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=Text=
=Text=
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r SOUTH CAROLH4A ELECTRIC & GAS COMPANY
r SOUTH CAROLH4A ELECTRIC & GAS COMPANY
  .                                                                            ,ou cerier so. ,..
,ou cerier so.,..
CotuMe:A. Souin CAnoLINA 29818 T. C. Nicuots, Jn.
CotuMe:A. Souin CAnoLINA 29818 i
V<t P.g sset.f .W G4wp CAECvmt January 9, 1981                                                                i nau. c .., ..                                                                                                         ;
T. C. Nicuots, Jn.
Mr. Harold R. Denton, Director                                                                                                 ;
January 9, 1981 V<t P.g sset.f.W G4wp CAECvmt nau. c..,..
Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commicsion                                                                                             [
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commicsion
Washington, D. C. 2055$
[
Washington, D. C.
2055$


==Subject:==
==Subject:==
Virgil C.                           uclear Station Docket No           /395
Virgil C.
        }                                                                                                   Shielding Review I
uclear Station Docket No
( s_ e       
/395
}
Shielding Review I
(


==Dear Mr. Denton:==
==Dear Mr. Denton:==
 
s_ e South Carolina Electric & Cas Company acting for itself and as agent for the South Carolina Public Service Authority, provides forty-five (45) copies of the Design Review of Plant Shielding and Environmenta.1 Qualification of Equipment for Spaces / Systems which may be used in post accident operations outside the reactor building at the Virgil C. Synser Nuclear Station. This information will be incorporated in Amendment 23 of FSAR.
South Carolina Electric & Cas Company acting for itself and as agent for the South Carolina Public Service Authority, provides forty-five (45) copies of the Design Review of Plant Shielding and Environmenta.1 Qualification of Equipment for Spaces / Systems which may be used in post accident operations outside the reactor building at the Virgil C. Synser Nuclear Station. This information will be incorporated in Amendment 23 of FSAR.
If you have any questions, please let us know, i
If you have any questions, please let us know, i
Very truly yours,                                                 .
Very truly yours, t
      ,                                                                                                              -                                    t L=       h          f #
h f
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                                                                                              <                    A'           . S'                     ;
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l_sk                                                                           T. C. Nichols, Jr.
A' S'
      $                    NEC:TCN:glb I        
l_sk T. C. Nichols, Jr.
NEC:TCN:glb I


==Enclosures:==
==Enclosures:==
 
cc:
cc: V. C. Summer w/o enclosures G. H. Fischer w/o enclosures T. C. Nichols, Jr. w/o enclosures E. H. Crews, Jr.
V. C. Summer w/o enclosures G. H. Fischer w/o enclosures T. C. Nichols, Jr. w/o enclosures E. H. Crews, Jr.
O. W. Dixon, Jr.
O. W. Dixon, Jr.
D. A. Nauman O. S. Bradham W. A. Williams, Jr.
D. A. Nauman O. S. Bradham W. A. Williams, Jr.
A. A. Smith-                               ~
A. A. Smith-A. R. Koon E3?
A. R. Koon                     E3?
~
R. B. Clary                               -
R. B. Clary J. B. Knotts, Jr.
J. B. Knotts, Jr.
J. L. Skolds I"
J. L. Skolds B. A. Bursey                    I"               C'.U ' '
C'.U ' '
NPCF/Whitaker File Ni;.
B. A. Bursey NPCF/Whitaker File Ni;.
I 8 1013 5 o gg, l     t                                   A
I 8 013 5 o gg, 1
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A


              #      O   ,
O 12A DESIGN REVIEW OF PLANT SHIELDING AND ENVIRONMENTAL QUALIFICATION OF EQUIPMENT FOR SPACES / SYSTEMS WHICH MAY BE USED IN POST ACCIDENT OPERATIONS OUTSIDE THE REACTOR BUILDING AT THE VIRGIL C. SUMMER NUCLEAR STATION t
12A DESIGN REVIEW OF PLANT SHIELDING AND ENVIRONMENTAL QUALIFICATION OF EQUIPMENT FOR SPACES / SYSTEMS WHICH MAY BE USED IN POST ACCIDENT OPERATIONS OUTSIDE THE REACTOR BUILDING AT THE VIRGIL C. SUMMER NUCLEAR STATION t
12A.1 INTRODUCTION l
12A.1       INTRODUCTION l                       This report has been prepared in response to the September 13, 1979, letter from Darrel G. Eisenhut of the NRC to all operating nuclear power plants. This , letter i
This report has been prepared in response to the {{letter dated|date=September 13, 1979|text=September 13, 1979, letter}} from Darrel G. Eisenhut of the NRC to all operating nuclear power plants. This, letter prerented an implementation schedule for the recommendations presented in "TMI-2 i
prerented an implementation schedule for the recommendations presented in "TMI-2 j         s Less ons Learned Task Force Status Report and Short-Term Recommendations" (NUB:G-0578). The requirements defined in the September 13th letter were subs equently clarified in a letter from Harold R. Denton to all operating nuclear powtr plants dated October 30, 1979.
j Less ons Learned Task Force Status Report and Short-Term Recommendations" s
(NUB:G-0578). The requirements defined in the September 13th letter were subs equently clarified in a letter from Harold R. Denton to all operating nuclear powtr plants dated October 30, 1979.
Among the requirements defined in the two NRC letters is a review to determine whether post-accident radiation fields unduly limit personnel access to areas necessary for mitigation of or recovery from an accident or unduly degrade the proper operation of safety equipment. Corrective actions for problems identified as a result of the review are also to be determined. This report presents the results of such a review for the Virgil C. Summer Nuclear Station.
Among the requirements defined in the two NRC letters is a review to determine whether post-accident radiation fields unduly limit personnel access to areas necessary for mitigation of or recovery from an accident or unduly degrade the proper operation of safety equipment. Corrective actions for problems identified as a result of the review are also to be determined. This report presents the results of such a review for the Virgil C. Summer Nuclear Station.
1             The review was based on the following guidelines:
1 The review was based on the following guidelines:
a)   The post-accident dose rate in areas requiring continuous occupancy should     23 not exceed 15 mr/hr.
a)
b)   The post-accident dose rate in areas which do not requi.:e continuous         l 23 occupancy should be such that the dose to an individual during a required access period is less than 5 Rem whole body or its equivalent, in order to maintain compliance with General Design Criterion 19.
The post-accident dose rate in areas requiring continuous occupancy should 23 not exceed 15 mr/hr.
c)   The integrated dose to safety equipment.as a result of the accident should be less than the dose for which the equipment has been qualified to ensure 11A-1 4
b)
The post-accident dose rate in areas which do not requi.:e continuous l 23 occupancy should be such that the dose to an individual during a required access period is less than 5 Rem whole body or its equivalent, in order to maintain compliance with General Design Criterion 19.
c)
The integrated dose to safety equipment.as a result of the accident should be less than the dose for which the equipment has been qualified to ensure 11A-1 4
i
i


