ML20102C148
| ML20102C148 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/28/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20102C149 | List: |
| References | |
| NUDOCS 8503050303 | |
| Download: ML20102C148 (36) | |
Text
,.
DRESDEN II DPR-19 s
Amendment 50. pd,83 Corrected February
, 1985 (Table of Contents. Cont'd.)
FEBRUAar 2 a E.811 4.9 Auxiliary Electrical Systems 3/4.9 - 1 4.9.A Station Batteries 3/4.9 - 1 4.9.B (N/A) 4.9.C Diesel Fuel 3/4.9 - 4 4.9.D Diesel Generator Operability 3/4.9 - 4 4.10 Refueling 3/4.10- 1 4.10.A Refueling Interlocks 3/4.10- 1 4.10.5 Core Monitoring 3/4.10- 1 4.10.C Fuel Storage Pool Water Level 3/4.10- 2 4.10.D Control Rod Drive and Control Rod Drive Maintenance 3/4.10- 3 4.10.E Estended Core Maintenance 3/4.10- 4 4.10.F Spent Fuel Cask Handling 3/4.10- 5 4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems 3/4.12-1 4.12.A Fire Detection Instrumentation 3/4.12-1 4.12.5 Fire Suppression Water System 3/4.12-2 4.12.C Sprinkler Systems 3/4.12-5 4.12.D CO2 System 3/4.12-7 4.12.E Fire Mose.0tations 3/4.12-8 4.12.F Penetration Fire Barriers 3/4.12-9 4.12.G Fire Pump Diesel Engine 3/4.12-10 4.12.H Halon System 3/4.12-13 5.0 Design Features 5-1 5.1, Site 5-1 5.2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Plant Operating Procedures 6-14 6.3 Actions to be taken in the Event of A Reportable Occurrence in Plant Operation 6-16 i
6.4 Action to be taken in the Event a Safety Limit is Exceeded 6-16 6.5 Plant Operating Records 6-17 6.6 Reporting Requirements 6-18 6.7 Environmental Quellfication 6-27
{
8503050303 B M228 PDR ADOCK 05000237 P
PDR vi l
l 3959a 3843A l
DRESDEN II DPR-19 Amendment C3. pf,83 COtrectepEbr.una iFebruary,1985
- 4 TABLE 3.2.1 INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION FUNCTIONS MINIMUM # OF OPERABLE INST.
CHANNELS PER TRIP SYSTEM (1)
INSTRUMENTS TRIP LEVEL SETTING ACTION (3) 2 Reactor Low Greater than 144" A
Water Level above top of active fuel (9) 2 Reactor Low Greater than or equal A
Low Water to 84" above top of active fuel (9) 2 High Drywell Less than or equal A
Pressure to 2 psig (4),(5) 2 (2)
High Flow Main Less than or equal B
Steam Line to 120% of rated steam flow 2 of 4 in each High Temperature Less than or equal B
of 4 sets Main Steamline to 200*F.
Tunnel 2
High Radiation Less than or equal B
Main Steamline to 3 times full Tunnel power background (7).(6) 2 Low Pressure Greater than or equal B
Main Steamline to 850 psig High Flow Isolation 1
Condenser Line Less than or equal C
Steamline side to 20 ps! diff on steamline side.
1 Condensate Less than or equal C
Returu Side to 32" water diff on condensate return side 2
High Flow HPCI Less than or equal D
Steamilne to 150 inches of water diff. (8) 4 High Temperature Less than or equal D
HPCI Steamline Ares to 200*F.
Notes l
(See Next Page) l t
l 3/4.2-8 3960s 3843A l
DRESDEN II DPR-19 Amendment N3. P4, 83 Corrected February
,1985 TABLE 3.2.1 (Notes)
FEBRUARY 2 6 1.
When primary containment integrity is required, there shall be two operable or tripped trip systems for each function, except for low pressure main steamline which only need be available in the RUN position.
2.
Per each steamline.
3.
Action: If the first column cannot be met for ggeh of the trip systems, that trip system shall be tripped.
If the first column cannot be met for bgth trip systems, the appropelate action listed below shall be taken:
A.
Initiate an orderly shutdown and have reactor in cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction and have reactor in hot standby condition in a hours.
C.
Close isolation valves in Isolation Condenser System.
D.
Close isolation valves in HPCI subsystem.
4.
Need not be operable when primary containment integrity is not required.
5.
May be bypassed when necessary during purging for containment inerting and deinerting.
6.
An alarm setting of less than or equal to 1.5 times normal background at rated power shall be established to alert the operator to abnormal radiation levels in the primary coolant.
7.
Due to addition of hydrogen to the primary coolant, the Main steam Line Radiation monitor setting will be less than or equal to 3 times full power background without hydrogen addition for all conditions oncept for greater than 20% power with hydrogen being injected during which the Main Steam Line Radiation trip setting will be less than or equal to 3 times full power background with hydrogen addition.
Required changes in Main steam Line Radiation monitor trip setting will be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> oncept during controlled power descensions at which time the setpoint change will be made prior to going below 20% power.
If due to a recirculation pump trip or other unanticipated power reduction event the reactor is below 20% power without the setpoint change, control rod motion will be suspended until the necessary trip setpoint adjustment is made.
8.
Verification of time delay setting between 3 and 9 seconds shall be performed during each refueling outage.
9.
Top of active fuel is defined as 360" above vessel aero for all water levels used in the LOCA analyses.
(See design Bases 3.2) 3/4.2-9 3960s 3843A
DRESDEJ II DPR-19 Ame:dment C3. 1)d,83 Corrected February 1985 O
TABLE 3.2.3 INSTRUMENTATION THAT INITIATES ROD BLOCK Minimum No. of Operable Inst.
