NRC Generic Letter 1978-25: Difference between revisions

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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY  
{{#Wiki_filter:UNITED STATES
COMMISSION
                    NUCLEAR REGULATORY COMMISSION
A~WSHN T N, .0 HNT .C. 205 5o9 y July 11, 1978 TO ALL POWER REACTOR LICENSEES Gentlemen:
                                  T  0N, 205 A~WSHN
In order to provide reasonable assurance that the requirements of 10 CFR 50 Appendix I are implemented at all nuclear power facilities, the NRC staff has prepared the enclosed Appendix I model Technical Specifications.
                                          . HNT
                                          .C.


These model specifications are intended to provide guidance in the scope and types of required specifications for each facility in the areas of equipment and administrative requirements including actions we consider appropriate if a limiting condition for operation cannot be met.The enclosure uses the Standard Technical Specification format with blanks or parentheses appearing where the information is plant specific.We request that you submit a license amendment application to incorporate the applicable specifications of the enclosed guidance into your Appendix "A" Technical Specifications within the number of days indicated for your facility in the attachment to this letter. A staggered submittal schedule has been selected to facilitate staff review. The staff considers such an amendment to be a CLASS III Amendment per 10 CFR 170.22, provided the application is consistent with the enclosed guidance.If you have any questions on this matter, please contact us.Sincerely, Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosures:
5o9 y                                July 11, 1978 TO ALL POWER REACTOR LICENSEES
Gentlemen:
In order to provide reasonable assurance that the requirements of
10 CFR 50 Appendix I are implemented at all nuclear power facilities, the NRC staff has prepared the enclosed Appendix I model Technical Specifications. These model specifications are intended to provide guidance in the scope and types of required specifications for each facility in the areas of equipment and administrative requirements including actions we consider appropriate if a limiting condition for operation cannot be met.
 
The enclosure uses the Standard Technical Specification format with blanks or parentheses appearing where the information is plant specific.
 
We request that you submit a license amendment application to incorporate the applicable specifications of the enclosed guidance into your Appendix "A" Technical Specifications within the number of days indicated for your facility in the attachment to this letter. A staggered submittal schedule has been selected to facilitate staff review. The staff considers such an amendment to be a CLASS III Amendment per 10 CFR 170.22, provided the application is consistent with the enclosed guidance.
 
If you have any questions on this matter, please contact us.
 
Sincerely, Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosures:
1. Model Appendix I Technical Specifications
1. Model Appendix I Technical Specifications
2. Submittal Schedule J  
2. Submittal Schedule         J
N v' NUREG NO. 0472 v-i DRAFT RADIOLOGICAL  
 
EFFLUENT TECHNICAL SPECIFICATIONS  
N
FOR PWR'S K-MAY 1978  
.,
1.0 DEFINITIONS
                                      v'   NUREG NO. 0472 v-i DRAFT
      RADIOLOGICAL EFFLUENT TECHNICAL
        SPECIFICATIONS FOR PWR'S
K-
                                        MAY 1978
 
1.0   DEFINITIONS
CHANNEL CALIBRATION
CHANNEL CALIBRATION
1.9 A CHANNEL CALIBRATION  
1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of         the channel output such that it responds with the     necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL
shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
                                                                    sensor and CALIBRATION shall encompass the entire channel including theFUNCTIONAL
alarm and/or trip functions,  and shall  include  the  CHANNEL
TEST. The CHANNEL CALIBRATION may be performed by any series of        sequen- channel  is tial, overlapping or total channel steps such that the entire calibrated.


The CHANNEL CALIBRATION
CHANNEL CHECK
shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL
1.10 A CHANNEL CHECK shall be the qualitative assessment of channel include, behavior during operation by observation. This determinationstatus  shall comparison of the channel  indication  and/or         with where possible, other indications and/or status derived from independent      instrumentation channels measuring the same parameter.
TEST. The CHANNEL CALIBRATION
may be performed by any series of sequen-tial, overlapping or total channel steps such that the entire channel is calibrated.


CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
CHANNEL FUNCTIONAL TEST
1.11 A CHANNEL FUNCTIONAL TEST shall be:
      a.  Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.


This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
b.  Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.


CHANNEL FUNCTIONAL
SOURCE CHECK
TEST 1.11 A CHANNEL FUNCTIONAL
  1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
TEST shall be: a. Analog channels -the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY
including alarm and/or trip functions.


b. Bistable channels -the injection of a simulated signal into the sensor to verify OPERABILITY
PROCESS CONTROL PROGRAM
including alarm and/or trip functions.
                                                                        and
  1.30 A PROCESS CONTROL PROGRAM shall be the operating procedure    wastes  from process parameters within which SOLIDIFICATION    of radioactive liquid systems is assured.


SOURCE CHECK 1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.PROCESS CONTROL PROGRAM 1.30 A PROCESS CONTROL PROGRAM shall be the operating procedure and process parameters within which SOLIDIFICATION
SOLIDIFICATION
of radioactive wastes from liquid systems is assured.SOLIDIFICATION
  1.31 SOLIDIFICATION shall be the conversion of radioactive       wastes from liquid systems to a homogeneous, monolithic, immobilized     solid with definite outline  on all volume and shape, bounded by a stable surface of distinct sides (free-standing).
1.31 SOLIDIFICATION  
I PWR-STS-I                           1-1
shall be the conversion of radioactive wastes from liquid systems to a homogeneous, monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
I PWR-STS-I 1-1 TABLE 1.2 FREQUENCY
NOTATION NOTATION FREQUENCY S At least once per 12 hours.D At least once per 24 hours.W At least once per 7 days.M At least once per 31 days.Q At least once per 92 days.SA At least once per 184 days.R At least once per 18 months.S/U Prior to each reactor startup.P Within 4 hours prior to each release.N.A. Not applicable.


K.1\1- PWR-STS-I 1-8 INSTRUMENTATION
TABLE 1.2 FREQUENCY NOTATION
RADIOACTIVE
            NOTATION                  FREQUENCY
LIQUID EFFLUENT INSTRUMENTATION
                S            At least once per 12 hours.
LIMITING CONDITION
FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their alarm/trip setpoints within the specified limits.APPLICABILITY:
As shown in Table 3.3-11.ACTION: a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than the value shown in Table 3.3-11, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.


b. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-11.c. The provisions of Specifications
D            At least once per 24 hours.
3.0.3-and
3.0.4 are not applicable.


SURVEILLANCE
W            At least once per 7 days.
REQUIREMENTS
 
4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION
M            At least once per 31 days.
and CHANNEL FUNCTIONAL
 
TEST operations during the MODES and at the frequencies shown in Table 4.3-11.PWR-STS-I 3/4 3-44 C C (I'.1 TABLE 3.3-11 RADIOACTIVE
Q            At least once per 92 days.
LIQUID EFFLUENT MONITORING
 
INSTRUMENTATION-o (A-I MINIMUM CHANNELS OPERABLE ALARM/TRIP
SA          At least once per 184 days.
SETPOINT MEASUREMENT
 
RANGE INSTRUMENT
R            At least once per 18 months.
APPLICABILITY
 
ACTION 1. Gross Activity Monitors Providing Automatic Isolation (a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Effluent Line c. Turbine Building (Floor Drains) Sumps Effluent Line**(1)(1)(1)***< (_cpm)< C-cpm)< (_cpm)(1-105 cpm)(1-105 cpm)(1-105 cpm)18 19 20 W 4b-n CA)2. Gross Activity Monitors Not Providing Automatic Isolation Control a. Service Water Effluent Line b. Component Cooling Water System (1)*< (_cpm)<!.(_cpm)(l-lO5 cpm)(1-105 cpu)20 (20 (1)** During releases via this pathway**Includes rinse, flush and slurry waste from secondary system demineralizer or filter-demineralizers.
S/U          Prior to each reactor startup.
 
P            Within 4 hours prior to each release.
 
N.A.         Not applicable.
 
K.1\1- PWR-STS-I            1-8


condensate deep bed TABLE 3.3-11 (Continued)
(>4-o-4I--I CA sI RADIOACTIVE
LIQUID EFFLUENT MONITORING
INSTRUMENTATION
INSTRUMENTATION
MINIMUM CHANNELS OPERABLE INSTRUMENT
RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION
APPLICABILITY
LIMITING CONDITION FOR OPERATION
ALARM/TRIP
3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their alarm/trip setpoints within the specified limits.
SETPOINT MEASUREMENT
 
RANGE ACTION 3. Continuous Composite Samplers and Sampler Flow Monitor f a. Steam Generator Blowdown Effluent Line b. Turbine Building Sumps Effluent Line *(1)*N.A.N.A.N.A.N.A.19 (1)*20 4h-4. Flow Rate Monitors a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Effluent Line c. Discharge Canal (1)*(1)*> (_gpm)> (_gpm)< (_gpm)(0-__gpm)(0-__gpm)(0-__gpm)21 21 (1)*21 (*During releases via this pathway**Includes rinse, flush and slurry waste from secondary system demineralizers or filter-demineralizers.
APPLICABILITY:  As shown in Table 3.3-11.
 
ACTION:
      a.  With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than the value shown in Table 3.3-11, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
 
b.  With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-11.
 
c.  The provisions of Specifications 3.0.3-and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL
CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST
operations during the MODES and at the frequencies shown in Table
4.3-11.
 
PWR-STS-I                          3/4 3-44
 
C                                                C                                              (          I'.1 TABLE 3.3-11
  -o                        RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
(A
  -I                                    MINIMUM
                                        CHANNELS                      ALARM/TRIP   MEASUREMENT
    INSTRUMENT                          OPERABLE      APPLICABILITY    SETPOINT         RANGE      ACTION
    1.  Gross Activity Monitors Providing Automatic                                                                            (
            Isolation a. Liquid Radwaste Effluent    (1)                *        < (_cpm)      (1-105 cpm)      18 Line b. Steam Generator Blowdown    (1)                *
                                                                      < C-cpm)      (1-105 cpm)      19 Effluent Line
                                                              *                      (1-105 cpm)      20
  W      c. Turbine Building (Floor      (1)                          < (_cpm)
4b-            Drains) Sumps Effluent Line**
CA)
  n
    2.  Gross Activity Monitors Not Providing Automatic Isolation Control a.    Service Water Effluent    (1)                *
                                                                        < (_cpm)      (l-lO5 cpm)    20  (
                Line b.    Component Cooling Water    (1)                *
                                                                      <!.(_cpm)      (1-105 cpu)    20
                  System
 
* During releases via this pathway
    **Includes rinse, flush and slurry waste from secondary system condensate deep bed demineralizer or filter-demineralizers.
 
(          >
                                              TABLE 3.3-11 (Continued)
                              RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
-o
-- I
-4I
CA                                      MINIMUM
sI
                                          CHANNELS                      ALARM/TRIP  MEASUREMENT
    INSTRUMENT                          OPERABLE      APPLICABILITY  SETPOINT        RANGE     ACTION
    3.   Continuous Composite Samplers and Sampler                                                                       f Flow Monitor a. Steam Generator Blowdown       (1)
                                                              *
                                                                            N.A.         N.A.       19 Effluent Line b. Turbine Building Sumps          (1)
                                                              *
                                                                            N.A.         N.A.       20
                  Effluent Line *
4h- 4.   Flow Rate Monitors a. Liquid Radwaste Effluent       (1)                *        > (_gpm)    (0-__gpm)        21 Line b. Steam Generator Blowdown       (1)                *        > (_gpm)    (0-__gpm)        21 Effluent Line c.   Discharge Canal             (1)
                                                                *        < (_gpm)    (0-__gpm)        21 (
    *During releases via this pathway
    **Includes rinse, flush and slurry waste from secondary system condensate deep bed demineralizers or filter-demineralizers.
 
C                                                                                                      C      "I
                                                                                                                  .I
  -o TABLE 3.3-11 (Continued)
  CAI
  -- I
  CA                          RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
                                          MINIMUM
                                          CHANNELS                      ALARM/TRIP    MEASUREMENT
                                          OPERABLE        APPLICABILITY  SETPOINT          RANGE      ACTION
      INSTRUMENT
      5.  Activity Recorders                                                                                (
                                                                *           N.A.      (1-105 cpm)       23 a.  Steam Generator Blowdown    (1)
                    Effluent Line b.  Liquid Radwaste            (1)
                                                                *           N.A.      (1-105 cpm)      23 Effluent Line
,  _
      6.    Tank Level Monitors (for tanks outside the buildings)
            a.                                (1)               **      <(     ft3 ) (0-1000 ft3 )    22
                                                                  **      <(      ft3 ) (0-1000 ft3)      22 b.                                (1)
                                                                  **
                                                                          <(      ft3)   (0-1000 ft3)      22 C.                                (1)
            d.                                (1)
                                                                  **
                                                                          <(      ft3 )  (0-1000 ft3)      22
                                                                                                              (
 
* During releases via this pathway.
 
**During liquid addition to the tank.
 
I
                      TABLE 3.3-11 (Continued)
                            TABLE NOTATION
  ACTION 18 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from the tank may continue for up to 72 hours provided that prior to initiating the release:
              1.    At least two independent samples of the tank's contents are analyzed, and
              2.    At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;
              otherwise, suspend release of radioactive effluents via this pathway.
 
ACTION 19 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 pCi/gram:
              1.    At least once per hour when the specific activity of the secondary coolant is > 0.001 uCi/gram DOSE
                    EQUIVALENT 1-131.
 
2.    At least once per 8 hours when the specific activity of the secondary coolant is < 0.001 pCi/gram DOSE
                    EQUIVALENT 1-131.
 
ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided that at least once per 8 hours grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 pCi/ml.
 
ACTION 21 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided the flow rate is estimated at least once per 4 hours.
 
ACTION 22 -  With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 7 days provided the tank liquid level is estimated during all liquid additions to the tank.
 
PWR-STS-I                        3/4 3-48
 
TABLE 3.3-11 (Continued)
                        TABLE NOTATION
ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to
            7 days provided the gross radioactivity level is recorded at least once per 4 hours.
 
PWR-STS I                      3/4 3-49
 
(C
:'
-o (A                                                TABLE 4.3-11 I-
                RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
                                                                                    CHANNEL      MODES IN WHICH
                                              CHANNEL    SOURCE    CHANNEL      FUNCTIONAL    SURVEILLANCE
    INSTRUMENT                                CHECK      CHECK  CALIBRATION        TEST          REQUIRED
                                                                                                                (
    1.  Gross Activity Monitors Providing Automatic Isolation
                                                                                                        *
          a. Liquid Radwaste Effluents Line      P            P        R(3)          Q(1)
          b. Steam Generator Blowdown                                                                  *
                Effluent Line                    D            M        R(3)          Q(1)
toi      c. Turbine Building (Floor                                                                    *
                Drains) Sumps Effluent Line      D            M        R(3)          Q(M)
    2.  Gross Activity Monitors Not Providing Automatic Isolation Control a. Service Water Effluent Line          D          M        R(3)          Q(2)
                                                                                                        *
                                                                                                                (
          b. Component Cooling Water            D          M        R(3)          Q(2)
                  System
 
61 C                                                                                                          C
-4                                          TABLE 4.3-11 (Continued)
LnI
'--
                RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
                                                                                    CHANNEL      MODES IN WHICH
                                              CHANNEL    SOURCE    CHANNEL      FUNCTIONAL    SURVEILLANCE
    INSTRUMENT                                CHECK      CHECK  CALIBRATION        TEST          REQUIRED
    3.  Continuous Composite Samplers                                                                        (
            and Sampler Flow Monitor
                                                                                                        *
          a. Steam Generator Blowdown            D        N.A.        R                Q
                Effluent Line
                                                                                                        *
  W      b. Turbine Building Sumps              D        N.A.        R                Q
-P.            Effluent Line
  -I 4.  Flow Rate Monitors a. Liquid Radwaste Effluent            D        N.A.        R                Q              *
                Line D                                                      *
          b. Steam Generator Blowdown                      N.A.        R                Q
                Effluent Line c. Discharge Canal                    D        N.A.        R                Q*                      (
 
(                                                (
                                            TABLE 4.3-11 (Continued)
-I
(A              RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
'-4I
                                                                                        CHANNEL  MODES IN WHICH
                                              CHANNEL    SOURCE      CHANNEL          FUNCTIONAL  SURVEILLANCE
                                              CHECK      CHECK    CALIBRATION            TEST      REQUIRED
      INSTRUMENT
      5.  Activity Recorders
                                                                                                          *
          a. Steam Generator Blowdown          D        N.A.        R                  Q
                Effluent Line
                                                                                                          *
          b. Liquid Radwaste                    D        N.A.        R                  Q
                  Effluent Line
  4-
      6.  Tank Level Monitors (for tanks outside the building)
  In                                                                                                    **
            a.
 
D          N.A.      R                  Q
                                                                                                          **
                                                  D          N.A.      R                  Q
            b.
 
**
            c.
 
D          N.A.      R                  Q
                                                  D          N.A.      R                  Q              **
            d.
 
(
 
K-                          TABLE 4.3-11 (Continued)
                                TABLE NOTATION
      * -  During releases via this pathway.
 
**  -  During liquid additions to the tank.
 
(1) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
          1.  Instrument indicates measured levels above the alarm/trip setpoint.
 
2.  Circuit failure.
 
3.  Instrument indicates a downscale failure.
 
4.  Instrument controls not set in operate mode.
 
(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
          1.  Instrument indicates measured levels above the alarm/trip setpoint.
 
2.  Circuit failure.
 
3.  Instrument indicates a downscale failure.
 
4.  Instrument controls not set in operate mode.
 
(3)- The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards radiation measurement system) liquid radioactive source positioned in a reproducible geometry with respect to the sensor and emitting beta and gamma radiation with fluences and energies in the ranges measured by the channel during normal operation.
 
PWR - STS-I                          3/4 3-53


condensate deep bed C TABLE 3.3-11 (Continued)
RADIOACTIVE
LIQUID EFFLUENT MONITORING
INSTRUMENTATION
INSTRUMENTATION
C 3"I-o CAI--I CA.I MINIMUM CHANNELS OPERABLE INSTRUMENT
RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION
5. Activity Recorders APPLICABILITY
LIMITING CONDITION FOR OPERATION
ALARM/TRIP
3.3.3.9 The radioactive gaseous effluent monitoring instrumentation their alarm/trip channels shown in Table 3.3-12 shall be OPERABLE with setpoints within the specified limits.
SETPOINT N.A.MEASUREMENT
RANGE (1-105 cpm)ACTION (a. Steam Generator Blowdown Effluent Line (1)*23 , _b. Liquid Radwaste Effluent Line 6. Tank Level Monitors (for tanks a.(1)*N.A.(1-105 cpm)outside the buildings)
(1) **b.(1)C.(1)******<( ft 3)<( ft 3)<( ft3)<( ft 3)(0-1000 ft 3)(0-1000 ft 3)(0-1000 ft 3)(0-1000 ft 3)23 22 22 22 22 d.(1)(* During releases via this pathway.**During liquid addition to the tank.


I TABLE 3.3-11 (Continued)
APPLICABILITY:    As shown in Table 3.3-12 ACTION:
TABLE NOTATION ACTION 18 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from the tank may continue for up to 72 hours provided that prior to initiating the release: ACTION 19 -1. At least two independent samples of the tank's contents are analyzed, and 2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;otherwise, suspend release of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 pCi/gram: 1. At least once per hour when the specific activity of the secondary coolant is > 0.001 uCi/gram DOSE EQUIVALENT
      a.   With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than the value of shown in Table 3.3-12, immediately suspend the release radioactive gaseous effluents  monitored by  the affected channel or declare the channel inoperable.
1-131.2. At least once per 8 hours when the specific activity of the secondary coolant is < 0.001 pCi/gram DOSE EQUIVALENT
1-131.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided that at least once per 8 hours grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 pCi/ml.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided the flow rate is estimated at least once per 4 hours.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 7 days provided the tank liquid level is estimated during all liquid additions to the tank.ACTION 20 -ACTION 21 -ACTION 22 -PWR-STS-I 3/4 3-48 TABLE 3.3-11 (Continued)
TABLE NOTATION ACTION 23 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 7 days provided the gross radioactivity level is recorded at least once per 4 hours.PWR-STS I 3/4 3-49 (C-o:'(A I-TABLE 4.3-11 RADIOACTIVE
LIQUID EFFLUENT MONITORING
INSTRUMENTATION
SURVEILLANCE
REQUIREMENTS
INSTRUMENT
1. Gross Activity Monitors Providing Automatic Isolation a. Liquid Radwaste Effluents Line b. Steam Generator Blowdown Effluent Line toi c. Turbine Building (Floor Drains) Sumps Effluent Line 2. Gross Activity Monitors Not Providing Automatic Isolation Control a. Service Water Effluent Line b. Component Cooling Water System CHANNEL CHECK P D D D D SOURCE CHECK P M M M M CHANNEL CALIBRATION
R(3)R(3)R(3)R(3)R(3)CHANNEL FUNCTIONAL
TEST Q(1)Q(1)Q(M)Q(2)Q(2)MODES IN WHICH SURVEILLANCE
REQUIRED****((
C TABLE 4.3-11 (Continued)
C 61-4 LnI'--RADIOACTIVE
LIQUID EFFLUENT MONITORING
INSTRUMENTATION
SURVEILLANCE
REQUIREMENTS
INSTRUMENT
CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION
CHANNEL FUNCTIONAL
TEST MODES IN WHICH SURVEILLANCE
REQUIRED (W-P.-I 3. Continuous Composite Samplers and Sampler Flow Monitor a. Steam Generator Blowdown Effluent Line b. Turbine Building Sumps Effluent Line 4. Flow Rate Monitors a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Effluent Line D D N.A.N.A.R Q R Q**D D N.A.N.A.R Q**R Q (c. Discharge Canal D N.A. R Q*
((-I (A'-4I TABLE 4.3-11 (Continued)
RADIOACTIVE
LIQUID EFFLUENT MONITORING
INSTRUMENTATION
SURVEILLANCE
REQUIREMENTS
CHANNEL SOURCE INSTRUMENT
CHECK CHECK 5. Activity Recorders a. Steam Generator Blowdown D N.A.Effluent Line b. Liquid Radwaste D N.A.Effluent Line 6. Tank Level Monitors (for tanks outside the building)CHANNEL CALIBRATION
CHANNEL FUNCTIONAL
TEST MODES IN WHICH SURVEILLANCE
REQUIRED*R Q R Q*4-In a.b.D D D D N.A.N. A.N.A.N.A.R R Q Q****c.R R Q Q****d.(
K-TABLE 4.3-11 (Continued)
TABLE NOTATION* -During releases via this pathway.** -During liquid additions to the tank.(1) -The CHANNEL FUNCTIONAL
TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(2) -The CHANNEL FUNCTIONAL
TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(3) -The CHANNEL CALIBRATION
shall include the use of a known (traceable to the National Bureau of Standards radiation measurement system) liquid radioactive source positioned in a reproducible geometry with respect to the sensor and emitting beta and gamma radiation with fluences and energies in the ranges measured by the channel during normal operation.


PWR -STS-I 3/4 3-53 INSTRUMENTATION
b.   With one or more radioactive gaseous effluent monitoring       in instrumentation channels inoperable, take the ACTION shown Table 3.3-12.
RADIOACTIVE
GASEOUS EFFLUENT INSTRUMENTATION
LIMITING CONDITION
FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints within the specified limits.APPLICABILITY:
As shown in Table 3.3-12 ACTION: a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than the value shown in Table 3.3-12, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.


b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-12.c. The provisions of Specifications  
not c.   The provisions of Specifications 3.0.3 and 3.0.4 are applicable.
3.0.3 and 3.0.4 are not applicable.


SURVEILLANCE  
SURVEILLANCE REQUIREMENTS
REQUIREMENTS
                                                          instrumentation
4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION  
4.3.3.9 Each radioactive gaseous effluent monitoring of the CHANNEL
and CHANNEL FUNCTIONAL
channel shall be demonstrated OPERABLE by performance               TEST
TEST operations during the MODES and at the frequencies shown in Table 4.3-12.PWR-STS-I  
                                                CHANNEL FUNCTIONAL
3/4 3-54 (A-I (n I-TABLE 3.3-12 RADIOACTIVE  
CHECK, SOURCE CHECK, CHANNEL CALIBRATION and                 in Table operations during the MODES and at   the frequencies shown
GASEOUS EFFLUENT MONITORING  
4.3-12.
INSTRUMENTATION
 
C MINIMUM CHANNELS INSTRUMENT  
PWR-STS-I                           3/4 3-54
OPERABLE 1. Waste Gas Holdup System a. Noble Gas Activity Monitor (1)b. Noble Gas Activity Recorder (1)c. Iodine Sampler (1)in d. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1)g, Hydrogen MQnitor (1)h. Hydrogen Monitor (alternate)
 
1) alarm 2 2) alarm and initiate 2 automatic control function APPLICABILITY
C
********ALARM/TRIP
(A
SETPOINT c (- cpm)N.A.N.A.N.A.> ( cfm)> (- cfm)4 (4%) by volume MEASUREMENT
-I
RANGE (10-106 cpm)(10.106 cpm)N.A.N.A.(0- cfm)(0- cfm)(0-20%) by volume (0-20%) by volume (0-20%) by volume (ACTION 25 23 25 25 26 26 29** s (2%) by volume* s (4X) by volume 30 30 (* During**During releases y1A this pathway.waste gas holdup system (treatment for primary system offgases)  
                                                TABLE 3.3-12 (n
operation.
I-
                            RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
                                          MINIMUM
                                          CHANNELS                       ALARM/TRIP          MEASUREMENT
    INSTRUMENT                             OPERABLE        APPLICABILITY    SETPOINT              RANGE        ACTION
    1.   Waste Gas Holdup System
                                                                                                                        (
        a.   Noble Gas Activity
                                                                      *                      (10-106 cpm)          25 Monitor                     (1)                           c (-      cpm)
                                                                      *                      (10.106 cpm)          23 b.   Noble Gas Activity Recorder   (1)                               N.A.
 
*                                            25 c.   Iodine Sampler                 (1)                               N.A.              N.A.
 
in
                                                                      *
        d.   Particulate Sampler           (1)                               N.A.              N.A.            25
                                                                      *                                            26 e.   Flow Rate Monitor             (1)                         > (      cfm)    (0-      cfm)
                                                                      *                                            26 f.   Sampler Flow Rate Monitor     (1)                         >  (-    cfm)    (0-      cfm)
                                                                    **
        g,   Hydrogen MQnitor               (1)                         4 (4%) by volume  (0-20%) by volume    29 h.   Hydrogen Monitor (alternate)
              1) alarm                       2                   **      s (2%) by volume  (0-20%) by volume
                                                                                              (0-20%) by volume
                                                                                                                  30
                                                                                                                  30
                                                                                                                        (
              2) alarm and initiate           2                   *      s (4X) by volume automatic control function
 
* During releases y1A this pathway.
 
**During waste gas holdup system (treatment for primary system offgases) operation.
 
-4 TABLE 3.3-12 (Continued)
  ~I)
1-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
                                            MIlUIMUM
                                            CH)%dNNELS                      ALARM/TRIP          MEASUREMENT
      INSTRUMENT                            OPI'RABLE      APPLICABILITY     SETPOINT              RANGE        ACTION
      1.  Waste Gas Holdup System (continued)
          i.  Oxygen Monitor                  (1)            **           s  (4%) by volume  (0-25%) by volume  29  (
          J.    Oxygen Monitor (alternate)
                1) alarm                        (2)            **          i (2%)  by volume (0-25%) by volume  30
                2) alarm and initiate          (21            *            Z (4%) by volume  (0-25%) by volume  30
                    automatic control function
  ,  2,  Condenser Evacuation System en a.    Noble Gas Activity Monitor      (1)            *            -C(_      cpm)    (l0-106 cpm)        27 b.    Noble Gas Activity Recorder    (.)            *
                                                                                N.A.          (10_106 cpm)        23 c.    Iodine Sampler                  (1)            *
                                                                                N.A.              N.A.            27 d.    Particulate Sampler            0l)            *
                                                                                N.A.              N.A.            27 e.    Flow Rate Monitor              (1)            *
                                                                            > (_      cfm)    (0-    cfm)        26
                                                                                                                        (
          f.    Sampler Flow Rate Monitor      (1)            *           > (-      cfm)    (0-    cfm)        26
 
* During releases via this pathway.
 
**During waste gas holdup system (treatment for primary system offgases) operation.
 
*I
                                            TABLE 3.3-12 (Continued)
                                                                                                            (
-o RADIOACTIVE GASEOUS EFrLUENT MCNITORING INSTRUMENTATION
(I
--4 (A
                                            MINIMUM
                                            CHANNELS                        ALARM/TRIP       MEASUREMENT
    INSTRUMENT                              OPERABLE        APPLICABILITY    SETPOINT           RANGF          ACTION
    3.    Vent Header System a.  Noble Gas Activity Monitor    (1)                *
                                                                              < (_    cpm)  (10-106 cpm)        27 (
          b.  Noble Gas Activity Recorder    (1)                                N.A.        (10106 cpm)         23
                                                                *
          c.  Iodine Sampler                (1)                                N.A.             N.A.          2/
          d.  Particulate Sampler            (1)                *              N.A.             N.A.         27 e.  Flow Rate Monitor              (1)                *                    cfM)  (O-        cfm)     26 f.  Sampler Flow Rate Monitor      (1)                *                    cfin) (0-       cfm)     26
    4.    Containment Purge System a.  Noble Gas Activity Monitor    (1)                *            < (-    cpm) (10-106 cpm)       28 b.  Nobel Gas Activity Recorder    (1)                *              N.A.        (10-106 cpm)       23 c.  Iodine Sampler                (1)                *              N.A.             N.A.           28(
          d.  Particulate Sampler            (1)                *              N.A.            N.A.          28
 
* During releases via this pathway.
 
IC                                                                                                    C
                                            TABLE 3.3-12 (Continued)
                            RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
:4
0-4 MINIMIL0M
                                            CHANN ELS                      ALARM/TRIP    MEASUREMENT
    INSTRUMENT                            OPERAI BLE      APPLICABILITY    SETPOINT        RANGE          ACTION
          e.    Flow Rate Mcnitor              (1)                          , (      cfm) (0-     cfm)        26 f.    Sampler Flow Rate Monitor      (1)                          > (      cfm) (0-_ cfm)            2( 'F
    5.  Auxiliary Building Ventilation System a.    Noble Gas Activity Monitor    (1)               *        < (-     cpm) (10-106 cpm)        27 b.    Noble Gas Activity Recorder    (1)               *              N.A.    (10_106 c pr-.)      23 C.    Iodine Sampler                (1)                *              N.A.          N.A.            27 X        d.    Particulate Sampler            (1)                *             N.A.          N.A.            27 e.    Flow Rate Monitor              (1)                *
                                                                            , (-    cfm) (0-_      cfm)      26 f.    Sampler Flow Rate Monitor      (1)               *         > (-    cfm) (0-      cfm)       26
    6.  Fuel Storage Area Ventilation System                                                                  (
          a.    Noble Gas Activity Monitor    (1)                *         < (-    cfm) (10-106 cpm)        27 b.    Noble Gas Activitv Recorder    (1)                *             N.A.    (10-106 cpm)        23
 
* During releases via this pathway.
 
(                                                                                                    (
                                              TABLE 3.3-12 (Continued)
CnI
-- I                          RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
0-4 MINIMUM
                                              CHANNELS                        ALARM/TRIP      MEASUREMENT
      INSTRUMENT                            OPERABLE        APPLICABILITY    SETPOINT          RANGE      ACTION
      6.  Fuel Storage Area Ventilation System (continued)
            c.    Iodine Sampler                (1)                  *          N.A.          N.A.          27 d.    Particulate Sampler          (1)                              N.A.          N.A.          27
                                                                  :*
            e.    Flow Rate Monitor            (1)                                    cfm)  (O-      cfm)    26
                                                                    *
            f.    Sampler Flow Rate Monitor    (1)                                    cfm)  (O-      cfm)    26
  ,    7.  Radwaste Area Ventilation System                        *
Ul qo a.    Noble Gas Activity Monitor    (1)                          < (~      cpm) (10-10 cpm)      27 b.    Noble Gas Activity Recorder  (1)                  *          N.A.        (10-106 cpm)      23 c.    Iodine Sampler                (1)                  *          N.A.                          27 N.A.
 
d.    Particulate Sampler          (1)                  *                                        2I>
                                                                                N.A.          N.A.
 
e.    Flow Rate Monitor            (1)                          > (-    cfm)  (0-    cfm)      26
                                                                    *
            f.    Sampler Flow Rate Monitor    (1)                          > (-    cfm)  (0-    cfm)     26
 
* During releases via this pathway.


-4~I)1-4 TABLE 3.3-12 (Continued)
TABLE 3.3-12 (Continued)
RADIOACTIVE  
                                                                                                              (
GASEOUS EFFLUENT MONITORING  
                              RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMFNTATION
INSTRUMENTATION
LAl
MIl CH)INSTRUMENT  
-I
OPI 1. Waste Gas Holdup System (continued)
                                            1INIMUM
i. Oxygen Monitor J. Oxygen Monitor (alternate)
                                            CHANNELS                    ALARM/TRIP        MEASUREMENT
1) alarm 2) alarm and initiate automatic control function , 2, Condenser Evacuation System en a. Noble Gas Activity Monitor b. Noble Gas Activity Recorder c. Iodine Sampler d. Particulate Sampler e. Flow Rate Monitor f. Sampler Flow Rate Monitor UIMUM%dNNELS'RABLE APPLICABILITY
      INSTRUMENT                           C)PERABLE      APPLICABILITY  SETPOINT            RANGE          ACTION
(1)(2)(21 (1)(. )(1)0l)(1)(1)**********ALARM/TRIP
    8.   Steam Generator Blowdown Vent a.   Noble Cas Activity Monitor                   (1)               *            < (      cpm) (10-106 cpm)        27 b.   Noble Gas Activity Recorder                   (1)               *              N.A.        (10-106 cpm)         23 c.   Iodine Sampler              (1)               *             N.A.               N.A           27
SETPOINT s (4%) by volume i (2%) by volume Z (4%) by volume-C (_ cpm)N.A.N.A.N.A.MEASUREMENT
-W        d.    Particulate Sampler          (1)               *              N.A.               N.A.           27 Wn e.    Flow Rate Mcnitor            (1)                            > (      cfm)
RANGE (0-25%) by volume (0-25%) by volume (0-25%) by volume (l0-106 cpm)(10_106 cpm)N.A.N.A.(0- cfm)(0- cfm)ACTION (29 30 30 27 23 27 27 26 26 (> (_ cfm)> (- cfm)** During releases via this pathway.**During waste gas holdup system (treatment for primary system offgases)
                                                                *
operation.
                                                                                            (0-~      cfm)     26 f.    Sampler Flow Rate Monitor    (1)              *            > (-_cfm)     (0-~~      cfm) -    26
                                                                                                                    (
    * During release via this pathway.