s                                                                                   .    .
s that the capability of the equipment to perform its safety function.has not been degraded, in order to maintain compliance with General Design 23 Criterion 4.
that the capability of the equipment to perform its safety function.has not been degraded, in order to maintain compliance with General Design 23 Criterion 4.
d)
d) The minimum radioactive source term used in the evaluation should be equivalent to the source terms recensnended in Regulator / Guides 1.3 and 1.4.
The minimum radioactive source term used in the evaluation should be equivalent to the source terms recensnended in Regulator / Guides 1.3 and 1.4.
I 1
I 1
i   .
i 4
4 r
r u
u 6
6 m
m h
h i
i l
l h
h 12A-2
12A-2 l
* l i
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9           &
9 s
s 12A.2    
12A.2


==SUMMARY==
==SUMMARY==
 
This report provides a review of the Virgil C. Summer Nuclear Power Plant to determine whether post-accident radiation fields unduly limit personnel access to areas necessary for mitigation of or recovery from an accident, or unduly degrade the proper operation of safety equipment. This review was accomplished using the recommendations and guidelines of NUREG-0578 and subsequent clarifications as l
This report provides a review of the Virgil C. Summer Nuclear Power Plant to determine whether post-accident radiation fields unduly limit personnel access to
provided by the NRC.
, ,                                areas necessary for mitigation of or recovery from an accident, or unduly degrade the proper operation of safety equipment. This review was accomplished using the recommendations and guidelines of NUREG-0578 and subsequent clarifications as l                     provided by the NRC.
A detailed discussion of the evaluation of plant vital areas and equipment qualification for post-accident conditions is presented in Sections 4.0 and 5.0.
A detailed discussion of the evaluation of plant vital areas and equipment
.! k,!
:        ,_,          qualification for post-accident conditions is presented in Sections 4.0 and 5.0.
Results indicated that certain areas of the plant required additional radiation shielding to reduce the post-accident radiation fields. These areas and the shielding modifications utilized are described in the following paragraphs.
        .!       k,!             Results indicated that certain areas of the plant required additional radiation shielding to reduce the post-accident radiation fields. These areas and the shielding modifications utilized are described in the following paragraphs.
Area "A" is the location of the residual heat removal (RER) pumps, reactor building spray pumps, and the pump room cooling units. The RER/ Spray piping is adequately shielded and does not restrict post-accident access to this area.
            !                      Area "A" is the location of the residual heat removal (RER) pumps, reactor building spray pumps, and the pump room cooling units. The RER/ Spray piping is adequately shielded and does not restrict post-accident access to this area.           -
However, a significant potential source of exposure to plant personnel can result a
a However, a significant potential source of exposure to plant personnel can result from the RER/ Spray pump room sump line. This line was unshielded and located in   23 the ha'11way between pump room B and the waste holdup tank, and resulted in a potentially high radiation ares during both normal and accident operating conditions. The resultant dose levels in the subject area have been reduced to l         /           acceptable values by the re-routing and venting of the line to permit the line to drain during sump pump shutdown periods, and the placement of lead shielding to       ,
from the RER/ Spray pump room sump line. This line was unshielded and located in 23 the ha'11way between pump room B and the waste holdup tank, and resulted in a potentially high radiation ares during both normal and accident operating conditions. The resultant dose levels in the subject area have been reduced to l
i                      prevent streaming to the operating floor 374'-0". The new pipe configuration and radiation shielding allows personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose       ,
/
requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
acceptable values by the re-routing and venting of the line to permit the line to drain during sump pump shutdown periods, and the placement of lead shielding to i
Following an accident, personnel access to the auxiliary building is controlled
prevent streaming to the operating floor 374'-0".
    ,                              at the 412'-0" elevation from the control building. As a result, the use of the stairway and elevator located in cubicle 12-09 as an access route to vital areas 12A-3 i
The new pipe configuration and radiation shielding allows personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
Following an accident, personnel access to the auxiliary building is controlled at the 412'-0" elevation from the control building. As a result, the use of the stairway and elevator located in cubicle 12-09 as an access route to vital areas 12A-3 i
1
1


