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WASHINGTON STATE UNIVERSITY PULLMAN, WASlilNGTON 'niss
WASHINGTON STATE UNIVERSITY
                                                                              ),g NL' CLEAR RADIATION CENTER March 2, 1981                                                     -      N 4                 S tt            -
),g PULLMAN, WASlilNGTON 'niss NL' CLEAR RADIATION CENTER March 2, 1981 N
L       'A 2
4 S
Mr. J. Wilson                                          I        MdRo $'193;w l.7 Standards and Special Projects Branch                          Ss. %*"""uma_-____~ e, 5}
L
Division of React (~ Licensing                                                 'g
'A tt 2
                                                                                      '/
MdRo $'193;w l.7 Mr. J. Wilson I
U.S. Nuclear Regulatory Commission                         -
Ss. %*"""uma_ __~ e, 5}
Washington, DC 20555                                                 8 3 84
Standards and Special Projects Branch Division of React (~ Licensing
'g
'/
U.S. Nuclear Regulatory Commission Washington, DC 20555 8 3 84


==Dear Mr. Wilson:==
==Dear Mr. Wilson:==
 
Enclosed cre 22 cooies of updated and corrected drawings for inclusion in the SAR for Facility R-76.
Enclosed cre 22 cooies of updated and corrected drawings for inclusion in the SAR for Facility R-76. The pages provided replace existing pages in the SAR submitted with the application to renew Facility License R-76. Please distri-bute these updates to holders of the SAR.
The pages provided replace existing pages in the SAR submitted with the application to renew Facility License R-76.
Please distri-bute these updates to holders of the SAR.
During a recent inspection by the I & E division of the NRC, a number of changes were suggested to the proposed facility Technical Specificiations.
During a recent inspection by the I & E division of the NRC, a number of changes were suggested to the proposed facility Technical Specificiations.
Enclosed are 4 copies of each page of the T.S. reflecting these changes.
Enclosed are 4 copies of each page of the T.S. reflecting these changes.
Please distribute to holders of the T.S.
Please distribute to holders of the T.S.
Did you ever receive the copy of the reactor pool structural drawings and the copy of the letter from Campbell Engineers about the pool design? Please advise.
Did you ever receive the copy of the reactor pool structural drawings and the copy of the letter from Campbell Engineers about the pool design? Please advise.
Sincerely, h' (' ' E ,hy W. E. Wilson Associate Director WEW:sms Enclosures t
Sincerely, h' (' ' E,hy W. E. Wilson Associate Director WEW:sms Enclosures t
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                                                                                                                      '3-9' h           .Dur.ing normal' operation, 9.44 x 10             5' cm3
j.,
                                                                                    /sec of air from the poolIroom is mixed with the beam room exhaust and discharges out the monitored exhaust.
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.Dur.ing normal' operation, 9.44 x 10 cm /sec of air from the poolIroom is 5'
3 mixed with the beam room exhaust and discharges out the monitored exhaust.
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. serve to prevent all air flow into and out of the pool. room.
In the
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                    . serve to prevent all air flow into and out of the pool . room.                          In the 5   3 dilution mode,1.42 x 10 c                /sec of pool room air. is passed through 'an 5
5 3/sec of pool room air. is passed through 'an dilution mode,1.42 x 10 c 5
absolute filter, mixed with 8.02 x 10 cm 3/sec of outside air, and dis-charges up the exhaust stack. _The main. control panel-for the system is located in the reactor control room and a set of emergency-controls is 3
3 absolute filter, mixed with 8.02 x 10 cm /sec of outside air, and dis-charges up the exhaust stack. _The main. control panel-for the system is located in the reactor control room and a set of emergency-controls is 3
located in the main office. The continuous air monitor and gaseous efflu-ent monitors are shown in Figure 3.2-2 and 3.2-3.
located in the main office.
.                    3. 3' Pool The reactor pool is a reinforced, above ground, unlined concrete pool                             '
The continuous air monitor and gaseous efflu-ent monitors are shown in Figure 3.2-2 and 3.2-3.
j                    with a volume of 247,000 liters.                 The pool is penetrated by a thermal col-4 umn and a nunber of beam ports as described in Section 4.11.                               A cross sec- ,
: 3. 3' Pool The reactor pool is a reinforced, above ground, unlined concrete pool j
tion of the pool is shown in Figure 3.3-1.
with a volume of 247,000 liters.
3.4 Liquid Waste Collection System                                                                     ,
The pool is penetrated by a thermal col-umn and a nunber of beam ports as described in Section 4.11.
,                          The Nuclear Radiation Center has two separate waste systems.                             The l                   sanitary waste system handles all the normal non-radioactive liquids and the " hot-drain" system handles all the radioactive liquids.                             The sanitary waste system connects all the washroom fixtures and cold laboratory drains to the campus sewer system.             The " hot drain" system connects all the j                   drains from the radiochemistry laboratories and reactor areas to a reten-l                   tion tank system.         Radioactive effluents from the Center are collected in
A cross sec-4 tion of the pool is shown in Figure 3.3-1.
                                                                                                                            ?
3.4 Liquid Waste Collection System The Nuclear Radiation Center has two separate waste systems.
l                   the retention tank system shown in Figure 3.4-1.                         Prior to discharge into the sanitary sewer, the contents of the retention tank are pumped to a                                   '
The l
          @        sampling tank.       The sampling tank is sampled, evaluated for activity con-tent,-and diluted as necessary during discharge. Discharges pass through a                               j particulate collection filter.                                                                           [
sanitary waste system handles all the normal non-radioactive liquids and the " hot-drain" system handles all the radioactive liquids.
i       .    -  -    .      .    .    . _ _ . . - .    .-.            _..
The sanitary waste system connects all the washroom fixtures and cold laboratory drains to the campus sewer system.
The " hot drain" system connects all the j
drains from the radiochemistry laboratories and reactor areas to a reten-l tion tank system.
Radioactive effluents from the Center are collected in
?
l the retention tank system shown in Figure 3.4-1.
Prior to discharge into the sanitary sewer, the contents of the retention tank are pumped to a sampling tank.
The sampling tank is sampled, evaluated for activity con-tent,-and diluted as necessary during discharge. Discharges pass through a j
particulate collection filter.
[
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FIGURE 3.4-1 1
FIGURE 3.4-1 1
1