TABLE 3.3-12 (Continued)
TABLE 3.3-12 (Continued)
RADIOACTIVE
                            TABLE NOTATION
GASEOUS EFrLUENT MCNITORING
ACTION 23 -  With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 7 days provided the gross radioactivity level is recorded at least once per
INSTRUMENTATION
              4 hours.
(*I-o (I--4 (A MINIMUM CHANNELS OPERABLE INSTRUMENT
 
3. Vent Header System a. Noble Gas Activity Monitor b. Noble Gas Activity Recorder c. Iodine Sampler d. Particulate Sampler e. Flow Rate Monitor f. Sampler Flow Rate Monitor 4. Containment Purge System a. Noble Gas Activity Monitor b. Nobel Gas Activity Recorder c. Iodine Sampler d. Particulate Sampler APPLICABILITY
ACTION 25 -  With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment for up to
(1)(1)(1)(1)(1)(1)**ALARM/TRIP
              72 hours provided that prior to initiating the release:
SETPOINT< (_ cpm)N.A.N.A.N.A.*(1)(1)(1)(1)******cfM)cfin)MEASUREMENT
              1.  At least two independent samples of the tank's content are analyzed, and
RANGF (10-106 cpm)(10106 cpm)N.A.N.A.(O- cfm)(0- cfm)(10-106 cpm)(10-106 cpm)N.A.N.A.ACTION 27 (23 2/27 26 26 28 23 28(28< (- cpm)N.A.N.A.N.A.* During releases via this pathway.
              2.  At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;
              otherwise, suspend release of radioactive effluents via this pathway.
 
ACTION 26 -  With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided the flow rate is estimated at least once per 4 hours.
 
ACTION 27 -  With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided grab samples are taken at least once per 4 hours and these samples are analyzed for gross activity at least once per 24 hours.
 
ACTION 28 -  With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend release of radioactive effluents via this pathway.
 
ACTION 29 -    With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to
                14 days provided gas samples are analyzed at least once per 4 hours.
 
ACTION 30 -  With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to 14 days. With both channels inoperable, immedi- ately suspend operation of this waste gas holdup system.
 
PWR-STS-I                          3/4 3-61
 
(                                                   C                                                    C
&#xa3;
                                                    TABLE 4.3-12
-o US                RAnIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
(I
                                                                                      CHANNEL      MODES IN WHICH
                                                CHANNEL    SOURCE    CHANNEL      FUNCTIONAL      SURVEILLANCE
                                                CHECK      CHECK  CALIBRATION        TEST          REQUIRED
        INSTRUMENT
        1.  Waste Gas Holdup System                                                                              (
                                                  P            P        R(3)            Q(0)
            a. Noble Gas Activity Monitor                                                                  *
            b. Noble Gas Activity Recorder        D          N.A.      R              Q                  *
                                                  D          N.A.      N.A.            N.A.
 
c. Iodine Sampler d. Particulate Sampler                D          N.A.      N.A.            N.A.                *
  w
4h- Ir~
aw          e. Flow Rate Monitor                  P          N.A.      R                Q                **
              f. Sampler Flow Rate Monitor          D          N.A.      R                Q                **
                                                              N.A.      Q(4)            M
              g. Hydrogen Monitor                  D                                                        **
              h. Hydrogen Monitor (alternate)      D          N.A.      Q(4)            M                **
              i. Oxygen Monitor                    D          N.A.      Q(5)            M                      (
              J. Oxygen Monitor (alternate)        D          N.A.      Q(5)            M
 
-o
      (                                                                                                          C
                                            TABLE 4.3-12 (Continued)
CA
(A             RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
14A
                                                                                    CHANNEL      MODES IN WHICH
                                              CHANNEL    SOURCE    CHANNEL      FUNCTIONAL      SURVEILLANCE
    INSTRUMENT                               CHECK      CHECK  CALIBRATION        TEST          REQUIRED
    2.  Condenser Evacuation System D            M        R(3)
                                                                                                                  (
          a. Noble Gas Activity Monitor                                                Q(2)
                                                                                                          *
          b. Noble Gas Activity Recorder        D          N.A.        R              Q                  *
          c. Iodtne Sampler                      D          N.A.        N.A.          N.A.              .*
          d. Particulate Sampler                D          N.A.        N.A.          N.A.
 
*      e, Flow Rate Monitor                  D          N.A.        R              Q
          f. Sampler Flow Rate Monitor          D          N.A.        R              Q
    3.   Vent Header System                                                                               *
          a. Noble Gas Activity Monitor         D            M        R(3)            Q(2)              *
          b. Noble Gas Actiyity Recorder         D          N.A.        R              Q                          (
          c. Iodine Sampler                     D          N.A.      N.A.            N.A.
 
d. Particulate Sampler                 D          N.A.      N.A.            N.A.
 
e. Flow Rate Monitor                   D          N.A.        R              Q
          f. Sampler Flow Rate Monitor         D          N.A.      R              q
 
C                                                    C
                                              TABLE 4.3-12 (Continued)
ICA
-ei RADIOACTIVE GASEOUS EFFLUENir MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
                                            -
                                                                                    CHANNEL      MODES IN WHICH
                                                CHA,NNEL    SOURCE    CHANNEL      FUNCTIONAL      SURVE ILLANCE
    INSTRUMENT                                  CHHECK      CHECK  CALIBRATION      TEST          REQUIRED
    4.   Containment Purge System
                                                                                                                  (
          a. Noble Gas Activity Monitor           D            P        R(3)            Q(l)              *
          b. Noble Gas Activity Recorder           D          N.A.      R              Q                *
          c. Iodine Sampler                         D          N.A.    N.A.            N.A.                *
4h        d. Particulate Sampler                   D          N.A.    N.A.            N.A.                *
          e. Flow Rate Monitor                      D          N.A.      R              Q                  *
          f. Sampler Flow Rate Monitor              D          N.A.      R              Q
                                                                                                            *
    5.  Auxiliary Building Ventilation System a. Noble Gas Actvity Monitor            D            M        R(3)           Q(2)
                                                                                                                  (
          b. Noble Gas Activity Recorder          D        N.A.          R              Q                  *
          c. Iodine Sampler                        D        N.A.        N.A.            N.A.
 
d. Particulate Sampler                  D          N.A.    N.A.            N.A.
 
e. Flow Rate Monitor                    D          N.A.      R              Q
          f. Sampler Flow Rate Monitor            D          N.A.      R              Q
 
(                                                                                                          (
-u                                          TABLE 4.3-12 (Continued)
--I
(A              RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
-4 CHANNEL      MODES IN WHICH
                                              CHANNEL    SOURCE    CHANNEL      FUNCTIONAL    SURVEILLANCE
    INSTRUMENT                                CHECK      CHECK  CALIBRATION        TEST          REQUIRED
    6.  Fuel Storage Area Ventilation System                                                                  (
          a. Noble Gas Activity Monitor          D          M        R(3)             Q(2)
                                                D                    R                                *
          b. Noble Gas Activity Recorder                    N.A.                      Q
          c. Iodine Sampler                      D          N.A.      N.A.            N.A.
 
*
          d. Particulate Sampler                D          N.A.      N.A.            N.A.
 
e. Flow Rate Monitor                  D          N.A.      R                Q
                                                                                                        *
cm f. Sampler Flow Rate Monitor          D          N.A.      R                Q
                                                                                                        *
    7.  Radwaste Area Ventilation System
                                                                                                        *
          a. Noble Gas Activity Monitor          D          M        R(3)            Q(2)
          b. Noble Gas Activity Recorder        D          N.A.     R                Q
                                                                                                        *
                                                                                                                (
          c. Iodine Sampler                      D          N.A.      N.A.             N.A
          d. Particulate Sampler                D          N.A.      N.A.            N.A
 
C
2:
-I                                        TABLE 4.3-12 (Continued)
LA4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
                                                                                  CHANNEL      MODES IN WHICH
                                            CHANNEL    SOURCE    CHANNEL      FUNCTIONAL      SURVEILLANCE
    INSTRUMENT                                CHECK      CHECK  CALIBRATION        TEST          REQUIRED
    7.  Radwaste Area Ventilation System (continued)
                                                                                                                (
        e.    Flow Rate Monitor                D          N.A.      R                Q                *
        f.    Sampler Flow Rate Monitor        D          N.A.      R                Q
X  8.  Steam Generator Blowdown Vent
                                                                                                        *
        a. Noble Gas Activity Monitor          D          M        R(3)             Q(2)
        b. Noble Gas Activity Recorder        D                    R                                  *
                                                            N.A.                      Q
        c. Iodine Sampler                      D          N.A.                                        *
                                                                      N.A.            N.A
        d. Particulate Sampler                D          N.A.      N.A.            N.A.
 
*
        e. Flow Rate Monitor                  D          N.A.      R                Q                        (
        f. Sampler Flow Rate Monitor          D          N.A.      R                Q
                                                                                      I
 
K>~
                              -TABLE 4.3-12 (Continued)
                                    TABLE NOTATION
      * -  During releases via this pathway.
 
** -  During waste gas holdup system operation.
 
(1) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
            1.    Instrument indicates measured levels above the alarm/trip setpoint.
 
2.  Circuit failure.
 
3.  Instrument indicates a downscale failure.
 
4.  Instrument controls not set in operate mode.
 
(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
          1.    Instrument indicates measured levels above the alarm/trip setpoint.
 
2.    Circuit failure.
 
3.    Instrument indicates a downscale failure.
 
4.    Instrument controls not set in operate mode.
 
(3) - The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards radiation measurement system)
          gaseous radioactive source positioned in a reproducible geometry with respect to the sensor and emitting beta and gamma radiation with fluences and energies in the ranges measured by the channel during normal operation.
 
PWR - STS -I                          3/4 3-67
 
K>
                                TABLE 4.3-12 (Continued TABLE NOTATION
  (4) - The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
        1.  One volume percent hydrogen, balance nitrogen, and
        2.  Four volume percent hydrogen, balance nitrogen.
 
(5) - The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
        1.  One volume percent oxygen, balance nitrogen, and
        2.  Four volume percent oxygen, balance nitrogen.
 
PWR-STS-I                          3/4 3-68
 
3/4.11 RADIOACTIVE EFFLUENTS
3/4.11.1 LIQUID EFFLUENTS
CONCENTRATION
LIMITING CONDITION FOR OPERATION
3.11.1.1 The concentration of radioactive material released from the site to unrestricted areas (see Figure 3.11-1) shall be limited to the concentra- tions specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases and 4 x 10-5 uCi/ml total activity concentration for all dissolved or entrained noble gases.
 
APPLICABILITY:  At all times.
 
ACTION:
With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.
 
SURVEILLANCE REQUIREMENTS
4.11.1.1.1 The concentration of radioactive material in unrestricted areas shall be determined to be within the above limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 4.11-1.
 
4.11.1.1.2 Reports - The semiannual Radioactive Effluent Release Report shall include the results of analyses performed in accordance with the program of Table 4.11-1 and a summary of all releases of radioactive liquid effluents.
 
PWR-STS-I                          3/4 11-1
 
TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
                                        Minimum                      Lower Limit Sampling        Analysis    Type of Activity of Detection Liquid Release Type      Frequency      Frequency        Analysis        (LLD)'a (pCi/ml),
W. Batch Waste Release  Each Batch      Each Batch  Principal Gamma      0.5 Tanks                                            Emitters P
                        One Batch/M        M        Dissolved and          10
                                                      Entrained Gases P
                        Each Batch        W        1-131                  1.0
                                        Compositec P-.I
                        Each Batch        M        H-3                    10
                                        Compositec Gross a                0.1 P-32                  1.0
                              P
                        Each Batch        Q        Sr-89, Sr-90        0.05 Compositec (Fe-55)              (1.0)
. Plant Continuous      Continuousd        W        Principal Gamma        0.5b Releases , (Steam                  Composited  Emitters generator blowdown and turbine build-                              I-131                  1.0
    ing drainage)          M
                        Grab Sample        M        Dissolved and          10
                                                      Entrained Gases Continuous d                H-3                    10
                                        Composite    H-
                                                      Gross a                0.1 P-32                  1.0
                        Continuous              ted  Sr-89, Sr-90          0.05 Composited (Fe-55)               (1.0)
PWR-STS- I                    3/4 11-2
 
I>
                            TABLE 4.11-1 (Continued)
                                  TABLE NOTATION
      a.  The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.12-1 of Specification 4.12.1.1.
 
b.  For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixture, it may not be possible to measure7 radionuclides in concentrations near the detection limit of 5 x 10
          uCi/ml. Under these circumstances, it may be necessary to calculate the concentration of such radionuclides to a lower limit of detection of 5 x 10  uCi/ml using observed ratios with those radionuclides which are measurable, or the lower limit of detection of 5 x 10- UCi/ml may be increased proportionally to the magnitude of the gamma yield (i.e., 5 x 10 /I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 2.
 
c.   A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
 
d.  To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples shall be con- tinuously collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be repre- sentative of the average effluent release.
 
e.   A batch release is the discharge of liquid wastes of a discrete volume. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuous release.
 
X, PWR-STS-I                          3/4 11-3
 
This figure shall consist of a map of the site area showing the unre- stricted area boundary for liquid effluents as defined in 10 CFR Part
          20.3(a)(17).
 
* Figure 3.11-1 PWR-STS-I                314 11-4
 
RADIOACTIVE EFFLUENTS
DOSE
LIMITING CONDITION FOR OPERATION
3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure
3.11-1) shall be limited:
      a.  During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, aWd b.  During any calendar year to < 3 mrem to the total body and to
          < 10 mrem to any organ.
 
APPLICABILITY:  At all times.
 
ACTION:
      a.  With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within 3 mrem to the total body and
          10 mrem to any organ. (This report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.)
      b.  With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits of Specification 3.11.1.2.a or 3.11.1.2.b, prepare and submit a Special Report to the Commission pursuant to Specification
          6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel'
          cycle sources is limited to < 25 mrem* to the total body or any organ (except thyroid, which is limited to < 75 mrem*)
          over 12 consecutive months. This Special Report shall include I
*The assessment of radiation doses shall be performed in accordance with NUREG-0133.
 
PWR-STS-I                          3/4 11-5
 
RADIOACTIVE EFFLUENTS
ACTION:    (Continued)
            an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR
            Part 190 Standard.
 
c.    The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.11.1.2.1      Dose Calculations - The dose contributions for the total m
time period r at, shall be determined by calculation at least once per 7 E=1 days and  a cumulative summation of these total body and any organ doses shall be  maintained for each calendar quarter. These dose contributions shall be  calculated for all radionuclides identified in liquid effluents released  to unrestricted areas using the following expression:
                                  m
                        =E EAi1r    1AItz  CIL F9J
      where- D      =    the cumulative dose or dose commitment to the total body or an organ T from the liquid effluents for the total time m
                  period      E Att, in mrem.


IC TABLE 3.3-12 (Continued)
L=1 At    =    the length of the ith time period over which CIL and FQ
RADIOACTIVE
                  are averaged for all liquid releases, in hours.
GASEOUS EFFLUENT MONITORING
INSTRUMENTATION
C:4 0-4 MINIMI CHANN INSTRUMENT
OPERAI e. Flow Rate Mcnitor (1)f. Sampler Flow Rate Monitor (1)5. Auxiliary Building Ventilation System a. Noble Gas Activity Monitor (1)b. Noble Gas Activity Recorder (1)C. Iodine Sampler (1)X d. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1)6. Fuel Storage Area Ventilation System a. Noble Gas Activity Monitor (1)b. Noble Gas Activitv Recorder (1)L0M ELS BLE APPLICABILITY
********ALARM/TRIP
SETPOINT , ( cfm)> ( cfm)< (- cpm)N.A.N.A.N.A., (- cfm)> (- cfm)< (- cfm)N.A.MEASUREMENT
RANGE (0- cfm)(0-_ cfm)(10-106 cpm)(10_106 c pr-.)N.A.N.A.(0- _ cfm)(0- cfm)(10-106 cpm)(10-106 cpm)ACTION 26 F 2( '27 23 27 27 26 26 (27 23* During releases via this pathway.


(TABLE 3.3-12 (Continued)
C          The average    concentration of radionuclide i in undiluted It        liquid effluent during time period at from any liquid release, in iiCi/ml.
RADIOACTIVE
GASEOUS EFFLUENT MONITORING
INSTRUMENTATION
(CnI--I 0-4 MINIMUM CHANNELS INSTRUMENT
OPERABLE 6. Fuel Storage Area Ventilation System (continued)
c. Iodine Sampler (1)d. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1), 7. Radwaste Area Ventilation System Ul qo a. Noble Gas Activity Monitor (1)b. Noble Gas Activity Recorder (1)c. Iodine Sampler (1)d. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1)APPLICABILITY
*:*******ALARM/TRIP
SETPOINT MEASUREMENT
RANGE N.A.N.A.N.A.N.A.cfm)cfm)< (~ cpm)N.A.N.A.N.A.> (- cfm)> (- cfm)(O- cfm)(O- cfm)(10-10 cpm)(10-106 cpm)N.A.N.A.(0- cfm)(0- cfm)ACTION 27 27 26 26 27 23 27 2I>26 26* During releases via this pathway.


(LAl-I TABLE 3.3-12 (Continued)
PWR-STS-I                                 3/4 11-6
GASEOUS EFFLUENT MONITORING
RADIOACTIVE
INSTRUMFNTATION
INSTRUMENT
C 8. Steam Generator Blowdown Vent a. Noble Cas Activity Monitor b. Noble Gas Activity Recorder c. Iodine Sampler d. Particulate Sampler e. Flow Rate Mcnitor f. Sampler Flow Rate Monitor 1INIMUM CHANNELS)PERABLE APPLICABILITY
W-Wn (1)(1)(1)(1)(1)(1)******ALARM/TRIP
SETPOINT< ( cpm)N.A.N.A.N.A.> ( cfm)> (- _cfm)MEASUREMENT
RANGE (10-106 cpm)(10-106 cpm)N.A N.A.ACTION 27 23 27 27 26 26 (0-~(0-~~cfm)cfm) -(* During release via this pathway.


TABLE 3.3-12 (Continued)
RADIOACTIVE EFFLUENTS
TABLE NOTATION ACTION 23 -ACTION 25 -ACTION 26 -ACTION 27 -ACTION 28 -ACTION 29 -ACTION 30 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 7 days provided the gross radioactivity level is recorded at least once per 4 hours.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment for up to 72 hours provided that prior to initiating the release: 1. At least two independent samples of the tank's content are analyzed, and 2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;otherwise, suspend release of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided the flow rate is estimated at least once per 4 hours.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided grab samples are taken at least once per 4 hours and these samples are analyzed for gross activity at least once per 24 hours.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend release of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to 14 days provided gas samples are analyzed at least once per 4 hours.With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to 14 days. With both channels inoperable, immedi-ately suspend operation of this waste gas holdup system.PWR-STS-I 3/4 3-61 (C C-o&#xa3;US (I TABLE 4.3-12 MONITORING
SURVEILLANCE REQUIREMENTS (Continued)
INSTRUMENTATION
      Ai    =  the site related ingestion dose and dose commitment factor to the total body or any organ T for each identified principal gamma and beta emitter listed in Table 4.11-2,
SURVEILLANCE
                                  1 .
REQUIREMENTS
              in mrem-ml per hr-uC
RAnIOACTIVE
      F.    =  the near field average dilution factor for C during any liquid effluent release. Defined as the ratl& of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times
GASEOUS EFFLUENT w 4h-aw Ir~INSTRUMENT
              (_    isthe site specific applicable factor for the mixing effect of the discharge structure.)
1. Waste Gas Holdup System a. Noble Gas Activity Monitor b. Noble Gas Activity Recorder c. Iodine Sampler d. Particulate Sampler e. Flow Rate Monitor f. Sampler Flow Rate Monitor g. Hydrogen Monitor h. Hydrogen Monitor (alternate)
For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximately by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses.
i. Oxygen Monitor J. Oxygen Monitor (alternate)
CHANNEL CHECK P D D D P D D D D D SOURCE CHECK P N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.CHANNEL CALIBRATION
R(3)R N.A.N.A.R R Q(4)Q(4)Q(5)Q(5)CHANNEL FUNCTIONAL
TEST Q(0)Q N.A.N.A.Q Q M M M M MODES IN WHICH SURVEILLANCE
REQUIRED***********((
(-o CA (A 14A TABLE 4.3-12 (Continued)
RADIOACTIVE
GASEOUS EFFLUENT MONITORING
INSTRUMENTATION
SURVEILLANCE
REQUIREMENTS
C INSTRUMENT
2. Condenser Evacuation System a. Noble Gas Activity Monitor b. Noble Gas Activity Recorder c. Iodtne Sampler d. Particulate Sampler* e, Flow Rate Monitor f. Sampler Flow Rate Monitor 3. Vent Header System a. Noble Gas Activity Monitor b. Noble Gas Actiyity Recorder c. Iodine Sampler d. Particulate Sampler e. Flow Rate Monitor f. Sampler Flow Rate Monitor CHANNEL CHECK D D D D D D D D D D D D SOURCE CHECK M N.A.N.A.N.A.N.A.N.A.M N.A.N.A.N.A.N.A.N.A.CHANNEL CALIBRATION
R(3)R N.A.N.A.R R R(3)R N.A.N.A.R R CHANNEL FUNCTIONAL
TEST Q(2)Q N.A.N.A.Q Q Q(2)Q N.A.N.A.Q q MODES IN WHICH SURVEILLANCE
REQUIRED**.***((
C C ICA-ei TABLE 4.3-12 (Continued)
r MONITORING
INSTRUMENTATION
SURVEILLANCE
REQUIREMENTS
RADIOACTIVE
GASEOUS EFFLUENi-CHA INSTRUMENT
CH 4. Containment Purge System a. Noble Gas Activity Monitor b. Noble Gas Activity Recorder c. Iodine Sampler 4h d. Particulate Sampler e. Flow Rate Monitor f. Sampler Flow Rate Monitor 5. Auxiliary Building Ventilation System a. Noble Gas Actvity Monitor b. Noble Gas Activity Recorder c. Iodine Sampler d. Particulate Sampler e. Flow Rate Monitor f. Sampler Flow Rate Monitor ,NNEL HECK D D D D D D SOURCE CHECK P N.A.N.A.N.A.N.A.N.A.CHANNEL CALIBRATION
R(3)R N.A.N.A.R R R(3)R N.A.N.A.R R CHANNEL FUNCTIONAL
TEST Q(l)Q N.A.N.A.Q Q Q(2)Q N.A.N.A.Q Q MODES IN WHICH SURVE ILLANCE REQUIRED*******(D D D D D D M N.A.N.A.N.A.N.A.N.A.(
(TABLE 4.3-12 (Continued)
RADIOACTIVE
GASEOUS EFFLUENT MONITORING
INSTRUMENTATION
SURVEILLANCE
REQUIREMENTS
(-u--I (A-4 CHANNEL INSTRUMENT
CHECK 6. Fuel Storage Area Ventilation System a. Noble Gas Activity Monitor D b. Noble Gas Activity Recorder D c. Iodine Sampler D d. Particulate Sampler D e. Flow Rate Monitor D cm f. Sampler Flow Rate Monitor D 7. Radwaste Area Ventilation System a. Noble Gas Activity Monitor D b. Noble Gas Activity Recorder D c. Iodine Sampler D d. Particulate Sampler D SOURCE CHECK M N.A.N.A.N.A.N.A.N.A.M N.A.N.A.N.A.CHANNEL CALIBRATION
R(3)R N.A.N.A.R R R(3)R N.A.N.A.CHANNEL FUNCTIONAL
TEST Q(2)Q N.A.N.A.Q Q Q(2)Q N.A N.A MODES IN WHICH SURVEILLANCE
REQUIRED******((
C 2:-I LA4 TABLE 4.3-12 (Continued)
RADIOACTIVE
GASEOUS EFFLUENT MONITORING
INSTRUMENTATION
SURVEILLANCE
REQUIREMENTS
INSTRUMENT
7. Radwaste Area Ventilation System e. Flow Rate Monitor f. Sampler Flow Rate Monitor X 8. Steam Generator Blowdown Vent a. Noble Gas Activity Monitor b. Noble Gas Activity Recorder c. Iodine Sampler d. Particulate Sampler e. Flow Rate Monitor f. Sampler Flow Rate Monitor CHANNEL CHECK (continued)
D D D D D D D D SOURCE CHECK N.A.N.A.M N.A.N.A.N.A.N.A.N.A.CHANNEL CALIBRATION
CHANNEL FUNCTIONAL
TEST R R Q Q MODES IN WHICH SURVEILLANCE
REQUIRED*****(R(3)R N.A.N.A.R R Q(2)Q N.A N.A.Q Q (I
K>~-TABLE 4.3-12 (Continued)
TABLE NOTATION* -During releases via this pathway.** -During waste gas holdup system operation.


(1) -The CHANNEL FUNCTIONAL
4.11.1.2.2 Reports - The calendar quarter cumulative summation of calculated dose contributions shall be included in the semiannual Radioactive Effluent Release Report.
TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(2) -The CHANNEL FUNCTIONAL
TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(3) -The CHANNEL CALIBRATION
shall include the use of a known (traceable to the National Bureau of Standards radiation measurement system)gaseous radioactive source positioned in a reproducible geometry with respect to the sensor and emitting beta and gamma radiation with fluences and energies in the ranges measured by the channel during normal operation.


PWR -STS -I 3/4 3-67 K>TABLE 4.3-12 (Continued TABLE NOTATION (4) -The CHANNEL CALIBRATION
PWR- STS- I                         3/4 11-7
shall include the use of standard gas samples containing a nominal: 1. One volume percent hydrogen, balance nitrogen, and 2. Four volume percent hydrogen, balance nitrogen.(5) -The CHANNEL CALIBRATION
shall include the use of standard gas samples containing a nominal: 1. One volume percent oxygen, balance nitrogen, and 2. Four volume percent oxygen, balance nitrogen.PWR-STS-I 3/4 3-68
3/4.11 RADIOACTIVE
EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION
LIMITING CONDITION
FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site to unrestricted areas (see Figure 3.11-1) shall be limited to the concentra- tions specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases and 4 x 10-5 uCi/ml total activity concentration for all dissolved or entrained noble gases.APPLICABILITY:
At all times.ACTION: With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits and provide prompt notification to the Commission pursuant to Specification
6.9.1.12.SURVEILLANCE
REQUIREMENTS
4.11.1.1.1 The concentration of radioactive material in unrestricted areas shall be determined to be within the above limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 4.11-1.4.11.1.1.2 Reports -The semiannual Radioactive Effluent Release Report shall include the results of analyses performed in accordance with the program of Table 4.11-1 and a summary of all releases of radioactive liquid effluents.


PWR-STS-I 3/4 11-1 TABLE 4.11-1 RADIOACTIVE
K>                              TABLE 4.11-2 LIQUID EFFLUENT INGESTION DOSE FACTORS*
LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit Sampling Analysis Type of Activity of Detection Liquid Release Type Frequency Frequency Analysis (LLD)'a (pCi/ml), W. Batch Waste Release Each Batch Each Batch Principal Gamma 0.5 Tanks Emitters P One Batch/M M Dissolved and 10 Entrained Gases P Each Batch W 1-131 1.0 Compositec P-.I Each Batch M H-3 10 Compositec Gross a 0.1 P-32 1.0 P Each Batch Q Sr-89, Sr-90 0.05 Compositec (Fe-55) (1.0).Plant Continuous Continuousd W Principal Gamma 0.5b Releases , (Steam Composited Emitters generator blowdown and turbine build- I-131 1.0 ing drainage)
                                            A. Dose or Dose Commitment Factors jT  (mrem-ml per hr-pCi)
M Grab Sample M Dissolved and 10 Entrained Gases Continuous d H-3 10 Composite H-Gross a 0.1 P-32 1.0 Continuous ted Sr-89, Sr-90 0.05 Composited (Fe-55) (1.0)PWR-STS- I 3/4 11-2 I>TABLE 4.11-1 (Continued)
  Radionuclide                        Total Body              Criticat Organs H-3 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60
TABLE NOTATION a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.12-1 of Specification
        Zn-65 Rb-86 Sr-89 Sr-90
4.12.1.1.b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixture, it may not be possible to measure7 radionuclides in concentrations near the detection limit of 5 x 10 uCi/ml. Under these circumstances, it may be necessary to calculate the concentration of such radionuclides to a lower limit of detection of 5 x 10 uCi/ml using observed ratios with those radionuclides which are measurable, or the lower limit of detection of 5 x 10- UCi/ml may be increased proportionally to the magnitude of the gamma yield (i.e., 5 x 10 /I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 2.c. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.d. To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples shall be con-tinuously collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be repre-sentative of the average effluent release.e. A batch release is the discharge of liquid wastes of a discrete volume. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuous release.X, PWR-STS-I 3/4 11-3 This figure shall consist of a map of the site area showing the unre-stricted area boundary for liquid effluents as defined in 10 CFR Part 20.3(a)(17).
          Y-91 Zr-95 Zr-97 Nb-95 Mo-99 Ru-103 Ru-1 06 Ag-llOm Sb-124 Sb-i 25 Te-125m Te-127m Te-129m Te-131m Te-132 I-131 I-133 Cs-134 Cs-136 Cs-i 37 Ba-140
* Figure 3.11-1 PWR-STS-I 314 11-4 RADIOACTIVE
        La-140
EFFLUENTS DOSE LIMITING CONDITION
        Ce-141 Ce-143 Ce-144 Np-239
FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 3.11-1) shall be limited: a. During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, aWd b. During any calendar year to < 3 mrem to the total body and to< 10 mrem to any organ.APPLICABILITY:
  *The listed dose factors are for radionuclides that may be detected in liquid effluents.
At all times.ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification
6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. (This report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.)b. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits of Specification
3.11.1.2.a or 3.11.1.2.b, prepare and submit a Special Report to the Commission pursuant to Specification
6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel'cycle sources is limited to < 25 mrem* to the total body or any organ (except thyroid, which is limited to < 75 mrem*)over 12 consecutive months. This Special Report shall include I*The assessment of radiation doses shall be performed in accordance with NUREG-0133.


PWR-STS-I 3/4 11-5 RADIOACTIVE
PWR-STS-I                           3/4 11-8
EFFLUENTS ACTION: (Continued)
an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation)
are less than the 40 CFR Part 190 Standard.


Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.c. The provisions of Specifications
v RADIOACTIVE EFFLUENTS
3.0.3 and 3.0.4 are not applicable.
LIQUID WASTE TREATMENT
LIMITING CONDITION FOR OPERATION
3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The appropriate subsystems shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses due to the liquid effluent releases to unrestricted areas (see Figure 3.11-1)
when averaged over 7 days, exceed 0.015 mrem to the total body or
0.05 mrem to any organ.


SURVEILLANCE
APPLICABILITY:   At all times.
REQUIREMENTS
4.11.1.2.1 Dose Calculations
-The dose contributions for the total m time period r at, shall be determined by calculation at least once per 7 E=1 days and a cumulative summation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:
m=E EAi 1 r 1 AItz CIL F9J where-D = the cumulative dose or dose commitment to the total body or an organ T from the liquid effluents for the total time m period E Att, in mrem.L=1 At = the length of the ith time period over which CIL and FQ are averaged for all liquid releases, in hours.C The average concentration of radionuclide i in undiluted It liquid effluent during time period at from any liquid release, in iiCi/ml.PWR-STS-I 3/4 11-6 RADIOACTIVE
EFFLUENTS SURVEILLANCE
REQUIREMENTS (Continued)
Ai = the site related ingestion dose and dose commitment factor to the total body or any organ T for each identified principal gamma and beta emitter listed in Table 4.11-2, in mrem-ml per hr-uC 1.F. = the near field average dilution factor for C during any liquid effluent release. Defined as the ratl& of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times (_ is the site specific applicable factor for the mixing effect of the discharge structure.)
For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximately by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses.


However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses.4.11.1.2.2 Reports -The calendar quarter cumulative summation of calculated dose contributions shall be included in the semiannual Radioactive Effluent Release Report.PWR- STS- I 3/4 11-7 K>TABLE 4.11-2 LIQUID EFFLUENT INGESTION
ACTION:
DOSE FACTORS*A. Dose or Dose Commitment Factors jT (mrem-ml per hr-pCi)Total Body Criticat Organs Radionuclide H-3 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Zr-97 Nb-95 Mo-99 Ru-103 Ru-1 06 Ag-llOm Sb-124 Sb-i 25 Te-125m Te-127m Te-129m Te-131m Te-132 I-131 I-133 Cs-134 Cs-136 Cs-i 37 Ba-140 La-140 Ce-141 Ce-143 Ce-144 Np-239*The listed dose factors are for radionuclides that may be detected in liquid effluents.
    a.    With the liquid radwaste treatment system inoperable for more than 72 hours or with liquid waste being discharged without treatment as required above, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
          1.   Identification of the inoperable equipment,
          2.   Cause of inoperability,
          3.  Action(s) taken to restore the inoperable equipment to OPERABLE status,
          4.   A description of alternate equipment used for treatment of radioactive materials,
          5.   Length of time the above requirements were not satisifed,
          6.   Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.


PWR-STS-I 3/4 11-8 v RADIOACTIVE
7.   Actionts) taken to prevent a recurrence of equipment failures.
EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION
FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE.


The appropriate subsystems shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses due to the liquid effluent releases to unrestricted areas (see Figure 3.11-1)when averaged over 7 days, exceed 0.015 mrem to the total body or 0.05 mrem to any organ.APPLICABILITY:
b.    The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
At all times.ACTION: a. With the liquid radwaste treatment system inoperable for more than 72 hours or with liquid waste being discharged without treatment as required above, prepare and submit to the Commission within 30 days pursuant to Specification
6.9.2 a Special Report which includes the following information:
1. Identification of the inoperable equipment, 2. Cause of inoperability, 3. Action(s)
taken to restore the inoperable equipment to OPERABLE status, 4. A description of alternate equipment used for treatment of radioactive materials, 5. Length of time the above requirements were not satisifed, 6. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.


7. Actionts)
PWR-STS- I                          3/4 11-9
taken to prevent a recurrence of equipment failures.b. The provisions of Specifications
3.0.3 and 3.0.4 are not applicable.


