ML20197A460

Revised Chapter IV to SAR for Penn State Breazeale Nuclear Reactor

ML20197A460
Person / Time
Site:	Pennsylvania State University
Issue date:	11/10/1997
From:	PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA
To:
Shared Package
ML20197A447	List: ML20197A440 ML20197A460 ML20197A510 ML20203K703
References
NUDOCS 9712230065
Download: ML20197A460 (17)

Text

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SAFETY ANALYSIS REPORT for the i Penn State Breazcale Nuclear Reactor License Number R-2 Docket Nurnber 50-05 <

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The Pennsylvania State University University Park, PA 16802 Novembe- 10,1997

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9712230065 971217 PDR ADOCK 05000005, R pm

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11 i SAFETY ANALYSIS REPORT I I

TABLE OF CONTENTS IJ st of Fi g ure s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vil u st of Effective Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ix

i. INTR ODU CD ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I1 II. S rm CHARA CTERISTIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-1 A . Geography and Demography 11 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111

1. Reactor Site Access Control . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 H. Nearby Industrial, Transportation, and Miliury Facilities ..................... 11- 6 C . Meteorology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 116 D. Geology and l iydrology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117 E . Sei smology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 10 F . R e fere nce s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1110 111. REACIDR DES lO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11!-l A . I n trod uction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ill-1 B . Mechanical Desi gn . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1111

1. - Reac tor B rid ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 1

2. Reactor S usl wnsion Tower . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1113 3 . Reac tor Grid Plates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III3

4. Fuel Moderator Elements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III6 5 . Control Rods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III6

6. Con trol Rod Drives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1119

7. Graphite Reflector Elemen ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III.16 C . N uc lear Desi gn . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-16

1. Standard TRIG A Cort . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III.16

2. External Neutron Source . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 23 D . 'Thennal De si gn . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 23 IV. REACTOR POOL AND WATER S YS'mM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV.1 A . R eac tor Pool . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV 1 B . PS BR Water liandling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-1 ,

1. General.......................................................................... IV-1

2. - Pool Recirculation loop . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-1 November 10.1997

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TABLE OF CONTENTS .

(Continued) l

3. Transfer of Pool Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV 2 ,

4 . Heat Exchanscr . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 IV 1

5. 13 quid Waste Evaporator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV 2  ;

i C . Water Quality Monitoring and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-3  :

V. FACILITY CONSTR UCI10N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V1 i A . B ui lding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V1 ,

B .- Heating and Ventilation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V1 C . U tilitie s . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V4 D . Fire Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V4 ,

VI. FACILITIES AND EXPERIM ENTERS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI l 1 A . Beam Port s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI l i B . D O hermal 2 Col umn . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-4 -

C . Central n lmble . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-4

1. Central nimble Oscillator . . . . . . . . . . . . . . . . . . . . . . . , < . . . . . . . . . . . . . . . . . . . , . . . . . . . . VI-6 D . Vertic le hbes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI 6 1 . J i b Crane . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI8 E. Pneumatic Transfer System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-8 5

1. Pneumatic Transfer System I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI 8 2 Pne umatic Transfer System 11. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI 12 -

F. In strume nt B rid ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI 14 O . Hot Ce l l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI.14 i H . Co-60 Irradiation Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI 14 i

VIt. REACTOR S AFETY, PROTECI'lON, CONTROL AND MON FIDRING S YSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII l i A . S ystem S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII l B. System Design Philosophy ................... ................................ VII 6 t C . Console Funct k n S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-6 D. RS S Function S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 7_ ,

1. SCRA M Functions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 7

2. Interlock Functions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII7 Novemter 10.1997 a

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TABLE OF CONTENTS (Continued) t E . RSS Descri ption . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-8

1. Wide Range Monitor Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII10

2. Power Range Monitor Desen ption . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 11 i

3. Contml anc Alarm S ubsystem Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 12 &

a. SCRAM and Contmllogic Assembly Description .................... VII12

b. SCRAM and Rod Contml Switch Assembly Descri VII 12

c. SCRAM and Alarm Panel Assembly Desenption ................... ...ption VII13.............