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SAFETY CHANNEL                                       LINEAR INDICATION CIIANNEL             -
O SAFETY CHANNEL LINEAR INDICATION CIIANNEL LOG-N LOG-N COMP.
LOG-N     LOG-N                                                     COMP.
POWER HIGH VOLTAGE SUPPLY VOLTAGE SAFETY LINEAR
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                            ^                 v                 v                                               v ANNUNCIATOR SLOW           LOGIC 8C ELEMENT g
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v ANNUNCIATOR SLOW LOGIC 8C ELEMENT g
                .                                    TRANSIENT                                                              's R0D AIR CATC'!ATO FIGURE 4.8-2
v v
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4-28 SCP'" CIRCUITRY C)
4-28 SCP'" CIRCUITRY C)
Scram Signal from upAmm #1 125%
Scram Signal from upAmm #1 125%
V min.                              '.
V min.
Scram Signal                                       1       Scram Signal from from C.I.C           >                                    Fuel Temp.< 500 C H.V. Failure                   LOGIC ELEMENT Scr'am Signal from
Scram Signal 1
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Scram Signal from from C.I.C Fuel Temp.< 500 C H.V. Failure LOGIC ELEMENT Scr'am Signal from L
Power from Slow         Master Sw.
Period Amp. T<5 sec.
Scram Relay v v                 v v           vv
Power from Slow Master Sw.
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A V                   V             v
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Channel               (Period                                 :
V V
Open        Open              I)                 ^*P)                   Power from Open           on           on           Open                 Open         Open     Master Sw.     i on       C.I.C.     Log-N             on                 on           on Seismic         H.V.       H.V.           Iligh               Short         Bldg.
v Transient l
Detection     Failure     Failure         Flux               Period         Evac. Manual
#1
,              Open on                                   125%               T<5 sec.
#2
liigh Fuel Temp.                             min.
*3 Blade Blade Blade p Rod Air i
              *C<500 c'                                                                                               '
Solenoid Maanet Maanet Maanet v
!  L
(Safety Channel (Period I)
    /~T@U     Slow Scram Relay l         '
^*P)
Open Open Power from Open on on Open Open Open Master Sw.
i on C.I.C.
Log-N on on on Seismic H.V.
H.V.
Iligh Short Bldg.
Detection Failure Failure Flux Period Evac.
Manual Open on 125%
T<5 sec.
liigh Fuel Temp.
min.
*C<500 c'
/~T@U L
Slow Scram Relay l
l' l
* NOTE: Period Trip installed for training use only and i
not required at all times.
l l
l l
* NOTE: Period Trip installed for training use only and i      _
FIGURE 4.8-4
not required at all times.
l        '
l                                                FIGURE 4.8-4