    ;          above and below the 412'-0" elevation is important. A 10-inch RER line penetrates the south and east shield walls of cubicle 12-09 at elevation 429'-6" resulting in significant doses to workers in this area. Shortly after the accident, the integrated dose to a worker transversing this area would be of the order of 1 rem. The resultant dose levels in the subject area have been reduced to acceptable values by the addition of lead shielding. The new configuration allows personnel access in accordance with the occupancy requirements of l             Table 12A.4-2, and the resultant integrated dose meets the dose requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
above and below the 412'-0" elevation is important. A 10-inch RER line penetrates the south and east shield walls of cubicle 12-09 at elevation 429'-6" resulting in significant doses to workers in this area. Shortly after the accident, the integrated dose to a worker transversing this area would be of the order of 1 rem. The resultant dose levels in the subject area have been reduced to acceptable values by the addition of lead shielding. The new configuration allows personnel access in accordance with the occupancy requirements of l
  !                                                                    ~
Table 12A.4-2, and the resultant integrated dose meets the dose requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
  ;            Area "I"   is the location of the charging / safety injection pump room cooling     -
~
  ,            units. This area was found to contain high radiation levels due to unshielded         -
Area "I" is the location of the charging / safety injection pump room cooling units. This area was found to contain high radiation levels due to unshielded CVCS piping located at several places within the area. In order to permit the required occupancy time in the area for aanual valve alignment or maintenance, the resultant dose levels in the area have been reduced to acceptable values by the addition of lead and concrete shielding. The new configuration allow's personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose require =ents of 10CFR50, 23 Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
CVCS piping located at several places within the area. In order to permit the
~.
  ,            required occupancy time in the area for aanual valve alignment or maintenance, the resultant dose levels in the area have been reduced to acceptable values by the addition of lead and concrete shielding. The new configuration allow's personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose require =ents of 10CFR50, 23 Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
r In the area of the intermediate building between the east and west penetration access areas, there were several RHR, safety injection, and CVCS lines which were routed above the sides of an open pipe chase at elevation 422'-3".
~.             r In the area of the intermediate building between the east and west penetration access areas, there were several RHR, safety injection, and CVCS lines which were routed above the sides of an open pipe chase at elevation 422'-3". This permitted direct streaming from the piping to reach the floor area of                     }
This
intermediate building floor elevation 412'-0" which contains safety related f               equipment. The resultant dose levels in this area of the intermediate building have b'een reduced to acceptable values by the modification of the pipe chase as
}
.              follows: (1) extension of the pipe chase side above the 12" RER line, (2) addition of 6" concrete shielding to the existing i foot concrete shiciding, (3) re-location of an access ladder to prevent streaming through a concrete cutout. The new configuration allows personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose. requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
permitted direct streaming from the piping to reach the floor area of intermediate building floor elevation 412'-0" which contains safety related f
equipment. The resultant dose levels in this area of the intermediate building have b'een reduced to acceptable values by the modification of the pipe chase as follows:
(1) extension of the pipe chase side above the 12" RER line, (2) addition of 6" concrete shielding to the existing i foot concrete shiciding, (3) re-location of an access ladder to prevent streaming through a concrete cutout. The new configuration allows personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose. requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737.
I a
I a
12A-:.
12A-:.
1 I
1 I


12A.3   SOURCE TERMS AND CALCULATIONAL METHODOLOGY t
12A.3 SOURCE TERMS AND CALCULATIONAL METHODOLOGY t
12A 3.1   SOURCE TERMS 12A.3.1.1   Basis for the Source Terms The activity releases assumed in this review are based on the assumptions and l                         regulatory positions contained in the Regulatory Guides 1.4 and 1.7. The activity assumed for liquid source term calculation is based on 100 percent of j                         the noble gas inventory, 50 percent of the halogen core inventory and 1 percent
12A 3.1 SOURCE TERMS 12A.3.1.1 Basis for the Source Terms The activity releases assumed in this review are based on the assumptions and l
                  '.            of all other nuclides in the core inventory. The activity assumed for gaseous
regulatory positions contained in the Regulatory Guides 1.4 and 1.7.
                    ,            source term calculation is based on 100 percent of the noble gas core inventory and 25 percent of the halogen core inventory.
The activity assumed for liquid source term calculation is based on 100 percent of j
12A.3.1.2   Liquid Source Terms
the noble gas inventory, 50 percent of the halogen core inventory and 1 percent of all other nuclides in the core inventory. The activity assumed for gaseous source term calculation is based on 100 percent of the noble gas core inventory and 25 percent of the halogen core inventory.
                                .                                                                                      23 Two liquid sources are considered in the design review: (1) the undiluted fluid as found within the reactor coolant system, and (2) the diluted fluid as found within the reacter building recirculation sump. The first source term, undiluted   .
12A.3.1.2 Liquid Source Terms 23 Two liquid sources are considered in the design review:
reactoc coolant, is required in the examination of those systems whose flow originates from either the Reactor Coolant System or an auxiliary system containing the undiluted primary fluid. The source terms are based on the j                       dilution of the liquid activity inventory discussed in the first paragraph with I     '~d the fluid volume of the Reactor Coolant System. This source is used for the examination of the reactor coolant fluid sampling section of the Nuclear Sampling System, and those portions of the Chemical and Volume System associated with the degasification of the reactor coolant fluid.
(1) the undiluted fluid as found within the reactor coolant system, and (2) the diluted fluid as found within the reacter building recirculation sump. The first source term, undiluted reactoc coolant, is required in the examination of those systems whose flow originates from either the Reactor Coolant System or an auxiliary system containing the undiluted primary fluid. The source terms are based on the j
In the second liquid source term, consideration is given for the dilution of the liquid activity inventory discussed in the first paragraph with the fluid volume contained in the reactor building recirculation sump. The minimum fluid volume expected in the sump, and the individual contributors to that volume, are given in Table 12A.3-1. These source terms are utilized in the examination of ,those 12A-5 i
dilution of the liquid activity inventory discussed in the first paragraph with I
'~d the fluid volume of the Reactor Coolant System. This source is used for the examination of the reactor coolant fluid sampling section of the Nuclear Sampling System, and those portions of the Chemical and Volume System associated with the degasification of the reactor coolant fluid.
In the second liquid source term, consideration is given for the dilution of the liquid activity inventory discussed in the first paragraph with the fluid volume contained in the reactor building recirculation sump. The minimum fluid volume expected in the sump, and the individual contributors to that volume, are given in Table 12A.3-1.
These source terms are utilized in the examination of,those 12A-5 i
i
i