PWR-STS- I 3/4 11-9 IRADIOACTIVE  
IRADIOACTIVE EFFLUENTS
EFFLUENTS SURVEILLANCE  
SURVEILLANCE REQUIREMENTS
REQUIREMENTS
4.11.1.3 The liquid radwaste treatment system shall be demonstrated OPERABLE at least once per 31 days by operating the radwaste treatment system equipment.
4.11.1.3 The liquid radwaste treatment system shall be demonstrated OPERABLE at least once per 31 days by operating the radwaste treatment system equipment.


IPWR-STS-I
IPWR-STS-I                               3/4 11-10
3/4 11-10  
 
RADIOACTIVE  
RADIOACTIVE EFFLUENTS
EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION  
LIQUID HOLDUP TANKS
FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to < curies, excluding tritium and dissolved or entrained noble gases.a.b.c.APPLICABILITY:  
LIMITING CONDITION FOR OPERATION
At all times.ACTION: a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification  
3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to <       curies, excluding tritium and dissolved or entrained noble gases.
6.9.1.12.
 
a.
 
b.
 
c.
 
APPLICABILITY:   At all times.
 
ACTION:
      a.   With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within
          48 hours either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1.12. The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.
 
b.  The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by nalyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
 
PWR-STS-I                          3/4 11-11
 
RADIOACTIVE EFFLUENTS
3/4.11.2 GASEOUS EFFLUENTS
DOSE
LIMITING CONDITION FOR OPERATION
3.11.2.1 The dose rate in unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following expressions:
      a.  Release rate limit for noble gases:
          z K;  E(x7/Q 1] < 500 mrem/yr, and r (Li + 1.1 M;)    [(X7/Q)4]  < 3000 mrem/yr i
          where the terms are defined below:
      b.  Release rate limit for all radiolodines and radioactive materials in particulate form and radionuclides other than noble gases:
          E P1 [W Qi]    < T500 mrem/yr where:
            K.  = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per pCi/M 3 from Table 4.11-3.
 
Li  = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per VCi/m 3 from Table 4.11-3.
 
M.  = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per pCi/m 3 from Table 4.11-3 (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).
PWR-STS-I                            3/4 11-12
 
K>
  RADIOACTIVE EFFLUENTS
  LIMITING CONDITION FOR OPERATION (Continued)
                P  =  The dose parameter for radionuclides other than noble 3 gases for the inhalatton pathway, in mrem/yr per2 pCi/m and for the food and ground plane pathways in m (mrem/
                        yrl per pCi/sec from Table 4.11-4. The dose factors are based on the critical individual organ and most restrictive age group (child or infant).
                    =  The release rate of radionuclides, i, add in gaseous effluent from all release points at the site, in MCi/sec.
 
t-x74      __      _ sec/m 3. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary.
 
W  =  The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:
                        W =  __      sec/M 3, for the inhalation pathway.  The location is the unrestricted area in the            sector.
 
W =          meter- 2 , for the food and ground plane pathways. The location is the unrestricted area boundary in the          sector.
 
APPLICABILITY:    At all times.


The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.b. The provisions of Specifications
ACTION:
3.0.3 and 3.0.4 are not applicable.
    With the release rates exceeding the above limits, immediately decrease the release rate to within its limit and provide prompt notification to the Commiission pursuant to Specification 6.9.1.12.


SURVEILLANCE
PWR-STS-I                               3/4 11-13
REQUIREMENTS
4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by nalyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.PWR-STS-I 3/4 11-11 RADIOACTIVE
EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE LIMITING CONDITION
FOR OPERATION 3.11.2.1 The dose rate in unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following expressions:
a. Release rate limit for noble gases: z K; E(x7/Q 1] < 500 mrem/yr, and r (Li + 1.1 M;) [(X7/Q)4]
< 3000 mrem/yr i where the terms are defined below: b. Release rate limit for all radiolodines and radioactive materials in particulate form and radionuclides other than noble gases: E P 1 [W Qi] < T500 mrem/yr where: K. = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per pCi/M 3 from Table 4.11-3.Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per VCi/m 3 from Table 4.11-3.M. = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per pCi/m 3 from Table 4.11-3 (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).PWR-STS-I 3/4 11-12 K>RADIOACTIVE
EFFLUENTS LIMITING CONDITION
FOR OPERATION (Continued)
P = The dose parameter for radionuclides other than noble gases for the inhalatton pathway, in mrem/yr per pCi/m 3 and for the food and ground plane pathways in m 2 (mrem/yrl per pCi/sec from Table 4.11-4. The dose factors are based on the critical individual organ and most restrictive age group (child or infant).= The release rate of radionuclides, i, add in gaseous effluent from all release points at the site, in MCi/sec.t-x74 __ _ sec/m 3.The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary.W = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location: W = __ sec/M 3 , for the inhalation pathway. The location is the unrestricted area in the sector.W = meter-2 , for the food and ground plane pathways.


The location is the unrestricted area boundary in the sector.APPLICABILITY:
RADIOACTIVE EFFLUENTS
At all times.ACTION: With the release rates exceeding the above limits, immediately decrease the release rate to within its limit and provide prompt notification to the Commiission pursuant to Specification
SURVEILLANCE REQUIREMENTS
6.9.1.12.PWR-STS-I 3/4 11-13 RADIOACTIVE  
4.11.2.1.1 The release rate of radioactive materials released in gaseous effluents from the site shall be determined to be within the above limits by obtaining representative samples In accordance with the sampling and analysis program specified in Table 4.11-5.
EFFLUENTS SURVEILLANCE  
REQUIREMENTS
4.11.2.1.1 The release rate of radioactive materials released in gaseous effluents from the site shall be determined to be within the above limits by obtaining representative samples In accordance with the sampling and analysis program specified in Table 4.11-5.4.11.2.1.2 Reports -The semiannual Radioactive Effluent Release Report shall include the results of analyses performed in accordance with the program of Table 4.11-5 and a summary of all releases of radioactive gaseous effluents.


PWR-STS-1 3/4 11-14 TABLE 4.11-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*
4.11.2.1.2 Reports - The semiannual Radioactive Effluent Release Report shall include the results of analyses performed in accordance with the program of Table 4.11-5 and a summary of all releases of radioactive gaseous effluents.
C-I 14 Total Body Dose Factor KI (mrem/yr per iCi/m 3)Skin Dose Factor L (mrem/yr per iiCi/m 3)Gamma Air Dose Factor M i (mrad/yr Rer pCi/M3)Beta Air Dose Factor N 1 (mrad/yr per pCi/m 3)Radionuclide-P.--a-.A Ia L'Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-i 31m Xe- 33mn Xe-133 Xe-i 35m Xe-i 35 Xe-i 37 Xe-i 38 Ar-41 7.56E- 02**1 .17E+03 1 .61E+Ol 5.92E+03 1 .47E+04 1 .66E+04 1.56E+04 9.15E+O1 2.51E+02 2. 94E+02 3.12E+03 1.81 E+03 1 .42E+03 8.83E+03 8.84E+03 1 .46E+03 1 .34E+03 9.73E+03 2.37E+03 1 .01 E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11E+02 1 .86E+03 1 .22E+04 4.13E+03 2.69E+03 1 .93E+Ol 1 .23E+03 1 .72E+Ol 6.17E+03 1 .52E+04 1 .73E+04 1 .63E+04 1 .56E+02 3.27E+02 3.53E+02 3.36E+03 1 .92E+03 1 .51E+03 9.21E+03 9.30E+03 2.88E+02 1 .97E+03 1 .95E+03 1 .03E+04 2.93E+03 1 .06E+04 7.83E+03 1 .l1E+03 1 .48E+03 1 .05E+03 7.39E+02 2.46E+03 1 .27E+04 4.75E+03 3.28E+03 C*The listed dose**7.56E-02
= 7.56 factors are X 10-2.for radionuclides that may be detected in gaseous effluents.


TABLE 4.11-4 DOSE PARAMETERS
PWR-STS-1                          3/4 11-14
FOR RADIOIODINES
AND RADIOACTIVE
PARTICULATE, GASEOUS EFFLUENTS*
C-g (AI-I (A Radio-nuclide P.Inhalation Pathway (mrem/yr per pCi/m 3)P.Food & Ground Pathways (m 2.mrern/yr per pCi/sec)Pi Inhalation Pathway (mrem/yr per vCi/m )Radio-nucli ide Pi Food & Ground Pathways-(m 2.mrem/yr per pCi/I )H-3 P-32 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Rb-86 Sr-89 Sr-90-IJ Y-91...A Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm 6.5E+02 2.OE+06 2.5E+04 2. 4E+04 1.lE+04 3.2E+04 6.3E+04 1.9E+05 4. OE tO5 4.1E+07 7.OE+04 2. 2E+04 1.3E+04 1.6E+04 1.6E+05 3.3E+04 2. 4E+03 1.5E+ll 1 .1 E+09 7. OE+08 5. 7E+08 4. 6E+09 1.7E+l0 1.6E+l0 1.OE+l0 9. 5E+i0 1.9E+09 3. 5E *08 3. 6E+08 3.4E 0 4.4E+ll 1.5E+10 Cd-il 5m Sn-123 Sn-126 Sb-124 Sb-125 Te-127m Te-129m Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 1-131 I-133 Unidentified**
7.OE+04 2.9E+05 1. 2E+06 5.9E+04 1.5E+04 3.8E+04 3.2E+04 7.OE+05 1.3E+05 6.1E+05 5.6E+04 2.2E+04 1 .5E+05 1 .5E+07 3.6E+06 4.1E+07 4.8E+07 3.4E+09 1.lE+09 1 .lE+09 1.lE+O9 7.4E+10 1.3E+09 5.3E+10 5.4E+09 4.7E+10 2.4E+08 8.7E+07 6.5E+08 l.lE+12 9.6E+09 9.5E+10 (*The listed dose parameters are gaseous effluents.


for radionuclides that may be detected in**If Sr-90 analysis is performed, use P. given in Ru-106 for unidentified components.
C
-I                                                TABLE 4.11-3
  14                                DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*
                        Total Body                                            Gamma Air          Beta Air Dose Factor                Skin Dose Factor        Dose Factor        Dose Factor KI                            L                    M i              N1 Radionuclide    (mrem/yr per iCi/m3 )      (mrem/yr per iiCi/m3)  (mrad/yr Rer pCi/M3) (mrad/yr per pCi/m 3 )
    Kr-83m              7.56E- 02**                                        1 .93E+Ol              2.88E+02 Kr-85m              1.17E+03                      1.46E+03              1.23E+03                1.97E+03 Kr-85              1.61E+Ol                      1.34E+03              1.72E+Ol                1.95E+03 Kr-87              5.92E+03                      9.73E+03              6.17E+03                1.03E+04 Kr-88              1.47E+04                      2.37E+03              1.52E+04                2.93E+03
-P.
 
Kr-89              1.66E+04                      1.01 E+04            1 .73E+04              1.06E+04
--a
-. A
  Ia Kr-90              1.56E+04                      7.29E+03              1.63E+04                7.83E+03 L'
    Xe-i 31m            9.15E+O1                      4.76E+02              1.56E+02                1.l1E+03 Xe- 33mn            2.51E+02                      9.94E+02              3.27E+02                1.48E+03
                        2.94E+02                      3.06E+02              3.53E+02                1.05E+03 Xe-133 Xe-i 35m            3.12E+03                      7.11E+02              3.36E+03                7.39E+02        C
    Xe-i 35              1.81 E+03                    1.86E+03              1.92E+03                2.46E+03 Xe-i 37              1.42E+03                      1.22E+04              1.51E+03                1.27E+04 Xe-i 38              8.83E+03                      4.13E+03              9.21E+03                4.75E+03 Ar-41                8.84E+03                      2.69E+03              9.30E+03                3.28E+03
      *The listed dose factors are for radionuclides that may be detected in gaseous effluents.
 
**7.56E-02 = 7.56 X 10-2.
 
C
                                                      TABLE 4.11-4
-g                                  DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE
(AI                                        PARTICULATE, GASEOUS EFFLUENTS*
-I
(A
                      P.                          P.                                  Pi                        Pi Radio- Inhalation Pathway        Food & Ground Pathways      Radio-    Inhalation Pathway  Food & Ground Pathways- nuclide  (mrem/yr  per pCi/m 3) (m2 . mrern/yr per pCi/sec)  nucliide (mrem/yr per vCi/m ) (m2 . mrem/yr per pCi/I )
    H-3          6.5E+02                    2.4E+03              Cd-il 5m      7.OE+04                4.8E+07 P-32          2.OE+06                      1.5E+ll            Sn-123        2.9E+05                3.4E+09 Mn-54        2.5E+04                      1. 1E+09            Sn-126        1.2E+06                1.lE+09 Fe-59        2.4E+04                      7. OE+08            Sb-124        5.9E+04                1.lE+09 Co-58        1.lE+04                      5. 7E+08            Sb-125        1.5E+04                1.lE+O9 Co-60        3.2E+04                      4. 6E+09            Te-127m        3.8E+04                7.4E+10
    Zn-65        6.3E+04                      1.7E+l0            Te-129m        3.2E+04                1.3E+09 Rb-86        1.9E+05                      1.6E+l0            Cs-134        7.OE+05                5.3E+10
    Sr-89        4. OE tO5                    1.OE+l0            Cs-136        1.3E+05                5.4E+09 Sr-90        4.1E+07                      9. 5E+i0            Cs-137        6.1E+05                4.7E+10
-IJ Y-91          7.OE+04                      1.9E+09            Ba-140        5.6E+04                2.4E+08
...
  A Zr-95        2.2E+04                      3. 5E *08          Ce-141        2.2E+04                8.7E+07 Nb-95        1.3E+04                      3. 6E+08            Ce-144        1.5E+05                6.5E+08 Ru-103        1.6E+04                      3.4E 0              1-131        1 .5E+07                l.lE+12 I-133        3.6E+06                9.6E+09 Ru-106 Ag-llOm
                  1.6E+05
                  3.3E+04
                                                4.4E+ll
                                                1.5E+10            Unidentified** 4.1E+07                  9.5E+10    (
        *The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
 
**If Sr-90 analysis is performed, use P. given in Ru-106 for unidentified components.


If Sr-90 and Ru-106 analyses are perfArmied, use Pi given In I-131 for unidentified components.
If Sr-90 and Ru-106 analyses are perfArmied, use Pi given In I-131 for unidentified components.
Line 396: Line 951:
If Sr-90, Ru-106 and I-131 analyses are performed, use Pi given in P-32 for unidentified components.
If Sr-90, Ru-106 and I-131 analyses are performed, use Pi given in P-32 for unidentified components.


C TABLE 4.11-5 (-g 2C/Cn-I--A RADIOACTIVE  
C                                             TABLE 4.11-5
GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)a P P A. Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters 100b Tank Grab Sample H-3 1 B. Containment Purge Each Purge Each Purgec Principal Gamma Emitters l 00 Grab Sample H-31 C. (List other release Mcf Mc Principal Gamma Emitters 100b points where gas- Grab eous effluents are Sample H-31 discharged from the facility, e.g. air ejector, steam gen-erator flash vent, equipment vents, ventilation ex-hausts, etc.)C (D. All Release Types as listed in A, B, C above.Continuous
                                                                                                                                    (
9 we Charcoal Sample 1-131 4.1-133 lo04 Continuous
                            RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM
9 We Principal Gamma Emitters 10 5 Particulate  
-g
(1-131, Others)Sample Continuous
2C/
9  M Gross a 10 5 Composite Particulate Sample _Continuous
                                              Minimum                                                                 Lower Limit of Sampling       Analysis                                 Type of                       Detection (LLD)
9 Q Composite Particulate Sample Sr-89, Sr-90 10-5... ._ _--_______ _________________
    Gaseous Release Type     Frequency       Frequency                             Activity Analysis                   (pCi/ml)a P               P
I. -I _________________________  
    A. Waste Gas Storage     Each Tank       Each Tank                       Principal Gamma Emitters               100b Tank                 Grab Sample                                         H-3                                     1 C
    B. Containment Purge     Each   Purge   Each   Purgec                   Principal Gamma Emitters     l             00
Cn                            Grab
-I                          Sample                                         H-31 C. (List other release   Mcf                   Mc                       Principal Gamma Emitters               100b points where gas-     Grab eous effluents are   Sample                                         H-31 discharged from the facility, e.g. air ejector, steam gen- erator flash vent, equipment vents, ventilation ex-
--A    hausts, etc.)
    D. All Release Types     Continuous 9          we                        1-131 as listed in A, B,                   Charcoal C above.                             Sample                           1-133
                                                                                                        4.
 
lo04
                                                                                                                                      (
                              Continuous 9         We                         Principal Gamma Emitters               10 5 Particulate                     (1-131, Others)
                                              Sample Continuous9          M                         Gross a                                 10 5 Composite Particulate Sample                 _
                              Continuous 9         Q                           Sr-89, Sr-90                           10-5 Composite Particulate
              . .. . _                     _
                                              Sample                                I.
 
-- ________________________            -I       _________________________
 
TABLE 4.11-5 (Continued)
TABLE 4.11-5 (Continued)
TABLE NOTATION a. The lower limit of detection (LLD) is defined in Table Notation a.of Table 4.12-1 of Specification  
                            TABLE NOTATION
4.12.1.1.b. For certain radionuclides with low gamma yield or low energies or for certain radionuclide mixtures, it may not be possible to measure radionulldes in concentrations near the detection limit of 1 x 10 pCi/ml. Under these circumstances, it may be necessary to calculate the concenration of such radionuclides to a lower limit of detection of 1 x 10 pCi/ml using observed ratios with those radionuclies which are measurable, or the lower limit of detection of 1 x 10. pCi/ml may be increased proportionally to the magnitude of the gamma yield (i.e., 1 x 10- /I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10% of the MPC value specified in 1 CFR 20, Appendix B, Table II, Column 1.c. Analyses shall also be performed following shutdown, startup, or similar operational occurrence which could alter the mixture of radionuclides.
a.   The lower limit of detection (LLD) is defined in Table Notation a.
 
of Table 4.12-1 of Specification 4.12.1.1.
 
b.   For certain radionuclides with low gamma yield or low energies or for certain radionuclide mixtures, it may not be possible to measure radionulldes in concentrations near the detection limit of
    1 x 10   pCi/ml. Under these circumstances, it may be necessary to calculate the concenration of such radionuclides to a lower limit of detection of 1 x 10   pCi/ml using observed ratios with those radionuclies which are measurable, or the lower limit of detection of 1 x 10. pCi/ml may be increased proportionally to the magnitude of the gamma yield (i.e., 1 x 10- /I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10% of the MPC value specified in 1 CFR 20, Appendix B, Table II, Column 1.
 
c.   Analyses shall also be performed following shutdown, startup, or similar operational occurrence which could alter the mixture of radionuclides.
 
d.  Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded.
 
e.  Analyses shall also be performed at least once per 24 hours for 7 days following each shutdown, startup or similar operational occurrence which could lead to significant increases or decreases in radiotodi'ne releases. Samplers shall also be changed and analyzed at intervals in Specifications 3.11.2.1 and 3.11.2.3.
 
f.  Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area.
 
g.  The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Specifications 3.11.2.1,
    3.11.2.2 and 3.11.2.3.
 
PWR-STS-I                          3/4 11-18
 
-
  RADIOACTIVE EFFLUENTS
  DOSE, NOBLE GASES
  LIMITING CONDITION FOR OPERATION
  3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to noble gases released in gaseous effluents from the site shall be limited to the following expressions:
        a.    During any calendar quarter, for gamma radiation:
                3.17 x 10i 8 E Mi [(-xm Qj + (-xq)        qia < 5 mrad, and i
                During any calendar quarter, for beta radiation:
                3.17 x 108 E N1 [(i7XM Qj + (j77) qj] < 10 mrad, and i
        b.    During any calendar year, for gamma radiation:
                3.17 x 10 8        Mi1 [( 77  Qj + (-Xq) qj] < 10 mrad, and K-i During any calendar year, for beta radiation:
                3.17 x 10  10-88              eV          1x/Q
                                    1 [ 770 Q. + (x/q) qj] < 20 mrad N.
 
where:
              3.17 x 10 8 = The inverse of the number of seconds in a year.
 
M. = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per VCi/m3 from Table 4.11-3.
 
Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per VCi/m3 from Table 4.11-3.
 
(G7n    =              sec/m 3. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for long term releases (greater than 500 hrs/year).
                                      3.  The relative concentration for any area (iJ7)    = _sec/m at or beyond the unrestricted area boundary for short term releases (equal to or less than 500 hrs/yr).
    PWR-STS- I                                  3/4 11-19
 
IIRADIOACTIVE EFFLUENTS
LIMITING CONDITION FOR OPERATION (Continued)
        Q  = The release of noble gas radionuclides, I, in gaseous.effluents, for long term releases (greater than 500 hrs/yr), in pCi.
 
Releases shall be cumulative over the calendar quarter or year as appropriate.
 
q=  The release of noble gas radionuclides, t, in gaseous effluents, for short term releases (equal to or less than 500 hrs/yr),
            in ACi. Releases shall be cumulative over the calendar quarter or year as appropriate.
 
CThe dose design objectives may be reduced based on predicted noble gas releases from the turbine building if effluent sampling is not provided.
 
The dose design objectives may also be reduced based on expected public occupancy of areas, e.g., beaches and visitor centers within the unrestricted area boundary.)
  APPLICABILITY:    At all times.


d. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded.e. Analyses shall also be performed at least once per 24 hours for 7 days following each shutdown, startup or similar operational occurrence which could lead to significant increases or decreases in radiotodi'ne releases.
ACTION:
        a.   With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 3( days, pursuant to Specifica- tton 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(ssl and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose during these four calendar quarters is within (10) mrad for gamma radiation and (20) wrad for beta radiation.


Samplers shall also be changed and analyzed at intervals in Specifications
b.   With the calculated air dose from radioactive noble gases in gaseous effluents exceeding twice the limits of Specification
3.11.2.1 and 3.11.2.3.f. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area.g. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Specifications
              3.11.2.2.a or 3.11.2.2.b, prepare and submi't a Special Report to the Commisston pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to 4 25 mrem* to the total body or any organ (except thyroid, which is limited to < 75 mrem*) over 12 consecutive months. This Special Report shall include an analysis which The assessment of radiation doses shall be performed in accordance with NURE6-O 33.
3.11.2.1, 3.11.2.2 and 3.11.2.3.PWR-STS-I 3/4 11-18
-RADIOACTIVE
EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION
FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to noble gases released in gaseous effluents from the site shall be limited to the following expressions:
a. During any calendar quarter, for gamma radiation:
3.17 x 10i 8 E Mi [(-xm Qj + (-xq) qia < 5 mrad, and i During any calendar quarter, for beta radiation:
3.17 x 108 E N 1 [(i7XM Qj + (j77) qj] < 10 mrad, and i b. During any calendar year, for gamma radiation:
3.17 x 10 8 Mi [(1 77 Qj + (-Xq) qj] < 10 mrad, and K-i During any calendar year, for beta radiation:
10-8 eV 1x/Q 3.17 x 10 8 N. [1 770 Q. + (x/q) qj] < 20 mrad where: 3.17 x 10 8 = The inverse of the number of seconds in a year.M. = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per VCi/m 3 from Table 4.11-3.Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per VCi/m 3 from Table 4.11-3.(G7n = sec/m 3.The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for long term releases (greater than 500 hrs/year).(iJ7) = _sec/m 3.The relative concentration for any area at or beyond the unrestricted area boundary for short term releases (equal to or less than 500 hrs/yr).PWR-STS- I 3/4 11-19 IIRADIOACTIVE
EFFLUENTS LIMITING CONDITION
FOR OPERATION (Continued)
Q = The release of noble gas radionuclides, I, in gaseous.effluents, for long term releases (greater than 500 hrs/yr), in pCi.Releases shall be cumulative over the calendar quarter or year as appropriate.


q= The release of noble gas radionuclides, t, in gaseous effluents, for short term releases (equal to or less than 500 hrs/yr), in ACi. Releases shall be cumulative over the calendar quarter or year as appropriate.
PWR-STS-I                            3/4 11-20


CThe dose design objectives may be reduced based on predicted noble gas releases from the turbine building if effluent sampling is not provided.The dose design objectives may also be reduced based on expected public occupancy of areas, e.g., beaches and visitor centers within the unrestricted area boundary.)
RADIOACTIVE EFFLUENTS
APPLICABILITY:  
ACTION:     (Continued)
At all times.ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 3( days, pursuant to Specifica- tton 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(ssl and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose during these four calendar quarters is within (10) mrad for gamma radiation and (20) wrad for beta radiation.
            demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190
            Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.


b. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding twice the limits of Specification
c.   The provisions of Speciftcations 3.0.3 and 3.0.4 are not applicable.
3.11.2.2.a or 3.11.2.2.b, prepare and submi't a Special Report to the Commisston pursuant to Specification
6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to 4 25 mrem* to the total body or any organ (except thyroid, which is limited to < 75 mrem*) over 12 consecutive months. This Special Report shall include an analysis which The assessment of radiation doses shall be performed in accordance with NURE6-O 33.PWR-STS-I 3/4 11-20
RADIOACTIVE
EFFLUENTS ACTION: (Continued)
demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation)
are less than the 40 CFR Part 190 Standard.


Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.c. The provisions of Speciftcations
SURVEILLANCE REQUIREMENTS
3.0.3 and 3.0.4 are not applicable.
4.11.2.2 The release of radioactive materials released in gaseous effluents from the site shall he determined to be within the above limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 4.11-5.


SURVEILLANCE
PWR-STS-I                           3/4 11-21
REQUIREMENTS
4.11.2.2 The release of radioactive materials released in gaseous effluents from the site shall he determined to be within the above limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 4.11-5.PWR-STS-I 3/4 11-21 RADIOACTIVE
EFFLUENTS DOSE, RADIOIODINES, RADIOACTIVE
MATERIAL IN PARTICULATE
FORM AND RADIONUCLIDES
OTHER THAN NOBLE GASES LIMITING CONDITION
FOR OPERATION 3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following expressions:
a. During any calendar quarter: 3.17 x 10 8 R 1 [W Q. + w qj] < 7.5 mrem, and b. During any calendar year: 3.17 x 10&deg; R. [W Q: + w qua < 15 mrem where: 3.17 x 10 8 = The inverse of the number of seconds in a year.Q. = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs/yr), in PCi. Releases shall be cumulative over the calendar quarter or year as appropriate.


q= The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short term releases (equal to or less than 500 hrs/yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate.
RADIOACTIVE EFFLUENTS
DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND
RADIONUCLIDES OTHER THAN NOBLE GASES
LIMITING CONDITION FOR OPERATION
3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following expressions:
    a.    During any calendar quarter:
          3.17 x 10 8    R1 [W Q. + w qj] < 7.5 mrem, and b.    During any calendar year:
          3.17 x 10&deg;    R. [W Q: + w qua < 15 mrem where:
    3.17 x 10 8 = The inverse of the number of seconds in a year.


W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long term releases (greater than 500 hrs/yr): W = (Ax/A for the inhalation pathway, in sec/m 3 from Table 4.11-6a.W = (D/Q) for the food and ground plane pathways, in meters 2 from Table 4.11-6b.w = The dispersion parameter for estimating the dose to an individual at the controlling location for short term releases (equal to or less than 500 hrs/yr): PWR-STS-I 3/4 11-22 RADIOACTIVE
Q.  = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs/yr),
EFFLUENTS LIMITING CONDITION
          in PCi. Releases shall be cumulative over the calendar quarter or year as appropriate.
FOR OPERATION (Continued)
w -(x-/q) for the inhalation pathway, in sec/m 3 from Table 4.11-6c.w = (W7q) for the food and ground plane pathway, in meters 2 from Table 4.11-6d.R = The dose factor for each identified radionuclide, i, in ml (mrem/yrl per zCi/sec or mrem/yr per pCi/m 3 from Table 4.11-7.For the direction sectors with existing pathways within 5 miles from the unit, use the values of R, for these pathways.


If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk R assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector. If the R for an existing pathway within 5 miles is less than a cow-milk R It 4.5 to 5.0 miles, then use the value of the cow-milk R at 4.5 to 5.0 miles. The values used for calculating dose contributions shall be consistent wtth. the results of the land use census performed pursuant to Specification
q= The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short term releases (equal to or less than
3.12.2. The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30 days after the completion of each required land use census. The parameters W and w shall correspond to the applicable R 1 for the same sector, pathway and location condition.(The dose design objective may be reduced based on predicted carbon-14 releases and turbine building releases if effluent sampling is not provided.)
          500 hrs/yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate.
APPLICABILITY:
At all times.ACTION: a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification
6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radiojodines, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within (C151 mrem to any organ.PWR-STS-I 3/4 11-23 RADIOACTIVE
EFFLUENTS ACTION: (Continued)
b. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding twice the limits of Specification
3.11.2.3.a.


or 3.11.2.3.b, prepare and submit a Special Report to the Commission pursuant to Specification
W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long term releases (greater than 500 hrs/yr):
6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem* to the total body or any organ (except thyroid, Which is limited to < 75 mrem*l over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation)
                                                          3 W = (Ax/A for the inhalation pathway, in sec/m from Table 4.11-6a.
are less than the 40 CFR Part 190 Standard.


Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.c. The provisions of Speciftcations
2 W = (D/Q) for the food and ground plane pathways, in meters from Table 4.11-6b.
3.Q.3 and 3.0.4 are not applicable.


SURVEILLANCE
w = The dispersion parameter for estimating the dose to an individual at the controlling location for short term releases (equal to or less than 500 hrs/yr):
REQUIREMENTS
PWR-STS-I                            3/4 11-22
4.11.2.3 The release of radioactive materials released is gaseous effluents from the site shall be determined to be within the above limits by obtaining representative samples in accordance with- the sampling and analysts program specified in Table 4.11-5.*I The assessment of radiation doses shall be performed in accordance with NUREG-0133.


PWR-STS-I 3/4 11-24 (C TABLE 4.11-6a (A DISPERSION
RADIOACTIVE EFFLUENTS
PARAMETER
LIMITING CONDITION FOR OPERATION (Continued)
(7M) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR Distance to the control location, in miles Sector e 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N NNE NE ENE E ESE SE SSE S WSW_a WSW W Ul WNW NW NNW ((
                                                            3 w - (x-/q) for the inhalation pathway, in sec/m from Table 4.11-6c.
(((-o-4--i TABLE 4.11-6b DISPERSION
PARAMETER (O7) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR Distance to the control location, in miles Sector e 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.04.5 4.5-5.0 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW (--A I9 (
2: 44 DISPE-I Sector e 0-0.5 N NNE NE ENE E ESE SE SSE S SW WSW I W 4 WNW NW NNW C (TABLE 4.11-6c`RSION PARAMETER (xlg) FOR SHORT TERM RELEASES i 500 HR/YR OR : 125 HR/QIR Distance to the control location, in miles 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 (.(
(<TABLE 4.11-6d (A DISPERSION
PARAMETER (Onh) FOR SHORT TERM RELEASES s 500 HR/YR OR r 125 HR/QTR CA Distance to the control location, in miles Sector o 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N NNE NE ENE E ESE SE SSE S SSW SW-. WSW W NW NNW
(C (CA TABLE 4.11-7 PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES
OTHER THAN NOBLE GASES Inhalation Pathway Rap (mrem/yr per pCli/m 3)Meat Pathway Ri (tm 2.mrem/yr per pCi/sec)Ground Plane Pathway Ri (W 2.mrem/yr per pCi/sec)Cow-Milk-Infant Pathway Rm 2.mrem/yr per MC1/sec).Leafy Vegetables Pathway Ri (m 2.mrem/yr per pCi/sec)(Radio-nucl ide-A-a (
IRADIOACTIVE
EFFLUENTS GASEOUS WASTE TREATMENT LIMITING CONDITION
FOR OPERATION 3.11.2.4 The gaseous radwaste treatment system shall be OPERABLE.


The appropriate subsystems shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent releases from all release points to unrestricted areas (see Figure 5.1-1)would result in a dose in any period of 7.days -that exceeds 0.05 mrad for gamma radiation, Q.lQ mrad for beta radiation, or 0.075 mrem to any organ for that same 7 day period.APPLICABILITY:
2 w = (W7q) for the food and ground plane pathway, in meters from Table 4.11-6d.
At all times.ACTION: a. With the gaseous radwaste treatment system inoperable for more than 72 hours or with gaseous waste being discharged without treatment as required above, prepare and submit to the Commission within 30 days pursuant to Specification
6.9.2 a Special Report which includes the following information:
1. Identiftcation of the inoperable equipment, 2. Cause of inoperability, 3. Actions)l taken to restore the inoperable equipment to OPERABLE status, 4. A description of alternate equipment used for treatment of radioactive materials, 5. Length of time the above requirements were not satisfied, 6. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.


7. Actionts)
R = The dose factor for each identified radionuclide,    i, in ml
taken to prevent a recurrence of equipment failures.b. The provisions of Specifications
                                                        3 from Table 4.11-7.
3.0.3 and 3.0.4 are not applicable.


PWR-STS-I 3/4 11-30  
(mrem/yrl per zCi/sec  or mrem/yr per pCi/m For the direction sectors with existing pathways within 5 miles from the unit, use the values of R, for these pathways. If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk R assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector. If the R for an existing pathway within 5 miles is less than a cow-milk R It 4.5 to 5.0 miles, then use the value of the cow-milk R at 4.5 to 5.0
RADIOACTIVE  
      miles. The values used for calculating dose contributions shall be consistent wtth. the results of the land use census performed pursuant to Specification 3.12.2. The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30
EFFLUENTS SURVEILLANCE  
      days after the completion of each required land use census. The parameters W and w shall correspond to the applicable R1 for the same sector, pathway and location condition.
REQUIREMENTS
 
(The dose design objective may be reduced based on predicted carbon-14 releases and turbine building releases if effluent sampling is not provided.)
APPLICABILITY:      At all times.
 
ACTION:
      a.  With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclidesof other than noble gases in gaseous effluents exceeding any the above limits, prepare and submit to the Commission within
            30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radiojodines, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within (C151 mrem to any organ.
 
PWR-STS-I                            3/4 11-23
 
RADIOACTIVE EFFLUENTS
ACTION:    (Continued)
      b.    With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding twice the limits of Specification 3.11.2.3.a. or 3.11.2.3.b, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem* to the total body or any organ (except thyroid, Which is limited to < 75 mrem*l over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation)
            are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.
 
c.    The provisions of Speciftcations 3.Q.3 and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.11.2.3 The release of radioactive materials released is gaseous effluents from the site shall be determined to be within the above limits by obtaining representative samples in accordance with- the sampling and analysts program specified in Table 4.11-5.
 
