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DB-1
DB-1
, D ENVIRONMENTAL TECHNICAL SPECIFICATIONS TABLE OF CONTENTS                                                            .
, D ENVIRONMENTAL TECHNICAL SPECIFICATIONS TABLE OF CONTENTS                                                            .
                                                      .
PAGE-
PAGE-
       ,      LIST OF TABLES .        . . . . . . . .. ..... ..... ..                                                iii LIST OF FIGURES.        . . .. . . . ....... .......                                                    iv 1.0 DEFINITIONS.    . . . . .. . . . ..... .. .. .....                                                    1.0 2.0 LIMITING CONDITIONS FOR OPERATION.                            ...... .                      .. .. 2.1-1 2.1 Deleted .      . . . . . . .. ........ ......
       ,      LIST OF TABLES .        . . . . . . . .. ..... ..... ..                                                iii LIST OF FIGURES.        . . .. . . . ....... .......                                                    iv 1.0 DEFINITIONS.    . . . . .. . . . ..... .. .. .....                                                    1.0 2.0 LIMITING CONDITIONS FOR OPERATION.                            ...... .                      .. .. 2.1-1 2.1 Deleted .      . . . . . . .. ........ ......
2.1.1 Deleted . . . . . . . . . . . . .                                    ...... .          2.1-1
2.1.1 Deleted . . . . . . . . . . . . .                                    ...... .          2.1-1 2.2 Deleted 2.3    Deleted . . . . . .    . . . ...... .. .. ....                                                2.3-1 2.3.1 Deleted.        . . . . . ....... .... ...
* 2.2 Deleted
  .
2.3    Deleted . . . . . .    . . . ...... .. .. ....                                                2.3-1 2.3.1 Deleted.        . . . . . ....... .... ...
2.3.2 Deleted.        . . . . . .. .... .. .. .. ..
2.3.2 Deleted.        . . . . . .. .... .. .. .. ..
2.3.3 Deleted.        . . . . . ....... . ......
2.3.3 Deleted.        . . . . . ....... . ......
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3.1.2.a    Deleted.        . . . . ... .... .. .. ...                                                              .
3.1.2.a    Deleted.        . . . . ... .... .. .. ...                                                              .
3.1.2.b    Deleted.        . . . . . .. .... .... .. .
3.1.2.b    Deleted.        . . . . . .. .... .... .. .
3.2    Environmental Radiation Monitoring.                            ... .. ....                  3.2-1 4.0 SPECIAL SURVEILLANCE, AND STUDY ACTIVITIES .                                        .......          4.0-1 4.1 Deleted .        . . . . . . . . .. .... .. .... ..                                              4.0-1
3.2    Environmental Radiation Monitoring.                            ... .. ....                  3.2-1 4.0 SPECIAL SURVEILLANCE, AND STUDY ACTIVITIES .                                        .......          4.0-1 4.1 Deleted .        . . . . . . . . .. .... .. .... ..                                              4.0-1 4.2 Deleted .        . . . . . . . . .. .... .. .. .. ..                                              4.0-1 4.3      Deleted .  . .. . . . . . . ...... .. .. .. ..                                              4.0-1 8006170 9 1 p        I                                                i
                                                                                                                                              .
4.2 Deleted .        . . . . . . . . .. .... .. .. .. ..                                              4.0-1 4.3      Deleted .  . .. . . . . . . ...... .. .. .. ..                                              4.0-1
                                                                                *
                                                                                                                  .
8006170 9 1 p        I                                                i
                                                                                                              '
                    . .              -      .-            . - . - . . . - .          ._. _ - . . . -.              ..-.-. -  - . - . - - .