4. 'the Power Distribution System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII13 F . PCM S Function S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII13 ,

1. DCC- X Funct ion s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 14 l a . Reactor Control and Regulation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 14 b . Reactor Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII.16 (a) Reactor Sie hack . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII16 (b) Reactor SC (A M s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Vil 16 (c) Reactor Interlocks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 17 (d) Facilitie s Systems S upport . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 17 (i) Emergency Evacuation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 17 (ii) Reactor Operation inhibit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII18 (iii) Manual Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII.18 (iv) Operating History Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 18 (v) Police Services Notification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VIIl8 (e) Alarms................................................................ VII 19 (f) Operator Interface . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 19 (g) Se lf Te sti n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 20 -

2 . DCC Z Function s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-20 -

O . Systems Operation Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII20

, 1. Reactor Safety System Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 22

2. - RSS Relay logic Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 22 a . SCRAM 1ogic . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 24

b. Transient Rod Air Interlock logic e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 25 .

c . Rod Drive Interlocks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII26 H . PCMS Hardware De scription . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 27 1 . Compu ters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 27 ,

2. Input / Output Hardware . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 29

a. Chassis Arrangement and Watchdog / rest Cards ....................... VII 29 -

b. Analm Signal I/O Card s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 30

' c. Digita Signal I/O Cards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Vll 32 J . Watchdog and 1/0 Self Test Cirwits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 32 November 10.1997 m -

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TABLE OF CONTENTS (Continued)

3. Motors and Associated Controllers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII33 a . Motor Cont ol . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 34

' 4 . Power S upplies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII37 5 . IK) A ssi gnment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Yll 37

1. PRO 1DL Generic Software Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII39 l . Control langua se . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .VII

. . . 39

2. *!he g Ly stem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH-40

3. c Tasks Running in the PRO 1ROL System ......................... VH 41

4. System Self Checks and Defenses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII42-a . Defenses A gainst less of Field Sensor. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH 43

b. Defenses Against less of Power . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-43 c . Defenses Against 1/0 Failcre . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 43

d. Defenses Against Computational Faults ....... ......... ..... ... .... ... .. VII-44

, c. Defenses Against Program Corruption Faults........................... VH 44 o

5. DCC-X/DCC Z Self Tests and Robustness Functions..................... VII45 i a . Self Tests on S tart Up. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 45 b . Self Tests While On Line . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-46 J. Application Softward . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH-48

1. Block language Task s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH 48 l 2. Non Block Language Tasks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Vil 48 K . Con trol R oom . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH 50

1. General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH 50 L 2. Monitor Indications in the Control Room . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Vll 50 l L . Minimum S afety SCR AMS and Interlock s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH 53 M . R efere nce s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH 55 N . O los sary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VH 56 Vill, CONDUCT OF OPERA *I1ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VIII-l A . Organization and Respon sibility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Vill 1 -

B . Reactor Operating Safety Philosophy . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VHI-1 C.-Training............................................................................... VHI 3 D . Written Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VIII 3 E .L Record s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VHI-4 ........

F . Revie w and Audit of Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VHI-4 November 10,1997

i i

vi l TABLE OF CONTENTS (Continued)

IX. S A11TlY EV ALU ATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX.1 A . I n troduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 1 B. 'IRIGA FuelTemperature Analysis of the Penn State Breazcale Reactor .... IX 3

1. S teady S tate A nalyse s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX-4  ;

2. Pulsing Characteristics of the PS B R. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 10

3. 'IRIO A Experimen_t to Measure Fuel Temperatures......................... IX 13

4. Evaluation of the A t, for Fuel Element I 14. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 15

5. Evaluation of the Pulse Data for Fuel Element 1 14......................... IX 19

6. Evaluation of the Fuel Element 1 13 Temperature Data (Pulse and Stead y S taic) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 21

7. ~~ .Junion (Temperature Analy s1s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 23 C. Evaluation of the Limiting Safety System Setting (LSSS)...................... IX 25 D . Ioss of Coolant Accident . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 27 F. Maximum f lypothe tical Accident (MilA). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 36 F. Reactivity Acc iden t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX-42 G . Conc l u sion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 43 1 1. R e fe re nc e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IX 45 November 10,1997