Channels Per Trio System (1)
Instrument Trip Level Settint 1
APRM upscale (flow bles) (7)
Less than or equal to (0.58 Wo plus 50) (FRP/MFLPD)
(See Note 2) 1 APRM upscale (refuel and Less than or equal to Startup/ Hot Standby mode) 12/125 full scale 2
APRM downscale (7)
Creater than or equal to 3/125 full scale 7
1 Rod block monitor Less than or equal to upscale (flow blas) (7)
(0.65 WD Plus 45)
(see Note 2) 1 Rod block monitor creater than or equal to downscale (7) 5/125 full scale 3
IRN downscale (3)
Creater than or equal to 5/125 full scale 3
IRM upscale Less than or equal to 108/125 full scale 3
IRN detector not fully N/A inserted in the core 2 (5)
SRM detector not in startup position (4) 2 (5) (6)
SRM upscale Less than or equal to 105 counts /sec.
1 Scram discharge volume Less than or equal to water level - high 25 gallons l
Notest j
(See West Page) l 3/4.2 12
}
3960s j
3043A
DRESDEN II DPR-19 CorrectedFebr%,83 Amendment N3.
uary
,1985 Ftsu/M 2 d TABLE 3.2.5 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum No.
of Operable Total No.
Channels (1) of Channels Parameter Action (2) 1 2
SJAE Radiation Activity Monitor D
1 3
Main chimney Noble cas SPING/GE A
Low Range Activity Monitor 1
1 Main Chimney SPING Noble Gas A
Monitors Mid, Hi Range 1
1 Main Chimney Iodine Sampler C
1 1
Main Chimney Particulate Sampler C
~
1 1
Main Chimney Flow Rate Monitor B
1 1
Main chimney Sampler Flow B
Rate Monitor 1
2 Reactor Building Vent Exhaust E
Duct Radiation Monitor 1
1 Reactor Building Vent SPING Noble F
Gas Monitor Low, Mid High Range 1
1 Reactor Building Vent Flow Rate B
Monitor 1
1 Reactor Building Vent Sampler Flow B
Rate Monitor 1
1 Reactor Bu11ains Vent Iodine C
Sampler 1
1 Reactor Building Vent Particulate C
Sampler Notes:
(See Next Page) 3/4.2-15 l
3960s 3843A
DRESDEN II DPR-19 Amendment N3. P4 83 Corrected February
,1985 FEEht/ay 2,
TABLE 4.2.2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibration Functional Source Instrument Check (1)(7)
(1)(7)(3)(4)
Test (1)(2)(7) Chock (1)
Liquid Radweste D
R Q (6)
(5)
Rffluent Gross Activity Monitor Service Water D
R Q (6)
R Effluent Cross Activity Monitor Tank Level Indicating Device
- a. A Waste Sample Tank D
R Q
N/A
- b. B Weste Sample Tank D
R Q
N/A
- c. C Waste Sample Tank D
R Q
N/A
- d. A Floor Drain Sample D
R Q
N/A Tank
- e. 3 Floor Drain Sample D
R Q
N/A Tank
- f. Weste Surge Tank D
R Q
N/A Notes:
(See Next Page) 3/4.2-20 l
3960s 3043A l
DRESDEN II DPR-19 Amendment N3. Pd,83 Corrected February
,1985 FEb h u A,- i J TABLE 4.2.3 (Notes) 1.
D = Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = Once per 31 days Q = Once per 92 days R = Once per refueling outage 2.
The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.
Instrument indicates levels above the alarm setpoint.
a.
b.
Circuit Failure.
c.
Instrument indicates a downscale failure, d.
Instrument controls not set in OPERATE mode.
3.
Calibration shall include performance of a functional test.
4.
Instrument check to verify operability of sampler; that the sampler is in place and functioning properly.
5.
Function Test shall be performed on local switches providing low flow alarm.
6.
Function test calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped.
Calibration shall be performed once per refueling outage and not more than once every 18 months.
Instrument checks shall be performed at least once per day during those periods when the instruments are required to be operable.
3/4.2-23 3960s 3843A
DRESDEN II DPR-19 Amendment No. Pf, 83 Corrected February
,1985 FEBhU?at 2 s 3.2 LIMITING CONDITION FOR OPERATION BASES In addition to reactor protection instrumentation which initiates a reactor scram, protective instrumentation has been provided which initiates action to mitigate the consequences of accidents which are beyond the operator's ability to control, or terminates operator errors before they result in serious consequences. This set of specifications provides the limiting conditions of operation for the primary system isolation function, initiation of the emergency core cooling system, control rod block and standby gas treatment systems. The objectives of the specifications are
- 1) to assure the effectiveness of the protective instrumentation when required by preserving its capability to tolerate a single failure of any component of such systems even during periods when portions of such systems are out of service for asintenance, and
- 2) to prescribe the trip settings required to assure adequate performance. When necessary, one channel may be made inoperable for brief intervals to conduct required functional tests and calibrations.
Some of the settings on the instrumentation that initiates or control core and containment cooling have tolerances explicitly stated where the high and low values are both critical and may have a substantial effect on safety.
It should be noted that the setpoints of other instrumentation, where only the high or low end of the setting has a direct bearing on safety, are chosen at a level away from the normal operating range to prevent inadvertent actuation of the safety system involved and exposure to abnormal situations.
Isolation valves are installed in those lines that penetrate the primary containment and must be isolated during a loss-of-coolant accident so that the radiation dose limits are not exceeded during an accident condition. Actuation of these valves is initiated by protective instrumentation which serves the condition for which isolation is required (this instrumentation is shown in Table 3.2.1).
such instrumentation must be available whenever primary containment integrity is required. The objective is to isolate the primary containment so that the guidelines of 10 CFR 100 are I
not exceeded during an accident.
l The instrumentation which initiates primary system isolation is connected in a dual bus arrangement. Thus the discussion given in the bases for specification 3.1 is applicable here.
i The low-reactor level instrumentation is set to trip at greater l
than 8 inches on the level instrument (top of active fuel is defined to be 360 inches above vessel sero) and after allowing for the full power pressure drop across the steam dryer the low level
{
trip is at 504 inches above vessel sero, or 144 inches above the l
[
8 3/4.2-24 l
3960s 3843A
DRESDEN II DPR-19 Amendment No. pt, 83 Corrected February
,1985 FEBRu/d, 23 4.2 SURVEILLANCE REOUIREMENT BASES The instrumentation listed in Table 4.2.1 will be functionally tested and calibrated at regularly scheduled intervals. Although this instrumentation is not generally considered to be as important_to plant safety as the Reactor Protection System, the same design reliability goal of 0.99999 is generally applied for all applications of (1 out of 2) I (2) logic. Therefore, on-off sensors are tested once/3 months, and bi-stable trips associated with analog sensors and amplifiers are tested once/ week.