                                                                                                    .
   .                                                      DB-1 PAGE 5.0 ADMINISTRATIVE CONTROLS .      . .    .'.    . . . . . .. . . . . . .          5.1-1 5.1  Review and Audit . . . . .. . .. . . . .. . . . . .                      5.1-1 5.1.1 Station Review Board. . . . . . .. .. . . . .                      5.1-1 5.1.2 Company Nuclear Review Board. . . . . . . . . .                    5.1-1 5.1.3  Quality Assurance Manager .                . . . .. . . . . . 5.1-1 5.2 Action To Be Taken In The Evnet Cf Violation Of An Environmental Technical Specification.                    . .. . . . . . 5.2-1 5.3 Operating Procedures .        . . . . . . . .. . . . . . . .                5.3-1 5.4 Unit Reporting Requirements.            . . . .. .. .. . . . .            5.4-1 5.4.1 Routine Reports . . . . ..        . . .. .. . . . .                  5.4-1 5.4.2  Non-Rout;ine Reports .          . . . . . .. . . . . . .          5.4-2 5.4.3  Changes  . . . . . .. . . . . . . .. . . . . .                      5.4-4 5.5  Record Retention .    . . . .. .. . . .. .. . . . . .                      5.5-1 I
        .
e 11
          < .
      *
                                                                                                                    '
   .                                                      DB-1
    .
PAGE
                                                                                                              .
5.0 ADMINISTRATIVE CONTROLS .      . .    .'.    . . . . . .. . . . . . .          5.1-1 5.1  Review and Audit . . . . .. . .. . . . .. . . . . .                      5.1-1 5.1.1 Station Review Board. . . . . . .. .. . . . .                      5.1-1 5.1.2 Company Nuclear Review Board. . . . . . . . . .                    5.1-1 5.1.3  Quality Assurance Manager .                . . . .. . . . . . 5.1-1 5.2 Action To Be Taken In The Evnet Cf Violation Of An Environmental Technical Specification.                    . .. . . . . . 5.2-1 5.3 Operating Procedures .        . . . . . . . .. . . . . . . .                5.3-1 5.4 Unit Reporting Requirements.            . . . .. .. .. . . . .            5.4-1 5.4.1 Routine Reports . . . . ..        . . .. .. . . . .                  5.4-1 5.4.2  Non-Rout;ine Reports .          . . . . . .. . . . . . .          5.4-2 5.4.3  Changes  . . . . . .. . . . . . . .. . . . . .                      5.4-4 5.5  Record Retention .    . . . .. .. . . .. .. . . . . .                      5.5-1
                                                                                                            .
                                                                                                                .
                                                                                    .
I e
                                                                    .
                                                                      .
'
11
    .
                                                                                                                  .


      , .
.                                      DB-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF TABLES Table Numbe r                      Title                Page 2.4-1    Radioactive Liquid Waste Sampling and    2.4-13 Analysis 2.4-2    Radioactive Gaseous Waste Sampling and  2.4-14 Analysis 2.4-3    Pressurized Water Reactor Liquid Waste  2.4-16 System, Location of Process and Effluent Monitors and Samplers Required by Technical Specifications 2.4-4    Pressurized Water Reactor Gaseous Waste  2.4-17 System, Location of Process and Effluent Monitors and Samplers Required by Technical Specifications 2.4-5    Gamma and Beta Dose Factors              2.4-18 3.1-1    Deleted 1
    *
.                                      DB-1
  .
ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF TABLES
                                    ,
Table Numbe r                      Title                Page 2.4-1    Radioactive Liquid Waste Sampling and    2.4-13 Analysis 2.4-2    Radioactive Gaseous Waste Sampling and  2.4-14 Analysis 2.4-3    Pressurized Water Reactor Liquid Waste  2.4-16 System, Location of Process and Effluent Monitors and Samplers Required by Technical Specifications 2.4-4    Pressurized Water Reactor Gaseous Waste  2.4-17 System, Location of Process and Effluent Monitors and Samplers Required by Technical Specifications 2.4-5    Gamma and Beta Dose Factors              2.4-18 3.1-1    Deleted 1
3.2-1    Radiological Environmental Moitoring    3.2-3 Program 3.2-2    Sampling Locations                      3.2-6      ,
3.2-1    Radiological Environmental Moitoring    3.2-3 Program 3.2-2    Sampling Locations                      3.2-6      ,
                                                                          .
3.2-3    Typical Estimated Minimum Detectable    3.2-7 Concentrations l
3.2-3    Typical Estimated Minimum Detectable    3.2-7
            -
Concentrations l
                                                                            ;
T e
T e
S e
S e
e 111
e 111 j
                                                                  .
                                  .                                  _
j