systems which receive their fluid supply from the reactor building recirculation sump. Those systems which are considered in the review are:
systems which receive their fluid supply from the reactor building recirculation sump. Those systems which are considered in the review are:
* Residual Heat Removal System Reactor Building Spray System Safety Injection System Nuclear Sampling System (RHR process fluid sample)
Residual Heat Removal System Reactor Building Spray System Safety Injection System Nuclear Sampling System (RHR process fluid sample)
{
{
                            *2A.3.1.3     Gas Source Terms I
*2A.3.1.3 Gas Source Terms I
The gaseous source terms were determined for containment and the waste gas system using the activity releases described in Section 12A.3.1.1.
The gaseous source terms were determined for containment and the waste gas system using the activity releases described in Section 12A.3.1.1.
The containment airborne source term was based on the dilution of the gaseous activity inventory by the containment free volume atmosphere.
The containment airborne source term was based on the dilution of the gaseous activity inventory by the containment free volume atmosphere.
Although not designed for reactor coolant degasification under post-accident conditions, the waste gas system was evaluated for the exposures emitted and received under the post-accident conditions. The waste gas system is designed to
Although not designed for reactor coolant degasification under post-accident conditions, the waste gas system was evaluated for the exposures emitted and received under the post-accident conditions. The waste gas system is designed to remove the fissica product gases from the reactor coolant contained in the Volume Control Tank (VCT). The amount of fission gases renoved from the reactor coolant in the VCT and collected by the waste gas system can be related to the amount entering the VCT as follows:
    ,                      remove the fissica product gases from the reactor coolant contained in the Volume Control Tank (VCT). The amount of fission gases renoved from the reactor coolant in the VCT and collected by the waste gas system can be related to the amount entering the VCT as follows:                                                       , "'
l
l                                                                                                           \
\\
(1) Stripping Efficiency (SE):
(1) Stripping Efficiency (SE):
Cp  -C t
C
SE = C   -C R     L eq i
-C p
t SE = C
-C R
L eq i
(2) Stripping Fraction (SF):
(2) Stripping Fraction (SF):
l C
l C
a
-C a
                                                  -C t
t SF =
SF =
CR l
C R
12A-6 4
l 12A-6 4
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9 where C     =
9 where C
the gas concentration in the reactor coolant liquid entering the R
=
Volume Control Tank, Cg =   the gas concentration in the reactor coolant liquid leaving the Volume Control Tank, C.
R the gas concentration in the reactor coolant liquid entering the Volume Control Tank, C
u
=
                                        =
g the gas concentration in the reactor coolant liquid leaving the Volume Control Tank, C.
the gas concentration in the reactor coolant liquid leaving
the gas concentration in the reactor coolant liquid leaving
                                    '9 l                                      the Volume Control Tank, assuming the ratio of the gas concentration in the liquid and gas phases in the Volume
=
      ;                                      Control Tank follows Henry's Law.
u l
            /-' s I             The waste gas system source terms were determined for the degasification of the reactor coolant liquid by calculation of the quantity of activity entering the Volume Control Tank via the normal letdown path. For the sake of conservatism, the stripping efficiency of this process is assumed to be 100 percent.
'9 the Volume Control Tank, assuming the ratio of the gas concentration in the liquid and gas phases in the Volume Control Tank follows Henry's Law.
Therefore, in the previous equation of the stripping fraction, C7=C7         , and the stripping fraction is:                                                     'S C   -C                                                               -
/-' s I
R    7
The waste gas system source terms were determined for the degasification of the reactor coolant liquid by calculation of the quantity of activity entering the Volume Control Tank via the normal letdown path. For the sake of conservatism, the stripping efficiency of this process is assumed to be 100 percent.
    <                                  SF =           '**
Therefore, in the previous equation of the stripping fraction, C7=C7
, and the stripping fraction is:
'S C
-C R
7 SF =
gg Thus, the separation of the fission gases from the reactor coolant liquid in the
gg Thus, the separation of the fission gases from the reactor coolant liquid in the
(,             VCT will follow Henry's Law. This results in the maximum theoretical gas 1     %-
(,
concentration in the vapor phase of the VCT and, hence, the maximum quantity of t
VCT will follow Henry's Law. This results in the maximum theoretical gas 1
gas enters the waste gas system.
concentration in the vapor phase of the VCT and, hence, the maximum quantity of gas enters the waste gas system.
12A.3.2       METHODOLOGY 12A.3.2.1       Calculation of Dose Rates Dose cates for the areas of interest in this review were calculated by determining the potential contributing sources at a representative location and using the appropriate source term from Table 12A.3-2 adjusted for decay as required. The dose rate at the representative location was used as the general 12A-7 1
t 12A.3.2 METHODOLOGY 12A.3.2.1 Calculation of Dose Rates Dose cates for the areas of interest in this review were calculated by determining the potential contributing sources at a representative location and using the appropriate source term from Table 12A.3-2 adjusted for decay as required. The dose rate at the representative location was used as the general 12A-7 1
i
i