*I
  The assessment of radiation doses shall be performed in accordance with NUREG-0133.
 
PWR-STS-I                           3/4 11-24
 
(                                                                                                  C
                                                  TABLE 4.11-6a (A              DISPERSION PARAMETER (7M) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR
                                  Distance to the control location, in miles Sector e 0-0.5    0.5-1.0    1.0-1.5  1.5-2.0  2.0-2.5  2.5-3.0  3.0-3.5 3.5-4.0  4.0-4.5 4.5-5.0
      N
      NNE
                                                                                                            (
      NE
      ENE
      E
      ESE
      SE
      SSE
      S
      WSW
_a  WSW
      W
Ul  WNW
      NW
      NNW
                                                                                                            (
 
(                                                (                                              (
                                                  TABLE 4.11-6b
-o
-4 DISPERSION PARAMETER (O7) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR
-- i Distance to the control location, in miles Sector e 0-0.5    0.5-1.0  1.0-1.5  1.5-2.0  2.0-2.5  2.5-3.0  3.0-3.5  3.5-4.0  4.04.5 4.5-5.0
        N
        NNE
                                                                                                              (
        NE
        ENE
        E
        ESE
        SE
        SSE
        S
-
        SSW
        SW
-A
        WSW
  I9 W
        WNW
        NW
        NNW
                                                                                                              (
 
C                                                  (
                                                  TABLE 4.11-6c
2:
44              DISPE`RSION PARAMETER (xlg) FOR SHORT TERM RELEASES i 500 HR/YR OR : 125 HR/QIR
-I
                                    Distance to the control location, in miles Sector e 0-0.5      0.5-1.0  1.0-1.5  1.5-2.0  2.0-2.5  2.5-3.0  3.0-3.5  3.5-4.0  4.0-4.5 4.5-5.0
        N                                                                                                        (.
      NNE
      NE
      ENE
        E
      ESE
      SE
      SSE
        S
      SW
      WSW
  I    W
    4 WNW
      NW
      NNW
                                                                                                                (
 
(                                                                                                    <
                                                  TABLE 4.11-6d (A              DISPERSION PARAMETER (Onh) FOR SHORT TERM RELEASES s 500 HR/YR OR r 125 HR/QTR
CA
                                  Distance to the control location, in miles Sector o 0-0.5    0.5-1.0  1.0-1.5  1.5-2.0  2.0-2.5  2.5-3.0  3.0-3.5  3.5-4.0  4.0-4.5 4.5-5.0
        N
      NNE
      NE
      ENE
        E
      ESE
      SE
      SSE
        S
      SSW
      SW
    -. WSW
        W
      NW
      NNW
 
(                                                  C                                            (
                                            TABLE 4.11-7 PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES
CA
                Inhalation        Meat          Ground Plane    Cow-Milk-Infant .Leafy Vegetables Pathway        Pathway            Pathway        Pathway              Pathway Radio- Rap (mrem/yr        (tm2 .
                                      Ri mrem/yr Ri (W2 . mrem/yr      2.
 
Rmmrem/yr Ri (m2 . mrem/yr
                                                                                                      (
      nucl ide  per pCli/m3 )  per pCi/sec)      per pCi/sec)      per MC1/sec)    per pCi/sec)
-A
-a
                                                                                                      (
 
IRADIOACTIVE EFFLUENTS
GASEOUS WASTE TREATMENT
LIMITING CONDITION FOR OPERATION
                                                                          The
3.11.2.4 The gaseous radwaste treatment system shall be OPERABLE.          in used  to reduce  radioactive  materials appropriate subsystems shall be                                gaseous effluent gaseous waste prior to their  discharge  when the  projected Figure 5.1-1)
releases from all release points to unrestricted areas (see 0.05 mrad for would result in a dose in any period of 7.days -that exceeds to any gamma radiation, Q.lQ mrad for beta radiation, or 0.075 mrem organ for that same 7 day period.
 
APPLICABILITY:    At all times.
 
ACTION:
      a.    With the gaseous radwaste treatment system inoperable for more than 72 hours or with gaseous waste being discharged without treatment as required above, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
            1.    Identiftcation of the inoperable equipment,
            2.    Cause of inoperability,
            3.  Actions)l taken to restore the inoperable equipment to OPERABLE status,
            4.  A description of alternate equipment used for treatment of radioactive materials,
            5.  Length of time the above requirements were not satisfied,
            6.  Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.
 
7.  Actionts) taken to prevent a recurrence of equipment failures.
 
b.    The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
PWR-STS-I                            3/4 11-30
 
RADIOACTIVE EFFLUENTS
SURVEILLANCE REQUIREMENTS
4.11.2.4.1 The gaseous radwaste treatment system shall be demonstrated OPERABLE at least once per 31 days by operating the radwaste treatment system equipment.
4.11.2.4.1 The gaseous radwaste treatment system shall be demonstrated OPERABLE at least once per 31 days by operating the radwaste treatment system equipment.


4.11.2.4.2 Dose Calculations.
4.11.2.4.2 Dose Calculations. The dose contributions shall be calculated for all radionuclides in gaseous effluents projected to be released to unrestricted areas during any projected 7 day period using the following expressions:
    For noble gases, the gamma radiation:
    3.17 x 10    z M1 [(x-7) Qi  + (V74) qa c Q0.O5 mrad, and i
    For noble gases, the beta radiation:
    3.17 x 1008E N1 &#xa3;ii7 Q1 + (x70) qi] < 0.10 Brad, and i
    For radioiodines, radioactive materials in particulate form and radionuclides other than nokle gases:
    3.17 x 10- z R1 &#xa3;WQi    + wqi] ;  0.075 mrem where:
    Q = The projected release over the next 7 days of radionuciides,
          1, in gaseous effluents for long term releases (greater than
          500. hrslyrL, in ICi .
    q    The projected release over the next 7 days of radionuclides,
          1, ingaseous effluents for short term releases (equal to or less than 50Q hrs/yrl, in pCi.
 
and.all other terms are defined inSpecifications 3.11.2.2 and
    3.11.2.3.
 
PWR-STS-I                              3/4 11-31
 
RADIOACTIVE EFFLUENTS
EXPLOSIVE GAS MIXTURE (Systems designed to withstand a hydrogen explosion)
LIMITING CONDITION FOR OPERATION
3.11.2.5 The concentration of (hydrogen or oxygen) in the waste gas holdup system shall be limited to < 4% by volume.
 
APPLICABILITY:    At all times.


The dose contributions shall be calculated for all radionuclides in gaseous effluents projected to be released to unrestricted areas during any projected
ACTION:
7 day period using the following expressions:
      a.   With the concentration of (hydrogen or oxygen) in the waste gas holdup system exceeding the limit, restore the concentration to within the limit within 48 hours.
For noble gases, the gamma radiation:
3.17 x 10 z M 1 [(x-7) Qi + (V74) qa c Q0.O5 mrad, and i For noble gases, the beta radiation:
3.17 x 100 8E N 1 &#xa3;ii7 Q 1 + (x70) qi] < 0.10 Brad, and i For radioiodines, radioactive materials in particulate form and radionuclides other than nokle gases: 3.17 x 10- z R 1 &#xa3;WQi + wqi] ; 0.075 mrem where: Q = The projected release over the next 7 days of radionuciides, 1, in gaseous effluents for long term releases (greater than 500. hrslyrL, in ICi .q The projected release over the next 7 days of radionuclides, 1, in gaseous effluents for short term releases (equal to or less than 50Q hrs/yrl, in pCi.and. all other terms are defined in Specifications
3.11.2.2 and 3.11.2.3.PWR-STS-I 3/4 11-31 RADIOACTIVE
EFFLUENTS EXPLOSIVE
GAS MIXTURE (Systems designed to withstand a hydrogen explosion)
LIMITING CONDITION
FOR OPERATION 3.11.2.5 The concentration of (hydrogen or oxygen) in the waste gas holdup system shall be limited to < 4% by volume.APPLICABILITY:
At all times.ACTION: a. With the concentration of (hydrogen or oxygen)gas holdup system exceeding the limit, restore to within the limit within 48 hours.in the waste the concentration b. The provisions of Specifications
3.0.3 and 3.0.4 are not applicable.


SURVEILLANCE
b.   The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
REQUIREMENTS
4.11.2.5 The concentration of (hydrogen or oxygen) in the waste gas holdup system shall be determined to be within the above limits by con-tinuously monitoring the waste gases in the waste gas holdup system with the (hydrogen or oxygen) monitors required OPERABLE by Table 3.3-12 of Specification
3.3.3.9.PWR-STS-I 3/4 11- 32 RADIOACTIVE
EFFLUENTS EXPLOSIVE
GAS MIXTURE (Systems not designed to withstand a hydrogen explosion)
LIMITING CONDITION
FOR OPERATION 3.11.2.5A
The concentration of (hydrogen and/or oxygen) in the waste gas holdup system shall be limited to < 2% by volume.APPLICABILITY:
At all times.ACTION: a. With the concentration of (hydrogen and/or oxygen) in the waste gas holdup system > 2% by volume but < 4% by volume, restore the concentration of (hydrogen and/orhoxygen)
to within the limit within 48 hours.b. With the concentration of (hydr'ogen and/or oxygen) in the waste gas holdup system > 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concen-tration of (hydrogen and/or oxygen) to < 2% within 48 hours.c. The provisions of Specifications  
3.0.3 and 3.0.4 are not applicable.


SURVEILLANCE  
SURVEILLANCE REQUIREMENTS
REQUIREMENTS
4.11.2.5 The concentration of (hydrogen or oxygen) in the waste gas holdup system shall be determined to be within the above limits by con- tinuously monitoring the waste gases in the waste gas holdup system with the (hydrogen or oxygen) monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.
4.11.2.5A
The concentrations of (hydrogen and/or oxygen) in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the (hydrogen and/or oxygen) monitors required OPERABLE by Table 3.3-12 of Specification  
3.3.3.9.IPWR-STS-I
3/4 11-33 RADIOACTIVE
EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION
FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to < -curies noble gases (considered as Xe-133).APPLICABILITY:
At all times.ACTION: a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification
6.9.1.12.


The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.b. The provisions of Specifications
PWR-STS-I                          3/4 11- 32
3.0.3 and 3.0.4 are not applicable.


SURVEILLANCE
RADIOACTIVE EFFLUENTS
REQUIREMENTS
  EXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen explosion)
4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tank.PWR-STS-I 3/4 11-34 RADIOACTIVE
  LIMITING CONDITION FOR OPERATION
EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE
3.11.2.5A The concentration of (hydrogen and/or oxygen) in the waste gas holdup system shall be limited to < 2% by volume.
WASTE LIMITING CONDITION  
FOR OPERATION 3.11.3.1 The solid radwaste system shall be OPERABLE and used, as appli-cable, in accordance with a PROCESS CONTROL PROGRAM, which provides SOLIDIFICATION
of wet solid wastes, to solidify and package radioactive wastes and to meet the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of radioactive wastes from the site.APPLICABILITY:
At all times.ACTION: a. With the requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend shipments of solid radioactive wastes from the site.b. With the solid radwaste system inoperable for more than 72 hours, prepare and submit to the Commission within 30 days pursuant to Specification
6.9.2 a Special Report which includes the following information:
1. Identification of the inoperable equipment, 2. Cause of inoperability, 3. Action(s)
taken to restore the inoperable equipment to OPERABLE status, 4. Length of time the above requirements were not satified.5. A description of alternate equipment used to solidify and package radioactive materials, 6. Type, volume and curie content of waste shipped using alternate equipment, and 7. Action(s)
taken to prevent a recurrence of equipment failures.c. The provisions of Specifications
3.0.3 and 3.0.4 are not applicable.


SURVEILLANCE  
APPLICABILITY:  At all times.
REQUIREMENTS
 
ACTION:
      a.  With the concentration of (hydrogen and/or oxygen) in the waste gas holdup system > 2% by volume but < 4% by volume, restore the concentration of (hydrogen and/orhoxygen) to within the limit within 48 hours.
 
b.  With the concentration of (hydr'ogen and/or oxygen) in the waste gas holdup system > 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concen- tration of (hydrogen and/or oxygen) to < 2% within 48 hours.
 
c.  The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.11.2.5A The concentrations of (hydrogen and/or oxygen) in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the (hydrogen and/or oxygen) monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.
 
IPWR-STS-I                          3/4 11-33
 
RADIOACTIVE EFFLUENTS
GAS STORAGE TANKS
LIMITING CONDITION FOR OPERATION
3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to < -    curies noble gases (considered as Xe-
133).
APPLICABILITY:    At all times.
 
ACTION:
      a.  With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1.12. The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.
 
b.  The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tank.
 
PWR-STS-I                          3/4 11-34
 
RADIOACTIVE EFFLUENTS
3/4.11.3  SOLID RADIOACTIVE WASTE
LIMITING CONDITION FOR OPERATION
3.11.3.1 The solid radwaste system shall be OPERABLE and used, as appli- cable, in accordance with a PROCESS CONTROL PROGRAM, which provides SOLIDIFICATION of wet solid wastes, to solidify and package radioactive wastes and to meet the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of radioactive wastes from the site.
 
APPLICABILITY:  At all times.
 
ACTION:
    a.  With the requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend shipments of solid radioactive wastes from the site.
 
b.  With the solid radwaste system inoperable for more than 72 hours, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
          1.  Identification of the inoperable equipment,
          2.  Cause of inoperability,
          3.  Action(s) taken to restore the inoperable equipment to OPERABLE status,
          4.  Length of time the above requirements were not satified.
 
5.  A description of alternate equipment used to solidify and package radioactive materials,
          6.  Type, volume and curie content of waste shipped using alternate equipment, and
          7.  Action(s) taken to prevent a recurrence of equipment failures.
 
c.  The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 31 days by performing functional tests of the equipment and verifying that the system performs its design functions.
4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 31 days by performing functional tests of the equipment and verifying that the system performs its design functions.


PWR-STS-I 3/4 11-35  
PWR-STS-I                         3/4 11-35
11RADIOACTIVE  
 
EFFLUENTS SURVEILLANCE  
11RADIOACTIVE EFFLUENTS
REQUIREMENTS (Continued)
  SURVEILLANCE REQUIREMENTS (Continued)
4.11.3.1.2 The above required PROCESS CONTROL PROGRAM shall verify SOLIDIFICATION  
  4.11.3.1.2 The above required PROCESS CONTROL PROGRAM shall verify SOLIDIFICATION of at least one representative test specimen obtained from at least every tenth batch of each type of radioactive waste from liquid systems when the test specimens are processed in accordance with the PROCESS CONTROL PROGRAM. If any test specimen falls to verify SOLIDI-
of at least one representative test specimen obtained from at least every tenth batch of each type of radioactive waste from liquid systems when the test specimens are processed in accordance with the PROCESS CONTROL PROGRAM. If any test specimen falls to verify SOLIDI-FICATION, additional waste samples shall be taken from consecutive batches of the same type waste until five consecutive test specimens demonstrate SOLIDIFICATION  
  FICATION, additional waste samples shall be taken from consecutive batches of the same type waste until five consecutive test specimens demonstrate SOLIDIFICATION and the PROCESS CONTROL PROGRAM shall be modified as required.
and the PROCESS CONTROL PROGRAM shall be modified as required.4.11.3.1.3 Reports -The semiannual Radioactive Effluent Release Report shall includ-ethIefollowing information for each type of solid waste shipped offsite during the report period: a. container burial volume, b. total curie quantity (determined by measurement or estimate), c. principal gamma radionuclides (determined by measurement or estimate), d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms), e. type of container (e.g., LSA, Type A, Type S, Large Quantity), and f. solidification agent (e.g., cement, urea formaldehyde).
 
PWR-STS-I 3/4 11-36  
4.11.3.1.3 Reports - The semiannual Radioactive Effluent Release Report shall includ-ethIefollowing information for each type of solid waste shipped offsite during the report period:
\ J 3/4.12 RADIOLOGICAL  
        a.   container burial volume, b.   total curie quantity (determined by measurement or estimate),
ENVIRONMENTAL  
        c.   principal gamma radionuclides (determined by measurement or estimate),
MONITORING
        d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
3/4.12.1 MONITORING  
        e.   type of container (e.g., LSA, Type A, Type S, Large Quantity),
PROGRAM LIMITING CONDITION  
            and f.   solidification agent (e.g., cement, urea formaldehyde).
FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.APPLICABILITY:  
  PWR-STS-I                           3/4 11-36
At all times.ACTION: a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
 
\ J
    3/4.12   RADIOLOGICAL ENVIRONMENTAL MONITORING
    3/4.12.1   MONITORING PROGRAM
    LIMITING CONDITION FOR OPERATION
    3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.
 
APPLICABILITY:   At all times.
 
ACTION:
        a.   With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
 
b.    With the level of radioactivity in an-environmental sampling medium at one or more of the locations specified in Table
              3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radio- logical Environmental Operating Report.
 
c.    With milk or fresh leafy vegetable samples unavailable from any of the sample locations required by Table 3.12-1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from Table 3.12-1 and Figure 3.12-1 provided the locations from which the replace- ment samples were obtained are added to the environmental monitoring program as replacement locations.
 
d.    The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
PWR-STS- I                          314 12-1
 
RADIOLOGICAL ENVIRONMENTAL MONITORING
  SURVEILLANCE REQUIREMENTS
  4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations shown on Figure 3.12-1 and shall be analyzed pursuant to the requirements of Tables 3.12-1 and
  4.12-1.
 
4.12.1.2 Reports - The results of analyses performed on the radio- logical environmental monitoring samples shall be summarized in the Annual Radiological Environmental Operating Report.
 
K>
  PWR-STS-                            3 12-2
                                      3/4
 
I'
                                                                                                          (
                                                  TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
-o CA
-4 CA                            Number of Samples Exposure Pathway                and                      Sampling and            Type and Frequency and/or Sample          Sample Locations**          Collection Frequency          of Analysis
    1. AIRBORNE
          a. Radiolodine and Particulates (Locations 1-5)            Continuous operation of    Radioiodine canister.    (
                                                            sampler with sample col-    Analyze at least once lection as required by      per 7 days for 1-131.
 
dust loading but at least once per 7 days.            Particulate sampler.
 
Analyze for gross beta radioactivity > 24 hours following filter change.
 
Perform gamma isotopic    A
                                                                                        analysis on each sample f1%.
4.J
                                                                                        when gross beta activity is >'10 times the mean of control samples for any medium. Perform gamma isotopic analysis on composite (by location)
                                                                                        sample at least once per 92 days.
 
2. DIRECT RADIATION        (Locations 1-8)            At least once per 31 days.  Gamma dose. At least
                                > 2 dosimeters or > 1                                  once per 31 days.
 
Tnstrument for con-                or                        or tinuously measuring        At least once per 92 days.  Gamma dose. At least and recording dose          (Read-out frequencies are  once per 92 days.
 
rate at each                determined by type of dosi- location.                  meters selected.)
    **  Sample locations are shown on Figure 3.12-1.
 
C                                                                                                        (
                                            TABLE 3.12-1 (Continued)
-o                                RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
-In                          Number of Samples (A0
I-.  Exposure Pathway                and                      Sampling and                Type and Frequency and/or Sample          Sample Locations**          Collection Frequency                of Analysis
      3. WATERBORNE
          a. Surface            (Locations 9 and 10)        Composite* sample collected    Gamma isotopic analysis (
                                                            over a period of < 31 days.    of each composite sample.
 
Tritium analysis of com- posite sample at least once per 92 days.
 
b. Ground            (Locations 11 and 12)      At least once per 92 days.      -Gamma isotopic and tritium analyses of each sample.
 
c. Drinking          (Locations 13-15)          Composite* sample collected      1-131 analysis over a period of < 14 days,    of each composite sample;
                                                            if 1-131 analysis is performed; or                              and Composite* sample collected    Gross beta and gamma over a period of  _ 31 days.    isotopic analysis of each composite sample. (
                                                                                            Tritium analysis of composite sample at least once per 92 days.
 
d, Sediment from      (Locations 181              At least once per 184 days.      Gamma isotopic analysis Shoreline                                                                  of each sample.
 
* Composite samples shall -be collected by collecting an aliquot at Intervals not exceeding 2 hours.
 
**Sample locations are shown on Figure 3.12-1.
 
(                                                  C                                                  (
                                            TABLE 3.12-1 (Continued)
                                  RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
CAI
-i (A
                              Number of Samples Exposure Pathway              and                        Sampling and              Type and Frequency and/or Sample          Sample Locations**          Collection Frequency              of Analysis
      4. INGESTION
          a. Milk              (Locations 17-20)          At least once per 15 days      Gamma isotopic and      (
                                                          when animals are on pasture;  I-131 analysis at least once per 31 days      of each sample.
 
at other times.
 
b. Fish and          (Locations 21 and 22)      One sample in season, or at    Gamma isotopic analysis Invertebrates                              least once per 184 days if    on edible portions.
 
not seasonal. One sample of W
1.g~                                                      each of the following species:
-J
in                                                        2.
 
c. Food Products      (Locations 23-25)          At time of harvest. One        Gamma isotopic analysis sample of each of the fol-    on edible portion.
 
lowing classes of food products:
                                                                                                                  (
                                                            1.
 
2.


b. With the level of radioactivity in an-environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded.
3.


This report is not required if the measured level of radioactivity was not the result of plant effluents;
(Location 26)              At time of harvest. One        1-131 analysis.
however, in such an event, the condition shall be reported and described in the Annual Radio-logical Environmental Operating Report.c. With milk or fresh leafy vegetable samples unavailable from any of the sample locations required by Table 3.12-1, prepare and submit to the Commission within 30 days, pursuant to Specification
6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from Table 3.12-1 and Figure 3.12-1 provided the locations from which the replace-ment samples were obtained are added to the environmental monitoring program as replacement locations.


d. The provisions of Specifications
sample of broad leaf vegetation.
3.0.3 and 3.0.4 are not applicable.


PWR-STS- I 314 12-1 RADIOLOGICAL
**Sample locations are shown on Figure 3.12-1.
ENVIRONMENTAL
MONITORING
SURVEILLANCE
REQUIREMENTS
4.12.1.1 collected and shall 4.12-1.The radiological environmental monitoring samples shall be pursuant to Table 3.12-1 from the locations shown on Figure 3.12-1 be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12.1.2 Reports -The results of analyses performed on the radio-logical environmental monitoring samples shall be summarized in the Annual Radiological Environmental Operating Report.K>PWR-STS- 3 3/4 12-2 I'TABLE 3.12-1 RADIOLOGICAL
ENVIRONMENTAL
MONITORING
PROGRAM (-o CA-4 CA Exposure Pathway and/or Sample Number of Samples and Sample Locations**
Sampling and Collection Frequency Type and Frequency of Analysis 1. AIRBORNE a. Radiolodine and Particulates (Locations
1-5)(Continuous operation of sampler with sample col-lection as required by dust loading but at least once per 7 days.Radioiodine canister.Analyze at least once per 7 days for 1-131.f1%.4.J Particulate sampler.Analyze for gross beta radioactivity
> 24 hours following filter change.Perform gamma isotopic analysis on each sample when gross beta activity is >' 10 times the mean of control samples for any medium. Perform gamma isotopic analysis on composite (by location)sample at least once per 92 days.A 2. DIRECT RADIATION (Locations
1-8)> 2 dosimeters or > 1 Tnstrument for con-tinuously measuring and recording dose rate at each location.At least once per 31 days.or At least once per 92 days.(Read-out frequencies are determined by type of dosi-meters selected.)
Gamma dose.once per 31 or Gamma dose.once per 92 At least days.At least days.** Sample locations are shown on Figure 3.12-1.


C (TABLE 3.12-1 (Continued)
Figure 3.12-1 Radiological Environmental Monitoring Sample Locations PWR-STS-I                          3/4 12-6
RADIOLOGICAL
ENVIRONMENTAL
MONITORING
PROGRAM-o-In (A0 I-.Exposure Pathway and/or Sample Number of Samples and Sample Locations**
Sampling and Collection Frequency Type and Frequency of Analysis 3. WATERBORNE
a. Surface b. Ground c. Drinking (Locations
9 and 10)(Locations
11 and 12)(Locations
13-15)Composite*
sample collected over a period of < 31 days.At least once per 92 days.Composite*
sample collected over a period of < 14 days, if 1-131 analysis is performed;
or Gamma isotopic analysis (of each composite sample.Tritium analysis of com-posite sample at least once per 92 days.-Gamma isotopic and tritium analyses of each sample.1-131 analysis of each composite sample;and Composite*
sample collected over a period of _ 31 days.Gross beta and gamma isotopic analysis of each composite sample. (Tritium analysis of composite sample at least once per 92 days.d, Sediment from Shoreline (Locations
181 At least once per 184 days.Gamma isotopic analysis of each sample.* Composite samples shall -be collected by collecting
**Sample locations are shown on Figure 3.12-1.an aliquot at Intervals not exceeding
2 hours.


(C (TABLE 3.12-1 (Continued)
(                                                     (                                                 (
RADIOLOGICAL
                                                    TABLE 4.12-1
ENVIRONMENTAL
-o MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a
MONITORING
--I                                9*                        -            w          -                -
PROGRAM CAI-i (A Exposure Pathway and/or Sample Number of Samples and Sample Locations**
(A
Sampling and Collection Frequency Type and Frequency of Analysis 4. INGESTION a. Milk (Locations
                                      Airborne Particulate Water                or Gas              Fish        Milk      Food Products    Sediment Analysis        (pCi/I)              (pci/m )          (pCi/kgwet)    (pCi/i)    (pCi/kg,wet)    (pCi/kg, dry:
17-20)At least once per 15 days when animals are on pasture;at least once per 31 days at other times.Gamma isotopic and (I-131 analysis of each sample.b. Fish and Invertebrates (Locations
                  -,              t                        t gross beta          2b              1 X 10-2
21 and 22)One sample in season, or at least once per 184 days if not seasonal.
      3H              330
      54Mn            15                                        130
      59 Fe
                        30                                        260
      5 8 ,6 0 Co
                        15                                         130
Ca~
      6 5 Zn
-. 8
                        30                                        260
      95 Zr-Nb
                        10
      1311                0. 5c
                                            7 X 10-2                          0.8c          2 5 c,d
      134,137cs        15                  1 X 10-2              130          15          80                    (
      140 Ba-La        15                                                      15
                        -          i                      a            a    --  a                a


One sample of each of the following species: Gamma isotopic analysis on edible portions.W 1.g~-J in 2.c. Food Products (Locations
TABLE 4.12-1 (Continued)
23-25)At time of harvest. One sample of each of the fol-lowing classes of food products: Gamma isotopic analysis on edible portion.(1.2.3.(Location
                                  TABLE NOTATION
26)At time of harvest.sample of broad leaf vegetation.
    a    -     The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding its presence.


One 1-131 analysis.**Sample locations are shown on Figure 3.12-1.
For a particular measurement system (which may include radio- chemical separation):
                    LLD                    4.66 sb E 
* V  *   2.22
* Y    *  exp(-Xat)
              where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
                    Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appro- priate Cas counts per minute)
                    E is the counting efficiency (as counts per transformation)
                    V is the sample size (in units of mass or volume)
                    2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable A is the radioactive decay constant for the particular radi.onuclide at is the elapsed time between sample collection and analysts The value of sb used in the calculation of the LLD for a detection systemnishall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate} rather than on an unverifted      theoretically predicted  variance.    In calculating  the LLD  for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present inthe samples (e.g., potassium-40 in milk samples).
' v PWR-STS-I                              3/4 12-8


Figure 3.12-1 Radiological Environmental Monitoring Sample Locations PWR-STS-I
TABLE 4.12-1 (Continued)
3/4 12-6
                            TABLE NOTATION
(((-o--I (A TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a 9* -w --Analysis Water (pCi/I)Airborne Particulate or Gas (pci/m )Fish (pCi/kgwet)
b    -   LLD for drinking water.
Milk (pCi/i)Food Products (pCi/kg,wet)
Sediment (pCi/kg, dry:-, t t Ca~-.8 gross beta 3 H 5 4 Mn 5 9 Fe 5 8 , 6 0 Co 6 5 Zn 9 5 Zr-Nb 1311 134,137cs 1 40 Ba-La 2b 330 15 30 15 30 10 0. 5 c 15 15 1 X 10-2 7 X 10-2 1 X 10-2 130 260 130 260 130 (0.8c 15 1 5 2 5 c,d 80-i a a -- a a TABLE 4.12-1 (Continued)
TABLE NOTATION a -The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding its presence.For a particular measurement system (which may include radio-chemical separation):
LLD 4.66 sb E
* V
* 2.22
* Y
* exp(-Xat)where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appro-priate Cas counts per minute)E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume)2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable A is the radioactive decay constant for the particular radi.onuclide at is the elapsed time between sample collection and analysts The value of sb used in the calculation of the LLD for a detection systemnishall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate}
rather than on an unverifted theoretically predicted variance.


In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40
c   -   LLDs for 1-131 in water, milk and other food products correspond to one-quarter of the Appendix I (10 CFR Part 50) design objec- tive dose-equivalent of 15 mrem/year for atmospheric releases and
in milk samples).' v PWR-STS-I 3/4 12-8 TABLE 4.12-1 (Continued)
          10 mrem/year for liquid releases to the most sensitive organ and individual using the assumptions given in Regulatory Guide
TABLE NOTATION b -LLD for drinking water.c -LLDs for 1-131 in water, milk and other food products correspond to one-quarter of the Appendix I (10 CFR Part 50) design objec-tive dose-equivalent of 15 mrem/year for atmospheric releases and 10 mrem/year for liquid releases to the most sensitive organ and individual using the assumptions given in Regulatory Guide 1.109.d -LLD for leafy vegetables.
          1.109.


PWR-STS-I 3/4 12-9 IRADIOLOGICAL
d    -   LLD for leafy vegetables.
ENVIRONMENTAL
MONITORING
3/4.12.2 LAND USE CENSUS LIMITING CONDITION
FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. (For elevated releases as defined in Regulatory Guide 1.111, March 1976. The land use census shall also identify the loca-tions of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)APPLICABILITY:
At all times.ACTION: a. With a land use census identifying a location(s)
which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification
4.11.2.3.1, prepare and submit to the Commission within 30 days, pursuant to Specification
6.9.2, a Special Report which identifies the new location(s).
b. With a land use census identifying a location(s)
which yields a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification
3.12.1, prepare and submit to the Commission within 30 days, pursuant to Specification
6.9.2, a Special Report which identifies the new location.


The new location shall be added to the radiological environmental monitoring program within 30 days.The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.
PWR-STS-I                          3/4 12-9


c. The provisions of Specifications
IRADIOLOGICAL ENVIRONMENTAL MONITORING
3.0.3 and 3.0.4 are not applicable.
3/4.12.2    LAND USE CENSUS
LIMITING CONDITION FOR OPERATION
3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. (For elevated releases as defined in Regulatory Guide
1.111, March 1976. The land use census shall also identify the loca- tions of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)
APPLICABILITY:    At all times.


*Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.PW-T-I / 21 PWR-STS- I 3/4 12-10
ACTION:
IRADIOLOGICAL
      a.    With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location(s).
ENVIRONMENTAL
      b.   With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification
MONITORING
            3.12.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days.
cirDiti AIUrc DcniITDrMMLrTC
JunXc WLLU~nucncu nrln 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.


4.12.2.2 Reports -The results of the land use census shall be included in the Annual Radlological Environmental Operating Report.PWR-STS-I 3/4 12-11 RADIOLOGICAL
The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.
ENVIRONMENTAL
MONITORING
3/4.12.3 CROSSCHECK
PROGRAM LIMITING CONDITION
FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program that are also included in Table 3.12-1.APPLICABILITY:
At all times.ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.b. The provisions of Specifications
3.0.3 and 3.0.4 are not applicable.


SURVEILLANCE
c.   The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
REQUIREMENTS
4.12.3 The results of analyses performed as part of the above required crosscheck program shall be included in the Annual Radiological Environmental Operating Report.PWR-STS- I 3/4 12-12 INSTRUMENTATION
BASES 3/4.3.3.8 RADIOACTIVE
LIQUID EFFLUENT INSTRUMENTATION
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.


The alarm/trip setpoints for these instruments are provided to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.The OPERABILITY
*Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.3/4.3.3.9 RADIOACTIVE
GASEOUS EFFLUENT INSTRUMENTATION
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.


The alarm/trip setpoints for these instruments are provided to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling)
PW-T-I                                /   21 PWR-STS- I                           3/4 12-10
the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY
and use of this instru-mentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.PWR-STS-I B 3/4 3-4
3/4.11 RADIOACTIVE
EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION
This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radio-isotope and its MPC in air (submersion)
was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication
2.3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 5a. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effleunts will be kept "as low as is reasonably achievable".
Also, for fresh water sites with drtnking water supplies which can be potentially effected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculatiohal procedures based on models and data such that the actual exposure of an Individual through appropriate pathways Is unlikely to be substantially underestimated.


The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of radioactive materials in liquid effluents were developed from the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the  
IRADIOLOGICAL ENVIRONMENTAL MONITORING
cirDiti JunXc AIUrc WLLU~nucncu DcniITDrMMLrTC
                          nrln
4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
 
4.12.2.2 Reports - The results of the land use census shall be included in the Annual Radlological Environmental Operating Report.
 
PWR-STS-I                          3/4 12-11
 
RADIOLOGICAL ENVIRONMENTAL MONITORING
3/4.12.3 CROSSCHECK PROGRAM
LIMITING CONDITION FOR OPERATION
3.12.3 Analyses shall be performed on radioactive materials supplied as part of the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program that are also included in Table 3.12-1.
 
APPLICABILITY:  At all times.
 
ACTION:
      a.  With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
 
b.  The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
 
SURVEILLANCE REQUIREMENTS
4.12.3 The results of analyses performed as part of the above required crosscheck program shall be included in the Annual Radiological Environmental Operating Report.
 
PWR-STS- I                          3/4 12-12
 
INSTRUMENTATION
BASES
3/4.3.3.8  RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION
      The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
 
The alarm/trip setpoints for these instruments are provided to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.
 
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10
CFR Part 50.
 
3/4.3.3.9  RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION
      The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments are provided to ensure that the alarm/trip will occur prior to exceeding the limits of 10
CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instru- mentation is consistent with the requirements of General Design Criteria
60, 63 and 64 of Appendix A to 10 CFR Part 50.
 
PWR-STS-I                          B 3/4 3-4
 
3/4.11  RADIOACTIVE EFFLUENTS
BASES
3/4.11.1  LIQUID EFFLUENTS
3/4.11.1.1  CONCENTRATION
      This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in
10 CFR Part 20, Appendix B, Table II. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radio- isotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2.
 