__._                    .. _
     .                                                        DB-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF FIGURES 1
        .-
Figure
          .
     .                                                        DB-1
      .
ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF FIGURES
  .
                                                                                                          .
1 Figure
  .          Number                                          Title                                            Page J
  .          Number                                          Title                                            Page J
;            3.1-1                  Deleted I          3.2-1                  Environmental Media and Exposure Pathways                                3.2-9
;            3.1-1                  Deleted I          3.2-1                  Environmental Media and Exposure Pathways                                3.2-9 3.2-2                  Sampling Locations On The Site Periphery                                3.2-10 3.2-3                  Sampling Locations (Excepting Those On                                  3.2-11 The Site Periphery) i f
,
3.2-2                  Sampling Locations On The Site Periphery                                3.2-10 3.2-3                  Sampling Locations (Excepting Those On                                  3.2-11 The Site Periphery) i f
                                                                                                                                        .
I                                                                                                                                        e i                                                                                                                .
I                                                                                                                                        e i                                                                                                                .
                                                    .
T G
,
T
!
!
.
G
                        ,
                                                                        .
                                                                            .
iv
iv
,
                 , , - ,  ,r - --,-      , - - - -    ,.e <-,s    -e-e---rwe.~emw,,--n.nm  r,wm,~~-ns,_,,    ,emmer-,~.ev,-,na,wv,ws
                 , , - ,  ,r - --,-      , - - - -    ,.e <-,s    -e-e---rwe.~emw,,--n.nm  r,wm,~~-ns,_,,    ,emmer-,~.ev,-,na,wv,ws


  .
    '
.                  ,
DB-1 1.0      DEFINITIONS Beach Sampling Station - Sampling station located on the discharge conduit at the beachfront approximately 2700 feet from the collection box.
DB-1 1.0      DEFINITIONS Beach Sampling Station - Sampling station located on the discharge conduit at the beachfront approximately 2700 feet from the collection box.
                    .
e Circulating Water System - System for conveying waste heat from the condensers to the cooling tower for rejection to the atmosphere.
e
                              .
Circulating Water System - System for conveying waste heat from the condensers to the cooling tower for rejection to the atmosphere.
      .
Circulating Water - Water used for heat transport in the circulating water system.
Circulating Water - Water used for heat transport in the circulating water system.
Commercial Operation - When the unit is declared commercial by the Toledo Edison Company.
Commercial Operation - When the unit is declared commercial by the Toledo Edison Company.
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         *1ake to maintain circulating water dissolved solids at or below the desired concentration.
         *1ake to maintain circulating water dissolved solids at or below the desired concentration.
Daily - Every day except Saturdays, Sundays and Holidays (New Year's Day, Presi-dent's Day, Good Friday, Memorial Day, Independence Day, Labor Day, Thanksgiving Day, and Christmas Day).
Daily - Every day except Saturdays, Sundays and Holidays (New Year's Day, Presi-dent's Day, Good Friday, Memorial Day, Independence Day, Labor Day, Thanksgiving Day, and Christmas Day).
1 Discharge Conduit - 72 inch diameter conduit, underground and beneath the lake bottom to convey the unit's discharge water from the collection box to the dis-
1 Discharge Conduit - 72 inch diameter conduit, underground and beneath the lake bottom to convey the unit's discharge water from the collection box to the dis-charge structure in Lake 3 Erie.
* charge structure in Lake 3 Erie.
Initial Criticality - The First attainment of a self-sustaining fission reaction within the reactor core.
Initial Criticality - The First attainment of a self-sustaining fission reaction within the reactor core.
Intake Canal - Open canal, with' earthen embankments, to convey lake water from the intake conduit to the intake structure.
Intake Canal - Open canal, with' earthen embankments, to convey lake water from the intake conduit to the intake structure.
Line 132: Line 62:
Quarterly - At least once every 92 days with a maximum allowable extension of 25%.
Quarterly - At least once every 92 days with a maximum allowable extension of 25%.
1.0-1  ,  -- .- - -
1.0-1  ,  -- .- - -
                                                                              . _ . - - , - - .-


