ML20106D507
| ML20106D507 | |
| Person / Time | |
|---|---|
| Site: | Pennsylvania State University |
| Issue date: | 09/21/1992 |
| From: | PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA |
| To: | |
| Shared Package | |
| ML20106D498 | List: |
| References | |
| NUDOCS 9210130030 | |
| Download: ML20106D507 (15) | |
Text
_ - - _ - - - - _ - - - - - -- -- - - - - - - -- - - _ -
0 0 Safety Analysis Report for the Penn State Breazeale Reactor License Number R 2 Docket Number 50 05 The Pennsylvania State University University Park, PA 16802 September 21,1992 i
R 0 06 OS R PDR
TillRTY-SEVENTil ANNUAL PROGRESS REPORT PENN STATE RADIATION SCIENCE AND ENGINEERING CENTER July 1,1991 to June 30,1992
%,.:8'ted to: _
s 6tm stac xp . nt of Energy and The Penn'yhania State University By:
Marcus 11. Voth (Director)
Terry L Flinchbaugh (Editor)
Penn State Radiation Science and Enginering Center Department of Nuclear Engineering The Pennsylvania State University -
University Park, PA 16802 August 1992 Contract DE-AC07-761D01570 Subcontmet C88-101857 U,Ed.ENG 93-7 PENNSTATE University Park Campus
I STATEMENT OF NONDISCRIMINATION The Pennsylvania State University is committed to the policy that all persons shall have equal access to programs, facilities, admission, and employment without regard to personal characteristics not related to ability, perfonnance, or qualifications as detennined by University policy or by state or fedenti authorities 'lhe Pennsylvania State University does not discriminate against any person because of age, ancestry, color, disability or handicap, national origin, race, religious creed, sex, sexual orientation, or veteran status. Dirret all affinnative action inquities to the Affinnative Action Office.The Pennsylvania State University,201 Willard lluilding, University Park, PA 16802 2801, i
i k
TAllLE OF CONTENTS het PR E FA CE - M . I 1. V ot h . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
v 1
- 1. I NTRODU CrlO N M . I 1. Voth . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 11. P E R S O N N E L T. L. Fli n c h b a u g h . . . .... . . .. . ... .. . . . . . . . . . .. . . . . . . .. . ... . . . . . . . . . .. . . . . 3 111. REACTOR OPERATION S T. L. Flinchbaugh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 IV. O AMM A IRRADIATION FACILITY - C. C. Davison ... ..... ....... . . ... . ..... . .. .. .. 11 V. EDUCATION AND TRAINING - T. L. Flinchbaugh, C. C. Davison .... ............ 13 V1. NEUTRON BEAM LABORATORY D. E. I1ughes ............................. ....... 19 Vil RADIONUCLEAR APPLICATIONS LABORATORY - D. C. Raupach ............. 21 Vill. LOW LEVEL RADIATION MONITORING LABORATORY - 11. Boyle ............. 23 IX. ANGULAR CORRELATIONS LABORATORY - G. L. Catchen .................. . 25 X. NUCLEAR MATERIALS ENGINEERING LABORATORY - T. L. Flinchbaugh .. 27 XI. RADIATION SCIENCE AND ENGINEERING CENTER RESEARCll UTILIZATION T. L. Flinc hba u gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 A. Penn State University Research Utilizing the Facilities of the Penn State Radiation Science and Engineering Center ........................ 31 B. Other Universities' and Industrial Research Utilizing the Facilities of the Penn State Radiation Science and En gin ee ri n g Ce n te r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 APPENDIX A. Faculty, Staff, Students, and Industries Utilizing the Facilities of the -
Penn State Radiation Science and Engineering Center - T. L.