O                                                                                         O                                               O                                   .
O O
4 i                                                               .
O 4
HIGH V0LTAGE                 P0' DER                 H.V. FAILURE                       t SUPPLY                 SUPPLIES                       MONITOR                       l I
i HIGH V0LTAGE P0' DER H.V. FAILURE t
                                                                        '                                                I m
SUPPLY SUPPLIES MONITOR l
                  ~~
i                                            J,                      J,    - '
t                  s, t
LOG                                      LOG COUNT                              l I                                                                                        ERIOD                  se POWER                                          RATE I                                                                                                          SLOW SCRAM g    ,
N'                I      .-
                                                                                                                              <    CIRCUIT I
I LOW COUNT PRE-AMP                                PULSE                                                                  ERIOD    l RATE l4-  1                IN1!IBIT                                                                  ^#
IN!!IBIT                            I A        I                                                                                                                            o I                                                                                        PERIOD TRIP LOGIC 1                                                                                          SCRAM          )  ELEMENT    ) ACWATOR I                      AMPS.
I I
I I
I       se                                                                               SERVO     ,
m i
1                                                                                        IN!!IBIT                           sf I
J, J,
I                                                                                                           PULSE   '
~~
i lug                                                     LOG                                                             MAGNETS ROD AIR I
t s,
jPOWER                                                   COUNT                     s,                    ;0f.ENGID RATE                                       I I
t LOG LOG COUNT l
I i
ERIOD se I
I                                                                                PERIOD             y I
POWER RATE I
LOG-N DRAWER                               i I----
SLOW SCRAM g
s, l
N' I
FISSION                         RECORDER CII.WSER                                                                                                                                                                                   7 WIDE RANGE CllANNEL FIGURE 4.8-5
CIRCUIT I
LOW COUNT I
PULSE ERIOD l
PRE-AMP l4-RATE 1
IN1!IBIT
^#
IN!!IBIT I
A I
o TRIP I
PERIOD LOGIC
)
) ACWATOR 1
SCRAM ELEMENT I
AMPS.
I I
I se SERVO 1
IN!!IBIT sf I
I PULSE MAGNETS i lug LOG ROD AIR I
jPOWER COUNT
;0f.ENGID s,
RATE I
I I
i I
PERIOD y
I LOG-N DRAWER i
I----
l s,
FISSION RECORDER CII.WSER 7
WIDE RANGE CllANNEL FIGURE 4.8-5


              /
Q O
Q                                                         O b-         11C01 101-A                       e'                 kE! 10G                 G                 RCGI 201-C       k-                   ,'
b-
Do                                     U_y Watt  t        s                                                                                        $    Bldg. D                       30             ,
/
A                                                                                                      Sort Water 00                   smter nuter g                                                                                                 a                                         fi03i D                                                           1 3 f40                                                                                             0                                   " # i " ~'            '
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0   NO g0                       Deionizer m
kE! 10G G
1 4                        a       -
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Du Q         Cond.                                             I Cell /g         -    -      -                    :
s Sort Water A
Do
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1 3 f40 0
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g0 4 m
Totalizer s
a Du Q
b -Opens on 1.lakeup Signal               f'}y"er       Mixed       Drain Qo g
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7l                        lY Bed         Valve     #
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O                         East Sim) gas joy West Stanp V.         '  '
fel East Gutter ROry,; 201 M'
00 b                       p    A NC                   NO                                                       3 c
l C'y ao o, West Gutter s
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00 b
A NC NO p
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Cell                   ,
Cell
                                                                                                        'O NC                   NO                                                           Do O'o                                                           L a.
'O NC NO Do O'
(                                                                                                    d    OD #UI        Id8 o O D o a o tin o" 0? o3.0 Oo OSDoI F(
L o
l                                                                         ?> o es m n) i ImL WATER PURIFICATION & !!AKE-UP SYSIMI
a.
_    _  _    ,          FIGURE.4.10-1                     _                          ._        ____. _            __
o O D o a o tin o" ? Oo OSDoI F(
OD #UI Id8
(
l d
0 o3.0 ?> o es m n) i ImL WATER PURIFICATION & !!AKE-UP SYSIMI FIGURE.4.10-1