_ _ _
,
  .
    -
        .
                      ,
DB-1 2.0    LIMITING CONDITIONS FOR OPERATION 2.1  Deleted 2.2  Deleted
DB-1 2.0    LIMITING CONDITIONS FOR OPERATION 2.1  Deleted 2.2  Deleted
                                                          .
                                          .
           ~4. 3 Deleted    ,
           ~4. 3 Deleted    ,
      .
e f
e f
e I
e I
                                                      .
6 2.1-1
6
* 2.1-1


.    -
DB-1 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Deleted e
_
9 5
DB-1
e 3.1-1
  '
3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Deleted
                                      .
e 9
5
    .
e
                                                .
                                                        -
                                                    @
                                                  .
                                                          !
3.1-1


      .
        .
'
           ^
           ^
            .  .
DB-1
DB-1
* 4.0  SPECIAL SURVEILLANCE, AND STUDY ACTIVITIES 4.1  Deleted 4.2  Deleted
* 4.0  SPECIAL SURVEILLANCE, AND STUDY ACTIVITIES 4.1  Deleted 4.2  Deleted 4.3  Deleted O
                                                .
e e
4.3  Deleted
G
              .
O e
                              .
e G
  .
                                                                 )
                                                                 )
l l
l l
                                          .
1 4.0-1
1 4.0-1


        .
          .
.          .    .                                                DB-1
.          .    .                                                DB-1
  ,
       ..~                          .
       ..~                          .
    >
5,0    ADMINISTRATIVE CONTROLS 5.4    Unit Reporting Requirements 5.4.1  Routine Reports                                                .
5,0    ADMINISTRATIVE CONTROLS 5.4    Unit Reporting Requirements 5.4.1  Routine Reports                                                .
                                                                                                                      -
                   . A. Annual Environmental Operating Report Part A - Deleted Part B - A report on the radiological environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the'NR'C Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days af ter January 1 of each year. The period of the first report shall begin with the date of initial criticality. The 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 surveillance reports and an assessment of the observed impacts of the unit operation on the environment.            The' report shall also include the results of land use censuses required by the specification. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course                                                    .
                                                              .
                   . A. Annual Environmental Operating Report Part A - Deleted
              .
                .
                                                                                                      '
Part B - A report on the radiological environmental surveillance programs
      -
for the previous 12 months of operation shall be submitted to the Director of the'NR'C Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days af ter January 1 of each year. The period of the first report shall begin with the date of initial criticality. The 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 surveillance reports and an assessment of the observed impacts of the unit operation on the environment.            The' report shall also include the results of land use censuses required by the specification. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course                                                    .
of action to alleviate the problem.
of action to alleviate the problem.
                                                                                                                    .
Results of all radiological environmental samples taken shall be summarized and tabulated on an annual basis following a format similar to Table 1 of Regulatory Guide 4.8, December 1975.            In the event that some results are not available within the 90 day period, 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.
Results of all radiological environmental samples taken shall be summarized and tabulated on an annual basis following a format similar to Table 1 of Regulatory Guide 4.8, December 1975.            In the event that some results are not available within the 90 day period, 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.
                                                                          .
5.4-1
5.4-1
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                                             - , + , , , , - ,  e,    w        w -y,----v-  y , , - ,--w  e+, ,sw-,  s v--- msw-pm-p M-- 9 m "ovm-gm? v}}

