally known as W. S. Barstov and Ccmpany, the corporate name was changed to E. M.

Gilbert Engineering Corporation in 1933; in 19h2, the corporate structure l

vas revised to provide for ccmplete employee ownership and the name became Gilbert Associates, Inc.

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Throughout the past 60 years Gilbert Associates has pregressively grown in size and in scope of activity. The collective experience and capa-bilities of the firm offer ecmplete consulting cnd engineering services in both investor-owned utilities and to general industry in such diverse fields as : nuclear and conventional power generation; transmission, substation, and distribution systems ; economic engineering and management consulting service; steel making and processing; cement and minerals processing; chemical and general industrial facilities ; vater desalination plants ; institutional and commercial installations ; environ = ental and solid vaste treat =ent; and water production projects. Projects undertaken have ranged frca large electric power generating plants and production facilities to small industrial boiler plants and allied service facilities.

Since 1942 Gilbert Associates has been made responsible for the design of over 110 themal generating units both fossil and nuclear power representing more than 16,000,000 kilowatts of new generating capacity. Gilbert's experience includes one of the first reheat units , one of the first once through boiler units , and one of the first supercritical steam pressure units. Designs range in ratings up to 900,000 kw in stations of varied complexities - =ine-mouth, closed cycle cooling tower, base-load, peaking, and others. At present Gilbert has over 8,000,000 kw of generation under design.

3.2 NUCLEAR EXPERIENCE l Since 1950 Gilbert has played an active and i=portant role in the

) development of nuclear energy for private utilities , industry, and governmental agencies. Gilbert projects include ccmplete programs g of nuclear power developnent involving analysis of sites , cceplete evaluations of proposals , contract and fuel program assistance, prep-aration of license applications, ccmplete plant design and procurement.

The following is a chronological su= mary of scme of the significant nuclear projects undertaken by Gilbert:

1955 - Design proposal for South Carolina Electric 3: Gas Company in negotiation of possible demonstration pressurized water reactor (later Shippingport) sponsored by U. S. Atomic Energy Cannission.

i 1956 - Study and evaluation of 60 MWe pressurized water reactor I

plant for Manila Electric Ccmpany.

1957 - Detailed Design study for a 20 MWe pressurized water reactor plant for overseas application for Amy Reactors Branch of U. S. Atcmic Energy Ccamission.

1958 - Preliminary specifications , designs and cost estimates , and proposal evaluation for 5 to 10 MWe boiling and pressurised water reactors for General Public Utilities Corporation.

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1958 - Detailed study of application of water reactors (5 to 70 MWe)

O in remote locations for Department of The Air Force.

1959 - Design, and construction management of 20 MWt Saxton Experiments Power Reactor plant as subcontractor to Westinghouse for Genera' Public Utilities Corporation.

1960 - Detailed study of nuclear power reliability involving five operating reactors for Department of the Air Force including the SM-1 at Fort Belvoir, SL-1 in Idaho, Shippingport, EBWR at Argonne , and the Vallecitos BWR have been reviewed and the reliability of the ccuponents and systems in each plant evaluated.

1961 - Fallout shelter surveys in eastern Pennsylvania for Department of Defense.

1962 - Preliminary design and cost estimate for SPX reactor as part of Supercrities1, Once-through Tube Reactor (SCOTT-R) program for Westinghouse Electric Corporation.

1963 - For Atcmics International, development of original concept, prelim nary design, and cost estimates for 160 MWt organic reactor to provide power and steam to Packaging Corporation of America mill.

1963 - Engineering and econcmic evaluations for 600 MWe Oyster Creek turnkey proposed designs for Jersey Central Power s and Light Ccupany.

1963 - Develo; ment of a nuclear power reactor containment design concept for plants in close proximity to large population centers.

1963 - DeveloInent of system planning procedures which indicate capacity addition patterns for most economical power generation, broadening applicability of nuclear power.

1963 - Preliminary plant designs and cost estimates for 170 MWe and 260 MWe gas-cooled nuclear pcwer plants for Rochester Gas and Electric Corporation.

196h - Preliminary plant designs and cost estimates for a 200 MWe sodium cooled nuclear power plant for Rochester Gas and Electric Corporation.

196h - Over-all plant design and engineering for 470 MWe Ginna nuclear power plant, as subcontractor to Vestinghouse, for Rochester Gas and Electric Corporation.