3/4.11.1.2  DOSE
      This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 5a. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexi- bility and at the same time implement the guides set forth in Section IV.A
of Appendix I to assure that the releases of radioactive material in liquid effleunts will be kept "as low as is reasonably achievable". Also, for fresh water sites with drtnking water supplies which can be potentially effected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of
40 CFR 141. The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculatiohal procedures based on models and data such that the actual exposure of an Individual through appropriate pathways Is unlikely to be substantially underestimated. The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of radioactive materials in liquid effluents were developed from the methodology provided in Regulatory Guide 1.109,
"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the  


==Purpose==
==Purpose==
of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113,"Estimating Aquatic Dispersion of Effluents from Accidental and Routine 1eactor Releases for the  
of Evaluating Compliance with 10 CFR Part 50,
Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113,
"Estimating Aquatic Dispersion of Effluents from Accidental and Routine
1eactor Releases for the  


==Purpose==
==Purpose==
of Implementing Appendix I," April 1977.PWR-STS-I B 3/4 11-1 RADIOACTIVE  
of Implementing Appendix I," April
EFFLUENTS BASES This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.The OPERABILITY  
1977.
of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
 
PWR-STS-I                           B 3/4 11-1
 
RADIOACTIVE EFFLUENTS
BASES
      This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
 
The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assur- ance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification imple- ments the requirements of 10 CFR Part 50.36a, General Design Criterion 60
of Appendix A to 10 CFR Part 50 and the design objectives of Appendix I
to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I,
10 CFR Part 50, for liquid effluents.
 
3/4.11.1.4  LIQUID HOLDUP TANKS
      Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting dose or dose commitment to an individual in an unrestricted area will not exceed 0.5 rem.


The requirement that the appropriate portions of this system be used when specified provides assur-ance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".
3/4.11.2 GASEOUS EFFLUENTS
This specification imple-ments the requirements of 10 CFR Part 50.36a, General Design Criterion
3/4.11.2.1  DOSE
60 of Appendix A to 10 CFR Part 50 and the design objectives of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
      This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with the concentrations of
10 CFR Part 20, Appendix B, Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual either within or outside the.


3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting dose or dose commitment to an individual in an unrestricted area will not exceed 0.5 rem.3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual either within or outside the.unrestricted boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 CIO CFR Part 20.106(b)l.
unrestricted boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 CIO CFR
Part 20.106(b)l. For individuals who may at times be within the unrestricted boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the nearest unrestricted area. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose PWR-STS-I                          B 3/4 11-2


For individuals who may at times be within the unrestricted boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the nearest unrestricted area. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose PWR-STS-I B 3/4 11-2 RADIOACTIVE  
RADIOACTIVE EFFLUENTS
EFFLUENTS BASES rates.:above.background to an individual at or beyond the unrestricted boundary to < (500) mrem/ year to the total body or to < (3000) mrem/year to the skin. These release rate limits also restrict, it all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 15Q0 mrem/year for the nearest cow to the plant.This specification applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".
BASES
The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
rates.:above.background to an individual at or beyond the unrestricted boundary to < (500) mrem/ year to the total body or to < (3000) mrem/year to the skin. These release rate limits also restrict, it all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 15Q0 mrem/year for the nearest cow to the plant.


The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the  
This specification applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
 
3/4.11.2.2  DOSE, NOBLE GASES
      This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B
of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided in Regulatory Guide 1.109,
"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the  


==Purpose==
==Purpose==
of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dilspersl.on of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revtsion 1, July 1977. The specified equations provide for determining the air doses at the unrestricted area boundary based upon the historical average atmospheric conditions.
of Evaluating Compliance with 10 CFR Part 50,
Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dilspersl.on of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revtsion 1, July
1977. The specified equations provide for determining the air doses at the unrestricted area boundary based upon the historical average atmospheric conditions.


3/4.11.2.3 DOSE, RADIOIODINES, RADIOACTIVE  
3/4.11.2.3 DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM
MATERIAL IN PARTICULATE  
AND RADIONUCLIDES OTHER THAN NOBLE GASES
FORM AND RADIONUCLIDES  
      This specification is provided to Implement the requirements of Sections II.C, III.A and IV.A of Appenditx 1, 10 CFR Part 50. The Limiting PWR-STS-I                           B 3/4 11-3
OTHER THAN NOBLE GASES This specification is provided to Implement the requirements of Sections II.C, III.A and IV.A of Appenditx  
1, 10 CFR Part 50. The Limiting PWR-STS-I B 3/4 11-3 RADIOACTIVE
EFFLUENTS BASES Condition for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".
The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.


The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of the subject materials were also developed using the methodology provided in Regulatory Guide 1.10%, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the  
RADIOACTIVE EFFLUENTS
BASES
Condition for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexi- bility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".
The Surveillance Requirements implement the requirements in Section III.A        by of Appendix I that conformance with the guides of Appendix I be shown calculational procedures based on models    and  data  such  that  the  actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of the subject materials were also developed using the methodologyto Man provided in Regulatory Guide 1.10%, "Calculation of Annual Doses from Routine Releases of Reactor Effluents for the  


==Purpose==
==Purpose==
of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. As with the equations used in Specification  
of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric         Transport and Dispersion of Gaseous Effluents in Routine Releases       from Light- Water-Cooled Reactors," Revision 1, July 1977. As with the equations used in Specification 4.2.2.2.1, these equations also provide for           determining the actual doses based upon the historical     average   atmospheric   conditions.
4.2.2.2.1, these equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
 
The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.
 
The pathways which were examined in the development of these specifications deposition were: 12 individual inhalation of airborne radionuclides, 21 consumption of radionuclides  onto green leafy  vegetation  with  subsequent by man, 3) deposition onto grassy areas where mtilk animals and meat producing animals graze with consumption of the mtlk and meat by man, and 41 deposition on the ground with subsequent exposure of man.
 
3/4.11.2.4 GASEOUS WASTE TREATMENT
      The OPERABILITY of the gaseous radwaste treatment system ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the      reason- appropriate portions of this system be used when specified provides  liquid able assurance that the releases  of  radioactive,  materials  in effluents will be kept "as low as ts reasonably achievable". This Design    specifi- cation implements the requirements    of 10  CFR  Part  50.36a,  General Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the gaseous radwaste treatmentinsystem        were specified as a suttable fraction of the    guide  set  forth    Sections    II.B
and II.C of Appendix I, l0 CFR Part 5Q, for      gaseous  effluents.
 
PWR-STS-I                            B 3/4 11 -4


The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.The pathways which were examined in the development of these specifications were: 12 individual inhalation of airborne radionuclides, 21 deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where mtilk animals and meat producing animals graze with consumption of the mtlk and meat by man, and 41 deposition on the ground with subsequent exposure of man.3/4.11.2.4 GASEOUS WASTE TREATMENT The OPERABILITY
K>  RADIOACTIVE EFFLUENTS
of the gaseous radwaste treatment system ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.
    BASES
    3/4.11.2.5 EXPLOSIVE GAS MIXTURE
          This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.


The requirement that the appropriate portions of this system be used when specified provides reason-able assurance that the releases of radioactive, materials in liquid effluents will be kept "as low as ts reasonably achievable".
(Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.
This specifi-cation implements the requirements of 10 CFR Part 50.36a, General Design Criterion
60 of Appendix A to 10 CFR Part 50, and the design objectives of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the gaseous radwaste treatment system were specified as a suttable fraction of the guide set forth in Sections II.B and II.C of Appendix I, l0 CFR Part 5Q, for gaseous effluents.


PWR-STS-I B 3/4 11 -4 K>RADIOACTIVE
These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.)
EFFLUENTS BASES 3/4.11.2.5 EXPLOSIVE
    Maintaining the concentration of hydrogen and oxygen below their flam- mability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.(Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.)Maintaining the concentration of hydrogen and oxygen below their flam-mability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion  
60 of Appendix A to 10 CFR Part 50.3/4.11.2.6 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure".3/4.11.3 SOLID RADIOACTIVE
WASTE The OPERABILITY
of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a and General Design Criteria 60 of Appendix A to 10 CFR Part 50. The process parameters included in establish- ing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/lIquid/solIdification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.PWR-STS-I B 3/4 11-5
3/4.12 RADIOLOGICAL
ENVIRONMENTAL
MONITORING
BASES 3/4.12.1 MONITORING
PROGRAM The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation.


This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measur-able concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
3/4.11.2.6  GAS STORAGE TANKS
        Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.


The initially specified monitoring program will be effective for at least the first three years of commercial operation.
This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure".
  3/4.11.3    SOLID RADIOACTIVE WASTE
        The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a and General Design Criteria 60 of Appendix A to 10 CFR Part 50. The process parameters included in establish- ing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/lIquid/solIdification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.


Following this period, program changes may be initiated based on operational experience.
PWR-STS-I                          B 3/4 11-5


The detection capabilities required by Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories.
3/4.12  RADIOLOGICAL ENVIRONMENTAL MONITORING
BASES
3/4.12.1  MONITORING PROGRAM
      The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measur- able concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.


The specified lower limits of detection for 1-131 in water, milk and other food products correspond to approximately one-quarter of the Appendix I to 10 CFR Part 50 design objective dose-equivalent of 15 mrem/year for atmospheric releases and 10 mrem/year for liquid releases to the most sensitive organ and individual.
The detection capabilities required by Table 4.12-1 are state- of-the-art for routine environmental measurements in industrial laboratories.


They are based on the assumptions given in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the  
The specified lower limits of detection for 1-131 in water, milk and other food products correspond to approximately one-quarter of the Appendix I
to 10 CFR Part 50 design objective dose-equivalent of 15 mrem/year for atmospheric releases and 10 mrem/year for liquid releases to the most sensitive organ and individual. They are based on the assumptions given in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the  


==Purpose==
==Purpose==
of Evaluating Compliance with 10 CFR Part 50, Appendix I," March 1976, except the change for an infant consuming  
of Evaluating Compliance with 10 CFR Part 50, Appendix I," March 1976, except the change for an infant consuming 330 liters/year of drinking water instead of 510 liters/year.
330 liters/year of drinking water instead of 510 liters/year.


3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.PWR-STS-I
3/4.12.2   LAND USE CENSUS
B 3/4 12-1 K>RADIOLOGICAL
      This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.
ENVIRONMENTAL
MONITORING
BASES 3/4.12.3 CROSSCHECK
PROGRAM The requirement for participation in the EPA crosscheck program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.IPWR-STS-1 B 3/4 12-2 PWR-STS- I STANDARD TECHNICAL
SPECIFICATIONS
SECTION 6.0 ADMINISTRATIVE
CONTROLS
I>6.0 ADMINISTRATIVE
CONTROLS 6.1 RESPONSIBILITY
6.1.1 The (Plant Superintendent)
shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.6.2 ORGANIZATION
OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2-2 and: a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.b. At least one licensed Operator shall be in the control room when fuel is in the reactor.c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.e. All CORE ALTERATIONS
shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsi-bilities during this operation.


f. A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include (3)members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
This census satisfies the requirements of Section IV.B.3 of Appendix I
to 10 CFR Part 50. Restricting the census to gardens of greater than
500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.


PWR-STS-I 61 This figure shall show the organizational structure and lines of responsibility for the offsite groups that provide technical and management support for the unit. The organizational arrangement for performance and monitoring Quality Assurance activ-ities should also be indicated.
To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of
2 kg/square meter.
 
PWR-STS-I                           B 3/4 12-1
 
K>
  RADIOLOGICAL ENVIRONMENTAL MONITORING
  BASES
  3/4.12.3 CROSSCHECK PROGRAM
        The requirement for participation in the EPA crosscheck program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
 
IPWR-STS-1                          B 3/4 12-2
 
PWR-STS- I
        STANDARD
TECHNICAL SPECIFICATIONS
      SECTION 6.0
ADMINISTRATIVE CONTROLS
 
I>
    6.0 ADMINISTRATIVE CONTROLS
    6.1  RESPONSIBILITY
    6.1.1 The (Plant Superintendent) shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
 
6.2 ORGANIZATION
  OFFSITE
  6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.
 
UNIT STAFF
  6.2.2 The unit organization shall be as shown on Figure 6.2-2 and:
        a.  Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
 
b.  At least one licensed Operator shall be in the control room when fuel is in the reactor.
 
c.  At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
 
d.  An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
 
e.  All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsi- bilities during this operation.
 
f.  A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include (3)
            members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
 
PWR-STS-I                          61
 
This figure shall show the organizational structure and lines of responsibility for the offsite groups that provide technical and management support for the unit. The organizational arrangement for performance and monitoring Quality Assurance activ- ities should also be indicated.


Figure 6.2-1 OFFSITE ORGANIZATION
Figure 6.2-1 OFFSITE ORGANIZATION
PWR-STS-I 6-2 This figure shall show the organizational structure and lines of responsibility for the unit staff.Positions to be staffed by licensed personnel should be indicated.
PWR-STS-I                           6-2
 
This figure shall show the organizational structure and lines of responsibility for the unit staff.
 
Positions to be staffed by licensed personnel should be indicated.
 
Figure 6.2-2 N.-            UNIT ORGANIZATION
PWR-STS-I                        6-3
 
Ki'
                                  TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION#
          LICENSE                            APPLICABLE MODES
          CATEGORY                1, 2, 3 & 4              5 &6 SOL                            'I                1*
          OL                              2                1 Non-Licensed                    2                1
    *Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE
      ALTERATIONS.
 
#Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
 
PWR-STS-I                          6-4
 
*  A    .        I..V.rTflnt C
ALMINLZI5IKA I lV  W    I UL~a
6.3 UNIT STAFF QUALIFICATIONS
Minimum qualifications for members of the unitreferencing staff may be specified ANSI N18.1-1971 by use of an overall qualification statement                                  Gener- or alternately by specifying individual positionthequalifications.
 
second  method is ally, the first method is preferable; however,    special  qualification  statements adaptable to those        unit  staffs requiring because of a unique organizational structure.
 
exceed the minimum
  6.3.1 Each member of the unit staff shall meet orpositions, except for qualifications of ANSI N18.1-1971 for comparable            or exceed the quali- the (Radiation Protection Manager) who shall meet    1975.


Figure 6.2-2 N.-UNIT ORGANIZATION
fications of Regulatory Guide 1.8, September
PWR-STS-I 6-3 Ki'TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION#
  6.4 TRAINING
LICENSE APPLICABLE
  6.4.1 A retraining and replacement training          program for the unit staff the (position title) and shall be maintained under the direction of recommendations          of Section 5.5 shall meet or exceed the requirements and CFR Part 55.
MODES CATEGORY 1, 2, 3 & 4 5 & 6 SOL 'I 1*OL 2 1 Non-Licensed
2 1*Does not include Reactor Operator ALTERATIONS.


the licensed Senior Reactor Operator or Senior Limited to Fuel Handling, supervising CORE#Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.PWR-STS-I 6-4
of ANSI N18.1-1971 and Appendix "A" of 10
* A .I..V.rTflnt C ALMINLZI5IKA
  6.4.2 A training program for the Fire Brigade          shall be maintained under the direction of the (position title) and        shall meet or exceed the require- ments of Section 27 of the NFPA Code - at1975,      except for Fire Brigade training sessions which shall be held            least once per 92 days.
I lV W I UL~a 6.3 UNIT STAFF QUALIFICATIONS
Minimum qualifications for members of the unit staff may be specified by use of an overall qualification statement referencing ANSI N18.1-1971 or alternately by specifying individual position qualifications.


Gener-ally, the first method is preferable;
6.5 REVIEW AND AUDIT
however, the second method is adaptable to those unit staffs requiring special qualification statements because of a unique organizational structure.
  The method by which independent review and          audit of facility operations is accomplished may take one of      several  forms.  The licensee may either assign this function to an organizational unit     unit separate and independent from the group having responsibility for              operation or may utilize within and outside the a standing committee composed of individuals from licensee's organization.


6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the (Radiation Protection Manager) who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September
Irrespective of the method used, the licensee        shall specify the details review and audit of each functional element provided for the independent specifications.
1975.6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the (position title) and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.6.4.2 A training program for the Fire Brigade shall be the direction of the (position title) and shall meet or ments of Section 27 of the NFPA Code -1975, except for training sessions which shall be held at least once per 6.5 REVIEW AND AUDIT maintained under exceed the require-Fire Brigade 92 days.The method by which independent review and audit of facility operations is accomplished may take one of several forms. The licensee may either assign this function to an organizational unit separate and independent from the group having responsibility for unit operation or may utilize a standing committee composed of individuals from within and outside the licensee's organization.


Irrespective of the method used, the licensee shall specify the details of each functional element provided for the independent review and audit process as illustrated in the following example specifications.
process as illustrated in the following example
    6.5.1  UNIT REVIEW GROUP (URG)
    FUNCTION
    6.5.1.1 The (Unit Review Group) shall function to safety. advise the (Plant Superintendent) on all matters related      to  nuclear PWR-STS-I                                6-5


6.5.1 UNIT REVIEW GROUP (URG)FUNCTION 6.5.1.1 The (Unit Review Group) shall Superintendent)
ADMINISTRATIVE CONTROLS
on all matters related function to advise the (Plant to nuclear safety.PWR-STS-I 6-5 ADMINISTRATIVE  
COMPOSITION
CONTROLS COMPOSITION
6.5.1.2   The (Unit Review Group) shall be composed of the:
6.5.1.2 The (Unit Review Group) shall be composed of the: Chairman: (Plant Superintendent)
      Chairman:                 (Plant Superintendent)
Member: (Operations Supervisor)
      Member:                   (Operations Supervisor)
v Member: (Technical Supervisor)
v     Member:                   (Technical Supervisor)
Member: (Maintenance Supervisor)
      Member:                   (Maintenance Supervisor)
Member: (Plant Instrument and Control Engineer)Member: (Plant Nuclear Engineer)Member: (Health Physicist)
      Member:                   (Plant Instrument and Control Engineer)
      Member:                   (Plant Nuclear Engineer)
      Member:                   (Health Physicist)
ALTERNATES
ALTERNATES
6.5.1.3 All alternate members shall be appointed in writing by the (URG) Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in CURG) activities at any one time.MEETING FREQUENCY 6.5.1.4 The (URG) shall meet at least once per calendar month and as convened by the (URG) Chairman or his designated alternate.
6.5.1.3 All alternate members shall be appointed in writing by the (URG) Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in CURG) activities at any one time.
 
MEETING FREQUENCY
6.5.1.4 The (URG) shall meet at least once per calendar month and as convened by the (URG) Chairman or his designated alternate.


QUORUM 6.5.1.5 The minimum quorum of the (URG) necessary for the performance of the (URG) responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and four members including alternates.
QUORUM
6.5.1.5 The minimum quorum of the (URG) necessary for the performance of the (URG) responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and four members including alternates.


RESPONSIBILITIES
RESPONSIBILITIES
6.5.1.6 The (Unit Review Group) shall be responsible for: a. Review of 1) all procedures required by Specification  
6.5.1.6   The (Unit Review Group) shall be responsible for:
6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the (Plant Superintendent)  
      a.   Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the (Plant Superintendent) to affect nuclear safety.
to affect nuclear safety.b. Review of all proposed tests and experiments that affect nuclear safety.PWR-STS-I 6-6 AnTurTCTDATTvv mPJTDnli nuR1L s &aIF~nn Iu a I. %%#I I W_c. Review of all proposed changes to Appendix "A" Technical Specifications.
 
b.   Review of all proposed tests and experiments that affect nuclear safety.
 
PWR-STS-I                       6-6
 
AnTurTCTDATTvv             mPJTDnli nuR1L s&aIF~nn Iu a I. %%#I I W_
        c.     Review of all proposed changes to Appendix "A" Technical Specifications.
 
d.      Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.
 
e.      Investigation of all violations.of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the (Superintendent of Power Plants) and to the (Company Nuclear Review and Audit Group).
        f.      Review of events requiring 24 hour written notification to the Commission.
 
g.      Review of unit operations to detect potential nuclear safety hazards.
 
h.      Performance of special reviews, investigations or analyses and reports thereon as requested by the (Plant Superintendent) or the (Company Nuclear Review and Audit Group).
        i.      Review of the Security Plan and implementing procedures and shall submit recommended changes to the (Company Nuclear Review and Audit Group).
        J.      Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the (Company Nuclear Review and Audit Group).
AUTHORITY
6.5.1.7 The (Unit Review Group) shall:
        a.      Recommend to the (Plant Superintendent) written approval or disapproval of items considered under 6.5.1.6(a) through (d)
                above.
 
b.      Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
 
c.      Provide written notification within 24 hours to the (Super- intendent of Power Plants) and the (Company Nuclear Review and Audit Group) of disagreement between the (URG) and the (Plant Superintendent); however, the (Plant Superintendent) shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
 
PWR-STS-I                              6-7
 
AnUrTmtrCTDTTWV
rW1ILI'SLaI F~  IL V L
                      rnNTfln
                      %,FeII.
 
4J
RECORDS
6.5.1.8 The (Unit Review Group) shall maintain written minutes of each (URG) meeting that, at a minimum, document the results of all (URG)
activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the (Superintendent of Power Plants) and the (Company Nuclear Review and Audit Group).
6.5.2 COMPANY NUCLEAR REVIEW AND AUDIT GROUP (CNRAG)
FUNCTION
6.5.2.1 The (Company Nuclear Review and Audit Group) shall function to provide independent review and audit of designated activities in the areas of:
        a.    nuclear power plant operations b.    nuclear engineering c.    chemistry and radiochemistry d.    metallurgy e.    instrumentation and control f.    radiological safety g.    mechanical and electrical engineering h.    quality assurance practices i.    (other appropriate fields associated with the unique char- acteristics of the nuclear power plant)
  PWR-STS-I                              6-8
 
ADMINISTRATIVE CONTROLS
COMPOSITION
6.5.2.2  The (CNRAG)  shall be composed of the:
      Director:        Position Title)
      Member:          Position Title)
      Member:          Position Title)
      Member:          Position Title)
      Member:        (Position Title)
ALTERNATES
6.5.2.3 All alternate members shall be appointed in writing by the (CNRAG) Director to serve on a temporary basis; however, no more than two alternates shall participate as voting members in (CNRAG) activities at any one time.
 
CONSULTANTS
6.5.2.4 Consultants shall be utilized as determined by the (CNRAG)
Director to provide expert advice to the (CNRAG).
MEETING FREQUENCY
6.5.2.5 The (CNRAG) shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.
 
QUORUM
6.5.2.6 The minimum quorum of the (CNRAG) necessary for the performance of the (CNRAG) review and audit functions of these technical specifica- tions shall consist of the Director or his designated alternate and (at least 4 CNRAG) members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.
 
PWR-STS- I                          6-9
 
ADMINISTRATIVE CONTROLS
REVIEW
6.5.2.7 The (CNRAG) shall review:
    a.  The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
 
b.  Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section
          50.59, 10 CFR.
 
c.  Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
 
d.  Proposed changes to Technical Specifications or this Operating License.
 
e.  Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
 
f.  Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
 
g.  Events requiring 24 hour written notification to the Commission.
 
h.  All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
 
i.  Reports and meetings minutes of the (Unit Review Group).
PWR-STS-I                          6-10
 
* al y.,  e  &#xa3;lsar i jfnSj  lns e ADJMlNlZbAl  M 1L      oUtI MUL-2 AUDITS
                                                                  the cognizance
6.5.2.8 Audits of unit activities shall be performed under of the (CNRAG). These audits shall encompass:
        a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
 
b.    The performance, training and qualifications of the entire unit staff at least once per 12 months.
 
c.    The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
 
d.      The performance of activities required by the Operational "B",
                Quality Assurance Program to meet the criteria of Appendix
                10 CFR 50, at least once per 24 months.
 
e.      The Emergency Plan and implementing procedures at least once per 24 months.
 
f.      The Security Plan and implementing procedures at least once per 24 months.
 
g.      Any other area of unit operation considered appropriate by the (CNRAG) or the (Vice President Operations).
          h.    The Fire Protection Program and implementing procedures at least once per 24 months.
 
i.    An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
 
J.      An inspection and audit of the fire protection and loss preven- tion program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
 
1.      The radiological environmental monitoring program and the results there of at least once per 12 months.
 
PWR-STS-I                                6-11
 
. -.-..    n a    ,r ihnaTrilr c APUMr4LlRKlAVrL      %u#IIVL4 AUTHORITY
                                                                President
6.5.2.9 The (CNRAG) shall report to and advise the (Vice        Sections Operations) on those areas of responsibility      specified in
6.5.2.7 and 6.5.2.8.
 
RECORDS
                                                                          and
6.5.2.10 Records of (CNRAG) activities shall be prepared, approved distributed as indicated below:
        a.    Minutes of each (CNRAG) meeting shall be prepared, approved and forwarded to the (Vice President-Operations) within 14 days following each meeting.
 
b.    Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the (Vice President- Operations) within 14 days following completion of the review.
 
c.    Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the (Vice President-Operations) and to the management positions responsible for the areas audited within
              30 days after completion of the audit.
 
6.6    REPORTABLE OCCURRENCE ACTION
6.6.1    The following actions shall be taken for REPORTABLE OCCURRENCES:
        a.    The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
 
b.      Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission shall be reviewed by the (URG) and submitted to the (CNRAG) and the (Superintendent of Power Plants).
  PWR-STS-I                              6-12
 
ADMINISTRATIVE CONTROLS
6.7  SAFETY LIMIT VIOLATION
6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
    a.  The unit shall be placed in at least HOT STANDBY within one hour.
 
b.  The Safety Limit violation shall be reported to the Commission, the (Superintendent of Power Plants) and to the (CNRAG) within
          24 hours.
 
c.  A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the (URG). This report shall describe
          (1) applicable circumstances preceding the violation, (2)
          effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
 
d.  The Safety Limit Violation Report shall be submitted to the Commission, the (CNRAG) and the (Superintendent of Power Plants) within 14 days of the violation.
 
6.8  PROCEDURES
6.8.1 Written procedures shall be established, implemented and main- tained covering the activities referenced below:
    a.  The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
 
b.  The radiological environmental monitoring program.
 
c.  Refueling operations.
 
d.  Surveillance and test activities of safety related equipment.


d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.e. Investigation of all violations.of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the (Superintendent of Power Plants) and to the (Company Nuclear Review and Audit Group).f. Review of events requiring
e.   Security Plan implementation.
24 hour written notification to the Commission.


g. Review of unit operations to detect potential nuclear safety hazards.h. Performance of special reviews, investigations or analyses and reports thereon as requested by the (Plant Superintendent)
f.   Emergency Plan implementation.
or the (Company Nuclear Review and Audit Group).i. Review of the Security Plan and implementing procedures and shall submit recommended changes to the (Company Nuclear Review and Audit Group).J. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the (Company Nuclear Review and Audit Group).AUTHORITY 6.5.1.7 The (Unit Review Group) shall: a. Recommend to the (Plant Superintendent)
written approval or disapproval of items considered under 6.5.1.6(a)
through (d)above.b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a)
through (e) above constitutes an unreviewed safety question.c. Provide written notification within 24 hours to the (Super-intendent of Power Plants) and the (Company Nuclear Review and Audit Group) of disagreement between the (URG) and the (Plant Superintendent);
however, the (Plant Superintendent)
shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.PWR-STS-I 6-7 AnUrTmtrCTDTTWV
rnNTfln 4 rW1ILI'SLaI
F~ IL V L %,FeII. J RECORDS 6.5.1.8 The (Unit Review Group) shall maintain written minutes of each (URG) meeting that, at a minimum, document the results of all (URG)activities performed under the responsibility and authority provisions of these technical specifications.


Copies shall be provided to the (Superintendent of Power Plants) and the (Company Nuclear Review and Audit Group).6.5.2 COMPANY NUCLEAR REVIEW AND AUDIT GROUP (CNRAG)FUNCTION 6.5.2.1 The (Company Nuclear Review and Audit Group) shall function to provide independent review and audit of designated activities in the areas of: a. nuclear power plant operations b. nuclear engineering c. chemistry and radiochemistry d. metallurgy e. instrumentation and control f. radiological safety g. mechanical and electrical engineering h. quality assurance practices i. (other appropriate fields associated with the unique char-acteristics of the nuclear power plant)PWR-STS-I 6-8 ADMINISTRATIVE
g.   Fire Protection Program implementation.
CONTROLS COMPOSITION
6.5.2.2 The (CNRAG) shall be composed of the: Director:
Position Title)Member: Position Title)Member: Position Title)Member: Position Title)Member: (Position Title)ALTERNATES
6.5.2.3 All alternate members shall be appointed in writing by the (CNRAG) Director to serve on a temporary basis; however, no more than two alternates shall participate as voting members in (CNRAG) activities at any one time.CONSULTANTS
6.5.2.4 Consultants shall be utilized as determined by the (CNRAG)Director to provide expert advice to the (CNRAG).MEETING FREQUENCY 6.5.2.5 The (CNRAG) shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.


QUORUM 6.5.2.6 The minimum quorum of the (CNRAG) necessary for the performance of the (CNRAG) review and audit functions of these technical specifica- tions shall consist of the Director or his designated alternate and (at least 4 CNRAG) members including alternates.
h.   Offsite releases of gaseous and liquid effluents containing radioactive materials.


No more than a minority of the quorum shall have line responsibility for operation of the facility.PWR-STS- I 6-9 ADMINISTRATIVE
i.   The PROCESS CONTROL PROGRAM for solidification of radioactive waste.
CONTROLS REVIEW 6.5.2.7 The (CNRAG) shall review: a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.d. Proposed changes to Technical Specifications or this Operating License.e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.


f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.g. Events requiring
PWR-STS-I                          6-13
24 hour written notification to the Commission.


h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.i. Reports and meetings minutes of the (Unit Review Group).PWR-STS-I 6-10
*smlrCTAIrTt~r      PMKTOM C
* al ., y &#xa3;l e i sar jfnSj lns e ADJMlNlZbAl M 1L oUtI MUL-2 AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the (CNRAG). These audits shall encompass:
MALJ1llKM1LVC        W111rUL-
a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.b. The performance, training and qualifications of the entire unit staff at least once per 12 months.c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.e. The Emergency Plan and implementing procedures at least once per 24 months.f. The Security Plan and implementing procedures at least once per 24 months.g. Any other area of unit operation considered appropriate by the (CNRAG) or the (Vice President Operations).
                                                changes thereto, shall be
h. The Fire Protection Program and implementing procedures at least once per 24 months.i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.J. An inspection and audit of the fire protection and loss preven-tion program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.1. The radiological environmental monitoring program and the results there of at least once per 12 months.PWR-STS-I 6-11
6.8.2 Each procedure of 6.8.1 above, and (Plant Superintendent) prior reviewed by the (URG) and approved by the           as set forth in administrative to implementation and reviewed periodically procedures.
.-.-.. n a ,r ihnaTrilr c APUMr4LlRKlAVrL
%u#IIVL4 AUTHORITY 6.5.2.9 The (CNRAG) shall report to and advise the (Vice President Operations)
on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.RECORDS 6.5.2.10 Records of (CNRAG) activities shall be prepared, approved and distributed as indicated below: a. Minutes of each (CNRAG) meeting shall be prepared, approved and forwarded to the (Vice President-Operations)
within 14 days following each meeting.b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the (Vice President- Operations)  
within 14 days following completion of the review.c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the (Vice President-Operations)
and to the management positions responsible for the areas audited within 30 days after completion of the audit.6.6 REPORTABLE
OCCURRENCE
ACTION 6.6.1 The following actions shall be taken for REPORTABLE
OCCURRENCES:
a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification
6.9.b. Each REPORTABLE
OCCURRENCE
requiring
24 hour notification to the Commission shall be reviewed by the (URG) and submitted to the (CNRAG) and the (Superintendent of Power Plants).PWR-STS-I 6-12 ADMINISTRATIVE
CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The unit shall be placed in at least HOT STANDBY within one hour.b. The Safety Limit violation shall be reported to the Commission, the (Superintendent of Power Plants) and to the (CNRAG) within 24 hours.c. A Safety Limit Violation Report shall be prepared.


The report shall be reviewed by the (URG). This report shall describe (1) applicable circumstances preceding the violation, (2)effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
above may be made pro-
.6.8.3 Temporary changes to procedures of 6.8.1 vided:
                                                        is not altered.


d. The Safety Limit Violation Report shall be submitted to the Commission, the (CNRAG) and the (Superintendent of Power Plants) within 14 days of the violation.
a. The intent of the original procedure of the plant management b. The change is approved by two members    Senior  Reactor Operator's staff, at least one of whom holds  a License on the unit affected.


6.8 PROCEDURES
the (URG) and approved by c. The change is documented, reviewed bydays of implementation.
6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below: a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.b. The radiological environmental monitoring program.c. Refueling operations.


d. Surveillance and test activities of safety related equipment.
the (Plant Superintendent) within 14
6.9        REPORTING REQUIREMENTS
ROUTINE REPORTS AND REPORTABLE OCCURRENCES
                                                        requirements of Title 10,
6.9.1 In addition to the applicable reporting    reports  shall be submitted Code of Federal Regulations, the following      Inspection  and Enforcement to the Director of the Regional Office of unless otherwise noted.


e. Security Plan implementation.
STARTUP REPORT
                                                  and power escalation testing
6.9.1.1 A summary report of plant startupof an operating license, (2)
shall be submitted following (1) receipt  planned increase in power level, amendment to the license involving adifferent        design or has been manu-
  (3) installation of fuel that has a              (4)modifications that may factured by a different fuel supplier, and    thermal, or hydraulic perfor- have significantly altered the nuclear, mance of the plant.


f. Emergency Plan implementation.
each of the tests identified in
  6.9.1.2 The startup report shall address of the measured values of the the FSAR and shall include a description obtained during the test program operating conditions or characteristicsdesign predictions and specifica- and a comparison of these values with          required to obtain satisfactory tions. Any corrective actions that were additional specific details operation shall also be described. Any        other commitments shall be in- required in license conditions based on cluded in this report.


g. Fire Protection Program implementation.
PWR-STS-I                              6-14


h. Offsite releases of gaseous and liquid effluents containing radioactive materials.
K>
ADMINISTRATIVE CONTROLS
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.


i. The PROCESS CONTROL PROGRAM for solidification of radioactive waste.PWR-STS-I 6-13
ANNUAL REPORTSY
*smlrCTAIrTt~r PMKTOM C MALJ1llKM1LVC
6.9.1.4 Annual reports covering the activities of the unit as described1 below for the previous calendar year shall be submitted prior to March of each year. The initial report shall be submitted prior to March I of the year following initial criticality.
W111rUL-6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the (URG) and approved by the (Plant Superintendent)
prior to implementation and reviewed periodically as set forth in administrative procedures.