Latest revision as of 18:14, 21 February 2020

Mod to ETS Eliminating Sections 2.1,2.2,2.3,3.1,4.0,5.4.1 Part a & Changing Table of Contents,Lists of Figures & Table, & Section 1.0 of App B to Tech Specs
ML19312E827
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/13/1980
From:
TOLEDO EDISON CO.
To:
Shared Package
ML19312E825 List:
References
TAC-42152, NUDOCS 8006170472
Download: ML19312E827 (9)


Text

n'.- .

DB-1

, D ENVIRONMENTAL TECHNICAL SPECIFICATIONS TABLE OF CONTENTS .

PAGE-

, LIST OF TABLES . . . . . . . . .. ..... ..... .. iii LIST OF FIGURES. . . .. . . . ....... ....... iv 1.0 DEFINITIONS. . . . . .. . . . ..... .. .. ..... 1.0 2.0 LIMITING CONDITIONS FOR OPERATION. ...... . .. .. 2.1-1 2.1 Deleted . . . . . . . .. ........ ......

2.1.1 Deleted . . . . . . . . . . . . . ...... . 2.1-1 2.2 Deleted 2.3 Deleted . . . . . . . . . ...... .. .. .... 2.3-1 2.3.1 Deleted. . . . . . ....... .... ...

2.3.2 Deleted. . . . . . .. .... .. .. .. ..

2.3.3 Deleted. . . . . . ....... . ......

2.4 Radioactive Effluents . . ........ .... .. 2.4-1 3.0 ENVIRONMENTAL SURVEILLANCE . . . ...... .... ... 3.1-1 3.1 Deleted . . . . . . . . . . ...... .. .. ... 3.1-1 3.1.1.a Deleted. . . . . ....... .. .. ...

3.1.2.a Deleted. . . . . ... .... .. .. ... .

3.1.2.b Deleted. . . . . . .. .... .... .. .

3.2 Environmental Radiation Monitoring. ... .. .... 3.2-1 4.0 SPECIAL SURVEILLANCE, AND STUDY ACTIVITIES . ....... 4.0-1 4.1 Deleted . . . . . . . . . .. .... .. .... .. 4.0-1 4.2 Deleted . . . . . . . . . .. .... .. .. .. .. 4.0-1 4.3 Deleted . . .. . . . . . . ...... .. .. .. .. 4.0-1 8006170 9 1 p I i

. DB-1 PAGE 5.0 ADMINISTRATIVE CONTROLS . . . .'. . . . . . .. . . . . . . 5.1-1 5.1 Review and Audit . . . . .. . .. . . . .. . . . . . 5.1-1 5.1.1 Station Review Board. . . . . . .. .. . . . . 5.1-1 5.1.2 Company Nuclear Review Board. . . . . . . . . . 5.1-1 5.1.3 Quality Assurance Manager . . . . .. . . . . . 5.1-1 5.2 Action To Be Taken In The Evnet Cf Violation Of An Environmental Technical Specification. . .. . . . . . 5.2-1 5.3 Operating Procedures . . . . . . . . .. . . . . . . . 5.3-1 5.4 Unit Reporting Requirements. . . . .. .. .. . . . . 5.4-1 5.4.1 Routine Reports . . . . .. . . .. .. . . . . 5.4-1 5.4.2 Non-Rout;ine Reports . . . . . . .. . . . . . . 5.4-2 5.4.3 Changes . . . . . .. . . . . . . .. . . . . . 5.4-4 5.5 Record Retention . . . . .. .. . . .. .. . . . . . 5.5-1 I

