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- . - .
                                                                                                                                                    ,
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION l
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1
      *
Docket Nos.:
                                                                                                                                                    j
50-277; 50-278
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l                                                                                                                                                    l
l                                                                                                                                                    I
l                                                                                                                                                    1
l                                                            U.S. NUCLEAR REGULATORY COMMISSION                                                    I
                                                                                REGION l                                                            i
                                                                                                                                                    !
                                                                                                                                                    i
                                                                                                                                                      l
                                                                                                                                                    1
                                                                                                                                                    1
                        Docket Nos.:                              50-277; 50-278
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l                      Report Nos.:                               50-277/97-03; 50-278/97-03
Report Nos.:
50-277/97-03; 50-278/97-03
!
!
r
r
  .
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                        Licensee:                                 Philadelphia Electric Company
Licensee:
                        Facility:                                 Peach Bottom Atomic Power Station                                                 !
Philadelphia Electric Company
[                       Location:                                 P.O. Box 195                                                                       ,
Facility:
Peach Bottom Atomic Power Station
[
Location:
P.O. Box 195
,
'
'
                                                                  Wayne, Pennsylvania 19087-0195
Wayne, Pennsylvania 19087-0195
                        Dates:                                     December 9,1996 - January 24,1997
Dates:
December 9,1996 - January 24,1997
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                        Inspector:                                 Laurie A. Peluso, Health Physicist
Inspector:
'
Laurie A. Peluso, Health Physicist
                                                                  Radiation Safety Branch, DRS
'
                        Approved by:                               John R. White, Chief                                                               l
Radiation Safety Branch, DRS
Approved by:
John R. White, Chief
Radiation Safety Branch
,
,
                                                                  Radiation Safety Branch
                                                                  Division of Reactor Safety
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Division of Reactor Safety
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I                                                                                                                                                      l
t                                                                                                                                                    .
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:                                                                                                                                                     i
:
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                                                                                                                                                    l
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                                                                                                                                                    1
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                    @ A8bu M88bgr,                                                                                                                   l
@ A8bu M88bgr,
                                                  PDR                                                                                                 l
PDR
                                                                                                                                                    !
!
                                                                                                                                                  .l
.l


          .       ..                       -   -_           .-         .-   _-   -_-   . _ - - .
,
,                                                                                                    ,
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t ,                                                                                                   !
..
                                                                                                      ,
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l .                                                                                                 !
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1                                                                                                    1
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j                                           Report Details
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                                                                                                      ,
Report Details
                                                                                                      '
,
'
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!
i                                         IV. Plant Support
i
    R1     Radiological Protection and Chemistry (RP&C) Controls                                     !
IV. Plant Support
    R1.1 Imolementation of the Radioloaical Environmental Monitorina Proara_rn
R1
      a.   Insoection Scope (84750)
Radiological Protection and Chemistry (RP&C) Controls
          The inspector observed and assessed the licensee's capability to implement the
R1.1 Imolementation of the Radioloaical Environmental Monitorina Proara_rn
            radiological environmental monitoring program (REMP). The program was inspected
a.
            against ODCM Sections 3.8.E.1 and 3.8.E.2, Regulatory Guide 4.1, " Programs for
Insoection Scope (84750)
            Monitoring Radioactivity in the Environs of Nuclear Power Plants," and the Updated
The inspector observed and assessed the licensee's capability to implement the
            Final Safety Analysis Report (UFSAR).
radiological environmental monitoring program (REMP). The program was inspected
      b.   Observations and Findinas
against ODCM Sections 3.8.E.1 and 3.8.E.2, Regulatory Guide 4.1, " Programs for
Monitoring Radioactivity in the Environs of Nuclear Power Plants," and the Updated
Final Safety Analysis Report (UFSAR).
b.
Observations and Findinas
I
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          The inspector examined selected sampling stations to determine whether samples
The inspector examined selected sampling stations to determine whether samples
            were being obtained from the locations designated in the ODCM and whether air
were being obtained from the locations designated in the ODCM and whether air
            samplers were operable and calibrated. Air sampling equipment was calibrated at
samplers were operable and calibrated. Air sampling equipment was calibrated at
l           the frequency specified in the associated procedure. The sampling stations included       l
l
l          air samplers for iodines and particulates, composite water sampling stations located
the frequency specified in the associated procedure. The sampling stations included
            at the plant intake and discharge, milk farms, vegetation locations, and
l
          thermoluminescent dosimeter (TLD) stations for measurement of direct ambient
air samplers for iodines and particulates, composite water sampling stations located
!           radiation. All air sampling equipment and water compositors at the selected
at the plant intake and discharge, milk farms, vegetation locations, and
            locations were functioning as designed. The sampling equipment, as evidenced by
thermoluminescent dosimeter (TLD) stations for measurement of direct ambient
          the sample log books and analysis results, had operated continuously through the
!
            year with few exceptions. The above environmental sampling media were available
radiation. All air sampling equipment and water compositors at the selected
            at the locations designated in the ODCM, and TLDs were placed at locations
locations were functioning as designed. The sampling equipment, as evidenced by
l           designated in the ODCM. Analytical results did not indicate any anomalous trends.
the sample log books and analysis results, had operated continuously through the
l           Sampling and analysis was performed as required. Compensatory sampling
year with few exceptions. The above environmental sampling media were available
at the locations designated in the ODCM, and TLDs were placed at locations
l
designated in the ODCM. Analytical results did not indicate any anomalous trends.
l
Sampling and analysis was performed as required. Compensatory sampling
(suriace, drinking water) was performed as required when applicable. Although the
'
'
            (suriace, drinking water) was performed as required when applicable. Although the
number of samples taken had been reduced, the licensee continued to collect and
            number of samples taken had been reduced, the licensee continued to collect and
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j           analyze more samples than required by the ODCM. Program changes were made in
analyze more samples than required by the ODCM. Program changes were made in
l           1995 and were documented in the annual Radiological Environmental Operating
l
            Report (REOR). The changes made have not reduced the original intent of the
1995 and were documented in the annual Radiological Environmental Operating
!           REMP.                                                                                     1
Report (REOR). The changes made have not reduced the original intent of the
                                                                                                      l
!
                                                                                                      l
REMP.
                                                                                                      l
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:
:
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                                                                                                      i


      - - . .       . .               .               - - -         .     ._       -.           -.
-
  '
-
    .
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                    .
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  *
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    .
.
                                                                                                          ]
- - -
                                                                                                        '
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2
Review of the land use census, required yearly by the ODCM, revealed that the
licensee performed the census in 1994,1995 and 1996. During the 1994 census,
!
the licensee noted that a milk farm close to the plant had been reestablished.
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During the 1995 census, completed in September 1995, the licensee calculated the
D/O values for all the sectors and determined that the "new" farm has a D/O value
i
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(a calculated dose or dose commitment) that is at least 20% greater than the
I
location from which samples were currently being obtained in accordance with
1
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                                                      2
ODCM Section 3.8.E.1. The licensee added the new location to the REMP and
I
included the reew milk location to the ODCM. (The licensee expects the next
revision, Rev.10, to be published by the end of December 1996.) Changes made in
1995 will be documented in the 1996 REOR.
1
The inspector also reviewed the wind direction (wind roses) and D/O values from
'
the past five (5) years and compared them to the preoperational wind roses,
documented in the UFSAR Section 2.3.26, to detect changes, if any, in the
1
prevalent and least prevalent wind direction. No significant changes were found.
The environmental monitoring control stations are still located in the lean prevalent
wind direction.
The U.S. Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring
i
Network is operated by the NRC (Region l} to provide continuous measurements of
the ambient radiation levels around nuclear power plants throughout the United
States. Each site is monitored by approximately 30 to 50 thermoluminescent
!
dosimeter stat:ons in two concentric rings extending to about 5 miles from the
power plant. The monitoring results are published quarterly in NUREG-0837.
During the period covered by this inspection, three of the NRC TLDs were
collocated v,ith licensee TLDs at the Peach Bottom plant site as indicated in
Table 1. Yhe licensee's dosimeters, as of January 1995, are the same model
J
dosimeter used by the NRC. Previously, the licensee used dosimeters which
contain cs!cium sulfate activated with dysprosium (CaSO.:Dy), which were supplied
and analyzed by Teledyne isotopes, Inc. The NRC uses the Panasonic Model 801
dosimeter, which contains two elements of lithium borate activated with copper,
(Li,BO,:Cu) and two elements of calcium sulfate activated with thulium (CaSO,:Tm).
l
l
              Review of the land use census, required yearly by the ODCM, revealed that the
The licensee quarterly monitoring periods correlate well with the quarterly periods of
              licensee performed the census in 1994,1995 and 1996. During the 1994 census,
the NRC. During this inspection, the monitoring results of collocated TLDs were
!              the licensee noted that a milk farm close to the plant had been reestablished.            ;
compared, and the results are listed in Table 2. These reported values are the mean
l              During the 1995 census, completed in September 1995, the licensee calculated the          !
+/-1 standard deviation for all quarters for which net data were available. The
              D/O values for all the sectors and determined that the "new" farm has a D/O value        i
relatively small standard deviations indicate that the NRC results have remained
j              (a calculated dose or dose commitment) that is at least 20% greater than the
;
I              location from which samples were currently being obtained in accordance with              1
consistent over the 10-year period. The NRC " historical average" data are reported
l              ODCM Section 3.8.E.1. The licensee added the new location to the REMP and
in NUREG-0837. The licensee results, generally, are somewhat below those of the
I              included the reew milk location to the ODCM. (The licensee expects the next
              revision, Rev.10, to be published by the end of December 1996.) Changes made in
                1995 will be documented in the 1996 REOR.
                                                                                                          1
              The inspector also reviewed the wind direction (wind roses) and D/O values from          '
              the past five (5) years and compared them to the preoperational wind roses,
              documented in the UFSAR Section 2.3.26, to detect changes, if any, in the                  1
              prevalent and least prevalent wind direction. No significant changes were found.          I
              The environmental monitoring control stations are still located in the lean prevalent
              wind direction.
              The U.S. Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring
              Network is operated by the NRC (Region l} to provide continuous measurements of            i
              the ambient radiation levels around nuclear power plants throughout the United
              States. Each site is monitored by approximately 30 to 50 thermoluminescent                !
!              dosimeter stat:ons in two concentric rings extending to about 5 miles from the
              power plant. The monitoring results are published quarterly in NUREG-0837.
              During the period covered by this inspection, three of the NRC TLDs were
              collocated v,ith licensee TLDs at the Peach Bottom plant site as indicated in
              Table 1. Yhe licensee's dosimeters, as of January 1995, are the same model                J
              dosimeter used by the NRC. Previously, the licensee used dosimeters which
              contain cs!cium sulfate activated with dysprosium (CaSO.:Dy), which were supplied
              and analyzed by Teledyne isotopes, Inc. The NRC uses the Panasonic Model 801
              dosimeter, which contains two elements of lithium borate activated with copper,
              (Li,BO,:Cu) and two elements of calcium sulfate activated with thulium (CaSO,:Tm).        !
                                                                                                          l
              The licensee quarterly monitoring periods correlate well with the quarterly periods of
              the NRC. During this inspection, the monitoring results of collocated TLDs were
              compared, and the results are listed in Table 2. These reported values are the mean
                +/-1 standard deviation for all quarters for which net data were available. The
              relatively small standard deviations indicate that the NRC results have remained
;             consistent over the 10-year period. The NRC " historical average" data are reported
'
'
              in NUREG-0837. The licensee results, generally, are somewhat below those of the
NRC, and, for example, may be due to different methods of calibration of the two
              NRC, and, for example, may be due to different methods of calibration of the two
i
i             systems or differences in transit doses.
systems or differences in transit doses.
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I