.6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided: a. The intent of the original procedure is not altered.b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.c. The change is documented, reviewed by the (URG) and approved by the (Plant Superintendent)
6.9.1.5  Reports required on an annual basis shall include:
within 14 days of implementation.
      a.   A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions,= e.g.,
            reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
            waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.


6.9 REPORTING
b.   The results of steam generator tube inservice inspections performed during the report period. (CE, W-& B&W units only).
REQUIREMENTS
      c.   The results of the core barrel movement monitoring activities performed during the report period. (CE units only).
ROUTINE REPORTS AND REPORTABLE
      d.    (Any other unit unique reports required on an annual basis.)
OCCURRENCES
  YA single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following
(1) receipt of an operating license, (2)amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica- tions. Any corrective actions that were required to obtain satisfactory operation shall also be described.


Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.PWR-STS-I
This tabulation supplements the requirements of 520.407 of 10 CFR
6-14 K>ADMINISTRATIVE
    Part 20.
CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.


If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
PWR-STS-I                          6-15


ANNUAL REPORTSY 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March I of the year following initial criticality.
ADMINISTRATIVE CONTROLS
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT19
  6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.


6.9.1.5 Reports required on an annual basis shall include: a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors)  
6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveil- lance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions,=
e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.


The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.


Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equip- ment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses required by the Specification 3.12.2; and the results of licensee participation in the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program required by Specification 3.12.3.


b. The results of steam generator tube inservice inspections performed during the report period. (CE, W-& B&W units only).c. The results of the core barrel movement monitoring activities performed during the report period. (CE units only).d. (Any other unit unique reports required on an annual basis.)YA single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.PWR-STS-I 6-15 ADMINISTRATIVE
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-V
CONTROLS ANNUAL RADIOLOGICAL
6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the data of initial criticality.
ENVIRONMENTAL
OPERATING
REPORT 1 9 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.


6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveil-lance reports and an assessment of the observed impacts of the plant operation on the environment.
3/    A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.


The reports shall also include the results of land use censuses required by Specification
)WR-STS- I                          6-16
3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.The reports shall also include the following:
a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equip-ment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses required by the Specification
3.12.2; and the results of licensee participation in the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program required by Specification
3.12.3.SEMIANNUAL
RADIOACTIVE
EFFLUENT RELEASE REPORT-V 6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the data of initial criticality.


3/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.)WR-STS- I 6-16 (TABLE 6.9-1 ENVIRONMENTAL  
(                                                                           TABLE 6.9-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMMARY
RADIOLOGICAL  
* -o                                       -   Nam of Facility                                               Docmet No.__
MONITORING  
                                            Location of Facility                                                 Reporting Period
PROGRAM SUMMARY* -o I n--Nam of Facility Docmet No.__Location of Facility 1County. Staft)Reporting Period-, Y Y V I T Medium or Pathway SaMled (Unit of Measurement)
                                                                                1County. Staft)
Type and Totl Number of Andye Pomed Lower Limit of Detecion ILLD)All Indicator L -eions MRm If)ppb Location wh Highest Annual Mein Ne Distance and Direction Mesn (fib Ranpe ontrol Lons Me (f), Rngb 4 4 I 44 4.C.2 C i-J a-.E w1 Air Particulates (pCi/m 3)Fish pCi/kg (dry weight)Gross p 418 7-Spec. 32.137C.14000 0.003 0.003 0.003 0.002 0.0003 80 89sr 9 0 Sr 7-Spec. 8 137C.40 40 0.081200/312)
    I
(0.05-2.0)
  n-
0.05(4/24)
        -,                             Y                   Y               V                           I                                             T
(0.03.0.13)
                                              Type and        Lower Limit                                                                                                Nurnberof Medium or Pathway           Totl Number             of         All Indicator L -eions           Location wh Highest Annual Mein           ontrol Lons If)                                                                Me(f),   REPORTABLE,,
0.03(2/24)
                      SaMled                of Andye            Detecion              MRm                            Ne                  Mesn (fib (Unit of Measurement)          Pomed              ILLD)
10.01.0.08)
                                                                                            ppb              Distance and Direction                            Rngb       OCCURRENCM
<LLD<LLD<LLD<LLD 120(314)(90.200)Middletown
                                                                                                                                            Ranpe
5 miles 340" Smithvl le 2.5 miles 16 Podunk 4.0 miles 270Q River Mile 35 Podunk River 0.10(5152)
                                                        4   4                                           I                         44                                 4.
(0.082.0)0.08 (2/4)(0.03-0.13)
 
0.05 (2/4)(0.01Q.008)
Air Particulates (pCi/m 3 )           Gross p   418       0.003               0.081200/312)                Middletown            0.10(5152)        0.08(8/104)         I
<LLD<LLD See column 4 0.08(8/104)
                                                                                    (0.05-2.0)                   5 miles 340"            (0.082.0)        (0.05-1.40)
(0.05-1.40)
                                          7-Spec. 32
<LLD 0.02(1/8)<LLD<LLD 9011/4)<LLD<LLD Nurnberof REPORTABLE,, OCCURRENCM
                                              . 137C.
I 4 0&deg;(0 0-0 1 3 4 Cs 60 Co 80 Nominal Lower Limit of Detaction (LLD) as defined in table notation a. of Table 4.12.1 of Specification  
 
4.12.1.1.IIen nd rang based upon detectable measurements only. Fraction of detectable measurements at speflied lecetiona Is Indicated In parentheses.
0.003              0.05(4/24)                   Smithvl le            0.08 (2/4)         <LLD               4 C
          .2                                                                        (0.03.0.13)                 2.5 miles 16           (0.03-0.13)
            C                                  14000
            i                                                    0.003              0.03(2/24)                   Podunk                0.05 (2/4)         0.02(1/8)
                                                                                    10.01.0.08)                  4.0 miles 270Q          (0.01Q.008)
  -J        a                              89sr                                                                                                                                0
      -.                                              40        0.002              <LLD                                                                   <LLD
            E
                                          90
            w1                                Sr        40        0.0003            <LLD                                                                  <LLD                &deg;(
                  Fish pCi/kg (dry weight)     7-Spec. 8
                                                137C.
 
80                <LLD                                                 <LLD             9011/4)             0
                                                134 Cs                              <LLD                                                <LLD             <LLD                 0-
                                                60                                                                                                                              0
                                                    Co           80                 120(314)                    River Mile 35          See column 4      <LLD
                                                                                      (90.200)                    Podunk River Nominal Lower Limit of Detaction (LLD) as defined in table notation a. of Table 4.12.1 of Specification 4.12.1.1.
 
IIen nd rang based upon detectable measurements only. Fraction of detectable measurements at speflied lecetiona Is Indicated In parentheses.


i dNote: The example daft ae provided for Illustrative purposes only.
i dNote: The example daft ae provided for Illustrative purposes only.


ADMINISTRATIVE  
ADMINISTRATIVE CONTROLS
CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.The radioactive effluent release reports shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, with data summarized on a quarterly basis following the format of Appendix B thereof.The radioactive effluent release reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1)during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location)  
6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide
shall be included in these reports.The radioactive effluent release reports shall include the following information for all unplanned offsite releases of radioactive materials in gaseous and liquid effluents:
1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B
a. A description of the event and equipment involved.b. Cause(sl for the unplanned release.c. Actions taken to prevent recurrence.
thereof.
 
The radioactive effluent release reports shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, with data summarized on a quarterly basis following the format of Appendix B thereof.
 
The radioactive effluent release reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1)
during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.
 
The radioactive effluent release reports shall include the following information for all unplanned offsite releases of radioactive materials in gaseous and liquid effluents:
      a.   A description of the event and equipment involved.
 
b.   Cause(sl for the unplanned release.
 
c.   Actions taken to prevent recurrence.
 
d.  Consequences of the unplanned release.
 
The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive ltqutd and gaseous effluents released from the unit during each calendar quarter as outlined in
'Regulatory Gutde 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The meteorological conditions concurrent with the releases of effluents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with NUREG-0133.
 
PWR-STS-I                          6-18
 
ADMINISTRATIVE CONTROLS
MONTHLY REACTOR OPERATING REPORT
6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspec- tion and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
 
REPORTABLE OCCURRENCES
6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
 
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP
6.9.1.12 The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form.
 
Information provided on the licensee event report form shall be supple- mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
 
a.  Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored para- meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
 
b.  Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.
 
c.  Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
 
PWR-STS-I                          6-19
 
ADMINISTRATIVE CONTROLS
      d.    Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN
            less conservative than specified in the technical specifica- tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality.
 
e.    Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR,
      f.    Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require- ments of systems required to cope with accidents analyzed in the SAR.
 
g.    Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by technical specifications.
 
h.    Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
 
i.    Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica- tions bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or cor- rective measures to prevent the existence or development of an unsafe condition.
 
J.    Occurrence of an unusual or important event that causes a significant environmental impact, that affects potential environmental impact from unit operation, or that has high public or potential public interest concerning environmental impact from unit operation.
 
k.    Occurrence of radioactive material contained in liquid or gaseous holdup tanks in excess of that permitted by the limiting condi- tion for operation established in the technical specifications.
 
PWR-STS- I                            6-20
 
ADMINISTRATIVE CONTROLS
THIRTY DAY WRITTEN REPORTS
6.9.1.13 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
 
a.  Reactor protection system or engineered safety feature instru- ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
 
b.  Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re- quired by a limiting condition for operation.
 
c.  Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
 
d.  Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.
 
e.  An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than
          150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:
          1.  A description of the event and equipment involved.
 
2.  Cause(s) for the unplanned release.
 
3.  Actions taken to prevent recurrence.
 
4.  Consequences of the unplanned release.
 
PWR-STS-I                          6-21
 
ADMINISTRATIVE CONTROLS
      f.  Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 6.9-2 when averaged over any calendar quarter sampling period. When more than one of the radionuclides in Table 6.9-2 are detected in the sampling medium, this report shall be submitted if:
                concentration j1) +      concentration (2) + .... >1.0
                iMIT level (1)          limit Tevel (2)
          When radionuclides other than those in Table 6.9-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifica- tions 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
 
SPECIAL REPORTS
Special reports may be required covering inspections, test and main- tenance activities. These special reports are determined on an indi- vidual basis for each unit and their preparation and submittal are designated in the Technical Specifications.
 
6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.
 
PWR-STS-I                          6-22
 
(  'N
                                                    C
                                                TABLE 6.9-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES
(nI
-4 (A
                                              Reporting Levels
                                                        *9              -
    Analysis
              4 Water
                              .9 Airborne Particulate or Gases (pCI/M 3)
                                                        4 Fish (pCi/Kg, wet)
                                                                          4 Milk (pC/l)
                                                                                          4 Vegetables (pCi/Kg, wet)    1 H-3      3 x 104 Mn-54    1 x 103                                    3 x 104 Fe-59    4 x 102                                    1 x 104 Co-58    1 x 103                                    3 x 104 cm    Co-60    3 x 102                                    1 x 104 Zn-65    3 x 102                                    2 x 104 Zr-Nb-95    4 x 102
        1-131        2                0.9                                        3          I x 102 Cs-134      30                10                    1 x 103            60          1 x 103 Cs-137      50                20                    2 x 103            70          2 x 103 Ba-La-l 40  2
                2xx 102 to2                                                      3x
                                                                              3 x 10
                                                                                  102 I                                          1              4
 
&tRv&,*P-rnATriUD rnuirnn c AU~llr      lllVCr~AIiIEUL0
6.10 RECORD RETENTION
In addition to the applicable record retention requirements of Title 10,
Code of Federal Regulations, the following records shall be retained for at least the minimum period.indicated.
 
6.10.1    The following records shall be retained for at least five years:
      a.    Records and logs of unit operation covering time interval at each power level.
 
b.    Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
 
c.    ALL REPORTABLE OCCURRENCES submitted to the Commission.


d. Consequences of the unplanned release.The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive ltqutd and gaseous effluents released from the unit during each calendar quarter as outlined in'Regulatory Gutde 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated.
d.   Records of surveillance activities, inspections and calibrations required by these Technical Specifications.


The meteorological conditions concurrent with the releases of effluents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with NUREG-0133.
e.    Records of changes made to the procedures required by Specifica- tion 6.8.1.


PWR-STS-I 6-18 ADMINISTRATIVE
f.   Records of radioactive shipments.
CONTROLS MONTHLY REACTOR OPERATING
REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspec-tion and Enforcement, no later than the 15th of each month following the calendar month covered by the report.REPORTABLE
OCCURRENCES
6.9.1.11 The REPORTABLE
OCCURRENCES
of Specifications
6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.


In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.PROMPT NOTIFICATION
g.    Records of sealed source and fission detector leak tests and results.
WITH WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form.Information provided on the licensee event report form shall be supple-mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.a. Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.


c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
h.   Records of annual physical inventory of all sealed source material of record.


PWR-STS-I 6-19 ADMINISTRATIVE
6.10.2 The following records shall be retained for the duration of the Unit Operating License:
CONTROLS d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifica- tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality.
      a.    Records and drawing changes reflecting unit design modifica- tions made to systems and equipment described in the Final Safety Analysis Report.


e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s)
b.     Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
used to cope with accidents analyzed in the SAR, f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require-ments of systems required to cope with accidents analyzed in the SAR.g. Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by technical specifications.


h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.i. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica- tions bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or cor-rective measures to prevent the existence or development of an unsafe condition.
c.     Records of radiation exposure for all individuals entering radiation control areas.


J. Occurrence of an unusual or important event that causes a significant environmental impact, that affects potential environmental impact from unit operation, or that has high public or potential public interest concerning environmental impact from unit operation.
d.   Records of gaseous and liquid radioactive material released to the environs.


k. Occurrence of radioactive material contained in liquid or gaseous holdup tanks in excess of that permitted by the limiting condi-tion for operation established in the technical specifications.
PWR-STS -I                            6-24


PWR-STS- I 6-20
AnUThtfTCDA'TMvr  efnMTDnl C
ADMINISTRATIVE
      e.   Records of transient of operational cycles for those unit com- ponents identified in Table 5.7-1.
CONTROLS THIRTY DAY WRITTEN REPORTS 6.9.1.13 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.a. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.


c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.d. Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.e. An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents.
f.   Records of reactor tests and experiments.


The report of an unplanned offsite release of radioactive material shall include the following information:
g.   Records of training and qualification for current members of the unit staff.
1. A description of the event and equipment involved.2. Cause(s) for the unplanned release.3. Actions taken to prevent recurrence.


4. Consequences of the unplanned release.PWR-STS-I 6-21 ADMINISTRATIVE
h.   Records of in-service inspections performed pursuant to these Technical Specifications.
CONTROLS f. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 6.9-2 when averaged over any calendar quarter sampling period. When more than one of the radionuclides in Table 6.9-2 are detected in the sampling medium, this report shall be submitted if: concentration j1) + concentration
(2) + .... >1.0 iMIT level (1) limit Tevel (2)When radionuclides other than those in Table 6.9-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifica- tions 3.11.1.2, 3.11.2.2 and 3.11.2.3.


This report is not required if the measured level of radioactivity was not the result of plant effluents;
i.  Records of Quality Assurance activities required by the QA
however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.SPECIAL REPORTS Special reports may be required covering inspections, test and main-tenance activities.
            Manual.


These special reports are determined on an indi-vidual basis for each unit and their preparation and submittal are designated in the Technical Specifications.
J.    Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10
            CFR 50.59.


6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.PWR-STS-I 6-22 C ( 'N TABLE 6.9-2 REPORTING
k.   Records of meetings of the (URG) and the (CNRAG).
LEVELS FOR RADIOACTIVITY
6.11    RADIATION PROTECTION PROGRAM
CONCENTRATIONS
Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
IN ENVIRONMENTAL
SAMPLES (nI-4 (A Reporting Levels*9 -Airborne Particulate or Gases (pCI/M 3)Analysis Water Fish (pCi/Kg, wet)Milk (pC/l)Vegetables (pCi/Kg, wet)1 4 .9 4 4 4 cm H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-l 40 3 x 104 1 x 103 4 x 102 1 x 103 3 x 102 3 x 102 4 x 102 2 30 50 2 x 102 3 x 104 1 x 104 3 x 104 1 x 104 2 x 104 1 x 103 2 x 103 0.9 10 20 3 60 70 3 x 102 I x 102 1 x 103 2 x 103 2 x to 2  3 x I 1 4
&tRv&,*P-rnATriUD
rnuirnn c AU~llr lllVC r~AIiIEUL0
6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period.indicated.


6.10.1 The following records shall be retained for at least five years: a. Records and logs of unit operation covering time interval at each power level.b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.c. ALL REPORTABLE
6.12    HIGH RADIATION AREA (OPTIONAL)
OCCURRENCES
6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than
submitted to the Commission.
1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
      a.   A radiation monitoring device which continuously indicates the radiation dose rate in the area.


d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
*Health Physics personnel or personnel escorted by Health Physics per- sonnel in accordance with approved emergency procedures shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radia- tion protection procedures for entry into high radiation areas.


e. Records of changes made to the procedures required by Specifica- tion 6.8.1.f. Records of radioactive shipments.
PWR-STS-I                            6-25


g. Records of sealed source and fission detector leak tests and results.h. Records of annual physical inventory of all sealed source material of record.6.10.2 The following records shall be retained for the duration of the Unit Operating License: a. Records and drawing changes reflecting unit design modifica-tions made to systems and equipment described in the Final Safety Analysis Report.b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
a..tfl* ,
AI'
-
    DMINISTKAI LY  LCUN I KULQ
                                                                      integrates the b.     A radiation monitoring device which continuously when  a  preset inte- radiation dose rate in the area and alarms areas with this grated dose is received. Entry into suchdose rate level in the monitoring device may be made after the have been made knowl- area has been established and personnel edgeable of them.


c. Records of radiation exposure for all individuals entering radiation control areas.d. Records of gaseous and liquid radioactive material released to the environs.PWR-STS -I 6-24 AnUThtfTCDA'TMvr efnMTDnl C e. Records of transient of operational cycles for those unit com-ponents identified in Table 5.7-1.f. Records of reactor tests and experiments.
protection procedures who c. An individual qualified in radiation         monitoring device.


g. Records of training and qualification for current members of the unit staff.h. Records of in-service inspections performed pursuant to these Technical Specifications.
is equipped with a radiation dose ratefor providing positive This individual shall be responsible      area and shall perform control over the activities within the frequency specified by periodic radiation surveillance at  the Work Permit.


i. Records of Quality Assurance activities required by the QA Manual.J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.k. Records of meetings of the (URG) and the (CNRAG).6.11 RADIATION
the facility Health Physicist in the Radiation shall also apply to each high
PROTECTION
    6.12.2 The requirements of 6.12.1, above,radiation is greater than radiation area in which the Intensity of shall be provided to prevent
PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.6.12 HIGH RADIATION
    1000 mrem/hr. In addition, locked doors        keys shall be maintained unauthorized entry into such areas and the Shift  Supervisor on duty and/or under the administrative control    of the the Plant Health Physicist.
AREA (OPTIONAL)
6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph
20.203(c)(2)
of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.*Health Physics personnel or personnel escorted by Health Physics per-sonnel in accordance with approved emergency procedures shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radia-tion protection procedures for entry into high radiation areas.PWR-STS-I 6-25 I' a..tfl* , A-DMINISTKAI
LY LCUN I KULQ b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.


Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowl-edgeable of them.c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the Intensity of radiation is greater than 1000 mrem/hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist.
PWR-STS-I                            6-26


PWR-STS-I 6-26 ENCLOSURE  
ENCLOSURE NO. 2 APPENDIX I TECHNICAL SPECIFICATIONS
NO. 2 APPENDIX I TECHNICAL  
                      LICENSEE SUBMITTAL DATES
SPECIFICATIONS
60 Days   120 Days           150 Days               180 Days Farl ey  Big Rock Point     Arkansas 1              Beaver Valley Hatch 1/2 Ginna             Brunswick 1/2           Browns Ferry 1/2/3 Haddam Neck        Crystal River           Calvert Cliffs 1/2 La Crosse          Dresden 1/2/3           Cook 1/2 Oyster Creek      FitzPatrick             Cooper San Onofre        Indian Point 1/2/3     Davis Besse Surry 1/2          Millstone 1/2           Duane Arnold Yankee Rowe        Monticello             Fort Calhoun Nine Mile Point         Humboldt Bay Oconee 1/2/3           Kewaunee Peach Bottom 2/3       Maine Yankee Pilgrim 1               North Anna 1/2 Quad Cities 1/2         Palisades Robinson 2             Point Beach 1/2 Turkey Point 3/4        Prairie Island 1/2 Vermont Yankee         Rancho Seco Zion 1/2               Salem 1 St. Lucie 1 Three Mile Island 1/2 Trojan}}
LICENSEE SUBMITTAL  
DATES 60 Days Farl ey Hatch 1/2 120 Days 150 Days 180 Days Big Rock Point Ginna Haddam Neck La Crosse Oyster Creek San Onofre Surry 1/2 Yankee Rowe Arkansas 1 Brunswick
1/2 Crystal River Dresden 1/2/3 FitzPatrick Indian Point 1/2/3 Millstone  
1/2 Monticello Nine Mile Point Oconee 1/2/3 Peach Bottom 2/3 Pilgrim 1 Quad Cities 1/2 Robinson 2 Turkey Point 3/4 Vermont Yankee Zion 1/2 Beaver Valley Browns Ferry 1/2/3 Calvert Cliffs 1/2 Cook 1/2 Cooper Davis Besse Duane Arnold Fort Calhoun Humboldt Bay Kewaunee Maine Yankee North Anna 1/2 Palisades Point Beach 1/2 Prairie Island 1/2 Rancho Seco Salem 1 St. Lucie 1 Three Mile Island 1/2 Trojan}}


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Latest revision as of 01:59, 24 November 2019

NRC Generic Letter 1978-025: Appendix I Model Technical Specifications
ML031280330
Person / Time
Issue date: 07/11/1978
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
GL-78-025
Download: ML031280330 (113)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

T 0N, 205 A~WSHN

. HNT

.C.

5o9 y July 11, 1978 TO ALL POWER REACTOR LICENSEES

Gentlemen:

In order to provide reasonable assurance that the requirements of

10 CFR 50 Appendix I are implemented at all nuclear power facilities, the NRC staff has prepared the enclosed Appendix I model Technical Specifications. These model specifications are intended to provide guidance in the scope and types of required specifications for each facility in the areas of equipment and administrative requirements including actions we consider appropriate if a limiting condition for operation cannot be met.

The enclosure uses the Standard Technical Specification format with blanks or parentheses appearing where the information is plant specific.

We request that you submit a license amendment application to incorporate the applicable specifications of the enclosed guidance into your Appendix "A" Technical Specifications within the number of days indicated for your facility in the attachment to this letter. A staggered submittal schedule has been selected to facilitate staff review. The staff considers such an amendment to be a CLASS III Amendment per 10 CFR 170.22, provided the application is consistent with the enclosed guidance.

If you have any questions on this matter, please contact us.

Sincerely, Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosures:

1. Model Appendix I Technical Specifications

2. Submittal Schedule J

N

.,

v' NUREG NO. 0472 v-i DRAFT

RADIOLOGICAL EFFLUENT TECHNICAL

SPECIFICATIONS FOR PWR'S

K-

MAY 1978

1.0 DEFINITIONS

CHANNEL CALIBRATION

1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL

sensor and CALIBRATION shall encompass the entire channel including theFUNCTIONAL

alarm and/or trip functions, and shall include the CHANNEL

TEST. The CHANNEL CALIBRATION may be performed by any series of sequen- channel is tial, overlapping or total channel steps such that the entire calibrated.

CHANNEL CHECK

1.10 A CHANNEL CHECK shall be the qualitative assessment of channel include, behavior during operation by observation. This determinationstatus shall comparison of the channel indication and/or with where possible, other indications and/or status derived from independent instrumentation channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST

1.11 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

SOURCE CHECK

1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM

and

1.30 A PROCESS CONTROL PROGRAM shall be the operating procedure wastes from process parameters within which SOLIDIFICATION of radioactive liquid systems is assured.

SOLIDIFICATION

1.31 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous, monolithic, immobilized solid with definite outline on all volume and shape, bounded by a stable surface of distinct sides (free-standing).

I PWR-STS-I 1-1

TABLE 1.2 FREQUENCY NOTATION

NOTATION FREQUENCY

S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

P Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to each release.

N.A. Not applicable.

K.1\1- PWR-STS-I 1-8

INSTRUMENTATION

RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION

LIMITING CONDITION FOR OPERATION

3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-11.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than the value shown in Table 3.3-11, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-11.

c. The provisions of Specifications 3.0.3-and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL

CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST

operations during the MODES and at the frequencies shown in Table

4.3-11.

PWR-STS-I 3/4 3-44

C C ( I'.1 TABLE 3.3-11

-o RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

(A

-I MINIMUM

CHANNELS ALARM/TRIP MEASUREMENT

INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION

1. Gross Activity Monitors Providing Automatic (

Isolation a. Liquid Radwaste Effluent (1) * < (_cpm) (1-105 cpm) 18 Line b. Steam Generator Blowdown (1) *

< C-cpm) (1-105 cpm) 19 Effluent Line

  • (1-105 cpm) 20

W c. Turbine Building (Floor (1) < (_cpm)

4b- Drains) Sumps Effluent Line**

CA)

n

2. Gross Activity Monitors Not Providing Automatic Isolation Control a. Service Water Effluent (1) *

< (_cpm) (l-lO5 cpm) 20 (

Line b. Component Cooling Water (1) *

<!.(_cpm) (1-105 cpu) 20

System

  • During releases via this pathway
    • Includes rinse, flush and slurry waste from secondary system condensate deep bed demineralizer or filter-demineralizers.

( >

TABLE 3.3-11 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

-o

-- I

-4I

CA MINIMUM

sI

CHANNELS ALARM/TRIP MEASUREMENT

INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION

3. Continuous Composite Samplers and Sampler f Flow Monitor a. Steam Generator Blowdown (1)

N.A. N.A. 19 Effluent Line b. Turbine Building Sumps (1)

N.A. N.A. 20

Effluent Line *

4h- 4. Flow Rate Monitors a. Liquid Radwaste Effluent (1) * > (_gpm) (0-__gpm) 21 Line b. Steam Generator Blowdown (1) * > (_gpm) (0-__gpm) 21 Effluent Line c. Discharge Canal (1)

  • < (_gpm) (0-__gpm) 21 (
  • During releases via this pathway
    • Includes rinse, flush and slurry waste from secondary system condensate deep bed demineralizers or filter-demineralizers.

C C "I

.I

-o TABLE 3.3-11 (Continued)

CAI

-- I

CA RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

MINIMUM

CHANNELS ALARM/TRIP MEASUREMENT

OPERABLE APPLICABILITY SETPOINT RANGE ACTION

INSTRUMENT

5. Activity Recorders (

Effluent Line b. Liquid Radwaste (1)

  • N.A. (1-105 cpm) 23 Effluent Line

, _

6. Tank Level Monitors (for tanks outside the buildings)

a. (1) ** <( ft3 ) (0-1000 ft3 ) 22

    • <( ft3 ) (0-1000 ft3) 22 b. (1)

<( ft3) (0-1000 ft3) 22 C. (1)

d. (1)

<( ft3 ) (0-1000 ft3) 22

(

  • During releases via this pathway.
    • During liquid addition to the tank.

I

TABLE 3.3-11 (Continued)

TABLE NOTATION

ACTION 18 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from the tank may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, and

2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;

otherwise, suspend release of radioactive effluents via this pathway.

ACTION 19 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 pCi/gram:

1. At least once per hour when the specific activity of the secondary coolant is > 0.001 uCi/gram DOSE

EQUIVALENT 1-131.

2. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is < 0.001 pCi/gram DOSE

EQUIVALENT 1-131.

ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 pCi/ml.

ACTION 21 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 7 days provided the tank liquid level is estimated during all liquid additions to the tank.

PWR-STS-I 3/4 3-48

TABLE 3.3-11 (Continued)

TABLE NOTATION

ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to

7 days provided the gross radioactivity level is recorded at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

PWR-STS I 3/4 3-49

(C

'

-o (A TABLE 4.3-11 I-

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

CHANNEL MODES IN WHICH

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

(

1. Gross Activity Monitors Providing Automatic Isolation

a. Liquid Radwaste Effluents Line P P R(3) Q(1)

b. Steam Generator Blowdown *

Effluent Line D M R(3) Q(1)

toi c. Turbine Building (Floor *

Drains) Sumps Effluent Line D M R(3) Q(M)

2. Gross Activity Monitors Not Providing Automatic Isolation Control a. Service Water Effluent Line D M R(3) Q(2)

(

b. Component Cooling Water D M R(3) Q(2)

System

61 C C

-4 TABLE 4.3-11 (Continued)

LnI

'--

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

CHANNEL MODES IN WHICH

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

3. Continuous Composite Samplers (

and Sampler Flow Monitor

a. Steam Generator Blowdown D N.A. R Q

Effluent Line

W b. Turbine Building Sumps D N.A. R Q

-P. Effluent Line

-I 4. Flow Rate Monitors a. Liquid Radwaste Effluent D N.A. R Q *

Line D *

b. Steam Generator Blowdown N.A. R Q

Effluent Line c. Discharge Canal D N.A. R Q* (

( (

TABLE 4.3-11 (Continued)

-I

(A RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'-4I

CHANNEL MODES IN WHICH

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

CHECK CHECK CALIBRATION TEST REQUIRED

INSTRUMENT

5. Activity Recorders

a. Steam Generator Blowdown D N.A. R Q

Effluent Line

b. Liquid Radwaste D N.A. R Q

Effluent Line

4-

6. Tank Level Monitors (for tanks outside the building)

In **

a.

D N.A. R Q

D N.A. R Q

b.

c.

D N.A. R Q

D N.A. R Q **

d.

(

K- TABLE 4.3-11 (Continued)

TABLE NOTATION

  • - During releases via this pathway.
    • - During liquid additions to the tank.

(1) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

(3)- The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards radiation measurement system) liquid radioactive source positioned in a reproducible geometry with respect to the sensor and emitting beta and gamma radiation with fluences and energies in the ranges measured by the channel during normal operation.

PWR - STS-I 3/4 3-53

INSTRUMENTATION

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION

LIMITING CONDITION FOR OPERATION

3.3.3.9 The radioactive gaseous effluent monitoring instrumentation their alarm/trip channels shown in Table 3.3-12 shall be OPERABLE with setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-12 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than the value of shown in Table 3.3-12, immediately suspend the release radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b. With one or more radioactive gaseous effluent monitoring in instrumentation channels inoperable, take the ACTION shown Table 3.3-12.

not c. The provisions of Specifications 3.0.3 and 3.0.4 are applicable.

SURVEILLANCE REQUIREMENTS

instrumentation

4.3.3.9 Each radioactive gaseous effluent monitoring of the CHANNEL

channel shall be demonstrated OPERABLE by performance TEST

CHANNEL FUNCTIONAL

CHECK, SOURCE CHECK, CHANNEL CALIBRATION and in Table operations during the MODES and at the frequencies shown

4.3-12.

PWR-STS-I 3/4 3-54

C

(A

-I

TABLE 3.3-12 (n

I-

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

MINIMUM

CHANNELS ALARM/TRIP MEASUREMENT

INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION

1. Waste Gas Holdup System

(

a. Noble Gas Activity

  • (10-106 cpm) 25 Monitor (1) c (- cpm)
  • (10.106 cpm) 23 b. Noble Gas Activity Recorder (1) N.A.
  • 25 c. Iodine Sampler (1) N.A. N.A.

in

d. Particulate Sampler (1) N.A. N.A. 25

  • 26 e. Flow Rate Monitor (1) > ( cfm) (0- cfm)
  • 26 f. Sampler Flow Rate Monitor (1) > (- cfm) (0- cfm)

g, Hydrogen MQnitor (1) 4 (4%) by volume (0-20%) by volume 29 h. Hydrogen Monitor (alternate)

1) alarm 2 ** s (2%) by volume (0-20%) by volume

(0-20%) by volume

30

30

(

2) alarm and initiate 2 * s (4X) by volume automatic control function

  • During releases y1A this pathway.
    • During waste gas holdup system (treatment for primary system offgases) operation.

-4 TABLE 3.3-12 (Continued)

~I)

1-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

MIlUIMUM

CH)%dNNELS ALARM/TRIP MEASUREMENT

INSTRUMENT OPI'RABLE APPLICABILITY SETPOINT RANGE ACTION

1. Waste Gas Holdup System (continued)

i. Oxygen Monitor (1) ** s (4%) by volume (0-25%) by volume 29 (

J. Oxygen Monitor (alternate)

1) alarm (2) ** i (2%) by volume (0-25%) by volume 30

2) alarm and initiate (21 * Z (4%) by volume (0-25%) by volume 30

automatic control function

, 2, Condenser Evacuation System en a. Noble Gas Activity Monitor (1) * -C(_ cpm) (l0-106 cpm) 27 b. Noble Gas Activity Recorder (.) *

N.A. (10_106 cpm) 23 c. Iodine Sampler (1) *

N.A. N.A. 27 d. Particulate Sampler 0l) *

N.A. N.A. 27 e. Flow Rate Monitor (1) *

> (_ cfm) (0- cfm) 26

(

f. Sampler Flow Rate Monitor (1) * > (- cfm) (0- cfm) 26

  • During releases via this pathway.
    • During waste gas holdup system (treatment for primary system offgases) operation.
  • I

TABLE 3.3-12 (Continued)

(

-o RADIOACTIVE GASEOUS EFrLUENT MCNITORING INSTRUMENTATION

(I

--4 (A

MINIMUM

CHANNELS ALARM/TRIP MEASUREMENT

INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGF ACTION

3. Vent Header System a. Noble Gas Activity Monitor (1) *

< (_ cpm) (10-106 cpm) 27 (

b. Noble Gas Activity Recorder (1) N.A. (10106 cpm) 23

c. Iodine Sampler (1) N.A. N.A. 2/

d. Particulate Sampler (1) * N.A. N.A. 27 e. Flow Rate Monitor (1) * cfM) (O- cfm) 26 f. Sampler Flow Rate Monitor (1) * cfin) (0- cfm) 26

4. Containment Purge System a. Noble Gas Activity Monitor (1) * < (- cpm) (10-106 cpm) 28 b. Nobel Gas Activity Recorder (1) * N.A. (10-106 cpm) 23 c. Iodine Sampler (1) * N.A. N.A. 28(

d. Particulate Sampler (1) * N.A. N.A. 28

  • During releases via this pathway.