e 11

. DB-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF TABLES Table Numbe r Title Page 2.4-1 Radioactive Liquid Waste Sampling and 2.4-13 Analysis 2.4-2 Radioactive Gaseous Waste Sampling and 2.4-14 Analysis 2.4-3 Pressurized Water Reactor Liquid Waste 2.4-16 System, Location of Process and Effluent Monitors and Samplers Required by Technical Specifications 2.4-4 Pressurized Water Reactor Gaseous Waste 2.4-17 System, Location of Process and Effluent Monitors and Samplers Required by Technical Specifications 2.4-5 Gamma and Beta Dose Factors 2.4-18 3.1-1 Deleted 1

3.2-1 Radiological Environmental Moitoring 3.2-3 Program 3.2-2 Sampling Locations 3.2-6 ,

3.2-3 Typical Estimated Minimum Detectable 3.2-7 Concentrations l

T e

S e

e 111 j

. DB-1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS LIST OF FIGURES 1

Figure

. Number Title Page J

3.1-1 Deleted I 3.2-1 Environmental Media and Exposure Pathways 3.2-9 3.2-2 Sampling Locations On The Site Periphery 3.2-10 3.2-3 Sampling Locations (Excepting Those On 3.2-11 The Site Periphery) i f

I e i .

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iv

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DB-1 1.0 DEFINITIONS Beach Sampling Station - Sampling station located on the discharge conduit at the beachfront approximately 2700 feet from the collection box.

e Circulating Water System - System for conveying waste heat from the condensers to the cooling tower for rejection to the atmosphere.

Circulating Water - Water used for heat transport in the circulating water system.

Commercial Operation - When the unit is declared commercial by the Toledo Edison Company.

Collection box - A structure which collects all unit discharges to Lake Erie and discharges them to the discharge conduit Cooling Tower Blowdown - The portion of the circulating water removed from the coldside of the cooling tower and discharged to the collection box, then to the

  • 1ake to maintain circulating water dissolved solids at or below the desired concentration.

Daily - Every day except Saturdays, Sundays and Holidays (New Year's Day, Presi-dent's Day, Good Friday, Memorial Day, Independence Day, Labor Day, Thanksgiving Day, and Christmas Day).

1 Discharge Conduit - 72 inch diameter conduit, underground and beneath the lake bottom to convey the unit's discharge water from the collection box to the dis-charge structure in Lake 3 Erie.

Initial Criticality - The First attainment of a self-sustaining fission reaction within the reactor core.

Intake Canal - Open canal, with' earthen embankments, to convey lake water from the intake conduit to the intake structure.

Monthly - At least once every 31 days with a* maximum allowable extension of 25%

Quarterly - At least once every 92 days with a maximum allowable extension of 25%.

1.0-1 , -- .- - -

DB-1 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Deleted 2.2 Deleted

~4. 3 Deleted ,

e f

e I

6 2.1-1

DB-1 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Deleted e

9 5

e 3.1-1

^

DB-1

  • 4.0 SPECIAL SURVEILLANCE, AND STUDY ACTIVITIES 4.1 Deleted 4.2 Deleted 4.3 Deleted O

e e

G

)

l l

1 4.0-1

. . . DB-1

..~ .

5,0 ADMINISTRATIVE CONTROLS 5.4 Unit Reporting Requirements 5.4.1 Routine Reports .

. A. Annual Environmental Operating Report Part A - Deleted Part B - A report on the radiological environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the'NR'C Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days af ter January 1 of each year. The period of the first report shall begin with the date of initial criticality. The 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 surveillance reports and an assessment of the observed impacts of the unit operation on the environment. The' report shall also include the results of land use censuses required by the specification. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course .

of action to alleviate the problem.

Results of all radiological environmental samples taken shall be summarized and tabulated on an annual basis following a format similar to Table 1 of Regulatory Guide 4.8, December 1975. In the event that some results are not available within the 90 day period, 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.

5.4-1

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