Those instruments which, when tripped, result in a rod block have their contacts arranged in a 1 out of n logic, and all are capable of being bypassed. For such a tripping arrangement with bypass capability provided, there is an optimum test interval that should be maintained in order to maximize the reliability of a given channel (see note 7).
This takes account of the fact that testing degrades reliability and the optimum interval between tests is approximately given by:
i = (2t/c)1/2 Where:
l i = optimum interval between tests t = the time the trip contacts are disabled from performing their function while the test is in progress e = The expected failure rate of the relays To test the trip relays requires that the channel be bypassed, the test made, and the system returned to its initial state.
It is assumed this task requires an estimated 30 minutes to complete in a thorough and worbaanlike manner and that the relays have a failure rate of 10-6 failures per hour. Using this data and the above operation, the optimum test interval is:
i = [2(0.5)/10-6 1/2,1 g 103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> 3
= approximately 40 days For additional margin a t'est interval of once per month will be used initially.
Note:
(7) UCRL-50451, Improving Availability and Readiness of Field Equipment Through Periodic Inspection, Benjamin Epstein, Albert Shlff, July 16, 1968, page 10 Equation (24), Lawrence Radiatica ' boratory.
B 3/4.2-30 3960a 3843A 7
l
' hj)
DRESDEN II DPR-19' AmendJont No. pt, 83 t
Corrected February
, 1935 FEBRUARY 2 4 4.2 SURVEILLANCE REOUIREMENT BASES (Cont'd.)
A more usual case is that the testing is done independently.
If both channels are bypassed and tested at the same. time, the result is shown in Curve No. 3.
Note that the minimum occurs at about 40,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, much longer than for cases 1 and 2.
Also, the mini-num is not nearly as low as Case 2 which indicates that this method of testing does not take full advantage of the redundant channel.
Bypassing both channels for simultaneous testing should be avoided.
The most likely case would be to stipulate that one channel be by-passed, tested and restored. Then immediately following, the second channel be bypassed, tested and restored. This is shown by Curve No. 4.
Note that there is no true minimum. The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channel.
The best test procedure of all those examined is to perfectly stagger the tests. That is, if the test interval is four months, test one or the other channel every two months. This is shown in Curve No. 5.
The difference between Cases 4 and 5 is negligible.
There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.
The conclusions to be drawn are these:
1.
A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval; and 2.
More than one channel should not be bypassed for testing at any one time.
The radiation monitors in the ventilation duct and on the refueling floor which initiate building isolation and standby gas treatment operation are arranged in two 1 out of 2 logic systems.
The bases given above for the rod blocks applies here also and were used to arrive at the functional testing frequency.
Based on experience at Dresden Unit 1 with instruments of similar design, a testing interval of once every three months has been found to be adequate.
The adtomatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.
B 3/4.2-32 3960a 3843A
FEBht1ARY 2 S DRESDEN II DPR-19 Amendment No. pt, 83 Corrected Februar3t-
.1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
of radioactive materials in accordance with the shall be operated.
ODCM.
b.
The above specifica-tions shall not apply for the Off-Gas Char-coal Adsorber Beds below 30 percent of rated thermal power.
c.
The recombiner shall be operable whenever the reactor is oper-sting at a pressure greater than 900 psis, d.
The recombiner may be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
i 5.
Explosive Gas Mixture 5.
Explosive Gas Mixture a.
During power operation The instrument response there will be an operable of the hydrogen monitor hydrogen monitor in the shall be tested once off-gas hold-up system.
per day.
If this is inoperable, operation shall be limited according to Specification 3.8.A.S.b.
b.
The concentration of hydrogen in the off-
~
gas hold-up system, downstream of the re-combiner shall be limited by verifica-tion every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> that the recombiner is operating within the allowable band of the baseline plot of recombiner outlet temperature vs.
reactor power.
3/4.8-7 3817a 3843A
FEBRUAPY ?3 DRESDEN II DPR-19 I
Amendmint No. F, 83 Corrected February 1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS (Cont'd.)
(cont'd.)
released from the site unrestricted areas to unrestricted areas shall be determined to (at or beyond the site be within the pre-boundary, Figures 4.8.1 scribed limits by ob-and 4.8.2) shall be lim-taining representa-ited to the concentrations tive samples in accordance specified in 10 CFR Part with the sampling and 20, Appendix B. Table II, analysis program specified Column 2 with the Table in Table 4.8.3.
The sample 4.8.2 values represent-analysis results will be ing the MPC's for noble used with the calculational gases.
methods in the ODCM to de-termine that the concen-With the concentration trations are within the of radioactive material limits of Specification released from the site 3.8.B.1.
to unrestricted areas ex-ceeding the above limits, without delay decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.
2.
The dose or dose com-2a. The dose contribution mitment above background from measured quanti-l to a member of the public ties of radioactive from radioactive mater-material shall be ials in liquid effluents determined by calcu-i released to unrestricted lation at least once areas (at or beyond the per 31 days and cumula-site boundary) from the tive summation of these site shall be limited total body and organ to the following:
doses shall be main-tained for each calen-a.
During Any Calendar dar quarter.
Quarter:
(1) Less than or equal to 3 mrem to the whole body.
(2) Less than or equal to 10 meem to any organ.
3/4.8-10 3817a 3843A
FEEii; DRESDEN II DPR-19 Amendment No. pd, 83 Corrected February
,1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
the reasons' for not con-ducting the program as required and the plans for preventing a recur-rence.
Deviations are permitted from the re-quired sampling schedule if specimens are unob-tainable due to hazardous conditions, seasonal un-availability, contractor omission which is cor-rected as soon as dis-covered, malfunction of sampling equipment, or if a person who participates in the program goes out of business.
If the
~
equipment malfunctions, corrective actions shall De completed as soon as practical.