IC C

TABLE 3.3-12 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

4

0-4 MINIMIL0M

CHANN ELS ALARM/TRIP MEASUREMENT

INSTRUMENT OPERAI BLE APPLICABILITY SETPOINT RANGE ACTION

e. Flow Rate Mcnitor (1) , ( cfm) (0- cfm) 26 f. Sampler Flow Rate Monitor (1) > ( cfm) (0-_ cfm) 2( 'F

5. Auxiliary Building Ventilation System a. Noble Gas Activity Monitor (1) * < (- cpm) (10-106 cpm) 27 b. Noble Gas Activity Recorder (1) * N.A. (10_106 c pr-.) 23 C. Iodine Sampler (1) * N.A. N.A. 27 X d. Particulate Sampler (1) * N.A. N.A. 27 e. Flow Rate Monitor (1) *

, (- cfm) (0-_ cfm) 26 f. Sampler Flow Rate Monitor (1) * > (- cfm) (0- cfm) 26

6. Fuel Storage Area Ventilation System (

a. Noble Gas Activity Monitor (1) * < (- cfm) (10-106 cpm) 27 b. Noble Gas Activitv Recorder (1) * N.A. (10-106 cpm) 23

  • During releases via this pathway.

( (

TABLE 3.3-12 (Continued)

CnI

-- I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

0-4 MINIMUM

CHANNELS ALARM/TRIP MEASUREMENT

INSTRUMENT OPERABLE APPLICABILITY SETPOINT RANGE ACTION

6. Fuel Storage Area Ventilation System (continued)

c. Iodine Sampler (1) * N.A. N.A. 27 d. Particulate Sampler (1) N.A. N.A. 27

e. Flow Rate Monitor (1) cfm) (O- cfm) 26

f. Sampler Flow Rate Monitor (1) cfm) (O- cfm) 26

, 7. Radwaste Area Ventilation System *

Ul qo a. Noble Gas Activity Monitor (1) < (~ cpm) (10-10 cpm) 27 b. Noble Gas Activity Recorder (1) * N.A. (10-106 cpm) 23 c. Iodine Sampler (1) * N.A. 27 N.A.

d. Particulate Sampler (1) * 2I>

N.A. N.A.

e. Flow Rate Monitor (1) > (- cfm) (0- cfm) 26

f. Sampler Flow Rate Monitor (1) > (- cfm) (0- cfm) 26

  • During releases via this pathway.

TABLE 3.3-12 (Continued)

(

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMFNTATION

LAl

-I

1INIMUM

CHANNELS ALARM/TRIP MEASUREMENT

INSTRUMENT C)PERABLE APPLICABILITY SETPOINT RANGE ACTION

8. Steam Generator Blowdown Vent a. Noble Cas Activity Monitor (1) * < ( cpm) (10-106 cpm) 27 b. Noble Gas Activity Recorder (1) * N.A. (10-106 cpm) 23 c. Iodine Sampler (1) * N.A. N.A 27

-W d. Particulate Sampler (1) * N.A. N.A. 27 Wn e. Flow Rate Mcnitor (1) > ( cfm)

(0-~ cfm) 26 f. Sampler Flow Rate Monitor (1) * > (-_cfm) (0-~~ cfm) - 26

(

  • During release via this pathway.

TABLE 3.3-12 (Continued)

TABLE NOTATION

ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 7 days provided the gross radioactivity level is recorded at least once per

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment for up to

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that prior to initiating the release:

1. At least two independent samples of the tank's content are analyzed, and

2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;

otherwise, suspend release of radioactive effluents via this pathway.

ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 27 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 7 days provided grab samples are taken at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and these samples are analyzed for gross activity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend release of radioactive effluents via this pathway.

ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to

14 days provided gas samples are analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 30 - With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to 14 days. With both channels inoperable, immedi- ately suspend operation of this waste gas holdup system.

PWR-STS-I 3/4 3-61

( C C

£

TABLE 4.3-12

-o US RAnIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

(I

CHANNEL MODES IN WHICH

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

CHECK CHECK CALIBRATION TEST REQUIRED

INSTRUMENT

1. Waste Gas Holdup System (

P P R(3) Q(0)

a. Noble Gas Activity Monitor *

b. Noble Gas Activity Recorder D N.A. R Q *

D N.A. N.A. N.A.

c. Iodine Sampler d. Particulate Sampler D N.A. N.A. N.A. *

w

4h- Ir~

aw e. Flow Rate Monitor P N.A. R Q **

f. Sampler Flow Rate Monitor D N.A. R Q **

N.A. Q(4) M

g. Hydrogen Monitor D **

h. Hydrogen Monitor (alternate) D N.A. Q(4) M **

i. Oxygen Monitor D N.A. Q(5) M (

J. Oxygen Monitor (alternate) D N.A. Q(5) M

-o

( C

TABLE 4.3-12 (Continued)

CA

(A RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

14A

CHANNEL MODES IN WHICH

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

2. Condenser Evacuation System D M R(3)

(

a. Noble Gas Activity Monitor Q(2)

b. Noble Gas Activity Recorder D N.A. R Q *

c. Iodtne Sampler D N.A. N.A. N.A. .*

d. Particulate Sampler D N.A. N.A. N.A.

  • e, Flow Rate Monitor D N.A. R Q

f. Sampler Flow Rate Monitor D N.A. R Q

3. Vent Header System *

a. Noble Gas Activity Monitor D M R(3) Q(2) *

b. Noble Gas Actiyity Recorder D N.A. R Q (

c. Iodine Sampler D N.A. N.A. N.A.

d. Particulate Sampler D N.A. N.A. N.A.

e. Flow Rate Monitor D N.A. R Q

f. Sampler Flow Rate Monitor D N.A. R q

C C

TABLE 4.3-12 (Continued)

ICA

-ei RADIOACTIVE GASEOUS EFFLUENir MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

-

CHANNEL MODES IN WHICH

CHA,NNEL SOURCE CHANNEL FUNCTIONAL SURVE ILLANCE

INSTRUMENT CHHECK CHECK CALIBRATION TEST REQUIRED

4. Containment Purge System

(

a. Noble Gas Activity Monitor D P R(3) Q(l) *

b. Noble Gas Activity Recorder D N.A. R Q *

c. Iodine Sampler D N.A. N.A. N.A. *

4h d. Particulate Sampler D N.A. N.A. N.A. *

e. Flow Rate Monitor D N.A. R Q *

f. Sampler Flow Rate Monitor D N.A. R Q

5. Auxiliary Building Ventilation System a. Noble Gas Actvity Monitor D M R(3) Q(2)

(

b. Noble Gas Activity Recorder D N.A. R Q *

c. Iodine Sampler D N.A. N.A. N.A.

d. Particulate Sampler D N.A. N.A. N.A.

e. Flow Rate Monitor D N.A. R Q

f. Sampler Flow Rate Monitor D N.A. R Q

( (

-u TABLE 4.3-12 (Continued)

--I

(A RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

-4 CHANNEL MODES IN WHICH

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

6. Fuel Storage Area Ventilation System (

a. Noble Gas Activity Monitor D M R(3) Q(2)

D R *

b. Noble Gas Activity Recorder N.A. Q

c. Iodine Sampler D N.A. N.A. N.A.

d. Particulate Sampler D N.A. N.A. N.A.

e. Flow Rate Monitor D N.A. R Q

cm f. Sampler Flow Rate Monitor D N.A. R Q

7. Radwaste Area Ventilation System

a. Noble Gas Activity Monitor D M R(3) Q(2)

b. Noble Gas Activity Recorder D N.A. R Q

(

c. Iodine Sampler D N.A. N.A. N.A

d. Particulate Sampler D N.A. N.A. N.A

C

2:

-I TABLE 4.3-12 (Continued)

LA4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

CHANNEL MODES IN WHICH

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

7. Radwaste Area Ventilation System (continued)

(

e. Flow Rate Monitor D N.A. R Q *

f. Sampler Flow Rate Monitor D N.A. R Q

X 8. Steam Generator Blowdown Vent

a. Noble Gas Activity Monitor D M R(3) Q(2)

b. Noble Gas Activity Recorder D R *

N.A. Q

c. Iodine Sampler D N.A. *

N.A. N.A

d. Particulate Sampler D N.A. N.A. N.A.

e. Flow Rate Monitor D N.A. R Q (

f. Sampler Flow Rate Monitor D N.A. R Q

I

K>~

-TABLE 4.3-12 (Continued)

TABLE NOTATION

  • - During releases via this pathway.
    • - During waste gas holdup system operation.

(1) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

(3) - The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards radiation measurement system)

gaseous radioactive source positioned in a reproducible geometry with respect to the sensor and emitting beta and gamma radiation with fluences and energies in the ranges measured by the channel during normal operation.

PWR - STS -I 3/4 3-67

K>

TABLE 4.3-12 (Continued TABLE NOTATION

(4) - The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent hydrogen, balance nitrogen, and

2. Four volume percent hydrogen, balance nitrogen.

(5) - The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen.

PWR-STS-I 3/4 3-68

3/4.11 RADIOACTIVE EFFLUENTS

3/4.11.1 LIQUID EFFLUENTS

CONCENTRATION

LIMITING CONDITION FOR OPERATION

3.11.1.1 The concentration of radioactive material released from the site to unrestricted areas (see Figure 3.11-1) shall be limited to the concentra- tions specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases and 4 x 10-5 uCi/ml total activity concentration for all dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The concentration of radioactive material in unrestricted areas shall be determined to be within the above limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 4.11-1.

4.11.1.1.2 Reports - The semiannual Radioactive Effluent Release Report shall include the results of analyses performed in accordance with the program of Table 4.11-1 and a summary of all releases of radioactive liquid effluents.

PWR-STS-I 3/4 11-1

TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

Minimum Lower Limit Sampling Analysis Type of Activity of Detection Liquid Release Type Frequency Frequency Analysis (LLD)'a (pCi/ml),

W. Batch Waste Release Each Batch Each Batch Principal Gamma 0.5 Tanks Emitters P

One Batch/M M Dissolved and 10

Entrained Gases P

Each Batch W 1-131 1.0

Compositec P-.I

Each Batch M H-3 10

Compositec Gross a 0.1 P-32 1.0

P

Each Batch Q Sr-89, Sr-90 0.05 Compositec (Fe-55) (1.0)

. Plant Continuous Continuousd W Principal Gamma 0.5b Releases , (Steam Composited Emitters generator blowdown and turbine build- I-131 1.0

ing drainage) M

Grab Sample M Dissolved and 10

Entrained Gases Continuous d H-3 10

Composite H-

Gross a 0.1 P-32 1.0

Continuous ted Sr-89, Sr-90 0.05 Composited (Fe-55) (1.0)

PWR-STS- I 3/4 11-2

I>

TABLE 4.11-1 (Continued)

TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.12-1 of Specification 4.12.1.1.

b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixture, it may not be possible to measure7 radionuclides in concentrations near the detection limit of 5 x 10

uCi/ml. Under these circumstances, it may be necessary to calculate the concentration of such radionuclides to a lower limit of detection of 5 x 10 uCi/ml using observed ratios with those radionuclides which are measurable, or the lower limit of detection of 5 x 10- UCi/ml may be increased proportionally to the magnitude of the gamma yield (i.e., 5 x 10 /I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 2.

c. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

d. To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples shall be con- tinuously collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be repre- sentative of the average effluent release.

e. A batch release is the discharge of liquid wastes of a discrete volume. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuous release.

X, PWR-STS-I 3/4 11-3

This figure shall consist of a map of the site area showing the unre- stricted area boundary for liquid effluents as defined in 10 CFR Part

20.3(a)(17).

  • Figure 3.11-1 PWR-STS-I 314 11-4

RADIOACTIVE EFFLUENTS

DOSE

LIMITING CONDITION FOR OPERATION

3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure

3.11-1) shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, aWd b. During any calendar year to < 3 mrem to the total body and to

< 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within 3 mrem to the total body and

10 mrem to any organ. (This report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.)

b. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits of Specification 3.11.1.2.a or 3.11.1.2.b, prepare and submit a Special Report to the Commission pursuant to Specification

6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel'

cycle sources is limited to < 25 mrem* to the total body or any organ (except thyroid, which is limited to < 75 mrem*)

over 12 consecutive months. This Special Report shall include I

  • The assessment of radiation doses shall be performed in accordance with NUREG-0133.

PWR-STS-I 3/4 11-5

RADIOACTIVE EFFLUENTS

ACTION: (Continued)

an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR

Part 190 Standard.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations - The dose contributions for the total m

time period r at, shall be determined by calculation at least once per 7 E=1 days and a cumulative summation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:

m

=E EAi1r 1AItz CIL F9J

where- D = the cumulative dose or dose commitment to the total body or an organ T from the liquid effluents for the total time m

period E Att, in mrem.

L=1 At = the length of the ith time period over which CIL and FQ

are averaged for all liquid releases, in hours.

C The average concentration of radionuclide i in undiluted It liquid effluent during time period at from any liquid release, in iiCi/ml.

PWR-STS-I 3/4 11-6

RADIOACTIVE EFFLUENTS

SURVEILLANCE REQUIREMENTS (Continued)

Ai = the site related ingestion dose and dose commitment factor to the total body or any organ T for each identified principal gamma and beta emitter listed in Table 4.11-2,

1 .

in mrem-ml per hr-uC

F. = the near field average dilution factor for C during any liquid effluent release. Defined as the ratl& of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times

(_ isthe site specific applicable factor for the mixing effect of the discharge structure.)

For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximately by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual composite analyses.

4.11.1.2.2 Reports - The calendar quarter cumulative summation of calculated dose contributions shall be included in the semiannual Radioactive Effluent Release Report.

PWR- STS- I 3/4 11-7

K> TABLE 4.11-2 LIQUID EFFLUENT INGESTION DOSE FACTORS*

A. Dose or Dose Commitment Factors jT (mrem-ml per hr-pCi)

Radionuclide Total Body Criticat Organs H-3 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60

Zn-65 Rb-86 Sr-89 Sr-90

Y-91 Zr-95 Zr-97 Nb-95 Mo-99 Ru-103 Ru-1 06 Ag-llOm Sb-124 Sb-i 25 Te-125m Te-127m Te-129m Te-131m Te-132 I-131 I-133 Cs-134 Cs-136 Cs-i 37 Ba-140

La-140

Ce-141 Ce-143 Ce-144 Np-239

  • The listed dose factors are for radionuclides that may be detected in liquid effluents.

PWR-STS-I 3/4 11-8

v RADIOACTIVE EFFLUENTS

LIQUID WASTE TREATMENT

LIMITING CONDITION FOR OPERATION

3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The appropriate subsystems shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses due to the liquid effluent releases to unrestricted areas (see Figure 3.11-1)

when averaged over 7 days, exceed 0.015 mrem to the total body or

0.05 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the liquid radwaste treatment system inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or with liquid waste being discharged without treatment as required above, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment,

2. Cause of inoperability,

3. Action(s) taken to restore the inoperable equipment to OPERABLE status,

4. A description of alternate equipment used for treatment of radioactive materials,

5. Length of time the above requirements were not satisifed,

6. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.

7. Actionts) taken to prevent a recurrence of equipment failures.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

PWR-STS- I 3/4 11-9

IRADIOACTIVE EFFLUENTS

SURVEILLANCE REQUIREMENTS 4.11.1.3 The liquid radwaste treatment system shall be demonstrated OPERABLE at least once per 31 days by operating the radwaste treatment system equipment.

IPWR-STS-I 3/4 11-10

RADIOACTIVE EFFLUENTS

LIQUID HOLDUP TANKS

LIMITING CONDITION FOR OPERATION

3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to < curies, excluding tritium and dissolved or entrained noble gases.

a.

b.

c.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1.12. The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by nalyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

PWR-STS-I 3/4 11-11

RADIOACTIVE EFFLUENTS

3/4.11.2 GASEOUS EFFLUENTS

DOSE

LIMITING CONDITION FOR OPERATION

3.11.2.1 The dose rate in unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following expressions:

a. Release rate limit for noble gases:

z K; E(x7/Q 1] < 500 mrem/yr, and r (Li + 1.1 M;) [(X7/Q)4] < 3000 mrem/yr i

where the terms are defined below:

b. Release rate limit for all radiolodines and radioactive materials in particulate form and radionuclides other than noble gases:

E P1 [W Qi] < T500 mrem/yr where:

K. = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per pCi/M 3 from Table 4.11-3.

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per VCi/m 3 from Table 4.11-3.

M. = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per pCi/m 3 from Table 4.11-3 (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).

PWR-STS-I 3/4 11-12

K>

RADIOACTIVE EFFLUENTS

LIMITING CONDITION FOR OPERATION (Continued)

P = The dose parameter for radionuclides other than noble 3 gases for the inhalatton pathway, in mrem/yr per2 pCi/m and for the food and ground plane pathways in m (mrem/

yrl per pCi/sec from Table 4.11-4. The dose factors are based on the critical individual organ and most restrictive age group (child or infant).

= The release rate of radionuclides, i, add in gaseous effluent from all release points at the site, in MCi/sec.

t-x74 __ _ sec/m 3. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary.

W = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:

W = __ sec/M 3, for the inhalation pathway. The location is the unrestricted area in the sector.

W = meter- 2 , for the food and ground plane pathways. The location is the unrestricted area boundary in the sector.

APPLICABILITY: At all times.

ACTION:

With the release rates exceeding the above limits, immediately decrease the release rate to within its limit and provide prompt notification to the Commiission pursuant to Specification 6.9.1.12.

PWR-STS-I 3/4 11-13

RADIOACTIVE EFFLUENTS

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The release rate of radioactive materials released in gaseous effluents from the site shall be determined to be within the above limits by obtaining representative samples In accordance with the sampling and analysis program specified in Table 4.11-5.

4.11.2.1.2 Reports - The semiannual Radioactive Effluent Release Report shall include the results of analyses performed in accordance with the program of Table 4.11-5 and a summary of all releases of radioactive gaseous effluents.

PWR-STS-1 3/4 11-14

C

-I TABLE 4.11-3

14 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor KI L M i N1 Radionuclide (mrem/yr per iCi/m3 ) (mrem/yr per iiCi/m3) (mrad/yr Rer pCi/M3) (mrad/yr per pCi/m 3 )

Kr-83m 7.56E- 02** 1 .93E+Ol 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+Ol 1.34E+03 1.72E+Ol 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03

-P.

Kr-89 1.66E+04 1.01 E+04 1 .73E+04 1.06E+04

--a

-. A

Ia Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 L'

Xe-i 31m 9.15E+O1 4.76E+02 1.56E+02 1.l1E+03 Xe- 33mn 2.51E+02 9.94E+02 3.27E+02 1.48E+03

2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-133 Xe-i 35m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 C

Xe-i 35 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-i 37 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-i 38 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

  • The listed dose factors are for radionuclides that may be detected in gaseous effluents.
    • 7.56E-02 = 7.56 X 10-2.

C

TABLE 4.11-4

-g DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE

(AI PARTICULATE, GASEOUS EFFLUENTS*

-I

(A

P. P. Pi Pi Radio- Inhalation Pathway Food & Ground Pathways Radio- Inhalation Pathway Food & Ground Pathways- nuclide (mrem/yr per pCi/m 3) (m2 . mrern/yr per pCi/sec) nucliide (mrem/yr per vCi/m ) (m2 . mrem/yr per pCi/I )

H-3 6.5E+02 2.4E+03 Cd-il 5m 7.OE+04 4.8E+07 P-32 2.OE+06 1.5E+ll Sn-123 2.9E+05 3.4E+09 Mn-54 2.5E+04 1. 1E+09 Sn-126 1.2E+06 1.lE+09 Fe-59 2.4E+04 7. OE+08 Sb-124 5.9E+04 1.lE+09 Co-58 1.lE+04 5. 7E+08 Sb-125 1.5E+04 1.lE+O9 Co-60 3.2E+04 4. 6E+09 Te-127m 3.8E+04 7.4E+10

Zn-65 6.3E+04 1.7E+l0 Te-129m 3.2E+04 1.3E+09 Rb-86 1.9E+05 1.6E+l0 Cs-134 7.OE+05 5.3E+10

Sr-89 4. OE tO5 1.OE+l0 Cs-136 1.3E+05 5.4E+09 Sr-90 4.1E+07 9. 5E+i0 Cs-137 6.1E+05 4.7E+10

-IJ Y-91 7.OE+04 1.9E+09 Ba-140 5.6E+04 2.4E+08

...

A Zr-95 2.2E+04 3. 5E *08 Ce-141 2.2E+04 8.7E+07 Nb-95 1.3E+04 3. 6E+08 Ce-144 1.5E+05 6.5E+08 Ru-103 1.6E+04 3.4E 0 1-131 1 .5E+07 l.lE+12 I-133 3.6E+06 9.6E+09 Ru-106 Ag-llOm

1.6E+05

3.3E+04

4.4E+ll

1.5E+10 Unidentified** 4.1E+07 9.5E+10 (

  • The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
    • If Sr-90 analysis is performed, use P. given in Ru-106 for unidentified components.

If Sr-90 and Ru-106 analyses are perfArmied, use Pi given In I-131 for unidentified components.

If Sr-90, Ru-106 and I-131 analyses are performed, use Pi given in P-32 for unidentified components.

C TABLE 4.11-5

(

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

-g

2C/

Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)

Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)a P P

A. Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters 100b Tank Grab Sample H-3 1 C

B. Containment Purge Each Purge Each Purgec Principal Gamma Emitters l 00

Cn Grab

-I Sample H-31 C. (List other release Mcf Mc Principal Gamma Emitters 100b points where gas- Grab eous effluents are Sample H-31 discharged from the facility, e.g. air ejector, steam gen- erator flash vent, equipment vents, ventilation ex-

--A hausts, etc.)

D. All Release Types Continuous 9 we 1-131 as listed in A, B, Charcoal C above. Sample 1-133

4.

lo04

(

Continuous 9 We Principal Gamma Emitters 10 5 Particulate (1-131, Others)

Sample Continuous9 M Gross a 10 5 Composite Particulate Sample _

Continuous 9 Q Sr-89, Sr-90 10-5 Composite Particulate

. .. . _ _

Sample I.

-- ________________________ -I _________________________

TABLE 4.11-5 (Continued)

TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation a.

of Table 4.12-1 of Specification 4.12.1.1.

b. For certain radionuclides with low gamma yield or low energies or for certain radionuclide mixtures, it may not be possible to measure radionulldes in concentrations near the detection limit of

1 x 10 pCi/ml. Under these circumstances, it may be necessary to calculate the concenration of such radionuclides to a lower limit of detection of 1 x 10 pCi/ml using observed ratios with those radionuclies which are measurable, or the lower limit of detection of 1 x 10. pCi/ml may be increased proportionally to the magnitude of the gamma yield (i.e., 1 x 10- /I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10% of the MPC value specified in 1 CFR 20, Appendix B, Table II, Column 1.

c. Analyses shall also be performed following shutdown, startup, or similar operational occurrence which could alter the mixture of radionuclides.

d. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

e. Analyses shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or similar operational occurrence which could lead to significant increases or decreases in radiotodi'ne releases. Samplers shall also be changed and analyzed at intervals in Specifications 3.11.2.1 and 3.11.2.3.

f. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area.

g. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Specifications 3.11.2.1,

3.11.2.2 and 3.11.2.3.

PWR-STS-I 3/4 11-18

-

RADIOACTIVE EFFLUENTS

DOSE, NOBLE GASES

LIMITING CONDITION FOR OPERATION

3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to noble gases released in gaseous effluents from the site shall be limited to the following expressions:

a. During any calendar quarter, for gamma radiation:

3.17 x 10i 8 E Mi [(-xm Qj + (-xq) qia < 5 mrad, and i

During any calendar quarter, for beta radiation:

3.17 x 108 E N1 [(i7XM Qj + (j77) qj] < 10 mrad, and i

b. During any calendar year, for gamma radiation:

3.17 x 10 8 Mi1 [( 77 Qj + (-Xq) qj] < 10 mrad, and K-i During any calendar year, for beta radiation:

3.17 x 10 10-88 eV 1x/Q

1 [ 770 Q. + (x/q) qj] < 20 mrad N.

where:

3.17 x 10 8 = The inverse of the number of seconds in a year.

M. = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per VCi/m3 from Table 4.11-3.

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per VCi/m3 from Table 4.11-3.

(G7n = sec/m 3. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for long term releases (greater than 500 hrs/year).

3. The relative concentration for any area (iJ7) = _sec/m at or beyond the unrestricted area boundary for short term releases (equal to or less than 500 hrs/yr).

PWR-STS- I 3/4 11-19

IIRADIOACTIVE EFFLUENTS

LIMITING CONDITION FOR OPERATION (Continued)

Q = The release of noble gas radionuclides, I, in gaseous.effluents, for long term releases (greater than 500 hrs/yr), in pCi.

Releases shall be cumulative over the calendar quarter or year as appropriate.

q= The release of noble gas radionuclides, t, in gaseous effluents, for short term releases (equal to or less than 500 hrs/yr),

in ACi. Releases shall be cumulative over the calendar quarter or year as appropriate.

CThe dose design objectives may be reduced based on predicted noble gas releases from the turbine building if effluent sampling is not provided.

The dose design objectives may also be reduced based on expected public occupancy of areas, e.g., beaches and visitor centers within the unrestricted area boundary.)

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 3( days, pursuant to Specifica- tton 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(ssl and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose during these four calendar quarters is within (10) mrad for gamma radiation and (20) wrad for beta radiation.

b. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding twice the limits of Specification

3.11.2.2.a or 3.11.2.2.b, prepare and submi't a Special Report to the Commisston pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to 4 25 mrem* to the total body or any organ (except thyroid, which is limited to < 75 mrem*) over 12 consecutive months. This Special Report shall include an analysis which The assessment of radiation doses shall be performed in accordance with NURE6-O 33.

PWR-STS-I 3/4 11-20

RADIOACTIVE EFFLUENTS

ACTION: (Continued)

demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190

Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.

c. The provisions of Speciftcations 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 The release of radioactive materials released in gaseous effluents from the site shall he determined to be within the above limits by obtaining representative samples in accordance with the sampling and analysis program specified in Table 4.11-5.

PWR-STS-I 3/4 11-21

RADIOACTIVE EFFLUENTS

DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND

RADIONUCLIDES OTHER THAN NOBLE GASES

LIMITING CONDITION FOR OPERATION

3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following expressions:

a. During any calendar quarter:

3.17 x 10 8 R1 [W Q. + w qj] < 7.5 mrem, and b. During any calendar year:

3.17 x 10° R. [W Q: + w qua < 15 mrem where:

3.17 x 10 8 = The inverse of the number of seconds in a year.

Q. = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs/yr),

in PCi. Releases shall be cumulative over the calendar quarter or year as appropriate.

q= The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short term releases (equal to or less than

500 hrs/yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate.

W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long term releases (greater than 500 hrs/yr):

3 W = (Ax/A for the inhalation pathway, in sec/m from Table 4.11-6a.

2 W = (D/Q) for the food and ground plane pathways, in meters from Table 4.11-6b.

w = The dispersion parameter for estimating the dose to an individual at the controlling location for short term releases (equal to or less than 500 hrs/yr):

PWR-STS-I 3/4 11-22

RADIOACTIVE EFFLUENTS

LIMITING CONDITION FOR OPERATION (Continued)

3 w - (x-/q) for the inhalation pathway, in sec/m from Table 4.11-6c.

2 w = (W7q) for the food and ground plane pathway, in meters from Table 4.11-6d.

R = The dose factor for each identified radionuclide, i, in ml

3 from Table 4.11-7.

(mrem/yrl per zCi/sec or mrem/yr per pCi/m For the direction sectors with existing pathways within 5 miles from the unit, use the values of R, for these pathways. If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk R assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector. If the R for an existing pathway within 5 miles is less than a cow-milk R It 4.5 to 5.0 miles, then use the value of the cow-milk R at 4.5 to 5.0

miles. The values used for calculating dose contributions shall be consistent wtth. the results of the land use census performed pursuant to Specification 3.12.2. The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30

days after the completion of each required land use census. The parameters W and w shall correspond to the applicable R1 for the same sector, pathway and location condition.

(The dose design objective may be reduced based on predicted carbon-14 releases and turbine building releases if effluent sampling is not provided.)

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclidesof other than noble gases in gaseous effluents exceeding any the above limits, prepare and submit to the Commission within

30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radiojodines, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within (C151 mrem to any organ.

PWR-STS-I 3/4 11-23

RADIOACTIVE EFFLUENTS

ACTION: (Continued)

b. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding twice the limits of Specification 3.11.2.3.a. or 3.11.2.3.b, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem* to the total body or any organ (except thyroid, Which is limited to < 75 mrem*l over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation)

are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.

c. The provisions of Speciftcations 3.Q.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 The release of radioactive materials released is gaseous effluents from the site shall be determined to be within the above limits by obtaining representative samples in accordance with- the sampling and analysts program specified in Table 4.11-5.

  • I

The assessment of radiation doses shall be performed in accordance with NUREG-0133.

PWR-STS-I 3/4 11-24

( C

TABLE 4.11-6a (A DISPERSION PARAMETER (7M) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR

Distance to the control location, in miles Sector e 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0

N

NNE

(

NE

ENE

E

ESE

SE

SSE

S

WSW

_a WSW

W

Ul WNW

NW

NNW

(

( ( (

TABLE 4.11-6b

-o

-4 DISPERSION PARAMETER (O7) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR

-- i Distance to the control location, in miles Sector e 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.04.5 4.5-5.0

N

NNE

(

NE

ENE

E

ESE

SE

SSE

S

-

SSW

SW

-A

WSW

I9 W

WNW

NW

NNW

(

C (

TABLE 4.11-6c

2:

44 DISPE`RSION PARAMETER (xlg) FOR SHORT TERM RELEASES i 500 HR/YR OR : 125 HR/QIR

-I

Distance to the control location, in miles Sector e 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0

N (.

NNE

NE

ENE

E

ESE

SE

SSE

S

SW

WSW

I W

4 WNW

NW

NNW

(

( <

TABLE 4.11-6d (A DISPERSION PARAMETER (Onh) FOR SHORT TERM RELEASES s 500 HR/YR OR r 125 HR/QTR

CA

Distance to the control location, in miles Sector o 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0

N

NNE

NE

ENE

E

ESE

SE

SSE

S

SSW

SW

-. WSW

W

NW

NNW

( C (

TABLE 4.11-7 PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES

CA

Inhalation Meat Ground Plane Cow-Milk-Infant .Leafy Vegetables Pathway Pathway Pathway Pathway Pathway Radio- Rap (mrem/yr (tm2 .

Ri mrem/yr Ri (W2 . mrem/yr 2.

Rmmrem/yr Ri (m2 . mrem/yr

(

nucl ide per pCli/m3 ) per pCi/sec) per pCi/sec) per MC1/sec) per pCi/sec)

-A

-a

(

IRADIOACTIVE EFFLUENTS

GASEOUS WASTE TREATMENT

LIMITING CONDITION FOR OPERATION

The

3.11.2.4 The gaseous radwaste treatment system shall be OPERABLE. in used to reduce radioactive materials appropriate subsystems shall be gaseous effluent gaseous waste prior to their discharge when the projected Figure 5.1-1)

releases from all release points to unrestricted areas (see 0.05 mrad for would result in a dose in any period of 7.days -that exceeds to any gamma radiation, Q.lQ mrad for beta radiation, or 0.075 mrem organ for that same 7 day period.

APPLICABILITY: At all times.

ACTION:

a. With the gaseous radwaste treatment system inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or with gaseous waste being discharged without treatment as required above, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identiftcation of the inoperable equipment,

2. Cause of inoperability,

3. Actions)l taken to restore the inoperable equipment to OPERABLE status,

4. A description of alternate equipment used for treatment of radioactive materials,

5. Length of time the above requirements were not satisfied,

6. Volume and curie content of the waste discharged which was not processed by the inoperable equipment but which required processing.

7. Actionts) taken to prevent a recurrence of equipment failures.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

PWR-STS-I 3/4 11-30

RADIOACTIVE EFFLUENTS

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 The gaseous radwaste treatment system shall be demonstrated OPERABLE at least once per 31 days by operating the radwaste treatment system equipment.

4.11.2.4.2 Dose Calculations. The dose contributions shall be calculated for all radionuclides in gaseous effluents projected to be released to unrestricted areas during any projected 7 day period using the following expressions:

For noble gases, the gamma radiation:

3.17 x 10 z M1 [(x-7) Qi + (V74) qa c Q0.O5 mrad, and i

For noble gases, the beta radiation:

3.17 x 1008E N1 £ii7 Q1 + (x70) qi] < 0.10 Brad, and i

For radioiodines, radioactive materials in particulate form and radionuclides other than nokle gases:

3.17 x 10- z R1 £WQi + wqi] ; 0.075 mrem where:

Q = The projected release over the next 7 days of radionuciides,

1, in gaseous effluents for long term releases (greater than

500. hrslyrL, in ICi .

q The projected release over the next 7 days of radionuclides,

1, ingaseous effluents for short term releases (equal to or less than 50Q hrs/yrl, in pCi.

and.all other terms are defined inSpecifications 3.11.2.2 and

3.11.2.3.

PWR-STS-I 3/4 11-31

RADIOACTIVE EFFLUENTS

EXPLOSIVE GAS MIXTURE (Systems designed to withstand a hydrogen explosion)

LIMITING CONDITION FOR OPERATION

3.11.2.5 The concentration of (hydrogen or oxygen) in the waste gas holdup system shall be limited to < 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of (hydrogen or oxygen) in the waste gas holdup system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of (hydrogen or oxygen) in the waste gas holdup system shall be determined to be within the above limits by con- tinuously monitoring the waste gases in the waste gas holdup system with the (hydrogen or oxygen) monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.

PWR-STS-I 3/4 11- 32

RADIOACTIVE EFFLUENTS

EXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen explosion)

LIMITING CONDITION FOR OPERATION

3.11.2.5A The concentration of (hydrogen and/or oxygen) in the waste gas holdup system shall be limited to < 2% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of (hydrogen and/or oxygen) in the waste gas holdup system > 2% by volume but < 4% by volume, restore the concentration of (hydrogen and/orhoxygen) to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. With the concentration of (hydr'ogen and/or oxygen) in the waste gas holdup system > 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concen- tration of (hydrogen and/or oxygen) to < 2% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5A The concentrations of (hydrogen and/or oxygen) in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the (hydrogen and/or oxygen) monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.