  *..                      .                                                                              6-13 (1) Maximum FLIP fuel temperature of 950*CI (2) Maximum Standard fuel temperature of 800 C (3) ' Maximum reactivity insertion of $2.50                                 ,
6-13 (1) Maximum FLIP fuel temperature of 950*CI (2) Maximum Standard fuel temperature of 800 C (3) ' Maximum reactivity insertion of $2.50 (4). LSSS of 500'C for fuel temperature scram (S) Maximum allowable power density of 23.5 Kw/ rod for FLIP and 22.3 Kw/ rod for Standard fuels.
(4). LSSS of 500'C for fuel temperature scram (S) Maximum allowable power density of 23.5 Kw/ rod for FLIP and 22.3 Kw/ rod for Standard fuels.
The analysis also demonstrates that 'no realistic hazard to the general public would result from the Design Base j
The analysis also demonstrates that 'no realistic hazard to the general public would result from the Design Base j                                                 Accident, a loss of Coolant Accident, the accidental addition of one 4-rod cluster, or the accidental ejection of the transient rod at' full power.
Accident, a loss of Coolant Accident, the accidental addition of one 4-rod cluster, or the accidental ejection of the transient rod at' full power.
j                                          6.4.2 Argon-41 Releases Section 6.5 of the S.A.R. for the conversion of the O                                     W.S.U. TRIGA reactor to FLIP fuel as given in Appendix A of this report substantiates a 4 x 10-3 dilution factor                       ,
6.4.2 Argon-41 Releases j
for Argon-41 release due to the atmospheric wake effect
Section 6.5 of the S.A.R. for the conversion of the O
,                                                  in the lee of the building. A more thorough analysis of the distribution-of Ar-41 in.the atmosphere about the site may be obtained by the use of equat' ion F-1 of Appen-dix F of Regulatory Guide.1.109, " Calculation Reactor Effluents for the Purposes of Compliance with 10 CFR Part 50, Appendix   I."
W.S.U. TRIGA reactor to FLIP fuel as given in Appendix A of this report substantiates a 4 x 10-3 dilution factor for Argon-41 release due to the atmospheric wake effect in the lee of the building. A more thorough analysis of the distribution-of Ar-41 in.the atmosphere about the site may be obtained by the use of equat' ion F-1 of Appen-dix F of Regulatory Guide.1.109, " Calculation Reactor Effluents for the Purposes of Compliance with 10 CFR Part 50, Appendix I."
l The annual release of Ar-41 from the W.S.U. facility for the past five years has averaged 10 Ci/ year. Thus                       i the daily release is .027 Ci/ day which is equivalent to a release rate of 3.17 x 10 -7 Ci/sec.     However, for the purposes of our calculations we shall assume a 100 Ci/ year i
l The annual release of Ar-41 from the W.S.U. facility for the past five years has averaged 10 Ci/ year. Thus i
the daily release is.027 Ci/ day which is equivalent to a
-7 release rate of 3.17 x 10 Ci/sec.
However, for the purposes of our calculations we shall assume a 100 Ci/ year i
d
d
  - - - - , , - - , - - - -    ~-a     e                 e-       ,              ,  -      -,c         ,-.    -------e-
~-a e
e-
-,c
-------e-


c ,
c 33 not to exceed 14 months and shall be verified to be operable at monthly intervals.
33 not to exceed 14 months and shall be verified to be operable at monthly intervals.
Basis Experience has shown that monthly verification of area radiation and air monitoring system set points in conjunction with annual calibration is adequate to correct for any variation in the system due_ to a change of operating characteristics over a long time span.
Basis Experience has shown that monthly verification of area radiation and air monitoring system set points in conjunction with annual calibration is adequate to correct for any variation in the system due_ to a change of operating characteristics over a long time span.
4.3.4 Ventilation System Applicability This specification applies to surveillance requirements for the pool room ventilation system.
4.3.4 Ventilation System Applicability This specification applies to surveillance requirements for the pool room ventilation system.
Objective                                                             :
Objective The objective is to assure the proper operation of the pool room i
The objective is to assure the proper operation of the pool room i             ventilation system in the isolation and dilution modes which would     >
ventilation system in the isolation and dilution modes which would be utilized in controlling the release of radioactive material to the uncontrollad environment in the event of an emergency.
be utilized in controlling the release of radioactive material to     .
Specification The operation of the pool room ventilation system shall be checked monthly by cycling the system from the " normal" to'the " isolate" and " dilution". modes of operation. The positions of the associated dampers, indicator display, and fan operation shall be visually checked to insure correspondence between the device performance and selected mode of operation.
the uncontrollad environment in the event of an emergency.
The pressure drop across the absolute filter in the pool ventilation system shall be measured at least I
Specification The operation of the pool room ventilation system shall be checked     ,
twice a year.
monthly by cycling the system from the " normal" to'the " isolate" and " dilution" . modes of operation. The positions of the associated dampers, indicator display, and fan operation shall be visually checked to insure correspondence between the device performance and   -
The absolute filter shall be changed at least every two years and whenever the pressure drop across the filter exceeds 1 (one) inch of water.
selected mode of operation. The pressure drop across the absolute filter in the pool ventilation system shall be measured at least I
twice a year. The absolute filter shall be changed at least every two years and whenever the pressure drop across the filter exceeds     ,
1 (one) inch of water.


+. ,
+.
34 Basis Experience has shown that the only reliable method of testing the ventilation is to cycle tne system into the various modes and visually check each portion of the system for proper operation in that mode.
34 Basis Experience has shown that the only reliable method of testing the ventilation is to cycle tne system into the various modes and visually check each portion of the system for proper operation in that mode.
4.3.5 Experiment and Irradiation Limits Applicability This specification applies to the surveillance requirements for experiments installed in the reactor and its experimental facilities and for irradiations performed in the irradiation facilities.
4.3.5 Experiment and Irradiation Limits Applicability This specification applies to the surveillance requirements for experiments installed in the reactor and its experimental facilities and for irradiations performed in the irradiation facilities.
Specifications
Specifications a.
: a. A new experiment shall not be installed in the reactor or its experimental facilities until a hazards analysis has been per-fonned and reviewed for compliance with the Limitations on Experiments, Section 3.9, by the Reactor Safeguards Committee.
A new experiment shall not be installed in the reactor or its experimental facilities until a hazards analysis has been per-fonned and reviewed for compliance with the Limitations on Experiments, Section 3.9, by the Reactor Safeguards Committee.
Minor modifications to a reviewed and approved experiment may be made at the discretion of the senior operator responsible for the operation provided that the hazards associated with the modifications have been reviewed and a determination made and documented that the modifications do not create a significantly different, a new, or a greater hazard that the original approved experiment.
Minor modifications to a reviewed and approved experiment may be made at the discretion of the senior operator responsible for the operation provided that the hazards associated with the modifications have been reviewed and a determination made and documented that the modifications do not create a significantly different, a new, or a greater hazard that the original approved experiment.
: b. An irradiation of a new type of device or material shall not be oerformed until an analysis of the irradiation has been performed and reviewed for compliance with the Limitations on Irradiations, Section 3.10, by a licensed senior operator qualified in health physics, or a licensed senior operator and a person qualified in-health physics.
b.
An irradiation of a new type of device or material shall not be oerformed until an analysis of the irradiation has been performed and reviewed for compliance with the Limitations on Irradiations, Section 3.10, by a licensed senior operator qualified in health physics, or a licensed senior operator and a person qualified in-health physics.