J1 i n c h ba u gh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 APPENDIX B. Form al Group Tours - L. D. Large . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67 x
iii
i TABLES Table het 1 Person nel . . . . . . . . . . . . . ... . ..... . . . .......... . . ... .. ........ ....... . .. . ... 4 2 Reaetor Operation Data .. .. ... . .................................. .................... 9 3 Re actor U tilization Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........................ .......... 10 4 Cobalt 60 Utiliz ation Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ...... 12 5 College and liigh School Groups ............ . . ... . ...................................... 16 FIGURES Heute Eage 1 Orga ni za t ion Chan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 iv
Safety Analysis Report LIST OF EFFECTIVE PAGES SAR Title Page Pagei September 21,1992 l SAR .'able of Contents Pages ii lil April 19,1991 Pages iv August 23,1991 Pages v April 19,1991 SAR - List of Figures Pages vi vil April 19,1991 SAR List of Effective Pages t Pages viii lx September 21,1992 l SARl introduction Pages 12 March 1,1985 S A R il Site Characteristics Pages 110 March 1,1985 S AR ill Reactor Design Pages 123 April 19,1991 SARIV Reactor Pool and Water System Pages 12 April 19,1991 Page 3 September 21 1991 Pages 4 8 April 19,1991 Page 9 March 1,1985 S AR.V Facility Construction Pages 14 March 1,1985 Pages 5-6 April 19,1991 Pages 7-10 March 1,1985 yjjj Septemter 21,1992
SAR VI Facilities and Experimenters Pages 13 March 1,1985 Pago 4 September 21,1992 Page58 March 1,1985 Pages 912 April 19,1991 Pages 1314 March 1,1985 SAR Vil Reactor Safety, Protection, Control and Monitoring System Pages 117 April 19,1991 Page 18 September 21,1992 Pages 19 49 April 19,1991 Pages 50 54 February 28,1992 Page 55 August 19,1991 Page 56-57 August 23,1991 SAR Vill Conduct of Operation Pages 1-4 April 19,1991 SARIX Safety Evaluation Pages 128 March 1,1985 Pages 29-30 April 19,1991 Pages 3148 March 1,1985 Pages 49 53 April 19,1991 l.
i l-Septemler 21,1992 lX J
IV-3
- I 1 , i 11k 5x%s
, i =
k g \ $ ___ \ k RE b j ,
xs y :g
~
~
-H- ~
a jj .y g a
ex ,
"~
il N H-s s1 xc. x, }
hl 31 ex fjx n 2
/)]
f sy) -
+ M
.g 3
/ 3a t X,. >. _
~
n x &1 -
r fi '
a a
-H- I '
,e e_ As ji d11 a
- 9x=\
j -
2,-
" i
} xa
>x & -
I $1 h_ ,
A h R:; $
1 Jts (l a x- SCeJ x# -
g j ex o~ r ;j #b 2
$i l
_ku :
.! 3
,j
~_Lgh " E g
8h r- - -- ,2, x2 f y_
in "4} =
11 8'
15 i~ w j j ( ....
I 3 Il f . 4" gj Ig 3a xjj .
} . 1 "
e c
) ; 1 ty >- p fy c pgj r J e 0 a e ,,5 J 4xT bi g*j }$4)g^
. 1 H H
_ ]UI n
*E Wg e xs lT y x:: "
-H- 4! RE ;{ f]3 p'.
- = ,1 f,
q l} s }= =g
==>
m 4 E !-
~ I!,
e N l : KD ~t L 6
'1}}}~jfgt
- f o
September 21,~1992 I w ,~ ,~. ,, , <e-.. ,- , 4n- w _y ,,
l IV.4 4
.s ,
l. I 4 r t Figure 4 2 (This Figuro !c Deleted) , '4 . i j .. \- l 'l I .-) I d " i-lt '. 9
-i.
4
)
,(.
I
? a '_
Effective April 19,1991 4 e -s* +,w %--e , ,m a
- I VI-3
. II
- 3. . C y=) d I
c- - 0
. n.
a j i et . kk g _ _ _ _ _ .i 1 e
- f?
--- -ra u m:4 mr _' ,
,law=:)_$
! .. . ,, - i l Ee L- >
l 1 i.
- a. .;
o
- I
$re 2 j 'A yg $
- l * > .. .
i .. . et gi I ; gi' Q ,- s i"~i s , 3 l-l
^
7 ) -- I I i n. - , - - [ s =
. l , 30 a _ > n
/ l
'. j -
f
- bI 7-g . , 6 a
.h
. . g, . " " ' ' ' '
') *ge.
9 . -3 '"*"", 1 y I- - - J. i ,, . 5 =. 1. ,
.#,3
'. hk 3
i
., 95, t \
E f_f Za j j i " as \ . 'l 5-) i . g C, i# v%.+ \
- . \;
q\ ., u\ n ,::.nueenn 4
.1
- t. .e.