      . . _ - .         ._         -,.-         - .--..~.-               -
. . _ - .
                                                                              _ ..-. - - - -. - . _ - _ . - ._
._
  1
-,.-
    -
- .--..~.-
                                                                                                                          ,
-
                                                                                                                          i
_ ..-. - - - -. - . _ - _ . - ._
                                                                                                                          .
1
                                  .
-
                                                                                                                          ,
,
    ,
i
                                                                                                                          !
.
                                                                                                                          ;
.
                                                                                                                          L
,
                                                                                                                          .
,
                                                                                                                          i
!
                                                                                                                          ,
;
                                                                                                                          !
L
                                                                        3
.
                                                                                                                          !
i,
                    c.   Conclusion                                                                                     i
!
                                                                                                                          ;
3
                                                                                                                          t
!
                          Overallimplementation of the radiological environmental monitoring program was                 j
c.
                          very good. Based on the above program review, discussions with the responsible                 j
Conclusion
                          individuals, and review of the ODCM and UFSAR, the program was well                             j
i
                          implemented, results were valid, and equipment was functioning as designed and                 3
;
                          was well maintained.                                                                           ;
t
                                                                                                                          >
Overallimplementation of the radiological environmental monitoring program was
                                                                                                                          4
j
                                                                                                                            i
very good. Based on the above program review, discussions with the responsible
!                                                                                                                         .;
j
!                                                                                                                         l
individuals, and review of the ODCM and UFSAR, the program was well
                                                                                                                          1
j
                                                                                                                            !
implemented, results were valid, and equipment was functioning as designed and
3
was well maintained.
;
>
4
i
!
.;
!
l
1
!
,
,
t
t
                                                                                                                            5
5
t                                                                                                                          i
i
                                                                                                                            '
t
l
l
'
I
I
                                                                                                                            I
i
                                                                                                                            i
J
                                                                                                                            J
i
i
l
l
Line 240: Line 324:
l
l
,
,
:,
\\
k
I
1
i
;
i
..
_ _ _ .
- . _ . , . ,
,
,
\
- - , _ .
k                                                                                                                            I
. . , -
1                                                                                                                            !
. _ _ _ - - - .
i                                                                                                                            ;
                                                                                                                            i
                                                                                                                            :
                                                                                                                            !
                _ ..        _ _ _ .    - . _ . , . ,      ,  - - , _ .       . . , -                   . _ _ _ - - - .


  _.
_.
                                          _ . . . . - -         . - _ _ - _ _ - - _ - _ - - _ _ _ - - _ _ _ - _ - - _ _ _ _ - _ _ - _ _ - - - - - - _ _ - - - - _ - - - _ - _ - _ - _ _ _ - - - - _ - - - - - - - - - _ - - - - - _ _ _ _ - - _ - _ - - - - - _ - - _ - _ - - _ - - _ _ - _ -
_ . . . . - -
                                                                                                                                                                                                                                                                                                                                                                                            .
. - _ _ - _ _ - - _ - _ - - _ _ _ - - _ _ _ - _ - - _ _ _ _ - _ _ - _ _ - - - - - - _ _ - - - - _ - - - _ - _ - _ - _ _ _ - - - - _ - - - - - - - - - _ - - - - - _ _ _ _ - - _ - _ - - - - - _ - - _ - _ - - _ - - _ _ - _ -
                                                                                                                                                                                                                                                                                                                                                                                                ,-
.
                                                                                                                                                                                                                                                                    4                                                                                                                               ;
,-
                                                                                                                                                                                                                                                                                                                                                                                                  >
4
                                                                                                                                                                                                                                                                                                                                                                                              .
;
                                                                                                                                                                                                                                                      Table 1                                                                                                                                     ,
.
                                                                                                                                                                        Collocated Environmental TLDs at Peach Bottom
>
                                                                                                                                                                      -
Table 1
,
Collocated Environmental TLDs at Peach Bottom
-
,
;
;
                                                                                                                                                                                                                                                                                                                                                                                                  ,
                                                                                                                                                                                                                                                                                                                                                                                                  <
1
1
                                                                                                                                                                                                                                                                                                                                                                                                  ,
<
                                                                                                                                                                                                                                                                                            Peach Bottom
,
                                                          NRC No.                                                             Distance *                                                                     Azimuth * *                                                                         Loc. No.                     Distance *         Azimuth * '                                   ;
Peach Bottom
                                                                11                                                                           1.9                                                                               96                                                                   14                               2.1             93                                         !
NRC No.
                                                                14                                                                           4.6                                                                                 85                                                                   5                               4.8           84                                         ;
Distance *
                                                              31                                                                             9.9                                                                           261                                                                     18                               9.7           261                                         P
Azimuth * *
                                                                                                                                                                                                                                                                                                                                                                                                  i
Loc. No.
                                                                                                                                                                                                                                                                                                                                                                                                  e
Distance *
                                                              * Distance measured in miles
Azimuth * '
                                                                                                                                                                                                                                                                                                                                                                                                  t
;
                                                            * * Azimuth measured in degrees
11
                                                                                                                                                                                                                                                                                                                                                                                                  t
1.9
                                                        NOTE:               Distances and azimuths were measured independently and do not necessarily agree; however, collocation of                                                                                                                                                                                                               '
96
                                                                            these TLDs has been confirmed.
14
                                                                                                                                                                                                                                                                                                                                                                                                  *
2.1
93
!
14
4.6
85
5
4.8
84
;
31
9.9
261
18
9.7
261
P
i
e
* Distance measured in miles
t
* * Azimuth measured in degrees
t
NOTE:
Distances and azimuths were measured independently and do not necessarily agree; however, collocation of
'
these TLDs has been confirmed.
*
3
3
                                                                                                                                                                                                                                                                                                                                                                                                  ;
;
  _ _ _ _ _ _ - . _ - _ _ _ _ _ _ _ _ _ _                                                                                                                  ___ __.__ ___.                                                     . . _ . . .                 _ . . . _                          _ _        _ . _ _ . . . _ . . . _ _ _ _    , _ _ .     - _ . . , _ . _ _ . . . _ . _ _ - .
- .
-
.
.
. .
. . .
. . .
.
. . .
. . .
, _ _ .
- _ . . , _ . _ _ . . . _ . _ _ - .