48 audit of the faciiitty's activities including:
48 audit of the faciiitty's activities including:
: a. Reactor _ operations
a.
: b. Radiological safety
Reactor _ operations b.
: c. General safety
Radiological safety c.
: d. Testing and experiments
General safety d.
: e. Licensing and reports
Testing and experiments e.
: f. Quality Assurance 6.5.2 Composition and Qualifications The RSC shall be composed of at least 5 members knowledg-able in fields which relate to nuclear reactor safety. The membership of the committee shall include one facility Senior Reactor Operator and W.S.U. faculty and staff members designated to serve on the comittee in accordance with the procedures specified by the W.S.U. committee manual. The university Radiation Safety Supervisor shall be an ex-officio member of the comittee.
Licensing and reports f.
Quality Assurance 6.5.2 Composition and Qualifications The RSC shall be composed of at least 5 members knowledg-able in fields which relate to nuclear reactor safety.
The membership of the committee shall include one facility Senior Reactor Operator and W.S.U. faculty and staff members designated to serve on the comittee in accordance with the procedures specified by the W.S.U. committee manual.
The university Radiation Safety Supervisor shall be an ex-officio member of the comittee.
6.5.3 Operation The operation of the Reactor Safeguards Committee shall be in accordance with a written charter, including provisions for:
6.5.3 Operation The operation of the Reactor Safeguards Committee shall be in accordance with a written charter, including provisions for:
: a. Meeting frequency: The full comittee shall meet at least semiannually and a subcomittee thereof shall meet at least semiannually,
a.
: b. Voting rules,
Meeting frequency: The full comittee shall meet at least semiannually and a subcomittee thereof shall meet at least semiannually, b.
: c. Quorums:   Chairman or his designate and two members,
Voting rules, c.
: d. Method of submission and content of presentations to
Quorums:
!                        the committee, i
Chairman or his designate and two members, d.
Method of submission and content of presentations to the committee, i
L.
L.


    =       * .
=
49
49 e.
: e. Use of subcommittees, and
Use of subcommittees, and f.
: f. Review, approval, and dissemination of minutes.
Review, approval, and dissemination of minutes.
6.5.4 Reviews The responsibilities of the RSC or designated Subcommittee thereof shall include, but is not limited to, the following:
6.5.4 Reviews The responsibilities of the RSC or designated Subcommittee thereof shall include, but is not limited to, the following:
: a. Review and approval of all new. experiments utilizing the reactor facility,
Review and approval of all new. experiments utilizing the a.
: b. Review and approval of all proposed changes to the faci-4 lity license by amendment, and to the Technical Specifi-cations,                                                     .
reactor facility, b.
: c. Review of the operation and operational records of the facility, 4
Review and approval of all proposed changes to the faci-lity license by amendment, and to the Technical Specifi-4
: d. Review of significant operating abnormalities or devia-i tions from normal and expected performance of facility i
: cations, Review of the operation and operational records of the c.
equipment that affect nuclear safety,                         j
: facility, 4
: e. Review and approval of all determinations of whether a       ;
d.
proposed change, test, or experiment would constitute a       ;
Review of significant operating abnormalities or devia-i tions from normal and expected performance of facility i
o change in the Technical Specifications or on unreviewed       t
equipment that affect nuclear safety, j
  ~
e.
safety question as defined by 10 CFR Part 50.               ;
Review and approval of all determinations of whether a proposed change, test, or experiment would constitute a o
                                                                        -                    t
change in the Technical Specifications or on unreviewed t
: f. Review of reportable occurrences and the reports files with the Commission for said occurrences.                     ;
~
                                                                                            +
safety question as defined by 10 CFR Part 50.
I l                         g. Review and approval of all standard operating procedures     l and changes thereto.                                        .
t f.
I
Review of reportable occurrences and the reports files with the Commission for said occurrences.
: h. Biennial reviews of all standard procedures, the faci-lity emergency plan, and the facility security plan.       ;
+
6.5.5 Audits                                                               ,
l g.
f The RSC or a subcommittee thereof shall audit reactor opera-tions semiannually, but at intervals not to exceed eight
Review and approval of all standard operating procedures l
I and changes thereto.
I h.
Biennial reviews of all standard procedures, the faci-lity emergency plan, and the facility security plan.
6.5.5 Audits f
The RSC or a subcommittee thereof shall audit reactor opera-tions semiannually, but at intervals not to exceed eight