If a person supplying samples goes out of business, a re-placement supplier will be found as soon as possible. All deviations from the sampling i
schedule shall be described in the Annual Report.
3.
When the level of radio-3.
The land use census activity in an environ-shall be conducted at mental sampling medium least once per twelve at one or more of the months between the locations specified in dates of June 1 and the ODCM exceeds the October 1 by a door-limits of Table 4.8.5 to-door survey, serial when averaged over any survey, road survey, or calendar quarter, prepare by consulting local l
and submit to the Com-agriculture authorities.
t mission within 30 days from the end of the af-facted calendar quarter, a Special Report which 3/4.8-16 3817a 3843A
FEBRU4ar 9 e DRESDEN II DPR-19 Amendment No. p2, 83 Corrected February
,1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE REOUIREMENTS (Cont'd.)
(Cont'd.)
b.
In any form other than gas.
2.
Stored sources not in use - Each sealed source shall be tested prior to the use or transfer to another licensee unless tested within the previous 6 months. Sealed sources transferred without a certificate indicating the last test case shall be tested prior to being placed into use.
A complete inventory of radio-A Special Report shall be active materials in the prepared and submitted to licensee's possession shall the Commission pursuant to be maintained current at Specification 6.6.B. if all times.
source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.
H.
In the event a limiting con-dition for operation and/or associated action require-ments identified in Sections 3.8.A through 3.8.E and 4.8.A through 4.8.E cannot be satisfied because of cie-cumstances in excess of those addressed in the specifi-cations, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
3/4.8-21 3817a 3843A
FEBRUlaY 2 8 DRESDEN II DPR-19 Amendment No. pit, 83 Corrected February
, 1985 TABLE 4.8.5 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels 2
ANALYSIS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS (pCl/1) OR CASES (pCl/m3)
(pci/Kr. wet)
(DCi/1)
(pci/Kr. wet)
H-3 2 1 104 (see note 1)
Mn-54 1 I 103 3 x 104 Fe-59 4 1 102 1 I 104 Co-58 1 1 103 3 I 104 Co-60 3 1 102 2 I 104 Zn-65 3 I 102 2 I 104 Zr-Mb-95 4 1 102 I-131 2
0.9 3
1 1 102 Cs-134 30 10 1 I 103 60 2 1 103 Cs-137 50 20 1 1 103 70 2 X 103 Ba-La-140 2 I 102 3 1 102 Notes:
- 1) For drinking water samples. This is 40 CFR Part 141 value.
3/4.8-28 3817a 3843A
DRESDEN II DPR-19 Amendment No. pf, 83 Corrected February
,1985 TABLE 4.8.6 NOTES (Continued)
TABLE NOTATION D.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation) 4.66 - (S )
b LLD =
(A)-(E)-(V)-(2.22)-(Y)-(exp(-)Lat))-(t)
Where:
LLD is the "A priori" lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume).
Sb is the square root of the background count or of a blank sample
~
count; is the estimated standard error of a background count or a blank sample count as appropriate (in units of counts).
E is the counting efficiency (as counts per disintegration).
A is the number of gamma-rays emitted per disintegration for gamma-ray radio-nuclide analysis (A = 1.0 for gross alpha and tritium measurements).
V is the sample size (in units of mass or volume).
2.22 is the number of disintegrations per minute per picoeurie.
Y is the fractional radio-chemical yield when applicable (otherwise Y-1.0).
Lambda is the radioactive decay constant for the particular radionuclide (in units of reciprocal minutes).
Delta t it the elapsed time between the midpoint of sample collection and the start time,of counting.
( t = 0.0 for environmental samples and for gross alpha measurements).
t is the duration of the count (in units of minutes).
The value of "S " used in the calculation of the LLD for a detection b
system shall be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value. Typical values of "E",
"V",
"Y",
"t",
and " delta t" shall be used in the calculation.
3/4.8-30 3817a 3843A
DRESDEN II DPR-19 Amendment No. p2, 83 Corrected February
,1985 3.8 LIMITING CONDITION FOR OPERATION PASES (Cont'd.)
F.
Deleted G.
Miscellaneous Radioactive Materials Sources The objective of this specification is to assure that leakage from by-product, source and special nucleer material sources does not exceed allowable limits. The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39 (c) limits for plutonium.
4.8 SURVEILLANCE REOUIREMENT BASES None l
+
l 8 3/4.8-37 l
l 3817a 3843A l
DRESDEN III DPR-25 knendment No. p. 77 Corrected February
,1985 FEBRUAa( 0d (Table of Contents. Cont'd.)
Page 4.9 Auxiliary Electrical Systems 3/4.9 - 1 4.9.A Station Batteries 3/4.9 - 1 4.9.B (N/A) 4.9.C Diesel Fuel 3/4.9 - 4 4.9.D Diesel Generator Operability 3/4.9 - 4 4.10 Refueling 3/4.10- 1 4.10.A Refueling Interlocks 3/4.10- 1 4.10.B Core Monitoring 3/4.10- 1 4.10.C Fuel Storage Pool Water Level 3/4.10- 2 4.10.D Control Rod Drive and Control Rod Drive Maintenance 3/4.10- 3 4.10.E Extended Core Maintenance 3/4.10- 4 4.10.F Spent Fuel Cask Handling 3/4.10- 5 4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems 3/4.12-1 4.12.A Fire Detection Instrumentation 3/4.12-1 4.12.B Fire Suppression Water System 3/4.12-2 4.12.C Sprinkler Systems 3/4.12-5 4.12.D CO2 System 3/4.12-7 4.12.E Fire Mose Stations 3/4.12-8 4.12.F Penetration Fire Barriers 3/4.12-9 4.12.G Fire Pamp Diesel Engine 3/4.12-10 4.12.H Halon System 3/4.12-13 5.0 Design Features 5-1 5.1 Site 5-1 5.2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Plant Operating Procedures 6-14 j
6.3 Actions to be taken in the Event of l
A Reportable Occurrence in Plant Operation 6-16 l
6.4 Action to be taken in the Event a Safety Limit is Exceeded 6-16 6.5 Plant Operating Records 6-17 6.6 Reporting Requirements 6-18 6.7 Environmental Qualification 6-27 vi 3958a 0009A
DRESDEN III DPR-25 Amendment No. 7js Corrected February
,1985 TABLE 3.2.1 FEBRUARY 2 8 INSTRUMENTATION THAT INITIATES PRIMARY CONTAIMMENT ISOLATION FUNCTIONS MINIMUM # OF OPERABLE INST.