. - _ _ _                     _. .. __ ____---_-- . _ - - - - - - - - - - . - _ - - - -                                         ___ --__ - - _ _ _ - - - . - _ _ _ _ _ . . - . _ - - - - . - - - _ _ _ - - - _ - - . - - - - - _ - _ - - _ - - - - - - - -_ _ ------_-___ _ _ -- _-_ _ _ _ --- . - _ - _ _ _ _
. - _ _ _
                                                                                                                                                                                                                                                                                                                                                                          .           -
_. .. __ ____---_-- . _ - - - - - - - - - - . - _ - - - -
                                                                                                                                                                                                                                                                                                                                                                                    ,
___ --__ - - _ _ _ - - - . - _ _ _ _ _ . . - . _ - - - - . - - - _ _ _ - - - _ - - . - - - - - _ - _ - - _ - - - - - - - -_ _ ------_-___ _ _ -- _-_ _ _ _ --- . - _ - _ _ _ _
                                                                                                                                                                                                                                                                                                                                                                                        P
.
                                                                                                                                                                                                                                                                                                                                                                                  -
-
                                                                                                                                                                                                                                                                      5
,
                                                                                                                                                                                                                                                                                                                                                                            '
P
                                                                                                                                                                                                                                                Table 2
-
                                                                                                                        Environmental TLD Monitoring Results (mR/ quarter)*
5
                                                                                                                    Comparison of NRC TLDs Collocated with Peach Bottom TLDs                                                                                                                                                                                                             -
Table 2
                                                                                                                                                                        NRC no.:                                                                                                             11                       14                       31
'
                                                                                                              Monitoring Period                                 PBAPS no.:                                                                                                                     14                         5                       18
Environmental TLD Monitoring Results (mR/ quarter)*
                                                                                                              1995/1st Quarter                                                         NRC                                                                     19.8 i O.7                                           18.9 i O.7           21.9 i O.8
Comparison of NRC TLDs Collocated with Peach Bottom TLDs
                                                                                                                                                                                PBAPS                                                                           15.7 i 1.2                                           15.1 i 1.0           17.5     0.6
-
                                                                                                                2nd Quarter                                                             NRC                                                                     19.6 i O.7                                           19.3 i O.7           21.9 i O.8
NRC no.:
                                                                                                                                                                                PBAPS                                                                           15.7                                           0.7 15.7 i O.2           16.6 i O.6
11
                                                                                                                3rd Quarter                                                             NRC                                                                     19.6 i O.7                                           20.5 i O.7           21.7 i O.7
14
                                                                                                                                                                                PBAPS                                                                           15.4 i O.2                                           16.0 i O.6           16.9     0.7
31
                                                                                                                4th Quarter                                                             NRC                                                                     19.7 i 1.0                                           20.4 i 1.0           21.7 i 1.0
Monitoring Period
                                                                                                                                                                                PBAPS                                                                           14.2 i O.6                                           15.7 i 1.2           17.8 i 1.0
PBAPS no.:
                                                                                                                                                                                                                                                                                                                                                                                        ,
14
                                                                                                              1996/1st Quarter                                                         NRC                                                                     17.9 i O.6                                           18.2 i O.6           19.9 i O.7
5
                                                                                                                                                                                PBAPS                                                                           14.7 i O.6                                           16.1 i O.9           18.0 i O.4                                   '
18
                                                                                                                2nd Quarter                                                             NRC                                                                     18.5 i O.7                                           18.5 i O.7           21.6 i O.7
1995/1st Quarter
                                                                                                                                                                                PBAPS                                                                           15.7 i O.2                                           15.7 i O.4           17.9 i O.4
NRC
                                                                                                                                                                                                                                                                                                                                                                                        .
19.8 i O.7
                                                                        *
18.9 i O.7
                                                                                              All results are in milliroentgens and are normalized to a 90-day quarter.
21.9 i O.8
                                                                                              All data are shown as Result i 1 standard deviation.
PBAPS
                                                                                                                                                                                                                                                                                                                                                                                        .
15.7 i 1.2
  _ _ _ _ _ _ _ . - _ _ . _ _                    -__m-__m                  ___ _ _ _-- _ _ _ - - _ _ _ _ _-    -    -
15.1 i 1.0
                                                                                                                              m-                                                                       --,-v                         -. - _ -,                                                       . - - -     -,       ---..e . - , ,     .     - .- - - - , - 2 -     -,-
17.5
0.6
2nd Quarter
NRC
19.6 i O.7
19.3 i O.7
21.9 i O.8
PBAPS
15.7
0.7
15.7 i O.2
16.6 i O.6
3rd Quarter
NRC
19.6 i O.7
20.5 i O.7
21.7 i O.7
PBAPS
15.4 i O.2
16.0 i O.6
16.9
0.7
4th Quarter
NRC
19.7 i 1.0
20.4 i 1.0
21.7 i 1.0
PBAPS
14.2 i O.6
15.7 i 1.2
17.8 i 1.0
,
1996/1st Quarter
NRC
17.9 i O.6
18.2 i O.6
19.9 i O.7
PBAPS
14.7 i O.6
16.1 i O.9
18.0 i O.4
'
2nd Quarter
NRC
18.5 i O.7
18.5 i O.7
21.6 i O.7
PBAPS
15.7 i O.2
15.7 i O.4
17.9 i O.4
.
All results are in milliroentgens and are normalized to a 90-day quarter.
*
All data are shown as Result i 1 standard deviation.
.
. -
.
-
m-
m
--
- -
-
m-
--,-v
-. - _ -,
. - - -
-,
---..e
. - , ,
.
-
.-
- - - , -
2
-
-,-
-
-


  i
i
  .
.
                                                                                              l
6
                                                  6
R1.2 Meteoroloaical Monitorina Proaram (MMP)
    R1.2 Meteoroloaical Monitorina Proaram (MMP)
a.
      a.   _In_spection Scone (84750)
_In_spection Scone (84750)
            _
_
                                                                                              l
The MMP was evaluated to determine whether the instruments and equipment were
          The MMP was evaluated to determine whether the instruments and equipment were     l
operable, calibrated, and maintained. The MMP was inspected against UFSAR
          operable, calibrated, and maintained. The MMP was inspected against UFSAR
Section 2.3 and Regulatory Guide 1.23.
          Section 2.3 and Regulatory Guide 1.23.
The following associated procedures were reviewed:
                                                                                              l
'
          The following associated procedures were reviewed:                                 '
IC-11-00807,
          IC-11-00807,         Loop Calibration of the Climatronics Model F460 Wind
Loop Calibration of the Climatronics Model F460 Wind
                                Direction and Wind Speed Transmitters
Direction and Wind Speed Transmitters
:         IC-11 -00811,         Loop Calibration of the Bendix-Friez Model 120 Wind speed - l
:
                                wind Direction system                                       l
IC-11 -00811,
          IC-C-11 -00806,       Loop Calibration of the Climatronics 1000HM Platinum
Loop Calibration of the Bendix-Friez Model 120 Wind speed -
                                Temperature System
wind Direction system
          IC-C-11-00808,       Calibration of the Esterline Angus Model MS 424C Recorder   )
IC-C-11 -00806,
          IC-C-11 -00809,       Calibration of the Esterline Angus Model MS 1124S Speed     j
Loop Calibration of the Climatronics 1000HM Platinum
                                Servo 11 Multi Point Recorder
Temperature System
                                                                                              l
IC-C-11-00808,
          IC-C-11 -00810,       Calibration of the SUMX Model SX-410 Data Acquisition       ;
Calibration of the Esterline Angus Model MS 424C Recorder
                                System                                                       i
IC-C-11 -00809,
Calibration of the Esterline Angus Model MS 1124S Speed
j
Servo 11 Multi Point Recorder
IC-C-11 -00810,
Calibration of the SUMX Model SX-410 Data Acquisition
System
i
*
*
                                                                                              l
RT-0-094-800-2,
          RT-0-094-800-2,       Meteorology Equipment Functional Test                       i
Meteorology Equipment Functional Test
      b.   Observations and Findinas                                                         l
b.
          Calibration and functional tests of the meteorological instrumentation were
Observations and Findinas
          performed using the above IC procedures. Calibration results from January 1995 -
Calibration and functional tests of the meteorological instrumentation were
          December 1996 were reviewed. The licensee calibrated the instruments every 6
performed using the above IC procedures. Calibration results from January 1995 -
          months as required by the UFSAR commitments and the RG 1.23 recommendations.
December 1996 were reviewed. The licensee calibrated the instruments every 6
          Functional checks from October - December 1996 were reviewed. The functional
months as required by the UFSAR commitments and the RG 1.23 recommendations.
          checks were performed weekly as required in the UFSAR and the procedure, RT-0-
Functional checks from October - December 1996 were reviewed. The functional
          094-800-2. Results of the calibrations were within the established acceptance
checks were performed weekly as required in the UFSAR and the procedure, RT-0-
          criteria recommended by the vendor. Instrumentation was well maintained. The
094-800-2. Results of the calibrations were within the established acceptance
          inspector noted that the licensee had recently drafted a procedure to ensure paper
criteria recommended by the vendor. Instrumentation was well maintained. The
          from the recorders would be changed every 2 weeks.
inspector noted that the licensee had recently drafted a procedure to ensure paper
from the recorders would be changed every 2 weeks.


                                        .- --     .   -   -   .- . -         -
.-
  !
--
      .
.
            .
-
                                                                                                  1
-
                  ,
.- . -
    *
-
      .
!
.
.
1
,
*
.
<
<
!
!
;
;
                                                      7
7
              Log books and records of maintenance were also reviewed. The books were kept
Log books and records of maintenance were also reviewed. The books were kept
              at the tower and the control room and used to record maintenance, surveillance,
at the tower and the control room and used to record maintenance, surveillance,
'
'
              and calibration activities. The logs were up-to-date and coincided with maintenance
and calibration activities. The logs were up-to-date and coincided with maintenance
              and calibration records.
and calibration records.
!
!
#
#
        c.   Conclusions
c.
              Based on the above review of procedures, direct observations, and discussions with
Conclusions
              personnel, the inspector concluded that calibration and maintenance of the
Based on the above review of procedures, direct observations, and discussions with
              equipment were performed according to procedures, the meteorological monitoring
personnel, the inspector concluded that calibration and maintenance of the
              instrumentation was operable and sufficiently maintained, and the licensee
equipment were performed according to procedures, the meteorological monitoring
              continued to effectively implement the meteorological monitoring program in         ;
instrumentation was operable and sufficiently maintained, and the licensee
                                                                                                  '
continued to effectively implement the meteorological monitoring program in
;            accordance with UFSAR and RG 1.23 commitments.
;
,                                                                                                 i
accordance with UFSAR and RG 1.23 commitments.
'
'
        R6   RP&C Organization and Administration
;
        R6.1 Manaaement Controls
,
        a.   insoection Scope (84570)                                                             I
i
              The inspector reviewed organization changes and the responsibilities relative to
'
              oversight of the REMP and MMP, and reviewed the annual Radiological
R6
4             Environmental Operating Report and Dose Assessmer:t Report to verify the
RP&C Organization and Administration
R6.1 Manaaement Controls
a.
insoection Scope (84570)
The inspector reviewed organization changes and the responsibilities relative to
oversight of the REMP and MMP, and reviewed the annual Radiological
4
Environmental Operating Report and Dose Assessmer:t Report to verify the
implementation of ODCM Sections 3.8.E, 3.10.1 and 3.10.2.
.
.
              implementation of ODCM Sections 3.8.E, 3.10.1 and 3.10.2.
b.
Observations and Findinas
.
.
        b.  Observations and Findinas
3
3            The organization and responsibilities at the corporate office, located in
The organization and responsibilities at the corporate office, located in
              Chesterbrook, PA, essentially have remained the same since the previous inspection
Chesterbrook, PA, essentially have remained the same since the previous inspection
              conducted in March 1995. The responsibility to implement the REMP was with the
conducted in March 1995. The responsibility to implement the REMP was with the
              Program Manager, Programs Branch, Programs / Procedures Section, Nuclear
Program Manager, Programs Branch, Programs / Procedures Section, Nuclear
              Engineering Division. Responsibility to perform calibrations of the meteorological
Engineering Division. Responsibility to perform calibrations of the meteorological
              monitoring tower was with the Instrument and Controls Department at the site.
monitoring tower was with the Instrument and Controls Department at the site.
              The annual REORs for 1994 and 1995 provided a comprehensive summary of the
The annual REORs for 1994 and 1995 provided a comprehensive summary of the
              observed impacts of plant operation on the environment surrounding the Peach
observed impacts of plant operation on the environment surrounding the Peach
              Bottorn sites. The results met the ODCM reporting requirements. The reports also
Bottorn sites. The results met the ODCM reporting requirements. The reports also
              provided a summary of the land use census and interlaboratory comparison
provided a summary of the land use census and interlaboratory comparison
              program. The analytical data from 1996 were reviewed for sample frequency and
program. The analytical data from 1996 were reviewed for sample frequency and
              analysis requirements specified in the ODCM. No omissions, mistakes, obvious
analysis requirements specified in the ODCM. No omissions, mistakes, obvious
              anomalous results or trends were noted. Program deviations and/or changes in
anomalous results or trends were noted. Program deviations and/or changes in