o'   ** .
o' 50 months. The semiannual audit shall include at least the following:
50 months. The semiannual audit shall include at least the following:
a.
: a. Review of the reactor operating records,
Review of the reactor operating records, b.
: b. Inspection of the reactor opera ting areas,
Inspection of the reactor opera ting areas, c.
: c. Review of unusual or abnormal occurrences, and               !
Review of unusual or abnormal occurrences, and d.
: d. Radiation exposures at the facility and adjacent environs.
Radiation exposures at the facility and adjacent environs.
6.5.6 Records _                                                             ,
6.5.6 Records _
The activities of the RSC shall be documented by the secretary     I of the committee and distributed as follows:
The activities of the RSC shall be documented by the secretary I
: a. A written report of all audits performed under Section       l 6.5.5 shall be prepared and fomarded within 30 days to       j I
of the committee and distributed as follows:
the Dean of the Graduate School and Facility Director.
A written report of all audits performed under Section l
: b. A written report of all reviews performed under Section     -
a.
I 6.5.4 shall be prepared and fomarded to the Facility Director within 30 days following the completion of the review.                                                   I
6.5.5 shall be prepared and fomarded within 30 days to j
: c. The secretary of the RSC shall maintain a file of the i
I the Dean of the Graduate School and Facility Director.
minutes of all meetings.                                     t
b.
                                                                          ~
A written report of all reviews performed under Section I
6.0 Quality Assurance                                         ,
6.5.4 shall be prepared and fomarded to the Facility Director within 30 days following the completion of the I
In accordance with Regulatory Guide 2.5 and ANSI 402, " Quality Assur-     ;
review.
I ance Program Requirements for Research Reactors," section 2.17, the         :
c.
                  " facility shall not be required to prepare quality assurance documen-     !
The secretary of the RSC shall maintain a file of the i
tation for the as-built facility."         Q.A. requirements will still be limited to those specified in section 2.17 as follows:                     ;
t minutes of all meetings.
'                                                                                              i l
~
a) All replacements, modification, and changes to systems having a
6.0 Quality Assurance In accordance with Regulatory Guide 2.5 and ANSI 402, " Quality Assur-I ance Program Requirements for Research Reactors," section 2.17, the
!                      safety related function shall be subjected to a Q. A. review.
" facility shall not be required to prepare quality assurance documen-tation for the as-built facility."
Insofar as possible, the replacement, modification, or change         ,
Q.A. requirements will still be limited to those specified in section 2.17 as follows:
shall be documented as meeting the requirements of the nriginal system or component and have equal or better performance or rel iability.
i l
a) All replacements, modification, and changes to systems having a safety related function shall be subjected to a Q. A. review.
Insofar as possible, the replacement, modification, or change shall be documented as meeting the requirements of the nriginal system or component and have equal or better performance or rel iability.
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Latest revision as of 15:29, 23 December 2024

Forwards Updated & Corrected Drawings for Inclusion in SAR & Changes to Proposed Tech Specs Re Reactor Ventilation Sys
ML20003C568
Person / Time
Site: Washington State University
Issue date: 03/02/1981
From: Wilson W
WASHINGTON STATE UNIV., PULLMAN, WA
To: Joshua Wilson
Office of Nuclear Reactor Regulation
References
NUDOCS 8103060473
Download: ML20003C568 (14)
v • d • e


Text

WASHINGTON STATE UNIVERSITY

),g PULLMAN, WASlilNGTON 'niss NL' CLEAR RADIATION CENTER March 2, 1981 N

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MdRo $'193;w l.7 Mr. J. Wilson I

Ss. %*"""uma_ __~ e, 5}

Standards and Special Projects Branch Division of React (~ Licensing

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U.S. Nuclear Regulatory Commission Washington, DC 20555 8 3 84

Dear Mr. Wilson:

Enclosed cre 22 cooies of updated and corrected drawings for inclusion in the SAR for Facility R-76.

The pages provided replace existing pages in the SAR submitted with the application to renew Facility License R-76.

Please distri-bute these updates to holders of the SAR.

During a recent inspection by the I & E division of the NRC, a number of changes were suggested to the proposed facility Technical Specificiations.

Enclosed are 4 copies of each page of the T.S. reflecting these changes.

Please distribute to holders of the T.S.

Did you ever receive the copy of the reactor pool structural drawings and the copy of the letter from Campbell Engineers about the pool design? Please advise.