ares dose rate for the area. The SDC computer code (Ref. 1) was used in performing the dose rate calculations. Energy groups re' quired as input to the computer code were determined using the gansna ray energy and intensity data in Refs. 2 and 3 for the nuclides in Table 12A.3-2.
ares dose rate for the area. The SDC computer code (Ref. 1) was used in performing the dose rate calculations. Energy groups re' quired as input to the computer code were determined using the gansna ray energy and intensity data in Refs. 2 and 3 for the nuclides in Table 12A.3-2.
12A.3.2.2   Calculation of Doses to Personnel During Post Accident Access to Vital Areas i
12A.3.2.2 Calculation of Doses to Personnel During Post Accident Access to Vital Areas i
Personnel doses received in performing a specific task in a given vital area are calculated as the sum of the doses received during travel to and from the vital area and the dose received while performing the given operation in the vital         .
Personnel doses received in performing a specific task in a given vital area are calculated as the sum of the doses received during travel to and from the vital area and the dose received while performing the given operation in the vital area.
area.
The doses received during travel are determined by calculating dose rates at selected locations (or at a single location if the dose rate along the travel route is relatively uniform) along the travel route using the methodology discussed in Section 12A.3.2.1 and multiplying the dose rates by the appropriate travel time for each selected location along the travel route.
The doses received during travel are determined by calculating dose rates at selected locations (or at a single location if the dose rate along the travel route is relatively uniform) along the travel route using the methodology discussed in Section 12A.3.2.1 and multiplying the dose rates by the appropriate travel time for each selected location along the travel route.
Doses received while performing a given operation are determined by multiplying the dose rate for the given area by the time required to perform the operation.
Doses received while performing a given operation are determined by multiplying the dose rate for the given area by the time required to perform the operation.
Dose estes for the given vital ares are determined using the methodology discussed in Section 12A.3.2.1.                                                       -g l
Dose estes for the given vital ares are determined using the methodology discussed in Section 12A.3.2.1.
                                                                                                ']
-g l
12A.3.2.3     Calculation of Integrated Doses to Safety Equipment i
']
12A.3.2.3 Calculation of Integrated Doses to Safety Equipment i
The integrated dose to a given item of safety equipment is determined by integrating the dose rate appropriate for the given item over the time period that it is required to be available to perform its safety function. Dose estes are calculated using the methodology discussed in Section 12A.3.2.1.
The integrated dose to a given item of safety equipment is determined by integrating the dose rate appropriate for the given item over the time period that it is required to be available to perform its safety function. Dose estes are calculated using the methodology discussed in Section 12A.3.2.1.
I   4 12A-3 t   J l
I 4
12A-3 t
J l
I
I


TABLE 11A.3-1 CONTAINMENT SUMP MINIMUM LIQUID INVENTORY Liquid Source                                   Liquid Volume (ft3)
TABLE 11A.3-1 CONTAINMENT SUMP MINIMUM LIQUID INVENTORY Liquid Source Liquid Volume (ft3)
Refueling Vater Storage Tank                                   46,791*
Refueling Vater Storage Tank 46,791*
Safety Injection Accumulators                                   3,000 i           Boron Injection Tank                                               120 Sodium Hydroxide Storage Tank                                     408*
Safety Injection Accumulators 3,000 i
Reactor Coolant System                                         9,146 w          Minimum containment Sump Volume =                         59,465 ft 3 i
Boron Injection Tank 120 Sodium Hydroxide Storage Tank 408*
NOTES:
Reactor Coolant System 9,146 3
(a) Refueling Water Storage Tank at minimum operating water level at start of         -
Minimum containment Sump Volume =
drawdown of the tank. The tank drawdown will be terminated at LO-LO level upon the automatic initiation of recirculation via the RER system.
59,465 ft w
i NOTES:
(a) Refueling Water Storage Tank at minimum operating water level at start of drawdown of the tank. The tank drawdown will be terminated at LO-LO level upon the automatic initiation of recirculation via the RER system.
(b) The three (3) Safety Injection Accumulators have individual capacities of 3
(b) The three (3) Safety Injection Accumulators have individual capacities of 3
1000 ft each.
1000 ft each.
v8 (c) The minimum usable volume of liquid in the Sodium Hydroxide Storage Tank.
(c) The minimum usable volume of liquid in the Sodium Hydroxide Storage Tank.
l y.-                                                                                               !
v8 l
y.-
t b
t b
4 i                                                 12A-9 9
4 i
12A-9 9
I
I