- ,- ,n ,

vii l SAFETY ANALYSIS REPORT LIST OF FIGURES Bemx1 T1k 21 'Ihe location of Centre County in Pennsylvania 22 Map of Centre County, Pennsylvania 23 'Ihe PSilR Site lloundary 24 Population Within a Five Mile Radius of the PSBR 25 'Ihe Physiography of Centre County 2-6 'Ihe Spring Creek Drainage Ilasin 3-1 'Ihe location of the PSilR Core, Bridge, and Control Cons .c 3-2 1hc layout of the PSilR Grid Plates 33 'the Arrangernent of the PSBR Grid Plates and Safety Plate

?4 A StandaN TRIGA Fuel Moderator Element 35 An Instrumented TRIGA Fuel Ekment 36 A Fueled Follower Control Rai with Respect to the PSBR Core 37 A Transient Control Rai 3-8 A Rack and Pinion Control Rm! Drive 39 'lhe Transient Rai Drive 3 10 Core leading #1 layout 3 11 Core leading #4 layout 3 12 A Graph of Peak Power Versus Pmmpt Reac* vity for the First Nineteen Pulses with Core Loading #4 3 13 A Graph of Peak Fuel Temrerature Versus Prompt Reactivity for the First Nineteen Pulses with Core leading #4 3 14 A layout of Cort loading #36 41 'Ihe PSBR Water llandling System 42 The PSilR lleat Exchanger 4-3 The PSilR Liquid Waste Evaporating System 51 The location of the PSilR on The Pennsylvania State University Campus 5-2a *lhe First 11oor Plan of the Original Reactor Hullding 5 2b 'Ihe Gmund Floor Plan of the Original Reactor Building 53 location of the PSilR Electrical Supply Transfonner 5-4a The First Floor Location of Fire Extinguishers and Firr Alarm Boxes 5 4b 'Ihe Ground Floor location of Fire Extinguishers and Fire Alarm lloxes 61 1he location of a Number of PS11R Facilities for Experimenters 62 The location of the lleam llole laboratory, llot Cells and Co 60 Irradiation Facility 6-3 'Ihe D 20 Thennal Column 6-4 The Central *Ihimble Oscillator 65 Pneumati c Transfer System I 6-6 Pneumatic Transfer System I laboratory Tenninus 67 Pneumatic Transfer System 11 71 PSIIR Console Layout 72 New PSBR Safety, Protection and Control System Novemler 10,1997

l t

i i

viil l LIST OF FIGURES (Continued)  ;

. J fismLi Bit  !

- 73 Old PSBR Safety, Protection and Control System 74 Functional Block Diagram of RSS 75 PCMS and Interfaces to Other Systems  !

76 ' CMS Equipment layout (Console Rear View) .

-7 7 Watchdog and 1/0 Self Test Circuits 7-8 instrumentation Pedestal  !

79 Radiation Monitoring System l 81 Organization Chart i

i 91J PSBR Core Configurationloading #36

'92 ~ Corrimring Highest Measured Fuel Temperatures During a Pulse with EQ(34) for Fuel Element 114 '

93 PSHR Core Configuration leadin,g #47 -

94 'Ihe Time Dependence of Air Coo ed Fuel Body for Center Element with 267 W Input

• 95 Summary of Equilibrium Data for LOCA Simulation Showing the Fuel Element i Cladding Temperature Versus Power in )ut to the Element for All Seven Dummy  ;

, Elements lleated with the Same Power nput 96- Fuel / Cladding Temperature as a Function of Time After LOCA initiation -!