Sincerely, h' (' ' E,hy W. E. Wilson Associate Director WEW:sms Enclosures t

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.Dur.ing normal' operation, 9.44 x 10 cm /sec of air from the poolIroom is 5'

3 mixed with the beam room exhaust and discharges out the monitored exhaust.

In' the isolation mode, dampers on the pool room supply and exhaust lines t

. serve to prevent all air flow into and out of the pool. room.

In the

+

5 3/sec of pool room air. is passed through 'an dilution mode,1.42 x 10 c 5

3 absolute filter, mixed with 8.02 x 10 cm /sec of outside air, and dis-charges up the exhaust stack. _The main. control panel-for the system is located in the reactor control room and a set of emergency-controls is 3

located in the main office.

The continuous air monitor and gaseous efflu-ent monitors are shown in Figure 3.2-2 and 3.2-3.

3. 3' Pool The reactor pool is a reinforced, above ground, unlined concrete pool j

with a volume of 247,000 liters.

The pool is penetrated by a thermal col-umn and a nunber of beam ports as described in Section 4.11.

A cross sec-4 tion of the pool is shown in Figure 3.3-1.

3.4 Liquid Waste Collection System The Nuclear Radiation Center has two separate waste systems.

The l

sanitary waste system handles all the normal non-radioactive liquids and the " hot-drain" system handles all the radioactive liquids.

The sanitary waste system connects all the washroom fixtures and cold laboratory drains to the campus sewer system.

The " hot drain" system connects all the j

drains from the radiochemistry laboratories and reactor areas to a reten-l tion tank system.

Radioactive effluents from the Center are collected in

?

l the retention tank system shown in Figure 3.4-1.

Prior to discharge into the sanitary sewer, the contents of the retention tank are pumped to a sampling tank.

The sampling tank is sampled, evaluated for activity con-tent,-and diluted as necessary during discharge. Discharges pass through a j

particulate collection filter.

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FIGURE 3.4-1 1

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O SAFETY CHANNEL LINEAR INDICATION CIIANNEL LOG-N LOG-N COMP.

POWER HIGH VOLTAGE SUPPLY VOLTAGE SAFETY LINEAR

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4-28 SCP'" CIRCUITRY C)

Scram Signal from upAmm #1 125%

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Scram Signal 1

Scram Signal from from C.I.C Fuel Temp.< 500 C H.V. Failure LOGIC ELEMENT Scr'am Signal from L

Period Amp. T<5 sec.

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not required at all times.

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FIGURE 4.8-4

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SUPPLY SUPPLIES MONITOR l

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PERIOD LOGIC

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FISSION RECORDER CII.WSER 7

WIDE RANGE CllANNEL FIGURE 4.8-5

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0 o3.0 ?> o es m n) i ImL WATER PURIFICATION & !!AKE-UP SYSIMI FIGURE.4.10-1

6-13 (1) Maximum FLIP fuel temperature of 950*CI (2) Maximum Standard fuel temperature of 800 C (3) ' Maximum reactivity insertion of $2.50 (4). LSSS of 500'C for fuel temperature scram (S) Maximum allowable power density of 23.5 Kw/ rod for FLIP and 22.3 Kw/ rod for Standard fuels.

The analysis also demonstrates that 'no realistic hazard to the general public would result from the Design Base j

Accident, a loss of Coolant Accident, the accidental addition of one 4-rod cluster, or the accidental ejection of the transient rod at' full power.

6.4.2 Argon-41 Releases j

Section 6.5 of the S.A.R. for the conversion of the O

W.S.U. TRIGA reactor to FLIP fuel as given in Appendix A of this report substantiates a 4 x 10-3 dilution factor for Argon-41 release due to the atmospheric wake effect in the lee of the building. A more thorough analysis of the distribution-of Ar-41 in.the atmosphere about the site may be obtained by the use of equat' ion F-1 of Appen-dix F of Regulatory Guide.1.109, " Calculation Reactor Effluents for the Purposes of Compliance with 10 CFR Part 50, Appendix I."

l The annual release of Ar-41 from the W.S.U. facility for the past five years has averaged 10 Ci/ year. Thus i

the daily release is.027 Ci/ day which is equivalent to a

-7 release rate of 3.17 x 10 Ci/sec.

However, for the purposes of our calculations we shall assume a 100 Ci/ year i

d

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c 33 not to exceed 14 months and shall be verified to be operable at monthly intervals.

Basis Experience has shown that monthly verification of area radiation and air monitoring system set points in conjunction with annual calibration is adequate to correct for any variation in the system due_ to a change of operating characteristics over a long time span.

4.3.4 Ventilation System Applicability This specification applies to surveillance requirements for the pool room ventilation system.

Objective The objective is to assure the proper operation of the pool room i

ventilation system in the isolation and dilution modes which would be utilized in controlling the release of radioactive material to the uncontrollad environment in the event of an emergency.