                                . _ . .            _ - _ - . . - - - _        ~ _ _ - . _ . - . -_ . _ - -         -        _-_        .-.
~ _ _ -. _. -. -_. _ - -
!                                                                    . TABLE 12A.3-2 V. C. SUMMER SHIELDING S0t:RCE TERMS (T=0)
TABLE 12A.3-2 V. C. SUMMER SHIELDING S0t:RCE TERMS (T=0)
L Liquid (         Caseous ( }       Containment                         Reactor       Containment Source           Source                   Susp                       Coolant         Airborne             Waste Gas Activity         Activity     Concentration Concentration Concentration Concentration i       Isotope   (Ci)             (CL)               (uci/ce)                 (pci/ce)             (pCi/ce)             (pci/ce) a Be-84   7.5 + 6           3.75 + 6           4.46 + 3                   2.90 + 4             7.20 + 1             6.67 + 3 Kr-87   3.70 + 7         3.70 + 7           2.20 + 4                   1.43 + 5             7.10 + 2             1. 30 + 6. -
L Liquid (
Te-133 4.40 + 5               -
Caseous ( }
2.62 + 2                   1.70 + 3                       -                -
Containment Reactor Containment Source Source Susp Coolant Airborne Waste Gas Activity Activity Concentration Concentration Concentration Concentration i
Cs-134 1.70 + 5               -
Isotope (Ci)
1.01 + 2                 6.56 + 2                       -                -
(CL)
Cs-136 4.70 + 4               -
(uci/ce)
2.80 + 1                   1.81 + 2                         -              -
(pci/ce)
Cs-137 7.03 + 4               -
(pCi/ce)
4.18 + 1                   2.71 + 2                       -                -
(pci/ce) a Be-84 7.5 + 6 3.75 + 6 4.46 + 3 2.90 + 4 7.20 + 1 6.67 + 3 Kr-87 3.70 + 7 3.70 + 7 2.20 + 4 1.43 + 5 7.10 + 2
Ba-139 1.50 + 6               -
: 1. 30 + 6. -
8.93 + 2                   5.79 + 3                         -              -
Te-133 4.40 + 5 2.62 + 2 1.70 + 3 Cs-134 1.70 + 5 1.01 + 2 6.56 + 2 Cs-136 4.70 + 4 2.80 + 1 1.81 + 2 Cs-137 7.03 + 4 4.18 + 1 2.71 + 2 Ba-139 1.50 + 6 8.93 + 2 5.79 + 3 Be-83 3.20 + 6 1.60 + 6 1.90 + 3 1.24 + 4 3.07 +-1 2.85 + 3 Kr-83m 6.30 + 6 6.30 + 6 3.75 + 3 2.43 + 4 1.21 + 2 2.09 + 5 Kr-85m 1.90 + 7 1.90 + 7 1.13 + 4 7.34 + 4 3.65 + 2 5.06 + 5 Kr-85 7.42 + 5 7.42 + 5 4.42 + 2 2.36 + 3
Be-83   3.20 + 6         1.60 + 6             1.90 + 3                 1.24 + 4             3.07 +-1       -
.1.42 + 1 1.15 + 4 i
2.85 + 3 Kr-83m 6.30 + 6         6.30 + 6             3.75 + 3                 2.43 + 4             1.21 + 2             2.09 + 5 Kr-85m 1.90 + 7         1.90 + 7             1.13 + 4                 7.34 + 4             3.65 + 2             5.06 + 5 i
Kr-88 5.50 + 7 5.50 + 7 3.27 + 4 2.12 + 5 1.06 + 3 1.63 + 6 Rb-88 5.41 + 5 3.22 + 2 2.09 + 3 I
Kr-85   7.42 + 5         7.42 + 5           4.42 + 2                   2.36 + 3             .1.42 + 1             1.15 + 4 Kr-88   5.50 + 7         5.50 + 7             3.27 + 4                 2.12 + 5             1.06 + 3             1.63 + 6 Rb-88   5.41 + 5               -
Rb-89 6.80 + 5 4.05 + 2 2.63 + 3 Sr-89 7.40 + 5 4.40 + 2 2.36 + 3 St-90 5.00 + 4 2.98 + 1 1.93 + 2 Y-90 5.00 + 4 2.98 + 1 1.93 + 2 Sr-92 9.10 + 5 5.42 + 2 3.51 + 3 Y-92 1.00 + 6 5.95 + 2 3.86 + 3 Sr-93 1.10 + 6 6.55 + 2 4.25 + 3 Y-93 1.10 + 6 6.55 + 2 4.25 + 3 Mo-99 1.50 + 6 8.93 + 2 5.79 + 3 J
3.22 + 2                 2.09 + 3                         -              -
Tc-99m 1.30 + 6 7.74 + 2 5.02 + 3
I Rb-89   6.80 + 5               -
)
4.05 + 2                   2.63 + 3                         -              -
Ru-103 1.10 + 6 6.55 + 2 4.25 + 3 Rh-103m 1.10 + 6 6.55 + 2 4.25 - 3 Ru-106 4.10 + 5 2.44 + 2 1.58 + 3 12A-10 1
Sr-89   7.40 + 5               -
4 -
4.40 + 2                   2.36 + 3                         -              -
St-90   5.00 + 4               -
2.98 + 1                   1.93 + 2                       - -            -
Y-90   5.00 + 4               -
2.98 + 1                   1.93 + 2                       -              -
Sr-92   9.10 + 5               -
5.42 + 2                   3.51 + 3                         -              -
Y-92   1.00 + 6               -
5.95 + 2                   3.86 + 3                         -              -
Sr-93   1.10 + 6               -
6.55 + 2                 4.25 + 3                         -              -
Y-93   1.10 + 6               -
6.55 + 2                 4.25 + 3                         -              -
Mo-99   1.50 + 6               -
8.93 + 2                 5.79 + 3                         -              -
J Tc-99m 1.30 + 6               -
7.74 + 2                 5.02 + 3                         -              -                )
Ru-103 1.10 + 6               -
6.55 + 2                 4.25 + 3                         -              -
Rh-103m 1.10 + 6                 .
6.55 + 2                 4.25 - 3                     ' -                -
Ru-106 4.10 + 5               -
2.44 + 2                   1.58 + 3                       -              -
12A-10 1   4 -
l.
l.