97 Maximum Fuel Temperature Versus Power Density After LOCA for Various Cooling Times Between Reactor Shutdown and LOCA Initiation 98 Strength and Applied Stress as a Function of Temperature, U Zrlit.e Fuel with Fuel and Cladding the Same Temperature

+

h i

4 a

i Novemter 10,1997 .

k y

t 6n'-, e er ,, .- ,---.-+-r- ,, n,w--nr. v

ix l [

1 SAFETY ANALYSIS REPORT ,

LIST OF EFFECTIVE PAGES i

SAR Title Page ,

Page i November 10,1997 r SAR Table of Contents I Pages 11 vi November 10,1997 SAR List of Figures ,

Pages vil vill November 10,1997 SAR . List of Effective Pages Pages ix x November 10,1997 SAR I Introduction

• Pages 12 March 1,1985 SARIl Site Characteristics Pages1 10 March 1,1985 SAR.Ill Reactor Design Pages 123 ' April 19,1991 SARIV Reactor Pool and Water System Pages 16 - November 10,1997 l i

Novemter 10,1997

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i x l LIST OF EFFECTIVE PAGES -

(Continued)

I SARV Facility Construction Pages 1-4 March 1,1985 Pages 5 6 April 19,1991 ,

Pages 710 March 1,1985 <

SAR VI Facilities and Experimenters ,

Pages 13 Matrh 1,1985 Page 4 Septemter 21,1992 Pages 5 8 March 1,1985 Pages 912 April 19,1991 Pages 1314 March 1,1985 SAR VII Reactor Safety, Protection, Control and Monitoring System Pages1 17 April 19,1991 Page 18 September 21,1992 Pages 19-49 April 19,1991 Pages 50-54 February 28,1992 Page 55 Apnl 19,1991 Pages 56-57 August 23,1991 SAR Vill Conduct of Operation Pages 12 April 19,1991 Pages 3 4 June 7,1993 SARIX Safety Evaluation Pages1 46- January 14,19)7 Rev.1 (4/24/97) l November 10,1997

i i

SAFETY ANALYSIS REPORT ),

CHAPTER IV '

i for the t Penn State Breazcale Nuclear Reactor

, I I

P License Number R-2 '

Docket Number 50-05 I

1he Pennsylvania State University ,

University Park, PA 16802 1

f r

November 10,1997 i 1

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IV.1 IV. REACTOR POOL AND WATER SYSTEMS  ;

A. Remor ptml j i

1he reactor pool is approximately 30 feet long 14 feet wide, and 24 feet deep. The pool i is constructed of steel reinforced concrete.1he pool walls are 1 1/2 feet thick below the  !

level of the reactor bay floor and one foot thick above the reactor bay floor. The inside of the pool wall is coated with epoxy to form an epoxy pool liner. The pool is sunounded by carth fill with the exception of the south side. A room (Beam Hole Laboratory) exists outside the south side of 1ie pool at the elevation of the remor core. Additional shielding ,

is provided by 31/2 feet of high density concret: on the outside of the pool wall in this i room.: ,

3 1he total pool volume is appmnimately 71,000 gallons. The pool can be divided in two  !

+

by a removable gate which permits draining either part of the pool while maintaining the reactor undce water in the other pan of the pool.-

i Seven heam pons penetrate the pool wall from the Beam Hole Laboratory to pmvide access to reactor radiation. The pool is equipped with two Door drains; one for each side  ;

of the pool when it is divided with the removable gate. Four other pool wall penetrations  :

exist, two located approximately 10 feet above the pool floor to serve the pool recirculation loop and two located appmximately 17 feet above the pool floor for the heat exchanger, Several sources of water are available for adding water to the pool they are: (a) the distillate from the waste evaporator, which is stored in an und erground tank, can be i

> umped into the recirculation loop for normal pool water make up; (b) water fmm the Jniversity water system can te added to the pool through the demineralizer, (c) water fmm the Univenity water system can be added to the lmol at a high flow rate through the '

pool drain lines, after connecting a fire hose that is ma ntained in location for this

• pur pse; (d) water from the secondary side of the heat exchanger can be diverted directly to t ic pool thmugh a fire hose for emergency make up water.  :

i

' I B, PSHR Waterllandling System

l. O snttal  :

For the proper and safe operation of the reactor and related equipment, cenain 3ropenies of the water such as temperature and mineral content must be controlled.  ;

Fi,gure 4 1 shows all of the water handling systems for the PSBR facility and in the  :'

fo lowing sections the individual systems am discussed in detail.