IPWR-STS-I 3/4 11-33

RADIOACTIVE EFFLUENTS

GAS STORAGE TANKS

LIMITING CONDITION FOR OPERATION

3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to < - curies noble gases (considered as Xe-

133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1.12. The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.

PWR-STS-I 3/4 11-34

RADIOACTIVE EFFLUENTS

3/4.11.3 SOLID RADIOACTIVE WASTE

LIMITING CONDITION FOR OPERATION

3.11.3.1 The solid radwaste system shall be OPERABLE and used, as appli- cable, in accordance with a PROCESS CONTROL PROGRAM, which provides SOLIDIFICATION of wet solid wastes, to solidify and package radioactive wastes and to meet the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times.

ACTION:

a. With the requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend shipments of solid radioactive wastes from the site.

b. With the solid radwaste system inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment,

2. Cause of inoperability,

3. Action(s) taken to restore the inoperable equipment to OPERABLE status,

4. Length of time the above requirements were not satified.

5. A description of alternate equipment used to solidify and package radioactive materials,

6. Type, volume and curie content of waste shipped using alternate equipment, and

7. Action(s) taken to prevent a recurrence of equipment failures.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 31 days by performing functional tests of the equipment and verifying that the system performs its design functions.

PWR-STS-I 3/4 11-35

11RADIOACTIVE EFFLUENTS

SURVEILLANCE REQUIREMENTS (Continued)

4.11.3.1.2 The above required PROCESS CONTROL PROGRAM shall verify SOLIDIFICATION of at least one representative test specimen obtained from at least every tenth batch of each type of radioactive waste from liquid systems when the test specimens are processed in accordance with the PROCESS CONTROL PROGRAM. If any test specimen falls to verify SOLIDI-

FICATION, additional waste samples shall be taken from consecutive batches of the same type waste until five consecutive test specimens demonstrate SOLIDIFICATION and the PROCESS CONTROL PROGRAM shall be modified as required.

4.11.3.1.3 Reports - The semiannual Radioactive Effluent Release Report shall includ-ethIefollowing information for each type of solid waste shipped offsite during the report period:

a. container burial volume, b. total curie quantity (determined by measurement or estimate),

c. principal gamma radionuclides (determined by measurement or estimate),

d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. type of container (e.g., LSA, Type A, Type S, Large Quantity),

and f. solidification agent (e.g., cement, urea formaldehyde).

PWR-STS-I 3/4 11-36

\ J

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

3/4.12.1 MONITORING PROGRAM

LIMITING CONDITION FOR OPERATION

3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity in an-environmental sampling medium at one or more of the locations specified in Table

3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radio- logical Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from any of the sample locations required by Table 3.12-1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from Table 3.12-1 and Figure 3.12-1 provided the locations from which the replace- ment samples were obtained are added to the environmental monitoring program as replacement locations.

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

PWR-STS- I 314 12-1

RADIOLOGICAL ENVIRONMENTAL MONITORING

SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations shown on Figure 3.12-1 and shall be analyzed pursuant to the requirements of Tables 3.12-1 and

4.12-1.

4.12.1.2 Reports - The results of analyses performed on the radio- logical environmental monitoring samples shall be summarized in the Annual Radiological Environmental Operating Report.

K>

PWR-STS- 3 12-2

3/4

I'

(

TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

-o CA

-4 CA Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations** Collection Frequency of Analysis

1. AIRBORNE

a. Radiolodine and Particulates (Locations 1-5) Continuous operation of Radioiodine canister. (

sampler with sample col- Analyze at least once lection as required by per 7 days for 1-131.

dust loading but at least once per 7 days. Particulate sampler.

Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

Perform gamma isotopic A

analysis on each sample f1%.

4.J

when gross beta activity is >'10 times the mean of control samples for any medium. Perform gamma isotopic analysis on composite (by location)

sample at least once per 92 days.

2. DIRECT RADIATION (Locations 1-8) At least once per 31 days. Gamma dose. At least

> 2 dosimeters or > 1 once per 31 days.

Tnstrument for con- or or tinuously measuring At least once per 92 days. Gamma dose. At least and recording dose (Read-out frequencies are once per 92 days.

rate at each determined by type of dosi- location. meters selected.)

    • Sample locations are shown on Figure 3.12-1.

C (

TABLE 3.12-1 (Continued)

-o RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

-In Number of Samples (A0

I-. Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations** Collection Frequency of Analysis

3. WATERBORNE

a. Surface (Locations 9 and 10) Composite* sample collected Gamma isotopic analysis (

over a period of < 31 days. of each composite sample.

Tritium analysis of com- posite sample at least once per 92 days.

b. Ground (Locations 11 and 12) At least once per 92 days. -Gamma isotopic and tritium analyses of each sample.

c. Drinking (Locations 13-15) Composite* sample collected 1-131 analysis over a period of < 14 days, of each composite sample;

if 1-131 analysis is performed; or and Composite* sample collected Gross beta and gamma over a period of _ 31 days. isotopic analysis of each composite sample. (

Tritium analysis of composite sample at least once per 92 days.

d, Sediment from (Locations 181 At least once per 184 days. Gamma isotopic analysis Shoreline of each sample.

  • Composite samples shall -be collected by collecting an aliquot at Intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
    • Sample locations are shown on Figure 3.12-1.

( C (

TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

CAI

-i (A

Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations** Collection Frequency of Analysis

4. INGESTION

a. Milk (Locations 17-20) At least once per 15 days Gamma isotopic and (

when animals are on pasture; I-131 analysis at least once per 31 days of each sample.

at other times.

b. Fish and (Locations 21 and 22) One sample in season, or at Gamma isotopic analysis Invertebrates least once per 184 days if on edible portions.

not seasonal. One sample of W

1.g~ each of the following species:

-J

in 2.

c. Food Products (Locations 23-25) At time of harvest. One Gamma isotopic analysis sample of each of the fol- on edible portion.

lowing classes of food products:

(

1.

2.

3.

(Location 26) At time of harvest. One 1-131 analysis.

sample of broad leaf vegetation.

    • Sample locations are shown on Figure 3.12-1.

Figure 3.12-1 Radiological Environmental Monitoring Sample Locations PWR-STS-I 3/4 12-6

( ( (

TABLE 4.12-1

-o MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a

--I 9* - w - -

(A

Airborne Particulate Water or Gas Fish Milk Food Products Sediment Analysis (pCi/I) (pci/m ) (pCi/kgwet) (pCi/i) (pCi/kg,wet) (pCi/kg, dry:

-, t t gross beta 2b 1 X 10-2

3H 330

54Mn 15 130

59 Fe

30 260

5 8 ,6 0 Co

15 130

Ca~

6 5 Zn

-. 8

30 260

95 Zr-Nb

10

1311 0. 5c

7 X 10-2 0.8c 2 5 c,d

134,137cs 15 1 X 10-2 130 15 80 (

140 Ba-La 15 15

- i a a -- a a

TABLE 4.12-1 (Continued)

TABLE NOTATION

a - The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding its presence.

For a particular measurement system (which may include radio- chemical separation):

LLD 4.66 sb E

  • V * 2.22
  • Y * exp(-Xat)

where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appro- priate Cas counts per minute)

E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume)

2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable A is the radioactive decay constant for the particular radi.onuclide at is the elapsed time between sample collection and analysts The value of sb used in the calculation of the LLD for a detection systemnishall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate} rather than on an unverifted theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present inthe samples (e.g., potassium-40 in milk samples).

' v PWR-STS-I 3/4 12-8

TABLE 4.12-1 (Continued)

TABLE NOTATION

b - LLD for drinking water.

c - LLDs for 1-131 in water, milk and other food products correspond to one-quarter of the Appendix I (10 CFR Part 50) design objec- tive dose-equivalent of 15 mrem/year for atmospheric releases and

10 mrem/year for liquid releases to the most sensitive organ and individual using the assumptions given in Regulatory Guide

1.109.

d - LLD for leafy vegetables.

PWR-STS-I 3/4 12-9

IRADIOLOGICAL ENVIRONMENTAL MONITORING

3/4.12.2 LAND USE CENSUS

LIMITING CONDITION FOR OPERATION

3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. (For elevated releases as defined in Regulatory Guide 1.111, March 1976. The land use census shall also identify the loca- tions of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location(s).

b. With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification

3.12.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days.

The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

  • Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

PW-T-I / 21 PWR-STS- I 3/4 12-10

IRADIOLOGICAL ENVIRONMENTAL MONITORING

cirDiti JunXc AIUrc WLLU~nucncu DcniITDrMMLrTC

nrln

4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

4.12.2.2 Reports - The results of the land use census shall be included in the Annual Radlological Environmental Operating Report.

PWR-STS-I 3/4 12-11

RADIOLOGICAL ENVIRONMENTAL MONITORING

3/4.12.3 CROSSCHECK PROGRAM

LIMITING CONDITION FOR OPERATION

3.12.3 Analyses shall be performed on radioactive materials supplied as part of the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program that are also included in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The results of analyses performed as part of the above required crosscheck program shall be included in the Annual Radiological Environmental Operating Report.

PWR-STS- I 3/4 12-12

INSTRUMENTATION

BASES

3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments are provided to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments are provided to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instru- mentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

PWR-STS-I B 3/4 3-4

3/4.11 RADIOACTIVE EFFLUENTS

BASES

3/4.11.1 LIQUID EFFLUENTS

3/4.11.1.1 CONCENTRATION

This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in

10 CFR Part 20, Appendix B, Table II. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radio- isotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2.

3/4.11.1.2 DOSE

This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 5a. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexi- bility and at the same time implement the guides set forth in Section IV.A

of Appendix I to assure that the releases of radioactive material in liquid effleunts will be kept "as low as is reasonably achievable". Also, for fresh water sites with drtnking water supplies which can be potentially effected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of

40 CFR 141. The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculatiohal procedures based on models and data such that the actual exposure of an Individual through appropriate pathways Is unlikely to be substantially underestimated. The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of radioactive materials in liquid effluents were developed from the methodology provided in Regulatory Guide 1.109,

"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the

Purpose

of Evaluating Compliance with 10 CFR Part 50,

Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113,

"Estimating Aquatic Dispersion of Effluents from Accidental and Routine

1eactor Releases for the

Purpose

of Implementing Appendix I," April

1977.

PWR-STS-I B 3/4 11-1

RADIOACTIVE EFFLUENTS

BASES

This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assur- ance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification imple- ments the requirements of 10 CFR Part 50.36a, General Design Criterion 60

of Appendix A to 10 CFR Part 50 and the design objectives of Appendix I

to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I,

10 CFR Part 50, for liquid effluents.

3/4.11.1.4 LIQUID HOLDUP TANKS

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting dose or dose commitment to an individual in an unrestricted area will not exceed 0.5 rem.

3/4.11.2 GASEOUS EFFLUENTS

3/4.11.2.1 DOSE

This specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with the concentrations of

10 CFR Part 20, Appendix B, Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual either within or outside the.

unrestricted boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 CIO CFR

Part 20.106(b)l. For individuals who may at times be within the unrestricted boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the nearest unrestricted area. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose PWR-STS-I B 3/4 11-2

RADIOACTIVE EFFLUENTS

BASES

rates.:above.background to an individual at or beyond the unrestricted boundary to < (500) mrem/ year to the total body or to < (3000) mrem/year to the skin. These release rate limits also restrict, it all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 15Q0 mrem/year for the nearest cow to the plant.

This specification applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

3/4.11.2.2 DOSE, NOBLE GASES

This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B

of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided in Regulatory Guide 1.109,

"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the

Purpose

of Evaluating Compliance with 10 CFR Part 50,

Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dilspersl.on of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revtsion 1, July

1977. The specified equations provide for determining the air doses at the unrestricted area boundary based upon the historical average atmospheric conditions.

3/4.11.2.3 DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM

AND RADIONUCLIDES OTHER THAN NOBLE GASES

This specification is provided to Implement the requirements of Sections II.C, III.A and IV.A of Appenditx 1, 10 CFR Part 50. The Limiting PWR-STS-I B 3/4 11-3

RADIOACTIVE EFFLUENTS

BASES

Condition for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexi- bility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

The Surveillance Requirements implement the requirements in Section III.A by of Appendix I that conformance with the guides of Appendix I be shown calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the Surveillance Requirements for calculating the doses due to the actual release rates of the subject materials were also developed using the methodologyto Man provided in Regulatory Guide 1.10%, "Calculation of Annual Doses from Routine Releases of Reactor Effluents for the

Purpose

of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors," Revision 1, July 1977. As with the equations used in Specification 4.2.2.2.1, these equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.

The pathways which were examined in the development of these specifications deposition were: 12 individual inhalation of airborne radionuclides, 21 consumption of radionuclides onto green leafy vegetation with subsequent by man, 3) deposition onto grassy areas where mtilk animals and meat producing animals graze with consumption of the mtlk and meat by man, and 41 deposition on the ground with subsequent exposure of man.

3/4.11.2.4 GASEOUS WASTE TREATMENT

The OPERABILITY of the gaseous radwaste treatment system ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the reason- appropriate portions of this system be used when specified provides liquid able assurance that the releases of radioactive, materials in effluents will be kept "as low as ts reasonably achievable". This Design specifi- cation implements the requirements of 10 CFR Part 50.36a, General Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the gaseous radwaste treatmentinsystem were specified as a suttable fraction of the guide set forth Sections II.B

and II.C of Appendix I, l0 CFR Part 5Q, for gaseous effluents.

PWR-STS-I B 3/4 11 -4

K> RADIOACTIVE EFFLUENTS

BASES

3/4.11.2.5 EXPLOSIVE GAS MIXTURE

This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.

(Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.

These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.)

Maintaining the concentration of hydrogen and oxygen below their flam- mability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.6 GAS STORAGE TANKS

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.

This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure".

3/4.11.3 SOLID RADIOACTIVE WASTE

The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a and General Design Criteria 60 of Appendix A to 10 CFR Part 50. The process parameters included in establish- ing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/lIquid/solIdification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

PWR-STS-I B 3/4 11-5

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

BASES

3/4.12.1 MONITORING PROGRAM

The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measur- able concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 4.12-1 are state- of-the-art for routine environmental measurements in industrial laboratories.

The specified lower limits of detection for 1-131 in water, milk and other food products correspond to approximately one-quarter of the Appendix I

to 10 CFR Part 50 design objective dose-equivalent of 15 mrem/year for atmospheric releases and 10 mrem/year for liquid releases to the most sensitive organ and individual. They are based on the assumptions given in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the

Purpose

of Evaluating Compliance with 10 CFR Part 50, Appendix I," March 1976, except the change for an infant consuming 330 liters/year of drinking water instead of 510 liters/year.

3/4.12.2 LAND USE CENSUS

This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I

to 10 CFR Part 50. Restricting the census to gardens of greater than

500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.

To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of

2 kg/square meter.

PWR-STS-I B 3/4 12-1

K>

RADIOLOGICAL ENVIRONMENTAL MONITORING

BASES

3/4.12.3 CROSSCHECK PROGRAM

The requirement for participation in the EPA crosscheck program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

IPWR-STS-1 B 3/4 12-2

PWR-STS- I

STANDARD

TECHNICAL SPECIFICATIONS SECTION 6.0

ADMINISTRATIVE CONTROLS

I>

6.0 ADMINISTRATIVE CONTROLS

6.1 RESPONSIBILITY

6.1.1 The (Plant Superintendent) shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION

OFFSITE

6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.

UNIT STAFF

6.2.2 The unit organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the control room when fuel is in the reactor.

c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsi- bilities during this operation.

f. A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include (3)

members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

PWR-STS-I 61

This figure shall show the organizational structure and lines of responsibility for the offsite groups that provide technical and management support for the unit. The organizational arrangement for performance and monitoring Quality Assurance activ- ities should also be indicated.

Figure 6.2-1 OFFSITE ORGANIZATION

PWR-STS-I 6-2

This figure shall show the organizational structure and lines of responsibility for the unit staff.

Positions to be staffed by licensed personnel should be indicated.

Figure 6.2-2 N.- UNIT ORGANIZATION

PWR-STS-I 6-3

Ki'

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION#

LICENSE APPLICABLE MODES

CATEGORY 1, 2, 3 & 4 5 &6 SOL 'I 1*

OL 2 1 Non-Licensed 2 1

  • Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE

ALTERATIONS.

  1. Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

PWR-STS-I 6-4

  • A . I..V.rTflnt C

ALMINLZI5IKA I lV W I UL~a

6.3 UNIT STAFF QUALIFICATIONS

Minimum qualifications for members of the unitreferencing staff may be specified ANSI N18.1-1971 by use of an overall qualification statement Gener- or alternately by specifying individual positionthequalifications.

second method is ally, the first method is preferable; however, special qualification statements adaptable to those unit staffs requiring because of a unique organizational structure.

exceed the minimum

6.3.1 Each member of the unit staff shall meet orpositions, except for qualifications of ANSI N18.1-1971 for comparable or exceed the quali- the (Radiation Protection Manager) who shall meet 1975.

fications of Regulatory Guide 1.8, September

6.4 TRAINING

6.4.1 A retraining and replacement training program for the unit staff the (position title) and shall be maintained under the direction of recommendations of Section 5.5 shall meet or exceed the requirements and CFR Part 55.

of ANSI N18.1-1971 and Appendix "A" of 10

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the (position title) and shall meet or exceed the require- ments of Section 27 of the NFPA Code - at1975, except for Fire Brigade training sessions which shall be held least once per 92 days.

6.5 REVIEW AND AUDIT

The method by which independent review and audit of facility operations is accomplished may take one of several forms. The licensee may either assign this function to an organizational unit unit separate and independent from the group having responsibility for operation or may utilize within and outside the a standing committee composed of individuals from licensee's organization.

Irrespective of the method used, the licensee shall specify the details review and audit of each functional element provided for the independent specifications.

process as illustrated in the following example

6.5.1 UNIT REVIEW GROUP (URG)

FUNCTION

6.5.1.1 The (Unit Review Group) shall function to safety. advise the (Plant Superintendent) on all matters related to nuclear PWR-STS-I 6-5

ADMINISTRATIVE CONTROLS

COMPOSITION

6.5.1.2 The (Unit Review Group) shall be composed of the:

Chairman: (Plant Superintendent)

Member: (Operations Supervisor)

v Member: (Technical Supervisor)

Member: (Maintenance Supervisor)

Member: (Plant Instrument and Control Engineer)

Member: (Plant Nuclear Engineer)

Member: (Health Physicist)

ALTERNATES

6.5.1.3 All alternate members shall be appointed in writing by the (URG) Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in CURG) activities at any one time.

MEETING FREQUENCY

6.5.1.4 The (URG) shall meet at least once per calendar month and as convened by the (URG) Chairman or his designated alternate.

QUORUM

6.5.1.5 The minimum quorum of the (URG) necessary for the performance of the (URG) responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES

6.5.1.6 The (Unit Review Group) shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the (Plant Superintendent) to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety.

PWR-STS-I 6-6

AnTurTCTDATTvv mPJTDnli nuR1L s&aIF~nn Iu a I. %%#I I W_

c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

e. Investigation of all violations.of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the (Superintendent of Power Plants) and to the (Company Nuclear Review and Audit Group).

f. Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

g. Review of unit operations to detect potential nuclear safety hazards.

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the (Plant Superintendent) or the (Company Nuclear Review and Audit Group).

i. Review of the Security Plan and implementing procedures and shall submit recommended changes to the (Company Nuclear Review and Audit Group).

J. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the (Company Nuclear Review and Audit Group).

AUTHORITY

6.5.1.7 The (Unit Review Group) shall:

a. Recommend to the (Plant Superintendent) written approval or disapproval of items considered under 6.5.1.6(a) through (d)

above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the (Super- intendent of Power Plants) and the (Company Nuclear Review and Audit Group) of disagreement between the (URG) and the (Plant Superintendent); however, the (Plant Superintendent) shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

PWR-STS-I 6-7

AnUrTmtrCTDTTWV

rW1ILI'SLaI F~ IL V L

rnNTfln

%,FeII.

4J

RECORDS

6.5.1.8 The (Unit Review Group) shall maintain written minutes of each (URG) meeting that, at a minimum, document the results of all (URG)

activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the (Superintendent of Power Plants) and the (Company Nuclear Review and Audit Group).

6.5.2 COMPANY NUCLEAR REVIEW AND AUDIT GROUP (CNRAG)

FUNCTION

6.5.2.1 The (Company Nuclear Review and Audit Group) shall function to provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations b. nuclear engineering c. chemistry and radiochemistry d. metallurgy e. instrumentation and control f. radiological safety g. mechanical and electrical engineering h. quality assurance practices i. (other appropriate fields associated with the unique char- acteristics of the nuclear power plant)

PWR-STS-I 6-8

ADMINISTRATIVE CONTROLS

COMPOSITION

6.5.2.2 The (CNRAG) shall be composed of the:

Director: Position Title)

Member: Position Title)

Member: Position Title)

Member: Position Title)

Member: (Position Title)

ALTERNATES

6.5.2.3 All alternate members shall be appointed in writing by the (CNRAG) Director to serve on a temporary basis; however, no more than two alternates shall participate as voting members in (CNRAG) activities at any one time.

CONSULTANTS

6.5.2.4 Consultants shall be utilized as determined by the (CNRAG)

Director to provide expert advice to the (CNRAG).

MEETING FREQUENCY

6.5.2.5 The (CNRAG) shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

QUORUM

6.5.2.6 The minimum quorum of the (CNRAG) necessary for the performance of the (CNRAG) review and audit functions of these technical specifica- tions shall consist of the Director or his designated alternate and (at least 4 CNRAG) members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

PWR-STS- I 6-9

ADMINISTRATIVE CONTROLS

REVIEW

6.5.2.7 The (CNRAG) shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section

50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes to Technical Specifications or this Operating License.

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

i. Reports and meetings minutes of the (Unit Review Group).

PWR-STS-I 6-10

  • al y., e £lsar i jfnSj lns e ADJMlNlZbAl M 1L oUtI MUL-2 AUDITS

the cognizance

6.5.2.8 Audits of unit activities shall be performed under of the (CNRAG). These audits shall encompass:

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire unit staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational "B",

Quality Assurance Program to meet the criteria of Appendix

10 CFR 50, at least once per 24 months.

e. The Emergency Plan and implementing procedures at least once per 24 months.

f. The Security Plan and implementing procedures at least once per 24 months.

g. Any other area of unit operation considered appropriate by the (CNRAG) or the (Vice President Operations).

h. The Fire Protection Program and implementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.

J. An inspection and audit of the fire protection and loss preven- tion program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

1. The radiological environmental monitoring program and the results there of at least once per 12 months.

PWR-STS-I 6-11

. -.-.. n a ,r ihnaTrilr c APUMr4LlRKlAVrL %u#IIVL4 AUTHORITY

President

6.5.2.9 The (CNRAG) shall report to and advise the (Vice Sections Operations) on those areas of responsibility specified in

6.5.2.7 and 6.5.2.8.

RECORDS

and

6.5.2.10 Records of (CNRAG) activities shall be prepared, approved distributed as indicated below:

a. Minutes of each (CNRAG) meeting shall be prepared, approved and forwarded to the (Vice President-Operations) within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the (Vice President- Operations) within 14 days following completion of the review.

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the (Vice President-Operations) and to the management positions responsible for the areas audited within

30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION

6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the (URG) and submitted to the (CNRAG) and the (Superintendent of Power Plants).

PWR-STS-I 6-12

ADMINISTRATIVE CONTROLS

6.7 SAFETY LIMIT VIOLATION

6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT STANDBY within one hour.

b. The Safety Limit violation shall be reported to the Commission, the (Superintendent of Power Plants) and to the (CNRAG) within

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the (URG). This report shall describe

(1) applicable circumstances preceding the violation, (2)

effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the (CNRAG) and the (Superintendent of Power Plants) within 14 days of the violation.

6.8 PROCEDURES

6.8.1 Written procedures shall be established, implemented and main- tained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b. The radiological environmental monitoring program.

c. Refueling operations.

d. Surveillance and test activities of safety related equipment.

e. Security Plan implementation.

f. Emergency Plan implementation.

g. Fire Protection Program implementation.

h. Offsite releases of gaseous and liquid effluents containing radioactive materials.

i. The PROCESS CONTROL PROGRAM for solidification of radioactive waste.

PWR-STS-I 6-13

  • smlrCTAIrTt~r PMKTOM C

MALJ1llKM1LVC W111rUL-

changes thereto, shall be

6.8.2 Each procedure of 6.8.1 above, and (Plant Superintendent) prior reviewed by the (URG) and approved by the as set forth in administrative to implementation and reviewed periodically procedures.

above may be made pro-

.6.8.3 Temporary changes to procedures of 6.8.1 vided:

is not altered.

a. The intent of the original procedure of the plant management b. The change is approved by two members Senior Reactor Operator's staff, at least one of whom holds a License on the unit affected.

the (URG) and approved by c. The change is documented, reviewed bydays of implementation.

the (Plant Superintendent) within 14

6.9 REPORTING REQUIREMENTS

ROUTINE REPORTS AND REPORTABLE OCCURRENCES

requirements of Title 10,

6.9.1 In addition to the applicable reporting reports shall be submitted Code of Federal Regulations, the following Inspection and Enforcement to the Director of the Regional Office of unless otherwise noted.

STARTUP REPORT

and power escalation testing

6.9.1.1 A summary report of plant startupof an operating license, (2)

shall be submitted following (1) receipt planned increase in power level, amendment to the license involving adifferent design or has been manu-

(3) installation of fuel that has a (4)modifications that may factured by a different fuel supplier, and thermal, or hydraulic perfor- have significantly altered the nuclear, mance of the plant.

each of the tests identified in

6.9.1.2 The startup report shall address of the measured values of the the FSAR and shall include a description obtained during the test program operating conditions or characteristicsdesign predictions and specifica- and a comparison of these values with required to obtain satisfactory tions. Any corrective actions that were additional specific details operation shall also be described. Any other commitments shall be in- required in license conditions based on cluded in this report.

PWR-STS-I 6-14

K>

ADMINISTRATIVE CONTROLS

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTSY

6.9.1.4 Annual reports covering the activities of the unit as described1 below for the previous calendar year shall be submitted prior to March of each year. The initial report shall be submitted prior to March I of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions,= e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. The results of steam generator tube inservice inspections performed during the report period. (CE, W-& B&W units only).

c. The results of the core barrel movement monitoring activities performed during the report period. (CE units only).

d. (Any other unit unique reports required on an annual basis.)

YA single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of 520.407 of 10 CFR

Part 20.

PWR-STS-I 6-15

ADMINISTRATIVE CONTROLS

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT19

6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveil- lance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equip- ment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses required by the Specification 3.12.2; and the results of licensee participation in the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program required by Specification 3.12.3.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-V

6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the data of initial criticality.

3/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

)WR-STS- I 6-16

( TABLE 6.9-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMMARY

  • -o - Nam of Facility Docmet No.__

Location of Facility Reporting Period

1County. Staft)

I

n-

-, Y Y V I T

Type and Lower Limit Nurnberof Medium or Pathway Totl Number of All Indicator L -eions Location wh Highest Annual Mein ontrol Lons If) Me(f), REPORTABLE,,

SaMled of Andye Detecion MRm Ne Mesn (fib (Unit of Measurement) Pomed ILLD)

ppb Distance and Direction Rngb OCCURRENCM

Ranpe

4 4 I 44 4.

Air Particulates (pCi/m 3 ) Gross p 418 0.003 0.081200/312) Middletown 0.10(5152) 0.08(8/104) I

(0.05-2.0) 5 miles 340" (0.082.0) (0.05-1.40)

7-Spec. 32

. 137C.

0.003 0.05(4/24) Smithvl le 0.08 (2/4) <LLD 4 C

.2 (0.03.0.13) 2.5 miles 16 (0.03-0.13)

C 14000

i 0.003 0.03(2/24) Podunk 0.05 (2/4) 0.02(1/8)

10.01.0.08) 4.0 miles 270Q (0.01Q.008)

-J a 89sr 0

-. 40 0.002 <LLD <LLD

E

90

w1 Sr 40 0.0003 <LLD <LLD °(

Fish pCi/kg (dry weight) 7-Spec. 8

137C.

80 <LLD <LLD 9011/4) 0

134 Cs <LLD <LLD <LLD 0-

60 0

Co 80 120(314) River Mile 35 See column 4 <LLD

(90.200) Podunk River Nominal Lower Limit of Detaction (LLD) as defined in table notation a. of Table 4.12.1 of Specification 4.12.1.1.

IIen nd rang based upon detectable measurements only. Fraction of detectable measurements at speflied lecetiona Is Indicated In parentheses.

i dNote: The example daft ae provided for Illustrative purposes only.

ADMINISTRATIVE CONTROLS

6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B

thereof.

The radioactive effluent release reports shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1)

during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.

The radioactive effluent release reports shall include the following information for all unplanned offsite releases of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved.

b. Cause(sl for the unplanned release.

c. Actions taken to prevent recurrence.

d. Consequences of the unplanned release.

The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive ltqutd and gaseous effluents released from the unit during each calendar quarter as outlined in

'Regulatory Gutde 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The meteorological conditions concurrent with the releases of effluents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with NUREG-0133.

PWR-STS-I 6-18

ADMINISTRATIVE CONTROLS

MONTHLY REACTOR OPERATING REPORT

6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspec- tion and Enforcement, no later than the 15th of each month following the calendar month covered by the report.

REPORTABLE OCCURRENCES

6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP

6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supple- mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored para- meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.

b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.

c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

PWR-STS-I 6-19

ADMINISTRATIVE CONTROLS

d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN

less conservative than specified in the technical specifica- tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality.

e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR,

f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require- ments of systems required to cope with accidents analyzed in the SAR.

g. Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by technical specifications.

h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

i. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica- tions bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or cor- rective measures to prevent the existence or development of an unsafe condition.

J. Occurrence of an unusual or important event that causes a significant environmental impact, that affects potential environmental impact from unit operation, or that has high public or potential public interest concerning environmental impact from unit operation.

k. Occurrence of radioactive material contained in liquid or gaseous holdup tanks in excess of that permitted by the limiting condi- tion for operation established in the technical specifications.

PWR-STS- I 6-20

ADMINISTRATIVE CONTROLS

THIRTY DAY WRITTEN REPORTS

6.9.1.13 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Reactor protection system or engineered safety feature instru- ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re- quired by a limiting condition for operation.

c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d. Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.

e. An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than

150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:

1. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned release.

PWR-STS-I 6-21

ADMINISTRATIVE CONTROLS

f. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 6.9-2 when averaged over any calendar quarter sampling period. When more than one of the radionuclides in Table 6.9-2 are detected in the sampling medium, this report shall be submitted if:

concentration j1) + concentration (2) + .... >1.0

iMIT level (1) limit Tevel (2)

When radionuclides other than those in Table 6.9-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifica- tions 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

SPECIAL REPORTS

Special reports may be required covering inspections, test and main- tenance activities. These special reports are determined on an indi- vidual basis for each unit and their preparation and submittal are designated in the Technical Specifications.

6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.

PWR-STS-I 6-22

( 'N

C

TABLE 6.9-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

(nI

-4 (A

Reporting Levels

  • 9 -

Analysis

4 Water

.9 Airborne Particulate or Gases (pCI/M 3)

4 Fish (pCi/Kg, wet)

4 Milk (pC/l)

4 Vegetables (pCi/Kg, wet) 1 H-3 3 x 104 Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 104 Co-58 1 x 103 3 x 104 cm Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 Zr-Nb-95 4 x 102

1-131 2 0.9 3 I x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-l 40 2

2xx 102 to2 3x

3 x 10

102 I 1 4

&tRv&,*P-rnATriUD rnuirnn c AU~llr lllVCr~AIiIEUL0

6.10 RECORD RETENTION

In addition to the applicable record retention requirements of Title 10,

Code of Federal Regulations, the following records shall be retained for at least the minimum period.indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. ALL REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specifica- tion 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a. Records and drawing changes reflecting unit design modifica- tions made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

PWR-STS -I 6-24

AnUThtfTCDA'TMvr efnMTDnl C

e. Records of transient of operational cycles for those unit com- ponents identified in Table 5.7-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the unit staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA

Manual.

J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10

CFR 50.59.

k. Records of meetings of the (URG) and the (CNRAG).

6.11 RADIATION PROTECTION PROGRAM

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA (OPTIONAL)

6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than

1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

  • Health Physics personnel or personnel escorted by Health Physics per- sonnel in accordance with approved emergency procedures shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radia- tion protection procedures for entry into high radiation areas.

PWR-STS-I 6-25

a..tfl* ,

AI'

-

DMINISTKAI LY LCUN I KULQ

integrates the b. A radiation monitoring device which continuously when a preset inte- radiation dose rate in the area and alarms areas with this grated dose is received. Entry into suchdose rate level in the monitoring device may be made after the have been made knowl- area has been established and personnel edgeable of them.

protection procedures who c. An individual qualified in radiation monitoring device.

is equipped with a radiation dose ratefor providing positive This individual shall be responsible area and shall perform control over the activities within the frequency specified by periodic radiation surveillance at the Work Permit.

the facility Health Physicist in the Radiation shall also apply to each high

6.12.2 The requirements of 6.12.1, above,radiation is greater than radiation area in which the Intensity of shall be provided to prevent

1000 mrem/hr. In addition, locked doors keys shall be maintained unauthorized entry into such areas and the Shift Supervisor on duty and/or under the administrative control of the the Plant Health Physicist.

PWR-STS-I 6-26

ENCLOSURE NO. 2 APPENDIX I TECHNICAL SPECIFICATIONS

LICENSEE SUBMITTAL DATES

60 Days 120 Days 150 Days 180 Days Farl ey Big Rock Point Arkansas 1 Beaver Valley Hatch 1/2 Ginna Brunswick 1/2 Browns Ferry 1/2/3 Haddam Neck Crystal River Calvert Cliffs 1/2 La Crosse Dresden 1/2/3 Cook 1/2 Oyster Creek FitzPatrick Cooper San Onofre Indian Point 1/2/3 Davis Besse Surry 1/2 Millstone 1/2 Duane Arnold Yankee Rowe Monticello Fort Calhoun Nine Mile Point Humboldt Bay Oconee 1/2/3 Kewaunee Peach Bottom 2/3 Maine Yankee Pilgrim 1 North Anna 1/2 Quad Cities 1/2 Palisades Robinson 2 Point Beach 1/2 Turkey Point 3/4 Prairie Island 1/2 Vermont Yankee Rancho Seco Zion 1/2 Salem 1 St. Lucie 1 Three Mile Island 1/2 Trojan

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