CHANNELS PER TRIP SYSTEM (1)
INSTRUMENTS TRIP LEVEL SETTING ACTION (3) 2 Reactor Low Greater than 144" A
Water Level above top of active fuel (8) 2 Reactor Low Greater than or equal A
Low Water to 84" above top of active fuel (8) 2 High Drywell Less than or equal A
Pressure to 2 psig (4),(5) 2 (2)
High Flow Main Less than or equal B
Steam Line to 120% of rated steam flow 4
2 of 4 in each High Temperature Less than or equal B
of 4 sets Main Steamline to 200*F.
Tunnel 2
High Radiation Less than or equal B
Main Steamline to 3 times full Tunnel power background (6) 2 Low Pressure Greater than or equal B
Main Stetaline to 850 psis High Flow Isolation 1
Condenser Line Less than or equal C
Steamline side to 20 psi diff on steamline side.
1 Condensate Less than or equal C
Return Side to 32" water diff on condensate return l
side j
2 High Flow HPCI Less than or equal D
Steamline to 150 inches of water diff. (7) 4 High Temperature Less than or equal D
HPCI Steamline Area to 200*F.
Notes:
(See Next Page) 3/4.2-8 3840a 3845A
....r
DRESDEN III DPR-25 Amendment No. %, 77 Corrected February
,1985 FEBRUARY 2 8 TABLE 3.2.1 (Notes) 1.
When primary containment integrity is required, there shall be two operable or tripped trip systems for each function, except for low pressure main steamline which only need be available in the RUN position.
2.
Per each steamline.
3.
Action:
If the first column cannot be met for each of the trip systems, that trip system shall be tripped.
If the first column cannot be met for both trip systems, the appropriate action listed below shall be taken:
A.
Initiate an orderly shutdown and have reactor in cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Initiate an orderly load reduction and have reactor in hot standby B.
condition in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Close isolation valves in Isolation Condenser System.
D.
Close isolation valves in HPCI subsystem.
4.
Need not be operable when primary containment integrity is not required.
5.
May be bypassed when necessary during purging for containment inerting and deinerting.
6.
An alarm setting of less than or equal to 1.5 times normal background at rated power shall be established to alert the operator to abnormal radiation levels in the primary coolant.
7.
Verification of time delay setting between 3 and 9 seconds shall be performed during each refueling outage.
8.
Top of active fuel is defined as 360" above vessel zero for all water levels used in the LOCA analyses.
(See design Bases 3.2) 3/4.2-9 3840a 3845A
DRESDEN III DPR-25 Amendment No. %, 77 Corrected February,1985 FEBFUA.To 2 e TABLE 3.2.3 INSTRUMENTATION TRAT INITIATES ROD BLOCK Minimum No. of Operable Inst.
Channels Per Trip System (1)
Instrument Trip Level Setting 1
APRM upscale (flow bias) (7)
Less than or equal to (0.58 Wo plus 50) ( FRP/MFLPD)
(See Note 2) 1 APRM upscale (refuel and Less than or equal to Startup/ Hot Standby mode) 12/125 full scale 2
APRM downscale (7)
Greater than or equal to 3/125 full scale 1
Rod block monitor Less than or equal to upscale (flow bias) (7)
(0.65 WD Plus 45)
(See Note 2) 1 Rod block monitor Greater than or equal to downscale (7) 5/125 full scale 3
IRM downscale (3)
Greater than or equal to 5/125 full scale 3
IRM upscale Less than or equal to 108/125 full scale 3
IRM detector not fully N/A inserted in the core 2 (5)
SEM detector not in (See Note 4) i startup position 2 (5) (6)
SRM upscale Less than or equal to 105 counts /sec.
1 Scram discharge volume Less than or equal to water level - high 25 gallons Notes:
(See Next Page) 3/4.2-12 3840a 3845A
DRESDEN III DPR-25 Amendment No. %, 77 FEBRUAA TABLE 3.2.3 (Notes) 1.
For the Startup/ Hot' Standby and Run positions of the Reactor Mode Selector Switch, there shall be two operable or tripped trip systems for each function, except the SRM rod blocks, IRM upscale. IRM downscale and IRM detector not fully inserted in the core need not be operable in the "Run" position and APRM downscale, APRM upscale (flow bias), and RBM downscale need not be operable in the Startup/ Hot Standby mode. A RBM upscale need not be operable at less than 30%
rated thermal power. One channel may be bypassed above 30% rated thermal power provided that a limiting control rod pattern does not exist. For systems with more than one channel per trip system, if the first column cannot be met for both trip systems, the systems shall be tripped. For the scram discharge volume water level high rod block, there is one instrument channel per bank.
2.
WD percent of drive flow required to produce a rated core flow of 98 M1b/hr. NFLPD = highest value of FLPD for G.E. fuel.
3.
IRM downscale may be bypassed when 7.t is on its lowest range.
4.
This function may be bypassed when the count rate is greater than or equal to 100 cps.
5.
One of the four SRM inputs may be bypassed.
6.
This SRM function may be bypassed in the higher IRM ranges when the IRM upscale Rod Block is operable.
7.
Not required while performing low power physics test at atmospheric pressure during or after refueling at power levels not to exceed 5 MW(t).
l
\\
l t
3/4.2-13 3840a 3845A
DRESDEN III DPR-25 Amendment No. Jd, 77 Corrected February
,1985 F E 6h b.,R ( 2o TABLE 3.2.5 RADI0 ACTIVE GASEOUS EFFLUENT NONITORING INSTRUMENTATION Minimum No.
of Operable Total No.