* .
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.
              .
*
.
.
                                                  8
.
          sampling locations were reported. The Dose Assessment Report for the period
8
          January 1,1995, through December 31,1995, was reviewed. The report included
sampling locations were reported. The Dose Assessment Report for the period
          a summary of the radiation doses due to radioactive effluent releases from the sites
January 1,1995, through December 31,1995, was reviewed. The report included
          and annual summaries of hourly meteorological data joint frequency distributions of
a summary of the radiation doses due to radioactive effluent releases from the sites
          wind speed, wind direction and atmospheric stability.
and annual summaries of hourly meteorological data joint frequency distributions of
      c.   Conclusion
wind speed, wind direction and atmospheric stability.
          Based on the above review, the inspector determined that the licensee implemented
c.
          very good management control and oversight of the REMP and MMP and effectively
Conclusion
          implemented Sections 3.8.E, 3.10.1 and 3.10.2 of the ODCM.
Based on the above review, the inspector determined that the licensee implemented
    R7   Quality Assurance in RP&C Activities
very good management control and oversight of the REMP and MMP and effectively
    R7.1 Quality Assurance Audit Proaram
implemented Sections 3.8.E, 3.10.1 and 3.10.2 of the ODCM.
      a.   Insoection Scoce (84750)
R7
                                                                                                1
Quality Assurance in RP&C Activities
          Quality Assurance (QA) audit and surveillance programs were inspected against
R7.1 Quality Assurance Audit Proaram
          criteria contained in the licensee's procedures and TS requirements. Audits of the
a.
          REMP and MMP were reviewed and follow up was performed to ensure the 1994           ,
Insoection Scoce (84750)
          NUPIC audit findings had been closed by the licensee.
1
      b.   Observations and Findinas
Quality Assurance (QA) audit and surveillance programs were inspected against
          The inspector reviewed the following Quality Assurance Audit Report as part of the   ,
criteria contained in the licensee's procedures and TS requirements. Audits of the
          evaluation of the implementation of the TS audit requirement:                       '
REMP and MMP were reviewed and follow up was performed to ensure the 1994
                  A0956206, Emergency Plan and Procedures Assessment and
,
                    10CFR50.54.(t) Review, dated 1/10/96
NUPIC audit findings had been closed by the licensee.
                  A0903756, NQA Audit at the GPU Nuclear Corporation Environmental
b.
                  Radioactivity Laboratory (EML), dated
Observations and Findinas
                  A0919170, Radiological and Environmental Monitoring, dated 5/26/95
The inspector reviewed the following Quality Assurance Audit Report as part of the
          The audits were performed by qualified personnel and were of sufficient technical
,
          depth to assess the implementation of the programs. The audits were performed
evaluation of the implementation of the TS audit requirement:
          within the 'requency in TS.
'
          Licensee follow up of the NUPIC audit showed that all 5 items were closed in 1995.
A0956206, Emergency Plan and Procedures Assessment and
10CFR50.54.(t) Review, dated 1/10/96
A0903756, NQA Audit at the GPU Nuclear Corporation Environmental
Radioactivity Laboratory (EML), dated
A0919170, Radiological and Environmental Monitoring, dated 5/26/95
The audits were performed by qualified personnel and were of sufficient technical
depth to assess the implementation of the programs. The audits were performed
within the 'requency in TS.
Licensee follow up of the NUPIC audit showed that all 5 items were closed in 1995.


'
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                                                  9
9
      c.   Conclusion
c.
            Based on the above review, the inspector determined that the audits were sufficient
Conclusion
            to assess the REMP and MMP and that the licensee implemented the TS audit
Based on the above review, the inspector determined that the audits were sufficient
            requirements.
to assess the REMP and MMP and that the licensee implemented the TS audit
    R7.2 Quality Control Proarem of Analvtical Measurements
requirements.
      a.   Insoection Scoce (84750)
R7.2 Quality Control Proarem of Analvtical Measurements
            The inspector reviewed the quality control (OC) program of analytical measurements
a.
            against recommendation of Regulatory Guide 4.15, " Quality Assurance for
Insoection Scoce (84750)
            Radiological Monitoring Prograrr.s (Normal Operations) - Effluent Streams and the
The inspector reviewed the quality control (OC) program of analytical measurements
            Environment" to determine whether the licensee had adequate r,ontrol with respect
against recommendation of Regulatory Guide 4.15, " Quality Assurance for
            to sampling, analyzing, and evaluating data for the implementation of the REMP.
Radiological Monitoring Prograrr.s (Normal Operations) - Effluent Streams and the
            Included was a review of the intercomparison program required by ODCM Section
Environment" to determine whether the licensee had adequate r,ontrol with respect
            3.8.E.3.
to sampling, analyzing, and evaluating data for the implementation of the REMP.
      b.   Observations and Findinas
Included was a review of the intercomparison program required by ODCM Section
            The licensee uses the GPU Environmental Radioactivity Laboratory (ERL) as the
3.8.E.3.
            primary lab to analyze the environmental samples. The lab maintains an extensive
b.
            QC program including participation in the EPA cross check program (1995). Results
Observations and Findinas
            of this program were within the EPA acceptance criteria. With the exception of
The licensee uses the GPU Environmental Radioactivity Laboratory (ERL) as the
            drinking water, the EPA terminated the cross check program in December 1995.
primary lab to analyze the environmental samples. The lab maintains an extensive
            Therefore, the licensee was tasked with finding another laboratory to provide an
QC program including participation in the EPA cross check program (1995). Results
            independent intercomparison program. The EPA program was replaced using
of this program were within the EPA acceptance criteria. With the exception of
            Analytics, Inc. and the results were within the GPU laboratory criteria. Periodic
drinking water, the EPA terminated the cross check program in December 1995.
            reports of QC results are suppbed to the licensee. The data, with few exceptions,
Therefore, the licensee was tasked with finding another laboratory to provide an
            indicate agreement between the primary contractor laboratory and the QC
independent intercomparison program. The EPA program was replaced using
            laboratory. ~Where discrepsncies were found, reasons for the differences were
Analytics, Inc. and the results were within the GPU laboratory criteria. Periodic
            investigated and resolved.
reports of QC results are suppbed to the licensee. The data, with few exceptions,
      c.   Conclusion
indicate agreement between the primary contractor laboratory and the QC
            Based on the above review, the inspector determined that the licensee continued to
laboratory. ~Where discrepsncies were found, reasons for the differences were
            implement a good quality control program in accordance with regulatory
investigated and resolved.
            requirements and recommendations. The licensee maintained good control with
c.
            respect to sampling, analyzing, and evaluating data for the implementation of the
Conclusion
            REMP based on the data reviewed.
Based on the above review, the inspector determined that the licensee continued to
implement a good quality control program in accordance with regulatory
requirements and recommendations. The licensee maintained good control with
respect to sampling, analyzing, and evaluating data for the implementation of the
REMP based on the data reviewed.