Specification The operation of the pool room ventilation system shall be checked monthly by cycling the system from the " normal" to'the " isolate" and " dilution". modes of operation. The positions of the associated dampers, indicator display, and fan operation shall be visually checked to insure correspondence between the device performance and selected mode of operation.

The pressure drop across the absolute filter in the pool ventilation system shall be measured at least I

twice a year.

The absolute filter shall be changed at least every two years and whenever the pressure drop across the filter exceeds 1 (one) inch of water.

+.

34 Basis Experience has shown that the only reliable method of testing the ventilation is to cycle tne system into the various modes and visually check each portion of the system for proper operation in that mode.

4.3.5 Experiment and Irradiation Limits Applicability This specification applies to the surveillance requirements for experiments installed in the reactor and its experimental facilities and for irradiations performed in the irradiation facilities.

Specifications a.

A new experiment shall not be installed in the reactor or its experimental facilities until a hazards analysis has been per-fonned and reviewed for compliance with the Limitations on Experiments, Section 3.9, by the Reactor Safeguards Committee.

Minor modifications to a reviewed and approved experiment may be made at the discretion of the senior operator responsible for the operation provided that the hazards associated with the modifications have been reviewed and a determination made and documented that the modifications do not create a significantly different, a new, or a greater hazard that the original approved experiment.

b.

An irradiation of a new type of device or material shall not be oerformed until an analysis of the irradiation has been performed and reviewed for compliance with the Limitations on Irradiations, Section 3.10, by a licensed senior operator qualified in health physics, or a licensed senior operator and a person qualified in-health physics.

48 audit of the faciiitty's activities including:

a.

Reactor _ operations b.

Radiological safety c.

General safety d.

Testing and experiments e.

Licensing and reports f.

Quality Assurance 6.5.2 Composition and Qualifications The RSC shall be composed of at least 5 members knowledg-able in fields which relate to nuclear reactor safety.

The membership of the committee shall include one facility Senior Reactor Operator and W.S.U. faculty and staff members designated to serve on the comittee in accordance with the procedures specified by the W.S.U. committee manual.

The university Radiation Safety Supervisor shall be an ex-officio member of the comittee.

6.5.3 Operation The operation of the Reactor Safeguards Committee shall be in accordance with a written charter, including provisions for:

a.

Meeting frequency: The full comittee shall meet at least semiannually and a subcomittee thereof shall meet at least semiannually, b.

Voting rules, c.

Quorums:

Chairman or his designate and two members, d.

Method of submission and content of presentations to the committee, i

L.

=

49 e.

Use of subcommittees, and f.

Review, approval, and dissemination of minutes.

6.5.4 Reviews The responsibilities of the RSC or designated Subcommittee thereof shall include, but is not limited to, the following:

Review and approval of all new. experiments utilizing the a.

reactor facility, b.

Review and approval of all proposed changes to the faci-lity license by amendment, and to the Technical Specifi-4

cations, Review of the operation and operational records of the c.
facility, 4

d.

Review of significant operating abnormalities or devia-i tions from normal and expected performance of facility i

equipment that affect nuclear safety, j

e.

Review and approval of all determinations of whether a proposed change, test, or experiment would constitute a o

change in the Technical Specifications or on unreviewed t

~

safety question as defined by 10 CFR Part 50.

t f.

Review of reportable occurrences and the reports files with the Commission for said occurrences.

+

l g.

Review and approval of all standard operating procedures l

I and changes thereto.

I h.

Biennial reviews of all standard procedures, the faci-lity emergency plan, and the facility security plan.

6.5.5 Audits f

The RSC or a subcommittee thereof shall audit reactor opera-tions semiannually, but at intervals not to exceed eight

o' 50 months. The semiannual audit shall include at least the following:

a.

Review of the reactor operating records, b.

Inspection of the reactor opera ting areas, c.

Review of unusual or abnormal occurrences, and d.

Radiation exposures at the facility and adjacent environs.

6.5.6 Records _

The activities of the RSC shall be documented by the secretary I

of the committee and distributed as follows:

A written report of all audits performed under Section l

a.

6.5.5 shall be prepared and fomarded within 30 days to j

I the Dean of the Graduate School and Facility Director.

b.

A written report of all reviews performed under Section I

6.5.4 shall be prepared and fomarded to the Facility Director within 30 days following the completion of the I

review.

c.

The secretary of the RSC shall maintain a file of the i

t minutes of all meetings.

~

6.0 Quality Assurance In accordance with Regulatory Guide 2.5 and ANSI 402, " Quality Assur-I ance Program Requirements for Research Reactors," section 2.17, the

" facility shall not be required to prepare quality assurance documen-tation for the as-built facility."

Q.A. requirements will still be limited to those specified in section 2.17 as follows:

i l

a) All replacements, modification, and changes to systems having a safety related function shall be subjected to a Q. A. review.

Insofar as possible, the replacement, modification, or change shall be documented as meeting the requirements of the nriginal system or component and have equal or better performance or rel iability.

l I

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