196h - Design for electrical espects of Saxton Superheat Loop experimental installation for Westinghouse Electric

. Corporation.

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1965 - Evaluation of a syste=-vide series of ten sites for a =ajor eastern U. S. utility for =ultiple unit application of large (600 MWe and over) nuclear power plants. The scope includes themal pollution studies and nuclear siting criteria.

1965 - Develop =ent of a fuel cycle ec=puter program which will estimate fuel cycle ecsts over long term periods and i

calculate isotope buildup in the core.

1 1965 - Design study and cost evaluation for converting Saxton into l a fast-breeder prototype for Westinghouse Corporation.

1965 - Pioneering the design of containment vessels by empicying

[ new concepts of design and construction. The use of pcst-tensicned concrete combined with hinged joints and pre-stressed rock-anchors leads to an accurate predicticn of the lead-carrying capacity of the vessels and consequently to minimum construction costs. The aseismic design of the containment vessel and of equipment and piping vill be based upon a dyna =ic analysis of the structure-soils system.

1966 - Plant design and engineering as subcontractor to Westinghouse for the 3ko MWe Mihama plant, Kansai Electric Pcver Company, Japan. Scheduled for completien in July 1970, the plant is located on Tsuruga Peninsula on the main Japanese Island of Ecnshu. Gilbert vill provide design engineering for all of the nuclear steam supply systems and structures.

1966 - Site evaluation specification and evaluation of proposals leading to the design of large nuclear power plants (500 MWe to 1,000 MWe) for four major eastern utilities: Metropolitan Edisen Co. , Florida Power & Light Co. , Baltimore Gas and Electric Co., and Pa. Power & Light Co.

1966 - Architect-engineer for an 8h0 MWo nuclear unit for the Metropolitan Edison Ceepany. Preliminary studies, over a period of nere than two years, indicated an ecencmic advantage for a nuclear unit over a fossil fuel unit.

During the studies numerous sites were investigated through-cut the area served by the utility. The results of compet-itive bidding produced a unit utilizing a pressurized water reactor and non-reheat turbine generator. The site finally selected includes a c1csed cycle cooling tcver arrangement for cendenser circulating water. This arrangement eliminates themal stream pollution, and provides a captive veter source for cooling purposes.

1967 - Architect-engineer and censultant to Florida Power Corporation for an 8ho MWe nuclear unit. Ccmplete evaluatica of three possible sites was necessary, and a ecmplete program of sub-surface investigatien and procedures was instituted at the O

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i selected site. Evaluation of total plant equipment bids re-O sulted in a pressurized water reactor with a reheat turbine.

The site involves installation at a plant which will have

, two existing ccal fired units en a coastal location.

3.3 ORGANIZATION The Gilbert Associates organization includes nearly 700 employees with a ecmplete staff of engineers , draftsmen,' and many technical specialists.

Included in the total staff are over 300 engineers and technical specialists and 160 draftsmen. This includes members of management, professional personnel, and incividuals in other specialized fields.

Responsibility for engineering and design of nuclear power plants is centered in the Utilities Division of the Ccmpany. Every nuclear project is assigned to a project manager, selected frca a staff of engineers having an average of about 15 years with Gilbert Associates. Through this divisional control, the production function of the project is carried through to ccepletion.

The engineering disciplines such as nuclear, =echanical, electrical, civil, structural, architectrual, environmental engineering, etc. are grouped into departments and provide the technical resource to the project. Each department is managed b,y a chief engineer, who provides technical and administrative responsibility to the personnel assigned to the various projects.

Additional necessary support to the project is provided from other N

service departments, including: drafting , estimating , apecifications ,

legal, accounting, purchasing, expediting , etc.

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SUMMARY

In summary, and in view of the above, it is believed that Gilbert Associates ,

Inc. is que.lified and capable of discharging its responsibilities to the project for which this license application is made.

k TECHNICAL QUALIFICATIONS OF UNITED ENGINEEPS AND CONSTRUCT 0R'S CONSTRUCTION STAFF, k.1 GENERAL United Engineers & Ccnstructors Inc. , with headquarters in Philadelphia, Pa. , was founded and incorporated in 1928 under the laws of the State of Delaware as a consolidation of four successful engineering sud construction organizations. In January 196k Jackson & Moreland, Inc. , a vell known consulting engineering fim established in Ecsten, Massachusetts in 1697, was merged and became the Jackson & Moreland Division. There are two wholly evned subsidiary ccmpanies , U. E. & C. (Canada) Ltd., which was incorporated in 1955, and Jackson & Moreland International, Inc., which was incorporated in 1958.