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l                                                    10
      R1.2 Desian Modifications involvina the North Wall of the Unit 3 Turbine Buildina
      a.  laspection Scope (84750)
.
.
            The inspection scope, regarding Modification P00248, was to: (1) verify that
l
l           gaseous effluents were processed as specified in the ODCM (Section 3.8.C.5) or
.
            that compensatory measures had been taken: (2) ensure that an adequate safety
*
            evaluation was conducted in accordance with 10 CFR 50.59; and (3) determine if
.
            the turbine building atmosphere was processed consistent with the UFSAR
l
            description (Section 10.15).
10
      b.   Observations and Findinas
R1.2 Desian Modifications involvina the North Wall of the Unit 3 Turbine Buildina
            During the previous inspection, an inspector reviewed a PECO-identified event
a.
            involving a low level unmonitored release from the Unit 3 turbine building (TB)
laspection Scope (84750)
            which began on July 18 and ended on July 25,1996. (See Section R2 of the
.
            Routine Integrated inspection Report 50-277/96-06 and 50-278/96-06, dated
The inspection scope, regarding Modification P00248, was to: (1) verify that
            October 10,1996, for details.)
l
            During this inspection, a review of the licensee's 10 CFR 50.59 evaluation for
gaseous effluents were processed as specified in the ODCM (Section 3.8.C.5) or
            Modification P00248 (Mod) involving the construction of the new Plant Entrance
that compensatory measures had been taken: (2) ensure that an adequate safety
            and Radiochemistry Laboratory (PEARL) Building (including the associated               ;
evaluation was conducted in accordance with 10 CFR 50.59; and (3) determine if
            penetration of the north wall of the Unit 3 Turbine Building to support the Mod) was
the turbine building atmosphere was processed consistent with the UFSAR
            conducted by the inspector. According to the Mod, the licensee planned to breach
description (Section 10.15).
            the north wall of the Unit 3 Turbine Building on July 18,1996. Five out of seven
b.
            holes (3'x 5') were initially cut into the turbine building wall to install ventilation
Observations and Findinas
            duct supports for the new Plant Entrance and Radiochemistry Laboratory (PEARL)
During the previous inspection, an inspector reviewed a PECO-identified event
            building exhaust systems. The exhaust duct traveled along the outside of the
involving a low level unmonitored release from the Unit 3 turbine building (TB)
            turbine building, across the roof and entered the reactor building vent stack. After
which began on July 18 and ended on July 25,1996. (See Section R2 of the
            cutting holes in the TB, a worker on the job was identified with short lived activity   I
Routine Integrated inspection Report 50-277/96-06 and 50-278/96-06, dated
            (< 100 cpm) on his hand. The licensee reviewed the work conditions and collected
October 10,1996, for details.)
            an air sample from the 195 foot elevation, which identified short-lived activity of
During this inspection, a review of the licensee's 10 CFR 50.59 evaluation for
            SE-10 Ci/cc Cs-138. The licensee calculated doses to the public using a
Modification P00248 (Mod) involving the construction of the new Plant Entrance
            conservative assumption that the release through the holes was 10% of the total
and Radiochemistry Laboratory (PEARL) Building (including the associated
            reactor building vent flow (2E4 CFM). The offsite doses for the release were
;
            calculated to be 3.2E-5 mrem / year total body and 5.1E-5 mrem / year skin. The
penetration of the north wall of the Unit 3 Turbine Building to support the Mod) was
            ODCM limit is 500 mrem / year total body and 3000 mrem / year skin. The licensee         l
conducted by the inspector. According to the Mod, the licensee planned to breach
            stated that a full report of this event will be documented in the 1997 Annual
the north wall of the Unit 3 Turbine Building on July 18,1996. Five out of seven
            Radioactive Effluent Release Report as required by ODCM Section 3.10.2.
holes (3'x 5') were initially cut into the turbine building wall to install ventilation
            The inspector determined that the proper processing and monitoring of turbine
duct supports for the new Plant Entrance and Radiochemistry Laboratory (PEARL)
            building atmosphere was not adequately performed. The UFSAR (Section 10.15)
building exhaust systems. The exhaust duct traveled along the outside of the
            states that exhaust ventilation air from the turbine building and radwaste building is
turbine building, across the roof and entered the reactor building vent stack. After
            discharged to atmosphere from the ventilation stack above the reactor building roof
cutting holes in the TB, a worker on the job was identified with short lived activity
            (a monitored release point). The licensee, on July 22,1996, stated in the
(< 100 cpm) on his hand. The licensee reviewed the work conditions and collected
an air sample from the 195 foot elevation, which identified short-lived activity of
SE-10 Ci/cc Cs-138. The licensee calculated doses to the public using a
conservative assumption that the release through the holes was 10% of the total
reactor building vent flow (2E4 CFM). The offsite doses for the release were
calculated to be 3.2E-5 mrem / year total body and 5.1E-5 mrem / year skin. The
ODCM limit is 500 mrem / year total body and 3000 mrem / year skin. The licensee
stated that a full report of this event will be documented in the 1997 Annual
Radioactive Effluent Release Report as required by ODCM Section 3.10.2.
The inspector determined that the proper processing and monitoring of turbine
building atmosphere was not adequately performed. The UFSAR (Section 10.15)
states that exhaust ventilation air from the turbine building and radwaste building is
discharged to atmosphere from the ventilation stack above the reactor building roof
(a monitored release point). The licensee, on July 22,1996, stated in the
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                                                    11
11
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          Performance Evaluation Program (PEP) that, "After checking the covered openings
Performance Evaluation Program (PEP) that, "After checking the covered openings
          that flat sheeting on the corrugated outs:de wallleft wide gaps through which there
that flat sheeting on the corrugated outs:de wallleft wide gaps through which there
          was very noticeable outward air flow. This air flow is a potential release path for
was very noticeable outward air flow. This air flow is a potential release path for
          radioactive material." With regard to this statement, the inspector noted that the
radioactive material." With regard to this statement, the inspector noted that the
          licensee was aware of the potential for release of radioactive material after the holes
licensee was aware of the potential for release of radioactive material after the holes
          had been cut. Since the licensee could not ensure a negative pressure had been
had been cut. Since the licensee could not ensure a negative pressure had been
          maintained, the holes became a pathway for a potential unmonitored release. (See
maintained, the holes became a pathway for a potential unmonitored release. (See
          observations and findings of Section R2 of the previous inspection report, noted
observations and findings of Section R2 of the previous inspection report, noted
          above, for details.)
above, for details.)
          Based on the licensee's "10 CFR 50.59 Review for Modification P00248," the
Based on the licensee's "10 CFR 50.59 Review for Modification P00248," the
          inspector determined that no evaluation of the gaseous waste processing,
inspector determined that no evaluation of the gaseous waste processing,
          monitoring, nor dose assessment was addressed. The licensee stated that they
monitoring, nor dose assessment was addressed. The licensee stated that they
          assumed the turbine building was slightly negative and would remain slightly
assumed the turbine building was slightly negative and would remain slightly
          negative as specified in UFSAR during the Mod and, therefore, no further evaluation
negative as specified in UFSAR during the Mod and, therefore, no further evaluation
          was performed. The evaluation did not consider the creation of a potential
was performed. The evaluation did not consider the creation of a potential
          unmonitored release pathway. No monitoring of the turbine building (continuous or
unmonitored release pathway. No monitoring of the turbine building (continuous or
          grab sampling) was planned. The actual modification resulted in an outward flow of
grab sampling) was planned. The actual modification resulted in an outward flow of
          air from turbine building contrary to the licensee's assumptions of the maintenance
air from turbine building contrary to the licensee's assumptions of the maintenance
          of negative pressure. With the exception of the sample previously noted, no
of negative pressure. With the exception of the sample previously noted, no
          monitoring had been performed to evaluate this release pathway in a timely manner.
monitoring had been performed to evaluate this release pathway in a timely manner.
          Failure of the licensee's safety evaluation record to provide the bases for the
Failure of the licensee's safety evaluation record to provide the bases for the
          determination that the penetration did not involve an unreviewed safety question
determination that the penetration did not involve an unreviewed safety question
          constitutos a violation of 10 CFR 50.59(b)(1). (VIO 50-278/97-03-01)
constitutos a violation of 10 CFR 50.59(b)(1). (VIO 50-278/97-03-01)
          ODCM 3.8.C.S. states, in part, that gaseous effluents shall be processed through
ODCM 3.8.C.S. states, in part, that gaseous effluents shall be processed through
          the turbine Gaseous Waste Treatment System. The turbine building atmospheres
the turbine Gaseous Waste Treatment System. The turbine building atmospheres
          shall be processed through permanently or temporarily installed equipment in the
shall be processed through permanently or temporarily installed equipment in the
          appropriate building ventilation system and the vent stack. The inspector noted
appropriate building ventilation system and the vent stack. The inspector noted
          that, in the existing condition, the licensee could not assure that the turbine building
that, in the existing condition, the licensee could not assure that the turbine building
          atmosphere was processed through the turbine building gaseous waste treatment
atmosphere was processed through the turbine building gaseous waste treatment
          system, using either permanently or temporarily installed equipment. Failure to
system, using either permanently or temporarily installed equipment. Failure to
            assure that the turbine building atmosphere was processed and monitored in
assure that the turbine building atmosphere was processed and monitored in
            accordance with the applicable plant design and regulatory requirements,
accordance with the applicable plant design and regulatory requirements,
          constitutes a violation of ODCM 3.8.C.5. (VIO 50-278/97-03-02)
constitutes a violation of ODCM 3.8.C.5. (VIO 50-278/97-03-02)
        c. Conclusion
c.
            Based on the above findings, the inspector concluded the following. During the
Conclusion
            Mod, a small portion of the turbine building atmosphere was unmonitored and
Based on the above findings, the inspector concluded the following. During the
            released through the holes cut into the turbine building. The safety evaluation
Mod, a small portion of the turbine building atmosphere was unmonitored and
            performed in accordance with 10 CFR 50.59 failed to address changes to the
released through the holes cut into the turbine building. The safety evaluation
          Turbine Building that could result in unmonitored releases. The licensee identified
performed in accordance with 10 CFR 50.59 failed to address changes to the
Turbine Building that could result in unmonitored releases. The licensee identified


                -     -               . .                 .- -                   . -     . . -       .
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5
5
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                                                        12
12
                  these issues after the holes were cut. Overall, the immediate corrective actions to
these issues after the holes were cut. Overall, the immediate corrective actions to
                  ameliorate the condition were adequate, however, corrective actions relative to
ameliorate the condition were adequate, however, corrective actions relative to
                  assuring comprehensive evaluation of all elements of a facility change was not
assuring comprehensive evaluation of all elements of a facility change was not
                  evident during this inspection. No actual safety consequence was evident as a           !
!
                  result of in this occurrence.
evident during this inspection. No actual safety consequence was evident as a
          R8     Miscellaneous RP&C lasues                                                                 l
result of in this occurrence.
          R8.1 UFSAR
R8
Miscellaneous RP&C lasues
R8.1 UFSAR
A recent discovery of a licensee operating their facility in a manner contrary to the
,
Updated Final Safety Analysis Report (UFSAR) description highlighted the need for a
special focused review that compares plant practices, procedures and/or parameters
.
)
to the UFSAR description. While performing the inspection discussed in this report,
l
the inspectors reviewed the applicable portions of the UFSAR that related to the
areas inspected. The inspectors verified that the UFSAR wording was consistent
with the observed plant practices and procedures and/or parameters, except as
noted in Section R1.2 of this report.
V. Manaaement Meetinas
X1
Exit Meeting Summary
The inspector presented the inspection results to members of the licensee management at
the conclusion of the onsite inspection on December 13,1996. Subsequently, the
,
,
                  A recent discovery of a licensee operating their facility in a manner contrary to the
'
                  Updated Final Safety Analysis Report (UFSAR) description highlighted the need for a    .
inspector continued to review information relative to the onsite findings until a conclusion
                  special focused review that compares plant practices, procedures and/or parameters      )
was reached on January 24,1997. Following the conclusion, the inspection results were
                  to the UFSAR description. While performing the inspection discussed in this report,    l
discussed by telephone with licensee representatives on January 31,1997.
                  the inspectors reviewed the applicable portions of the UFSAR that related to the
w-
                  areas inspected. The inspectors verified that the UFSAR wording was consistent
                  with the observed plant practices and procedures and/or parameters, except as
                  noted in Section R1.2 of this report.
                                              V. Manaaement Meetinas
          X1      Exit Meeting Summary
          The inspector presented the inspection results to members of the licensee management at
          the conclusion of the onsite inspection on December 13,1996. Subsequently, the                  '
                                                                                                            ,
          inspector continued to review information relative to the onsite findings until a conclusion
          was reached on January 24,1997. Following the conclusion, the inspection results were
          discussed by telephone with licensee representatives on January 31,1997.
                                                                                                            l
                                                                                                            l
        w-