I i
I i
TABII 12A.3-2 (Cont'd)
TABII 12A.3-2 (Cont'd)
Liquid (I) Gaseous (2) Containment       Reactor   Containment Source       Source       Sump           Coolant   Airborne     Waste Gas Activity     Activity Concentration Concentration Concentration Concentration Isotone     (Ci)       (CL)     (pCi/cc)       (pCi/cc)     (pCi/cc)     (pCi/cc)
Liquid (I) Gaseous (2)
                ~Rh-106   4.10 + 5           -
Containment Reactor Containment Source Source Sump Coolant Airborne Waste Gas Activity Activity Concentration Concentration Concentration Concentration Isotone (Ci)
2.44 + 2       1.58 + 3           -            -
(CL)
Te-132   1.10 + 6           -
(pCi/cc)
6.55 + 2       4.25 + 3           -            -
(pCi/cc)
I-132   5.90 + 7     2.95 + 7   3.51 + 4       2.28 + 5     5.66 + 2     5.24 + 4 Te-134   1.60 + 6           -
(pCi/cc)
9.52 + 2       6.18 + 3           -            -
(pCi/cc)
[ 'i     I-134   8.90 + 7     4.45 + 7   5.30 + 4       3.44 + 5     8.54 + 2     7.88 + 4 Xe-138   1.50 + 8     1.50 + 8   8.93 + 4       5.79 + 5     2.88 + 3     6.64 + 6 Cs-138   1.50 + 6           -
~Rh-106 4.10 + 5 2.44 + 2 1.58 + 3 Te-132 1.10 + 6 6.55 + 2 4.25 + 3 I-132 5.90 + 7 2.95 + 7 3.51 + 4 2.28 + 5 5.66 + 2 5.24 + 4 Te-134 1.60 + 6 9.52 + 2 6.18 + 3
8.93 + 2       5.79 + 3           -            -
[ 'i I-134 8.90 + 7 4.45 + 7 5.30 + 4 3.44 + 5 8.54 + 2 7.88 + 4 Xe-138 1.50 + 8 1.50 + 8 8.93 + 4 5.79 + 5 2.88 + 3 6.64 + 6 Cs-138 1.50 + 6 8.93 + 2 5.79 + 3 Ba-140 1.40 + 6 8.33 + 2 5.41 + 3 La-140 1.50 + 6 8.93 + 2 5.79 + 3 Ce-143 1.20 + 6 7.14 + 2 4.63 + 3 Pr-143. 1.20 + 6 7.14 + 2 4.63 + 3 Ce-144 9.20 + 5 5.48 + 2 3.55 + 3 Pr-144 1.20 + 6 7.14 + 2 4.63 + 3 Sr-91 9.20 + 5 5.48 + 2 3.55 + 3 y.91m Y-91 9.60 + 5 5.71 + 2 3.71 + 3 Zr-95 1.30 + 6 7.74 + 2 5.02 + 3 Nb-95m Nb-95 1.10 + 6 7.74 + 2 5.02 + 3 Zr-97 1.30 + 6 7.74 + 2 5.02 + 3 Nb-97m Nb-97 1.30 + 6 7.74 + 2 5.02 + 3 Ru-105 8.60 + 5 5.12 + 2 3.32 + 3 Rh-105m 8.60 + 5 5.12 + 2 3.32 + 3 Rh-105 5.50 + 5 3.27 + 2 2.12 + 3 Te-131 7.20 + 5 4.29 + 2 2.78 + 3 I-131 4.10 + 7 2.05 + 7 2.44 + 4 1.58 + 3 3.93 - 2 3.64 + 4 Xe-131m 6.51 + 5 6.51 + 5 3.88 + 2 2.51 + 5
Ba-140   1.40 + 6           -
: 1. 25 + 1 1.15 + 4 I-133 7.30 + 7 3.90 + 7 4.64 - 4 3.01 - 5 7.49 + 2 6.91 - 4 l
8.33 + 2       5.41 + 3           -            -
12A-11
La-140   1.50 + 6           -
'l
8.93 + 2       5.79 + 3           -            -
Ce-143   1.20 + 6           -
7.14 + 2       4.63 + 3           -            -
Pr-143. 1.20 + 6           -
7.14 + 2       4.63 + 3           -            -
Ce-144   9.20 + 5           -
5.48 + 2       3.55 + 3           -            -
Pr-144   1.20 + 6           -
7.14 + 2       4.63 + 3           -            -
Sr-91   9.20 + 5           -
5.48 + 2       3.55 + 3           -            -
y.91m           .-          ,          .              .            .            .
            -    Y-91     9.60 + 5           -
5.71 + 2       3.71 + 3           -            -
Zr-95   1.30 + 6           -
7.74 + 2       5.02 + 3           -            -
Nb-95m         -          -          -              -            -            -
  ,              Nb-95   1.10 + 6           -
7.74 + 2       5.02 + 3           -            -
Zr-97   1.30 + 6           -
7.74 + 2       5.02 + 3           -            -
Nb-97m         -          -          -              -            -            -
Nb-97   1.30 + 6           -
7.74 + 2       5.02 + 3           -            -
Ru-105   8.60 + 5           -
5.12 + 2       3.32 + 3           -            -
Rh-105m 8.60 + 5           -
5.12 + 2       3.32 + 3           -            -
Rh-105   5.50 + 5           -
3.27 + 2       2.12 + 3           -            -
Te-131   7.20 + 5           -
4.29 + 2       2.78 + 3           -            -
I-131   4.10 + 7     2.05 + 7   2.44 + 4       1.58 + 3     3.93 - 2     3.64 + 4 Xe-131m 6.51 + 5     6.51 + 5   3.88 + 2       2.51 + 5     1. 25 + 1     1.15 + 4 I-133   7.30 + 7     3.90 + 7                   3.01 - 5 4.64 - 4                    7.49 + 2     6.91 - 4
  ;                                                                                                      l 12A-11
'l                       '