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The present scope of activities includes the design and/or construction of fcN.11 and nuclear pcver plants , power transmission lines and substations ,

researec snd development facilities, laboratories, cc==ercial and industrial .

buildings, chemical process plants, hot =etal, rolling, finishing and auxiliary plant facilities for steel and the other metal industries , and heavy industrial plants of other types. Consulting engineering is also provided for facility and site planning, ecencmic studies of steam and power systems , evaluations and appraisals , depreciation and rate studies ,

ccst analyses , continuing property records , studies of tax matters , and the furnishing of independent engineer's certificates.

General and engineering offices are located in Philadelphia and Boston.

A branch engineering office is =aintained in Chicago. There is also a cen=ercial office in Chicago and others in New York and Washington.

h.2 CONSTRUCTION All construction activities are managed frem the Philadelphia office.

Mr. R. H. reters is Vice President - Construction, and a = ember of the Board of Directors. Mr.' Peters is a C.E. graduate of Newark College of Engineering. He joined United Engineers in 19h5 As Vice President - Construction, Mr. Peters is responsible for all construction verk and maintains control over perfomance with respect to schedules , costs , purchasing, labor relations , and safety. Reporting to him are ten constructica managers , the chief safety engineer, the director of labor relations, and all field management and supervisory personnel.

The prestent United Engineers ' Construction Department includes more than h50 pemanent empicyees , including construction =anagers , super-intendents , resident job engineers , field engineers , craft supervisors ,

quality control engineers , accountants , and other required field service personnel. In addition, United Engineers currently employs = ore than 3,000 craft labor personnel. A substantial amount of modern construction equipment is maintained and kept in constant use and the latest con-struction techniques are employed. CPM scheduling is applied to every

=ajor project.

United Engineers is currently responsible for approximately $1,500,000,000 of construction verk in progress , including more than $1,000,000,000 in nuclear and fossil povered generating plants.

4.3 NUCLEAR EXPERIENCE A listing of specific nuclear construction assignments for which United Engineers & Constructors is new or has been responsible follows:

a. ATCMIC ENERGY CCMMISSION

'4ashington , D. C.

Ccnstruction =anagement services for Fast Reactor Test Facilities (FARET) in two phases. Phase 1 included over-all detailed pre-construction planning, CPM scheduling, estimating, coordinating ,

, .g  : and construction specification preparation. Phase 2, actual

.- > i construction, was cancelled. Phase 1 ce=pleted 1965 g 7 l

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/~ Design and supervision of construction of secondary shielding systems for PM-3A reactor at McMurdo Sound. Cmpleted 1962.

b. COMMONWEALTH EDISON COMPANY Chicago, Ill.

Morris , Ill. - Construction manegement services , in association with the General Electric Cmpany, for Units 2 and 3 at Dresden Nuclear Pcver Plant, each rated 600 MWe. Cmpletion - 1969/1970.

c. CCMMONWEALTH EDISON COMPANY ICWA-ILLINOIS GAS & ELECTRIC CCMPAIR Cordova, Ill. - Construction management services , in association with the General Electric Cmpany, for Units 1 and 2 at Quad-Cities Nuclear Station, each rated 800 MWe. Cmpletion - 1970/1971. i

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d. CONSOLIDATED EDISCN CCMPANY OF NEW YOFX l New York, N..Y. l

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Peekskill, N. Y. - Design and construction services , in association I with Westinghouse Electric Corporation, of Indian Point Nuclear i Unit No. 2, rated 986 MWe. Cmpletion - 1969 l

e. THE DETROIT EDISON COMPANY i l

Detroit, Mich. I p Monroe, Mich. - Construction of the Enrico Fermi sodium cooled i L/ fast breeder nuclear power plant, rated 100 MWe. (As member of Atmic Power Developent Associates , Inc. , contributed to the design and develop ent of the fast breeder reactor concept.)

C a pleted - 1961. l i

f. PUBLIC SERVICE ELECTRIC AND GAS CCMPANY Newark, N. J.

Burlington, N. J. - Construction of a pressuri::ed water reactor nuclear generating unit rated 1,03h MWe. Completion - 1971.

g. (CONFIDENTIAL PROJECT)

Design and construction of a nuclear power unit rated approxi-mate 17 1000 MW. Cmpletion - 1971.

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