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13
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel
i
*
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E. Anderson, System Manager, Plant Engineering Division
l
* T. Baxter, Nuclear Quality Assurance
l
* G. Beck, Manager Programs / Procedures Section
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                                                              13
D. Chase, Radiochemist, Chemistry
                                        PARTIAL LIST OF PERSONS CONTACTED
* G. Lengylle, Experience Assessment Manager
          Licensee Personnel                                                                              *
i
* T. Loomis, Licensing
J. Moore, Lead Responsible Engineer, Nuclear Engineering Division
* T. Mscisz, Engineer, Meteorology
' R. Nagle, l&C Technician
* A. O' Dell, Chemistry Manager
* D. Wahl, Physicist, Programs Branch
,
i
\\
Contractor Personnel
j
l
C. Reid, Sampling Contractor, Radiation Management Corporation, Inc.
1
l
'
' Denotes those present at the exit meeting on December 13,1996.
The inspector also interviewed other licensee personnel.
LIST OF INSPECTION PROCEDURES USED
84750:
Radioactive Waste Treatment, and Effluent and Environmental Monitoring
LIST OF ITEMS OPENED, CLOSED AND DISCUSSED
l
Opened
'
50-278/97-03-01
VIO
Failure to perform and adequate safety evaluation according to
i
i
,            E. Anderson, System Manager, Plant Engineering Division
10 CFR 50.59(b)(1)
l          * T. Baxter, Nuclear Quality Assurance
'
l          * G. Beck, Manager Programs / Procedures Section
50-278/97-03-02
              D. Chase, Radiochemist, Chemistry                                                              I
VIO
          * G. Lengylle, Experience Assessment Manager                                                      i
Failure to assure that the turbine building atmosphere was
          * T. Loomis, Licensing                                                                            !
processed through the turbine building gaseous waste
              J. Moore, Lead Responsible Engineer, Nuclear Engineering Division                              !
treatment system.
          * T. Mscisz, Engineer, Meteorology
Closed
            ' R. Nagle, l&C Technician
None
          * A. O' Dell, Chemistry Manager
;
          * D. Wahl, Physicist, Programs Branch                                                            ,
Discussed
                                                                                                            i
'
                                                                                                            \
None
          Contractor Personnel                                                                              j
          C. Reid, Sampling Contractor, Radiation Management Corporation, Inc.                            l
                                                                                                            1
                                                                                                            l
  '
          ' Denotes those present at the exit meeting on December 13,1996.
          The inspector also interviewed other licensee personnel.
                                        LIST OF INSPECTION PROCEDURES USED
          84750:          Radioactive Waste Treatment, and Effluent and Environmental Monitoring
                                LIST OF ITEMS OPENED, CLOSED AND DISCUSSED                                  l
          Opened                                                          '
          50-278/97-03-01        VIO        Failure to perform and adequate safety evaluation according to  i
                                                                                                            '
                                            10 CFR 50.59(b)(1)
          50-278/97-03-02       VIO       Failure to assure that the turbine building atmosphere was
                                            processed through the turbine building gaseous waste
                                            treatment system.
          Closed
          None
;         Discussed
'
          None
i
i


      _ . . . . . - - -             - .   .     .   - . . . . -. - .. . . - _ - - - . . . . .-- .._ . .
_ . . . . . - - -
  * .
- .
                            -
.
                              .
.
    * .
-
. . . .
-. - ..
.
. - _ - - - .
. . .
.--
.._ .
.
*
.
-
.
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4                                                                 14
14
4
:
:
                                                                                                              ;
i
i
;
:
:
,
,
,                                              PARTIAL LIST OF ACRONYMS
PARTIAL LIST OF ACRONYMS
,
EPA.
Environmental Protection Agency
,
,
,
                        EPA.    Environmental Protection Agency                                                ,
MMP
                        MMP    Meteorological Monitoring Program                                             i
Meteorological Monitoring Program
                        NCV     Non-Cited Violation
i
l                       NRC     Nuclear Regulatory Commission                                                 j
NCV
.                      ODCM   Offsite Dose Calculation Manual                                               i
Non-Cited Violation
l
NRC
Nuclear Regulatory Commission
j
ODCM
Offsite Dose Calculation Manual
i
.
QA
Quality Assurance
'
'
                        QA      Quality Assurance
OC
Quality Control
:
'
'
                        OC      Quality Control                                                                :
REMP
                        REMP    Radiological Environmental Monitoring Program
Radiological Environmental Monitoring Program
i                       REOR   Radiological Environmental Operating Report
i
                        TLD     Thermoluminescent Dosimeter
REOR
!                       TS     Technical Specifications                                                       ,
Radiological Environmental Operating Report
TLD
Thermoluminescent Dosimeter
!
TS
Technical Specifications
,
!
!
                        UFSAR   Updated Final Safety Analysis Report                                           l
UFSAR
                                                                                                              !
Updated Final Safety Analysis Report
                                                                                                              .
.
4
4
[
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                                                                                                              !
                                                                                                              l
                                                                                                              l
                                                                                                                l
                                                                                                              I
                                                                                                            .j
}}
}}

Latest revision as of 18:23, 11 December 2024

Insp Repts 50-277/97-03 & 50-278/97-03 on 961209-970131. Violations Noted.Major Areas Inspected:Areas Involving Radiological Environ Monitoring Programs
ML20138P266
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 02/10/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20135C595 List:
References
50-277-97-03, 50-277-97-3, 50-278-97-03, 50-278-97-3, NUDOCS 9703040154
Download: ML20138P266 (14)


See also: IR 05000277/1997003

Text

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U.S. NUCLEAR REGULATORY COMMISSION

I

REGION l

i

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Docket Nos.:

50-277; 50-278

l

l

Report Nos.:

50-277/97-03; 50-278/97-03

!

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.

Licensee:

Philadelphia Electric Company

Facility:

Peach Bottom Atomic Power Station

[

Location:

P.O. Box 195

,

'

Wayne, Pennsylvania 19087-0195

Dates:

December 9,1996 - January 24,1997

l

Inspector:

Laurie A. Peluso, Health Physicist

'

Radiation Safety Branch, DRS

Approved by:

John R. White, Chief

Radiation Safety Branch

,

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Division of Reactor Safety

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Report Details

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IV. Plant Support

R1

Radiological Protection and Chemistry (RP&C) Controls

R1.1 Imolementation of the Radioloaical Environmental Monitorina Proara_rn

a.

Insoection Scope (84750)

The inspector observed and assessed the licensee's capability to implement the

radiological environmental monitoring program (REMP). The program was inspected

against ODCM Sections 3.8.E.1 and 3.8.E.2, Regulatory Guide 4.1, " Programs for

Monitoring Radioactivity in the Environs of Nuclear Power Plants," and the Updated

Final Safety Analysis Report (UFSAR).

b.

Observations and Findinas

I

The inspector examined selected sampling stations to determine whether samples

were being obtained from the locations designated in the ODCM and whether air

samplers were operable and calibrated. Air sampling equipment was calibrated at

l

the frequency specified in the associated procedure. The sampling stations included

l

air samplers for iodines and particulates, composite water sampling stations located

at the plant intake and discharge, milk farms, vegetation locations, and

thermoluminescent dosimeter (TLD) stations for measurement of direct ambient

!

radiation. All air sampling equipment and water compositors at the selected

locations were functioning as designed. The sampling equipment, as evidenced by

the sample log books and analysis results, had operated continuously through the

year with few exceptions. The above environmental sampling media were available

at the locations designated in the ODCM, and TLDs were placed at locations

l

designated in the ODCM. Analytical results did not indicate any anomalous trends.

l

Sampling and analysis was performed as required. Compensatory sampling

(suriace, drinking water) was performed as required when applicable. Although the

'

number of samples taken had been reduced, the licensee continued to collect and

j

analyze more samples than required by the ODCM. Program changes were made in

l

1995 and were documented in the annual Radiological Environmental Operating

Report (REOR). The changes made have not reduced the original intent of the

!

REMP.

1

l

i

-

-

.

.

. .

.

- - -

.

._

-.

-.

'

.

.

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l

l

2

Review of the land use census, required yearly by the ODCM, revealed that the

licensee performed the census in 1994,1995 and 1996. During the 1994 census,

!

the licensee noted that a milk farm close to the plant had been reestablished.

l

During the 1995 census, completed in September 1995, the licensee calculated the

D/O values for all the sectors and determined that the "new" farm has a D/O value

i

j

(a calculated dose or dose commitment) that is at least 20% greater than the

I

location from which samples were currently being obtained in accordance with

1

l

ODCM Section 3.8.E.1. The licensee added the new location to the REMP and

I

included the reew milk location to the ODCM. (The licensee expects the next

revision, Rev.10, to be published by the end of December 1996.) Changes made in

1995 will be documented in the 1996 REOR.