.t \ ,
m ; L.1i
- L f +-
I 1\ [
, ,e h 7 i i 1 l '., . sl, ![,. 5; { !,T i
-v' 1 3 .. H tJ -
e I_ j 1 s
! Y. M.
$ I C b'
i
\ 1 y, g
t. Ts, l Figure 6-2 . -o a: - 4 [i l
- j. 1 Location of ths Beam Hole +---~ -
? 'jy i-aratory, Hot Cells, and Co-60 1 93 1
;adiati'on Facility I. (j' 4
l'l haemaatataEusuethl gu ye.3.4ft.FTfW'arJ@= t . I- . . s L " AH it i 1935 l' _ , . _ . . ,
~._ -.____._ .- ___ _ -._ _-_ __
. . - t VI 4 i
readout in the reactor control room. A TV camera is located in the BHL which can f view the beam port area in use. A remote TV receiver is located in the control room. Two remote manual scram buttons are located on the east and south walls of the BHL. A beam gate open alarm circuit is activated when any of the beam port doors is open. Opening the beam gate or the outside entry door (normally bolted and locked from the inside) to the beam area will give a sonalert alarm in the BHL and a beam gate open alarm to the Protection, Control and monitoring System (PCMS). , B. D20 Thermal Column The D2O thermal column in use at the PSBR is constructed of 6061-T6 aluminum and the. tank section measures 34"in diameter and is 27" long. Although ' : it is movable, its normal position is adjacent to beam port #4 (see Figures 61 and 6-3). The air filled flux trap that is built into the D2O tank is 9" long and 10"in diameter. The air filled flux trap creates an 18" thickness of D20 between the l reactor core and the trap, which provides an optimum flux for the rabbit thimble and ; beam port #4. Since mechanical interference prohibits the D20 tank from contacting the beam-port, an aluminum air filled extension is bolted to the beam port flange (see Figure 6 3) to remove pool water from the path of the neutron beam. To protect the pool wall directly behind the thermal column from neutron and gamma radiation, a boral shield is fitted to the beam port end of the D2O tank. A second boral shield on the reactor end of the D2O tank keeps the scattered neutron , interactions with the reactor instrumentation detectors to a minimum. Additional gamma shielding is provided for the pool wall by positioning a 2' x 2' x 1" lead shield around beam port #4. C. Central Thimble The central thimble, located in the radial center of the core, provides space for- , the irradiation of samples at the po"'. of maximum neutron flux. The thimble is an aluminum tube 1.5" O.D. and 1.33" 1.D. It extends from
- september 21, 1992 l
Y g v -T-- rt,P v g eyv y v' ry- - rrei-rp9x w am my-.,, -% e e, q- --g- y-+yrer- b4 w.W_ m W ,+ - g +mrF4 T
Vll.17 Radiation High frcm one of the following: East Bay Monitor. West Bay Monitor. East Air Monitor. West Air Monitor. Neutron Beam Lab Monitor. Co 60 Lab Monitor. Emergency Evacuation Button. Remote Pushbutton (1 of 4). Reactor Bay Truck Door Open. Both Eas* and West Facility Exhaust Fans Off. Interiock Validation Failure. Rod Velocity Signal Failure. Rod Motor Overspeed. . Square Wave Termination Request. To allow testing of the RSS logic, a testing bypass is provided for the DCC X SCRAMS as specified for the stepback function (see above). ' (c) Reactor Intericeks
*+
All of the operationalinterteck logic in the RSS is vclidated by DCC-X. DCC X' monitors all of the inputs and outputs of the hardware logic and performs the identical logic in software, if a validation failure is detected, a SCRAM is requested. The DCC-X control logic is designed to avoid signal outputs thM are in violation with the RSS interlocks. (d) FacHities Svstems Succort The following functions are performed for control and monitoring of various systems in the reactor facility: (1) Emercer'ev Evacuation ' An emergency evacuation is initiated on high radiation or manually from a switch on the console. Fol owing initiation these listed actions occur: evacuation hom is energized. emergency exhaust system is tumed on. alarm light on console is lighted. alarm is sent to police services. a facility exhaust system is secured. E.'fecWe Apnl 19.1991.
.. ~ . . _ . . _ . - _
i i vil 18 (ll) Reactor Ooeration inhibit; Reactor operation is inhibited by initiating a reactor stepback when an f inhibit conditi.an exists. The inhibit conditions cover the following situations: l
- keyswitch is off. ,
. a radiation hazard from the neut:on beam ports exists.