2, pool Rectrenladan I nnn The recirculation loop normally recirculates pool water continuously through filters and a demineralizer to maintain water quality.

The flow rate thmugh the system is about 40 gallons per minute. . Water enten the system through a skimmer arrangement at the south end of the pool, flows through -,

- the recirculat on pump, a filter, a mixed bed demineralizer and tben flows back into the pool.  ;

1 i

Novemtier 10.1997

IV 2

3. Trmfer of Pool WatcI l Occasionally, for maintenance purposes, it is necessary to drain the tractor pool. In order to provide shielding for the reactor core and any stored fuel elements, only one half of the poolis dramed at a time. The pool is divided into Iwo parts by insening an aluminum structure, or gate,into the gate suppon structures.

The water fmm either half of the pool can be stored in a 48,000 gallon aluminum hold-u i tank located behind the facility. 'lhe water leaves the pool via large drains locatec in the pool floor along the west wall near the partial concrete divider.

• lhe storage tank transfer pump (capac' 83(X) gal / min) located in the beam hole laboratory is used to pump the water. ater can be retumed to the pool from the storage tank using the same pump and floor drains (see Figure 41).

11y opening the valves on either of the pool drain lines one could release pool water to the storm sewer. Ilowever, to minimite the release of radioactivity and to conserve the demineralized ;mol water, the pool water is transferred to the storage tank when it is necessary to dra n the pool. To prevent any accidental release, valves #65 and #66 are secured with a padlock (see Figure 41). Keys to the lock are issued only to those with an NRC Senior Reactor Operator License.

4. Heat Exchanger The PSilR heat exchanger limits the temperature of the PSBR pool water (see Figure 4 2). Maintainin ; lower pool temperaturrs decreases pool water evaporation l losses and temperatures selow 110 F are needed to prevent damage to the deminerallier anion resins.

The system is composed of two loops, in the primary loop, pool water is pumped through the baffled shell side of two double pass heat exchangers connected in series.

In the secondary 100 ), cooling water is pumped from Thompson Pond, a spring fed mnd located approx mately 650 yards southeast of the PSilR, through the tube aundle side of the two heat exchangers and then to a storm sewer which returns the water to Thompson Pond. The lower quality secondary side water is passed thmugh the tube bundles si nce by removin the ends of the two heat exchangers, the tube bundles can be cleaned more easil than the baffled shell side.

When the measured pressure difference shows the secondary outlet pressure to be less than 1.5 psig greater than the primary inlet pressure, a llEAT EXCilANGER SECONDARY PRESSURE LOW _ signal is activated to the PCMS.

Since the source of cooling water is Thompson Pond, which is fed by a 3 million gallon per day spring, relatively small year round variations in cooling water tempeuture are noted (55 Fi 2 F).

5. Liquid Waste Evnoorntor Radioactive liquid waste is collected in either an underground holding tank just outside the evaporator building or in a holding tank below floor level inside the evaporator building. Liquid waste from either of these timks (see Figure 4 3), can be l pumped to the evaporator feed tank. This feed tank supplies the liquid to the evaporator during evaporator operation. The evaporator is a low aressure, low temperature unit which uses hot water as a heat source. The distil: ate from the evaporator is collected in a distillate tank.

November 10.1997

1%3 An overliow line installed in this tank directs the distillate to an undergmund Imiding tank where it is stored for later use as pool make-up water. The residue from the evaporation operation is removed from the evaporator, solidified and disposed by the llealth Physics Office.

L, idater Quality Monitoring and Maintenance S

Ponducthity is monitored by conductivity cells in the pool water recirc Figure 4 1), pil and gross radioactivity are r.ieasured in the laboratory using a grab sample of pool water.

All three parameters: conductivity, pil, and poss radioactivity are controlled by filters and a demineraliter in the pool water recirtu' ation loop. Abnormal levels in any of these parameters may indicate that this system is in need of service.

November 10.1997

IV 4

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Novemter 10,1997

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Novemter 10,1997 -

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