1

The inspector also reviewed the wind direction (wind roses) and D/O values from

'

the past five (5) years and compared them to the preoperational wind roses,

documented in the UFSAR Section 2.3.26, to detect changes, if any, in the

1

prevalent and least prevalent wind direction. No significant changes were found.

The environmental monitoring control stations are still located in the lean prevalent

wind direction.

The U.S. Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring

i

Network is operated by the NRC (Region l} to provide continuous measurements of

the ambient radiation levels around nuclear power plants throughout the United

States. Each site is monitored by approximately 30 to 50 thermoluminescent

!

dosimeter stat:ons in two concentric rings extending to about 5 miles from the

power plant. The monitoring results are published quarterly in NUREG-0837.

During the period covered by this inspection, three of the NRC TLDs were

collocated v,ith licensee TLDs at the Peach Bottom plant site as indicated in

Table 1. Yhe licensee's dosimeters, as of January 1995, are the same model

J

dosimeter used by the NRC. Previously, the licensee used dosimeters which

contain cs!cium sulfate activated with dysprosium (CaSO.:Dy), which were supplied

and analyzed by Teledyne isotopes, Inc. The NRC uses the Panasonic Model 801

dosimeter, which contains two elements of lithium borate activated with copper,

(Li,BO,:Cu) and two elements of calcium sulfate activated with thulium (CaSO,:Tm).

l

The licensee quarterly monitoring periods correlate well with the quarterly periods of

the NRC. During this inspection, the monitoring results of collocated TLDs were

compared, and the results are listed in Table 2. These reported values are the mean

+/-1 standard deviation for all quarters for which net data were available. The

relatively small standard deviations indicate that the NRC results have remained

consistent over the 10-year period. The NRC " historical average" data are reported

in NUREG-0837. The licensee results, generally, are somewhat below those of the

'

NRC, and, for example, may be due to different methods of calibration of the two

i

systems or differences in transit doses.

I

. . _ - .

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c.

Conclusion

i

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Overallimplementation of the radiological environmental monitoring program was

j

very good. Based on the above program review, discussions with the responsible

j

individuals, and review of the ODCM and UFSAR, the program was well

j

implemented, results were valid, and equipment was functioning as designed and

3

was well maintained.

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.

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Table 1

,

Collocated Environmental TLDs at Peach Bottom

-

,

1

<

,

Peach Bottom

NRC No.

Distance *

Azimuth * *

Loc. No.

Distance *

Azimuth * '

11

1.9

96

14

2.1

93

!

14

4.6

85

5

4.8

84

31

9.9

261

18

9.7

261

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  • Distance measured in miles

t

  • * Azimuth measured in degrees

t

NOTE:

Distances and azimuths were measured independently and do not necessarily agree; however, collocation of

'

these TLDs has been confirmed.

3

- .

-

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.

. .

. . .

. . .

.

. . .

. . .

, _ _ .

- _ . . , _ . _ _ . . . _ . _ _ - .

. - _ _ _

_. .. __ ____---_-- . _ - - - - - - - - - - . - _ - - - -

___ --__ - - _ _ _ - - - . - _ _ _ _ _ . . - . _ - - - - . - - - _ _ _ - - - _ - - . - - - - - _ - _ - - _ - - - - - - - -_ _ ------_-___ _ _ -- _-_ _ _ _ --- . - _ - _ _ _ _

.

-

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-

5

Table 2

'

Environmental TLD Monitoring Results (mR/ quarter)*

Comparison of NRC TLDs Collocated with Peach Bottom TLDs

-

NRC no.:

11

14

31

Monitoring Period

PBAPS no.:

14

5

18

1995/1st Quarter

NRC

19.8 i O.7

18.9 i O.7

21.9 i O.8

PBAPS

15.7 i 1.2

15.1 i 1.0

17.5

0.6

2nd Quarter

NRC

19.6 i O.7

19.3 i O.7

21.9 i O.8

PBAPS

15.7

0.7

15.7 i O.2

16.6 i O.6

3rd Quarter

NRC

19.6 i O.7

20.5 i O.7

21.7 i O.7

PBAPS

15.4 i O.2

16.0 i O.6

16.9

0.7

4th Quarter

NRC

19.7 i 1.0

20.4 i 1.0

21.7 i 1.0

PBAPS

14.2 i O.6

15.7 i 1.2

17.8 i 1.0

,

1996/1st Quarter

NRC

17.9 i O.6

18.2 i O.6

19.9 i O.7

PBAPS

14.7 i O.6

16.1 i O.9

18.0 i O.4

'

2nd Quarter

NRC

18.5 i O.7

18.5 i O.7

21.6 i O.7

PBAPS

15.7 i O.2

15.7 i O.4

17.9 i O.4

.

All results are in milliroentgens and are normalized to a 90-day quarter.

All data are shown as Result i 1 standard deviation.

.

. -

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6

R1.2 Meteoroloaical Monitorina Proaram (MMP)

a.

_In_spection Scone (84750)

_

The MMP was evaluated to determine whether the instruments and equipment were

operable, calibrated, and maintained. The MMP was inspected against UFSAR

Section 2.3 and Regulatory Guide 1.23.

The following associated procedures were reviewed:

'

IC-11-00807,

Loop Calibration of the Climatronics Model F460 Wind

Direction and Wind Speed Transmitters

IC-11 -00811,

Loop Calibration of the Bendix-Friez Model 120 Wind speed -

wind Direction system

IC-C-11 -00806,

Loop Calibration of the Climatronics 1000HM Platinum

Temperature System

IC-C-11-00808,

Calibration of the Esterline Angus Model MS 424C Recorder

IC-C-11 -00809,

Calibration of the Esterline Angus Model MS 1124S Speed

j

Servo 11 Multi Point Recorder

IC-C-11 -00810,

Calibration of the SUMX Model SX-410 Data Acquisition

System

i

RT-0-094-800-2,

Meteorology Equipment Functional Test

b.

Observations and Findinas

Calibration and functional tests of the meteorological instrumentation were

performed using the above IC procedures. Calibration results from January 1995 -

December 1996 were reviewed. The licensee calibrated the instruments every 6

months as required by the UFSAR commitments and the RG 1.23 recommendations.

Functional checks from October - December 1996 were reviewed. The functional

checks were performed weekly as required in the UFSAR and the procedure, RT-0-

094-800-2. Results of the calibrations were within the established acceptance

criteria recommended by the vendor. Instrumentation was well maintained. The

inspector noted that the licensee had recently drafted a procedure to ensure paper

from the recorders would be changed every 2 weeks.

.-

--

.

-

-

.- . -

-

!

.

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1

,

.

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!

7

Log books and records of maintenance were also reviewed. The books were kept

at the tower and the control room and used to record maintenance, surveillance,

'

and calibration activities. The logs were up-to-date and coincided with maintenance

and calibration records.

!

c.

Conclusions

Based on the above review of procedures, direct observations, and discussions with

personnel, the inspector concluded that calibration and maintenance of the

equipment were performed according to procedures, the meteorological monitoring

instrumentation was operable and sufficiently maintained, and the licensee

continued to effectively implement the meteorological monitoring program in

accordance with UFSAR and RG 1.23 commitments.

'

,

i

'

R6

RP&C Organization and Administration

R6.1 Manaaement Controls

a.

insoection Scope (84570)

The inspector reviewed organization changes and the responsibilities relative to

oversight of the REMP and MMP, and reviewed the annual Radiological

4

Environmental Operating Report and Dose Assessmer:t Report to verify the

implementation of ODCM Sections 3.8.E, 3.10.1 and 3.10.2.

.

b.

Observations and Findinas

.

3

The organization and responsibilities at the corporate office, located in

Chesterbrook, PA, essentially have remained the same since the previous inspection

conducted in March 1995. The responsibility to implement the REMP was with the

Program Manager, Programs Branch, Programs / Procedures Section, Nuclear

Engineering Division. Responsibility to perform calibrations of the meteorological

monitoring tower was with the Instrument and Controls Department at the site.

The annual REORs for 1994 and 1995 provided a comprehensive summary of the

observed impacts of plant operation on the environment surrounding the Peach

Bottorn sites. The results met the ODCM reporting requirements. The reports also

provided a summary of the land use census and interlaboratory comparison

program. The analytical data from 1996 were reviewed for sample frequency and

analysis requirements specified in the ODCM. No omissions, mistakes, obvious

anomalous results or trends were noted. Program deviations and/or changes in

.

.

.

8

sampling locations were reported. The Dose Assessment Report for the period

January 1,1995, through December 31,1995, was reviewed. The report included

a summary of the radiation doses due to radioactive effluent releases from the sites

and annual summaries of hourly meteorological data joint frequency distributions of

wind speed, wind direction and atmospheric stability.

c.

Conclusion

Based on the above review, the inspector determined that the licensee implemented

very good management control and oversight of the REMP and MMP and effectively

implemented Sections 3.8.E, 3.10.1 and 3.10.2 of the ODCM.

R7

Quality Assurance in RP&C Activities

R7.1 Quality Assurance Audit Proaram

a.

Insoection Scoce (84750)

1

Quality Assurance (QA) audit and surveillance programs were inspected against

criteria contained in the licensee's procedures and TS requirements. Audits of the

REMP and MMP were reviewed and follow up was performed to ensure the 1994

,

NUPIC audit findings had been closed by the licensee.

b.

Observations and Findinas

The inspector reviewed the following Quality Assurance Audit Report as part of the

,

evaluation of the implementation of the TS audit requirement:

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A0956206, Emergency Plan and Procedures Assessment and

10CFR50.54.(t) Review, dated 1/10/96

A0903756, NQA Audit at the GPU Nuclear Corporation Environmental

Radioactivity Laboratory (EML), dated

A0919170, Radiological and Environmental Monitoring, dated 5/26/95

The audits were performed by qualified personnel and were of sufficient technical

depth to assess the implementation of the programs. The audits were performed

within the 'requency in TS.