. both east and west bay or air radiation trips are defeated. .;
. pool temperature is high, ,
. reactor bay truck door is open.
(Ill) Manual Contro!s: Manual control of the following devices is provided:
. east and west facility exheust fans. I
. N 16 diffusion pump. ;
neutron beam !ab CCTV camera and monitor.
. rabbit system controls.
(iv) Onera'ino Historv Records; The following parameters are continually updated:
+ integrated power.
Mtal time that the reactor was critical. ;
. total operating time (i.e. time that the keyswitch was in *he operate position),
(v) Police Services Notification; The following operational conditions will initiate a signal of notification to Penn State University Police Services: evacuation initiate. . west air radiation high.
. reactor pool level #1 low. . east air radiation high.
reactor pool level #2 low. . . beam lab radiation high reactor pool level high. . Co 60 bay radiation high
- intrusion alarm, .
west bay radiation high
. Intrusion tamper alarm. . east bay radiatico high !
. UPS 1 low battery. .
hot cell fire
- waste tank level high. . DCC X computer down. .
. Co 60 pool level low.
Effective september 21,199;L -"M T' " w ggy + m n *
- y-y'-- y y4,r -
.m--mw -vyy---n ---q-v-r mv g9-g--- ,- --wg
P Vll 49 display driver command !!st for c! splay of the pulse. This task exists only on DCC X and thus its internal variables cannot be accessed on DCC Z. In the PROTiiOL operating environment, tasks have the following attributes:
- Independent scheduling frequency.
- definable scheduling priority relative to other tasks.
- Independent rnedule of code with controlled Interfaces to other tasks.
- critical /non-critical attribute to determine whether or not failure will drop the watchdog.
The principles used for the task structure out!!ned above, are as follows: [1] The independent ssty system suppert func:fons are separated into different tasks frorn control systeta functions. [2] Hardware I/O operations for safety support and control functions are performed independently in the associated task. This means that common 1/0 signals related to safety are Dnt read from the hardware in one task and men passed to the other task in software h (even though this would reduce CPU loading). Functions that do not have a high execution frequency [3] requirement are placed into separate slower tasks so that CPU loading is not made unnecessarily high. Far this reason there we both fast and slow safety support tasks (SSF & SSS) and control tasks (RRS & FAC). [4] Related functions a~a grouped into common tasks to minimize task interfaces (even though they may havo vsry!ng execution - frequency requirements). [5] Functions related to control of the operator Interface are implemented in non-block language tasks allowing use of conditionally executed code. For example, dynamic portions of - CRT displays are updated only when needed (i.e, s change has occurred). Much of the code must execute only when a key is pressed. This minimizes CPU loading without peak loading concems since the operator cannot physically generate requests fast enough to cause a high peak load. The operator interface has been slowed down to provide additional assurance. E!fecive April 19,1991
Vll.50 (6) Special purpose functions where the block language is mostly unusable. are implemented in non block language tasks (e.g. ( PULS). i The design details of the various application software tasks as they apply to DCC X and DCC-Z are provided in the design manual (reference (15)). K. Control Roorn , K.1. General Descriot!cn ' The consolo assembly is located in the control room. All of the equipment described above is located in the console assembly with the exception of the FC and Gl0 Detector Assemblies, the in core fuel 16mperature TCs, the Wide . Range Ampilfier and the field sensors. A window is provided between the control room and the reactor bay such that an operator seated at the console ) can observe personnel movement in the reactor bay. A CCTV system is'also provided in the control room so that the operator can observe personnel movement in the beam hole laboratory. Three in$rnal communication systems and a commercial telephone are available to the reactor operator in the control room. The intomal communication systems allow: 1) two way conversation with anyone on the , reactor bridge and the experimenters using the pneumatic transfer systems at (, any of the sending stations; 2) two way conversation between offices and offices within the building; and 3) the use of a page system that has speakers in all parts of the building. A window between the control room and a public corridor allows visitors to conveniently view the reactor controls;it allows Police Services to observe any unusual indications on their inspection tours; and it allows the reactor staff , to observe Instrumentation from outside the reactor bay, K.2. Monitor Indicat!ans in the Control Room Table 7-1 lists the monitors and type of detectors, their ranges and I alert and alarm settings for the major radiation monitors that provide inputs to ,
! the PCMS. All except the air east and air west monitors have readout modules located in an instrumentation pedestal as shown in Figure 7-8. For the monitors in the pedestal (except the Reactor Bridge West High) an alert
" results in an amber warning light on the monitor and a status and an alarm message is issued by the PCMS; an alarm results in a red alarm light on the monitor and a status alarm, an alarm message and an evacuation initiation is EMm.tNe Febmay 28,1992
Vll51 F i i l M. M. M. M. M.