Channels (1) of Channels Parameter Action (2) 1 2
SJAE Radiation Activity Monitor D
1 3
Main Chimney Noble Gas SPING/GE A
Low Range Activity Monitor 1
1 Main Chimney SPING Noble Gas A
Monitors Mid, Hi Range 1
1 Main Chimney Iodine Sampler C
1 1
Main Chimney Particulate Sampler C
1 1
Main Chimney Flow Rate Monitor B
1 1
Main Chimney Sampler Flow B
Rate Monitor 1
2 Reactor Building Vent Exhaust E
Duct Radiation Monitor 1
1 Reactor Building Vent SPING Noble F
Cas Monitor Low, Mid, High Range 1
1 Reactor Building Vent Flow Rate B
Monitor I
1 Reactor Building Vent Sampler Flow B
Rate Monitor 1
1 Reactor Building Vent Iodine C
Sampler 1
1 Reactor Building Vent Particulate C
Sampler Notes:
(See Next Page) 3/4.2-15 3840a 3845A
DRESDEN III DPR-25 Amendment No. %, 77 Corrected February
,1985 FEBRUA,qy 'a d,
TABLE 4.2.2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibration Functional Source Instrument Check (1)(7)
(1)(7)(3)(4)
Test (1)(2)(7) Check (1)
Liquid Radweste D
R Q (6)
(5)
Effluent Cross Activity Monitor Service Water D
R Q (6)
R Effluent Cross Activity Monitor Tank Level Indicating Device
- a. A Waste Sample Tank D
R Q
N/A
- b. B Waste Sample Tank D
R Q
N/A
- c. C Waste semple Tank D
R Q
N/A
- d. A Floor Drain Sample D
R Q
N/A Tank
- e. B Floor Drain Sample D
R Q
N/A Tank
- f. Waste Surge Tank D
R Q
N/A Notes:
(See Next Page) 3/4.2-20 3840a 3845A
DRESDEN III DPR-25 Amendment No. J6, 77 Corrected February
,1985 TABLE 4.2.3 (Notes)
FEBRUAny 1.
D = Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = Once per 31 days Q = Once per 92 days R = Once per refueling outage 2.
The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable, Instrument indicates levels above the alarm setpoint.
a.
b.
Circuit Failure.
^
c.
Instrument indicates a downscale failure.
d.
Instrument controls not set in OPERATE mode.
3.
Calibration shall include performance of a functional test.
4.
Instrument check to verify operability of sampler; that the stapler is in place and functioning properly.
5.
Function Test shall be performed on local switches providing low flow alarm.
6.
Function test calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped.
Calibration shall be performed once per refueling outage and not more than once every 18 months. Instrument checks shall be performed at least once
.per day during those periods when the instruments are required to be operable.
3/4.2-23 3840s 3845A
i DRESDgN III DPR-25 i
Amendment No. J6, 77 Corrected February
, 1985 l
3.2 LIMITING CONDITION FOR OPgEATION BASES FEBRU"?Y a In addition to reactor protection instrumentation which initiates a reactor scram, protective instrumentation has been provided which initiates action to mitigate the consequences of accidents which are beyond the operator's ability to control, or terminates operator errors before they result in serious consequences. This set of specifications provides the limiting conditions of operation for the primary system isolation function, initiation of the emergency core cooling system, control rod block and standby gas treatment systems. The objectives of the specifications are i
- 1) to assure the effectiveness of the protective instrumentation when required by preserving its capability to tolerate a single f ailure of any component of such systems even during periods wnen portions of such systems are out of service for maintenance, and
- 2) to prescribe the trip settings required to assure adequate performance. When necessary, one channel may be made inoperable for brief intervals to conduct required functional tests and calibrations.
i Some of the settings on the instrumentation that initiates or control core and containment cooling have tolerances explicitly stated where the high and low values are both critical and may have a substantial effect on safety.
It should be noted that the setpoints of other instrumentation, where only the high or low end of the setting has a direct bearing on safety, are chosen at a level away from the normal operating range to prevent inadvertent actuation of the safety system involved and exposure to abnormal situations.
Isolation valves are installed in those lines that penetrate the 4
primary containment and must be isolated during a loss-of-coolant accident so that the radiation dose limits are not exceeded during an accident condition. Actuation of these valves is initiated by
{
protective instrumentation which serves the condition for which isolation is required (this instrumentation is shown in Table 3.2.1).
Such instrumentation must be available whenever primary containment integrity is required. The objective is to isolate the primary containment so that the guidelines of 10 CFR 100 are l
not exceeded during an accident.
The instrumentation which initiates primary system isolation is connected in a dual bus arrangement. Thus the discussion given in the bases for Specification 3.1 is applicable here.
The low-reactor level instrumentation is set to trip at greater than 8 inches on the level instrument (top of active fuel is defined to be 360 inches above vessel zero) and after allowing for the full power pressure drop across the steam dryer the low level trip is at 504 inches above vessel sero, or 144 inches above the B 3/4.2-24 3840a 3845A i
.em-,_.-,m..__-..-ym
,_._,._,,--m..
_._._m,,.__.._,,__
DRESDEN III DPR-25 Amendment No. }d, 77 Corrected February
,1985 4.2 SURVEILLANCE REQUIREMENT BASES The instrumentation listed in Table 4.2.1 will be functionally tested and calibrated at regularly scheduled intervals. Although this instrumentation is not generally considered to be as important to plant safety as the Reactor Protection System, the same design reliability goal of 0.99999 is generally applied for all applications of (1 out of 2) I (2) logic. Therefore, on-off sensors are tested once/3 months, and bi-stable trips associated with analog sensors and amplifiers are tested once/ week.
Those instruments which, when tripped, result in a rod block have their contacts arranged in a 1 out of n logic, and all are capable of being bypassed. For such a tripping arrangement with bypass capability provided, there is an optimum test interval that should be maintained in order to maximize the reliability of a given channel (see note 7).
This takes account of the fact that testing degrades reliability and the optimum interval between tests is approximately given by:
i = (2t/c)1/2 Where:
i = optimum interval between tests a
t = the time the trip contacts are disabled from performing their function while the test is in progress e = The expected failure rate of the relays To test the trip relays requires that the channel be bypassed, the test made, and the system returned to its initial state. It is assumed this task requires an estimated 30 minutes to complete in a thorough and workmanlike manner and that the relays have a failure rate of 10-6 failures per hour. Using this data and the above operation, the optimum test interval is:
i = [2(0.5)/10-6 1/2 = 1 X 103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> 3
= approximately 40 days For additional marain a test interval of once per month will be used initially.