Licensee follow up of the NUPIC audit showed that all 5 items were closed in 1995.

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c.

Conclusion

Based on the above review, the inspector determined that the audits were sufficient

to assess the REMP and MMP and that the licensee implemented the TS audit

requirements.

R7.2 Quality Control Proarem of Analvtical Measurements

a.

Insoection Scoce (84750)

The inspector reviewed the quality control (OC) program of analytical measurements

against recommendation of Regulatory Guide 4.15, " Quality Assurance for

Radiological Monitoring Prograrr.s (Normal Operations) - Effluent Streams and the

Environment" to determine whether the licensee had adequate r,ontrol with respect

to sampling, analyzing, and evaluating data for the implementation of the REMP.

Included was a review of the intercomparison program required by ODCM Section

3.8.E.3.

b.

Observations and Findinas

The licensee uses the GPU Environmental Radioactivity Laboratory (ERL) as the

primary lab to analyze the environmental samples. The lab maintains an extensive

QC program including participation in the EPA cross check program (1995). Results

of this program were within the EPA acceptance criteria. With the exception of

drinking water, the EPA terminated the cross check program in December 1995.

Therefore, the licensee was tasked with finding another laboratory to provide an

independent intercomparison program. The EPA program was replaced using

Analytics, Inc. and the results were within the GPU laboratory criteria. Periodic

reports of QC results are suppbed to the licensee. The data, with few exceptions,

indicate agreement between the primary contractor laboratory and the QC

laboratory. ~Where discrepsncies were found, reasons for the differences were

investigated and resolved.

c.

Conclusion

Based on the above review, the inspector determined that the licensee continued to

implement a good quality control program in accordance with regulatory

requirements and recommendations. The licensee maintained good control with

respect to sampling, analyzing, and evaluating data for the implementation of the

REMP based on the data reviewed.

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R1.2 Desian Modifications involvina the North Wall of the Unit 3 Turbine Buildina

a.

laspection Scope (84750)

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The inspection scope, regarding Modification P00248, was to: (1) verify that

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gaseous effluents were processed as specified in the ODCM (Section 3.8.C.5) or

that compensatory measures had been taken: (2) ensure that an adequate safety

evaluation was conducted in accordance with 10 CFR 50.59; and (3) determine if

the turbine building atmosphere was processed consistent with the UFSAR

description (Section 10.15).

b.

Observations and Findinas

During the previous inspection, an inspector reviewed a PECO-identified event

involving a low level unmonitored release from the Unit 3 turbine building (TB)

which began on July 18 and ended on July 25,1996. (See Section R2 of the

Routine Integrated inspection Report 50-277/96-06 and 50-278/96-06, dated

October 10,1996, for details.)

During this inspection, a review of the licensee's 10 CFR 50.59 evaluation for

Modification P00248 (Mod) involving the construction of the new Plant Entrance

and Radiochemistry Laboratory (PEARL) Building (including the associated

penetration of the north wall of the Unit 3 Turbine Building to support the Mod) was

conducted by the inspector. According to the Mod, the licensee planned to breach

the north wall of the Unit 3 Turbine Building on July 18,1996. Five out of seven

holes (3'x 5') were initially cut into the turbine building wall to install ventilation

duct supports for the new Plant Entrance and Radiochemistry Laboratory (PEARL)

building exhaust systems. The exhaust duct traveled along the outside of the

turbine building, across the roof and entered the reactor building vent stack. After

cutting holes in the TB, a worker on the job was identified with short lived activity

(< 100 cpm) on his hand. The licensee reviewed the work conditions and collected

an air sample from the 195 foot elevation, which identified short-lived activity of

SE-10 Ci/cc Cs-138. The licensee calculated doses to the public using a

conservative assumption that the release through the holes was 10% of the total

reactor building vent flow (2E4 CFM). The offsite doses for the release were

calculated to be 3.2E-5 mrem / year total body and 5.1E-5 mrem / year skin. The

ODCM limit is 500 mrem / year total body and 3000 mrem / year skin. The licensee

stated that a full report of this event will be documented in the 1997 Annual

Radioactive Effluent Release Report as required by ODCM Section 3.10.2.

The inspector determined that the proper processing and monitoring of turbine

building atmosphere was not adequately performed. The UFSAR (Section 10.15)

states that exhaust ventilation air from the turbine building and radwaste building is

discharged to atmosphere from the ventilation stack above the reactor building roof

(a monitored release point). The licensee, on July 22,1996, stated in the

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Performance Evaluation Program (PEP) that, "After checking the covered openings

that flat sheeting on the corrugated outs:de wallleft wide gaps through which there

was very noticeable outward air flow. This air flow is a potential release path for

radioactive material." With regard to this statement, the inspector noted that the

licensee was aware of the potential for release of radioactive material after the holes

had been cut. Since the licensee could not ensure a negative pressure had been

maintained, the holes became a pathway for a potential unmonitored release. (See

observations and findings of Section R2 of the previous inspection report, noted

above, for details.)

Based on the licensee's "10 CFR 50.59 Review for Modification P00248," the

inspector determined that no evaluation of the gaseous waste processing,

monitoring, nor dose assessment was addressed. The licensee stated that they

assumed the turbine building was slightly negative and would remain slightly

negative as specified in UFSAR during the Mod and, therefore, no further evaluation

was performed. The evaluation did not consider the creation of a potential

unmonitored release pathway. No monitoring of the turbine building (continuous or

grab sampling) was planned. The actual modification resulted in an outward flow of

air from turbine building contrary to the licensee's assumptions of the maintenance

of negative pressure. With the exception of the sample previously noted, no

monitoring had been performed to evaluate this release pathway in a timely manner.

Failure of the licensee's safety evaluation record to provide the bases for the

determination that the penetration did not involve an unreviewed safety question

constitutos a violation of 10 CFR 50.59(b)(1). (VIO 50-278/97-03-01)

ODCM 3.8.C.S. states, in part, that gaseous effluents shall be processed through

the turbine Gaseous Waste Treatment System. The turbine building atmospheres

shall be processed through permanently or temporarily installed equipment in the

appropriate building ventilation system and the vent stack. The inspector noted

that, in the existing condition, the licensee could not assure that the turbine building

atmosphere was processed through the turbine building gaseous waste treatment

system, using either permanently or temporarily installed equipment. Failure to

assure that the turbine building atmosphere was processed and monitored in

accordance with the applicable plant design and regulatory requirements,

constitutes a violation of ODCM 3.8.C.5. (VIO 50-278/97-03-02)

c.

Conclusion

Based on the above findings, the inspector concluded the following. During the

Mod, a small portion of the turbine building atmosphere was unmonitored and

released through the holes cut into the turbine building. The safety evaluation

performed in accordance with 10 CFR 50.59 failed to address changes to the

Turbine Building that could result in unmonitored releases. The licensee identified

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these issues after the holes were cut. Overall, the immediate corrective actions to

ameliorate the condition were adequate, however, corrective actions relative to

assuring comprehensive evaluation of all elements of a facility change was not

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evident during this inspection. No actual safety consequence was evident as a

result of in this occurrence.

R8

Miscellaneous RP&C lasues

R8.1 UFSAR

A recent discovery of a licensee operating their facility in a manner contrary to the

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Updated Final Safety Analysis Report (UFSAR) description highlighted the need for a

special focused review that compares plant practices, procedures and/or parameters

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to the UFSAR description. While performing the inspection discussed in this report,

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the inspectors reviewed the applicable portions of the UFSAR that related to the

areas inspected. The inspectors verified that the UFSAR wording was consistent

with the observed plant practices and procedures and/or parameters, except as

noted in Section R1.2 of this report.

V. Manaaement Meetinas

X1

Exit Meeting Summary

The inspector presented the inspection results to members of the licensee management at

the conclusion of the onsite inspection on December 13,1996. Subsequently, the

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inspector continued to review information relative to the onsite findings until a conclusion

was reached on January 24,1997. Following the conclusion, the inspection results were

discussed by telephone with licensee representatives on January 31,1997.

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PARTIAL LIST OF PERSONS CONTACTED

Licensee Personnel

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E. Anderson, System Manager, Plant Engineering Division

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  • T. Baxter, Nuclear Quality Assurance

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  • G. Beck, Manager Programs / Procedures Section

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D. Chase, Radiochemist, Chemistry

  • G. Lengylle, Experience Assessment Manager

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  • T. Loomis, Licensing

J. Moore, Lead Responsible Engineer, Nuclear Engineering Division

  • T. Mscisz, Engineer, Meteorology

' R. Nagle, l&C Technician

  • A. O' Dell, Chemistry Manager
  • D. Wahl, Physicist, Programs Branch

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Contractor Personnel

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C. Reid, Sampling Contractor, Radiation Management Corporation, Inc.

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' Denotes those present at the exit meeting on December 13,1996.

The inspector also interviewed other licensee personnel.

LIST OF INSPECTION PROCEDURES USED

84750:

Radioactive Waste Treatment, and Effluent and Environmental Monitoring

LIST OF ITEMS OPENED, CLOSED AND DISCUSSED

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Opened

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50-278/97-03-01

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Failure to perform and adequate safety evaluation according to

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10 CFR 50.59(b)(1)

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50-278/97-03-02

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Failure to assure that the turbine building atmosphere was

processed through the turbine building gaseous waste

treatment system.

Closed

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Discussed

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PARTIAL LIST OF ACRONYMS

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EPA.

Environmental Protection Agency

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MMP

Meteorological Monitoring Program

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NCV

Non-Cited Violation

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NRC

Nuclear Regulatory Commission

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ODCM

Offsite Dose Calculation Manual

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QA

Quality Assurance

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OC

Quality Control

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REMP

Radiological Environmental Monitoring Program

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REOR

Radiological Environmental Operating Report

TLD

Thermoluminescent Dosimeter

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TS

Technical Specifications

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UFSAR

Updated Final Safety Analysis Report

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