. . e e e e . . e ee e ' .
e ee Cobalt 60 Bridge Bridge- Beam Lab Bridge - East West - West High , f r i-I- Figure 7 8 Instrumentation Pedestal Effective February 28,1992 r-.r.-- gr e, y - vg, ,,y,-,-,-,,n,, ,,,,w- w .y -
,_ - , . , , , _ _ - - , , - . . , , , ~ . , .
g- -- .w
f V!!52 Table 7-1 Contrc' cloom 'Algrmed Raciation Monitors l ymin rg n R2me seena~ Reac:ct Bridge G-M Tube 0.1 to 104 mR/hr Alert: 15 mR/hr East Atarm: 30 mfVhr Reactor Bridge GMTube 0.1 to 104mR/hr Alert: 50 mR/hr West Alarm: 200 mR/hr Reac:or Bridge lonemon 1.0 to 104 R/hr No afarm West H'gh Reac:ct Bay Thin Erd 10 to 105 c'm Alert: 6000 c/m Air Ea:2 GM Tube Alarm:10000 c/m Reactor Bay Thin Erd 10 to 105 c,m Alert: 6000 risa Air West G-M Tubo Alarm: 10000 c/m- t 4 Alarm: 6 mR/hr Co40 Bay GMTube 0.1 to 10 mR/hr Beam Laboratory GMTube 0,1 to 104mR/hr Afarm: 6 mR/hr
*An analog output f rom the monitors is an input to the PCMS. When that signal exceeds the ,
setpoint a status alarm is issued, an alarm message is issued and an Evacuation is initiated (see # e ( section 7.5.1.2.e.).
" Setting is determined internally and established by PSBR procedure. ,
T (s . et... g.~ u.1m L
i Vil53 s issued by the PCMS. The air east and air west monitors have their own lccal bells and flashing red light alarms that can be observed by the control room operator. A current radiation reading can be read on bar or trend graphs on the PCMS tor all the monitors listed in Table 7-1. Police DO bar trends indicate the status of console alarm conditions to Police Services. L. Minimum Safety SCRAMS and Interlacits Tables 2a and 2b in the Technical Specifications sec'Jon list the minimum safety circuits and the minimum operationalinterlocks for the PSBR. 9 L l l l Elfective February 28,1992 l , i L
l I II l,
- -' 1 5S kr o
& t w
m e N lee r t t i t A nys 1 N r o C, S o~ nn g i 7 q lw, e _
- erto J
i to . t S.C cd er ts e tol o rE W P r y , " = 5 l e, *s t 8e., , 'e t lee t u u3 h uh do8 *5 h ig d, 'g dg oi 7 t Eg, iL MLm -e M1 r, , t e ' n m' n, mr s o* RoA a& l A' R o ,, og ig & w oa RoA r 3 S y
" ' m ,, r imre g em '*
- e m ,, se ente n n8 *
- i o
CoM oM E' Cy M r C o
- it s
- n %
- , r - o M -
l n o _' ll a
- d m, t h
" r a r
leger r
&re b&r e
*Ied r
H A g, do t i mt r o 9-laie ct gc MMe t e1 cA eE A' d* @I' R c e 7 o R o
- l L L o r
u g _' i F l w de e e e d e b'u b nb se n b. Et7 b u b. T i T u ETu lorr e a T T e fh M i h iM h - M 8 4 M 4 - C TG
~
TG G G G G i yr o yor
* *g b o t Bi n oR b a ro t, ,
.go t r a r Bn eo L e Bn r a oR es 0 h r o oM r o oM t
h t En t ce t m Wg r ch a g A r ih 6h o e tos ct es ee B eh e iA ei RH C RE RW - pi\ a o . m:t -4e > $c25 r r". Do.r (
.}}