Note:
(7) UCRL-50451, Improving Availability and Readiness of Field Equipment Through Periodic Inspection, Benjamin Epstein, Albert Shiff, July 16, 1968, page 10, Equation (24), Lawrence Radiation Laboratory.
B 3/4.2-30 3840a 3845A
\\
t I
-. -.. -.. -. - - - - -,,.,. ~,. -,,. - _,,.. - - _ - - -,, - -, -,,, - - -, - - -, -, -, - - - -...,, - - -.,,,. - - - -, -
1 DRESDEN III DPR-25 d
Amendment No. J, 77 Corrected February
,1985
{
~
4.2 SURVEILLANCE REOUIREMENT BASES (Cont'd.)
FEBRUtgy 3 3 A more usual case is that the testing is done independently.
If both channels are bypassed and tested at the same time, the result is shown in curve No. 3.
Note that the minimum occurs at about 40,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, much longer than for cases 1 and 2.
Also, the mini-num is not nearly as low as Case 2 which indicates that this method of testing does not take full advantage of the redundant channel.
Bypassing both channels for simultaneous testing should be avoided.
The most likely case would be to stipulate that one channel be by-passed tested and restored. Then immediately following, the second channel will be bypassed, tested, and restored. This is shown by Curve No. 4.
Note that there is no true minimum. The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channel.
The best test procedure of all those examined is to perfectly stagger the tests. That is, if the test interval is four months, test one or the other channel every two months. This is shown in Curve No. 5.
The difference between Cases 4 and 5 is negligible.
There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.
The conclusions to be drawn are these:
1.
A 1 out of a system may be treated the same as a single channel in terms of choosing a test interval; and 2.
More than one channel should not be bypassed for testing at j
any one time.
The radiation monitors in the ventilation duct and on the refueling floor which initiate building isolation and standby gas treatment operation are arranged in two 1 out of 2 logic systems.
i The bases given above for the rod blocks applies here also and l
were used to arrive at the functional testing frequency.-
i I
Based on experience at Dresden Unit I with instruments of similar design, a testing interval of once every three months has been found to be adequate.
I The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.
I l
B 3/4.2-32 3840a i
3845A
FEBRUARY 2 3 DRESDEN III DPR-25 AmendmentNo.7/,77 Corrected February
,1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
released from the site to unrestricted areas unrestricted areas (at or shall be determined to l
boycnd the site boundary, be within the pre-Figures 4.8.1 and 4.8.2) scribed limits by ob-shall be limited to the taining representa-concentrations specified tive samples in accord-in 10 CFR Part 20, Ap-ance with the sampling pendix B. Table II, and analysis program Column 2 with the Table specified in Table 4.8.3.
4.8.2 values represent-The sampling analysis ing the NPC's for noble results will be used
- gases, with the calculational methods in the ODCM to 4
With the concentration determine that the con-of radioactive material centrations are within released from the site the limits of Specifi-to unrestricted areas ex-cation 3.8.B.1.
i coeding the above limits, without delay decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.
2.
The dose or dose com-2a. The dose contribution mitment above background from measured quanti-to a member of the public ties of radioactive from radioactive mater-material shall be ials in liquid effluents determined by calcu-released to unrestricted lation at least once areas (at or beyond the per 31 days and cumula-
~
site boundary) from the tive summation of these site shall be limited total body and organ to the following:
doses shall be main-tained for each calen-a '. During Any Calendar dar quarter.
Quarter:
(1) Less than or j
equal to 3 meem to the whole body.
]
(2) Less than or equal to 10 meem to any organ.
3/4.8-10 3844a 0009A
.-_ - =.
FEBtuaRY 2 8 DRESDEN III DPR-25 Amendment No. %, 77 Corrected February,1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE REOUIREMENTS (Cont'd.)
(Cont'd.)
whenever the main steam isolation valves are open.
D.
Radioactive Waste Storage D.
Radioactive Waste Storage The maximum amount of radio-A sample from each of the activity in liquid storage Waste Sample Tanks. Floor in the Weste Sample Tanks.
Drain Tanks, and Waste the Floor Drain Sample Tanks Surge Tank shall be taken, and the Waste Surge Tank analyzed and recorded every sh
- .1 not exceed 3.0 curies 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If no additions ana the maximum amount of to a tank have occurred radioactivity in any tank since the last sample, the shall not exceed 0.7 curies.
tank need not be sampled If these conditions cannot until the next addition, be met, the stored liquid shall be recycled within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Waste Collector Tanks or the Weste Neutralizer Tanks until the condition is met.
E.
Radiological Invironmental E.
Radiological Environmental Monitoring Program Monitoring Program 1.
The radiological environ-1.
The radiological en-mental monitoring program vironmental monitoring given in Table 4.8.4 shall samples shall be col-be conducted except as lected pursuant to specified below:
Table 4.8.4 from the locations specified in the ODCM, and shall be analyzed pursuant to the requirements of Table 4.8.6.
2.
With the radiological 2.
The results of analyses environmental monitor-performed on radio-ing program not being logical environmental conducted as specified monitoring samples in Table 4.8.4, prepare shall be summarized in and submit to the Com-the Annual Radiological mission, in the Annual Environmental Radiological Operating Operating Report.
Report, a description of 3/4.8-15 3844a 0009A
FEbnuARY Z 3 DRESDEN III DPR-25 Amendment No. %, 77 Corrected February
, 1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE RIOUIREMENTS (Cont'd.)
(Cont'd.)
the reasons for not con-ducting the program as required and the plans for preventing a recur-rence. Deviations are permitted from the re-quired sampling schedule if specimens are unob-tainable due to hazardous conditions, seasonal un-availability, contractor omission which is cor-rected as soon as dis-covered, malfunction of sampling equipment, or if a person who participates in the program goes out of business.
If the
~
equipment malfunctions, corrective actions shall be completed as soon as practical.
If a person supplying samples goes out of business, a re-placement supplier will be found as soon as possible. All deviations from the sampling schedule shall be described in the Annual Report.
3.
When the level of radio-3.
The land use census activity in an environ-shall be conducted at mental sampling medium least once per twelve at one or more of the months between the locations specified in dates of June 1 and the ODCM exceeds the October 1 by a door-limits of Table 4.8.5 to-door survey. serial when averaged over any survey, road survey, or calendar quarter, prepare by consulting local and submit to the Con-agriculture authorities.
mission within 30 days from the end of the af-facted calendar quarter, a Special Report which 3/4.8-16 3844a OOO9A
FEBEUARY 2 S DRESDEN III DPR-25 Amendment No. Jf, 77 Corrected February,1985 3.8 LIMITING CONDITION FOR OPERATION 4.8 SURVEILLANCE REOUIREMENTS (Cont'd.)
(Cont'd.)
b.
In any form other 1
than gas.
2.
Stored sources not in use - Each sealed source shall be tested prior to the 'ase or transfer to another licensee unless tested within the previous 6 months. Sealed sources
~
transferred without a certificate indicating the last test case shall be tested prior to being placed into use.
~
A complete inventory of radio-A Spec!al Report shall be active materials in the prepared and submitted to licensee's possession shall the commission pursuant to i
be maintained current at Specification 6.6.B. if j
all times.
source leakage tests reveal the presence of greater than or equal to 0.005 i
microcuries of removable contamination.
i H.
In the event a limiting con-dition for operation and/or associated action require-ments identified in Sections 3.8.A through 3.8.E and 4.8.A through 4.8.E cannot be satisfied because of cir-cuestances in excess of those addressed in the specif1-cations, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode.
3/4.8-21 4
3844a 0009A
FEBRUAdr 2 e DRESDEN III DPR-25 Amendment No. Jf. 77 Corrected February
,1985 TABLE 4.8.5 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels ANALYSIS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS (DCl/1) OR CASES (DCi/m3)
(DCi/Kr. wet)
(DCl/1)
(DCi/Ka. wet)
H-3 2 1 104 (see note 1)
Mn-54 1 1 103 3 I 104 Fe-59 4 1 102 1 1 104 Co-58 1 1 103 3 I 104 Co-60 3 1 102 2 1 104 2n-65 3 1 102 2 1 104 Zr-Nb-95 4 1 102 I-131 2
0.9 3
1 1 102 Cs-134 30 10 1 1 103 60 2 X 103 Cs-137 50 20 1 1 103 70 2 X 103 Ba-La-140 2 X 102 3 I 102 Notes: 1) For drinking water samples.
This is 40 CFR Part 141 value.
3/4.8-28 3844a 0009A
f(BRdARY 2 6 DRESDEN III DPR-25 Amendment No. 7/, 77 Corrected February
,1985 TABLE 4.8.6 NOTES (Continued)
TABLE NOTATION D.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation) 4.65 - (S )
b LLD =
(A)-(E)-(V)-(2.22)-(Y)-(exp (->Jit))-(t)
Where:
LLD is the "A priori" lower limit of detection for a blank sample or background analysis as defined above (as PCi per unit mass or volume).
is the square root of the background count or of a blank sample Sb count; is the estimated standard error of a background count or a blank sample count as appropriate (in units of counts).
E is the counting efficiency (as counts per dis' integration).
A is the number of gamma-rays emitted per disintegration for gamma-ray radio-nuclide analysis (A = 1.0 for gross alpha and tritium measurements).
V is the sample size (in units of mass or volume).
2.22 is the number of disintegrations per minute per picoeurie.
Y is the fractional radio-chemical yield when applicable (otherwise Y=1.0).
,t Lambda is the radioactive decay constant for the particular radionuclide (in units of reciprocal minutes).
Delta t is the-elapsed time between the midpoint of sample collection and the start time of counting.
( t = 0.0 for environmental samples and for gross alpha measurements).
t is the duration of the count (in units of minutes).
The value of "S " used in the calculation of the LLD for a detection b
system sha1*. be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value. Typical values of "E",
"V",
"Y",
"t", and " delta t" shall be used in the calculation.
3/4.8-30 3844a 0009A
-.. - _ _. _ _. = - - _. -
DRESDEN ff DPR-25 Amendment No. Jd, 77 Corrected February
,1985 3.8 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)
F.
Deleted G.
Miscellaneous Radioactive Materials Sources The objective of this specification is to assure that leakage from by-product, source and special nuclear material sources does not exceed allowable limits. The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39 (c) limits for plutonium.
4.8 SURVEILLANCE REQUIREMENT BASES None e
9 B 3/4.8-37 3844a 0009A m
~*
FEBRUARY 2 8 DRESDEN III DPR-25 Amendment No. Jf, 77 Corrected February,1985 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
(7) Suditonsiteandoffsitereviews.
4 (8) Audit of Facility Fire Protection Program and in-plementing procedures at least once per 24 months.
(9) The raC! alogical environmental monitoring program and the results thereof at least once per 12 months.
(10) The ODCN and implementing procedures at least once per 24 months.
(11) The PCP and implementing procedures for solidifi-cation of radioactive waste at least once per 24 months.
(12) Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station riuperintendent, the Division Manager-Nuclear Stations, Mar.4ger of Quality Assurance, the Generst Superintendent of Production Systems Analysis, and to the Vice l
President of Construction, Production, Licensing and Environmental Affairs.
c.
Authority The Kanager of Quality Assurance reports to the l
Executive Vice-President and the Supervisor of the Offsite Review and Investigative Function reports to the General Superintendent of Production Systems Analysis. Either the Manager of Quality Assurance or the Supervisor of the Offsite Review and Investigative l
Function has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.
I d.
Records l
(1) Reviews, audits and recommendations shall be documented and distributed as covered in 6.1.G.1.a and 6.1.C.1.b.
(2) Copies of documentation, reports, and correspon-dence shall be kept on file at the station.
l e.
Procedures Written administrative procedures shall be prepared and maintained for the off-site reviews and investigative functions described in Specifications 6.1.G.1.a.
These procedures shall cover the following:
f 6-8 l
3826a 3845A L
.