e.e a- er s r-TABII 12A.3-2 (Cont'd)
e.e a-er s r-TABII 12A.3-2 (Cont'd)
Liquid ( } Gaseous f)   Containment       Reactor. Containment Source'     Source       Sump           Coolant   Airborne       Waste Gas Activity     Activity   Concentration Concentration Concentration Concentration Isotooe     (Ci)         (Ci)     (mci /ce)     (mci /ce)   (mci /ce)     (mci /ce)
Liquid ( }
  ,                    Xe-133m 3.80 + 6       3.80 + 6     2.26 + 3       1.47 + 4     7.29 + 1       7.24 + 4 Xe-133     1.50 + 8     1.50 + 8     8.93 + 4       5.79 + 5     2.88 + 3       2.72 + 6 I-135     6.90 + 7     3.45 + 7     4.11 + 4       2.66 + 5     6.62 + 2       6.09 + 4 Xe-135m 4.20 + 7       4.20 + 7     2.50 + 4       1.62 + 5     8.06 + 2       1.77 + 6 ,
f)
Xe-135   2.90 + 7     2.90 + 7     1.73 + 4       1.12 + 5     5.57 + 2       7.18 + .' , )
Gaseous Containment Reactor.
Ba-141     1.30 + 6         -
Containment Source' Source Sump Coolant Airborne Waste Gas Activity Activity Concentration Concentration Concentration Concentration Isotooe (Ci)
7.74 + 2       5.02 + 3           -              -
(Ci)
La-141     1.30 + 6         -
(mci /ce)
7.74 + 2       5.02 + 3           -              -
(mci /ce)
Ce-141     1.40 + 6         -
(mci /ce)
8.33 + 2       5.41 + 3           -              -
(mci /ce)
NOTES:
Xe-133m 3.80 + 6 3.80 + 6 2.26 + 3 1.47 + 4 7.29 + 1 7.24 + 4 Xe-133 1.50 + 8 1.50 + 8 8.93 + 4 5.79 + 5 2.88 + 3 2.72 + 6 I-135 6.90 + 7 3.45 + 7 4.11 + 4 2.66 + 5 6.62 + 2 6.09 + 4 Xe-135m 4.20 + 7 4.20 + 7 2.50 + 4 1.62 + 5 8.06 + 2 1.77 + 6,
7.18 +.', )
Xe-135 2.90 + 7 2.90 + 7 1.73 + 4 1.12 + 5 5.57 + 2 Ba-141 1.30 + 6 7.74 + 2 5.02 + 3 La-141 1.30 + 6 7.74 + 2 5.02 + 3 Ce-141 1.40 + 6 8.33 + 2 5.41 + 3 NOTES:
(1) Based on 100% noble gas core inventory, 50% halogen core inventory, and 1%
(1) Based on 100% noble gas core inventory, 50% halogen core inventory, and 1%
of all others core inventory.
of all others core inventory.
I (2) Based on 100% noble gas core inventory and 25% halogen core inventory.
I (2) Based on 100% noble gas core inventory and 25% halogen core inventory.
\                                                                                                                   3r I
\\
h 4
3rh I
  ,                                                                  12A-12 a -
4 12A-12 l
l
a -


12A.4     REVIEW OF AREAS REQUIRING ACCESS FOR POSTACCloENT OPERATIONS A vital area is defined as any area which will or may require occupancy to permit an operator to aid in the mitigation of or recover from an accid'ent. Vital areas for the Virgil C. Summer Nuclear Station are shown in Figures 12A.4-1 through 12A.4-7. Calculated exposure rates as a function of time after the accident are given in Table 12A.4-1. Vital area occupancy and access dose are summarized in Table 12A.4-2. Access routes to the vital areas are described in Table 12A.4-3.
12A.4 REVIEW OF AREAS REQUIRING ACCESS FOR POSTACCloENT OPERATIONS A vital area is defined as any area which will or may require occupancy to permit an operator to aid in the mitigation of or recover from an accid'ent. Vital areas for the Virgil C. Summer Nuclear Station are shown in Figures 12A.4-1 through 12A.4-7.
!      i 12A.4.1   AREA A: RHR/ SPRAY PUMP ROOMS AND COOLING UNITS i
Calculated exposure rates as a function of time after the accident are given in Table 12A.4-1.
            '~~ N     Area "A" as identified on Figure 12A.4-1 is the location of the residual heat removal (RHR) pumps, reactor building spray pumps and the common pump room           l23 cooling units. The reactor building spray pump is only required for short term cooling (2 hours). Failure of an RHR pump following an accident will result in a minimum safeguard condition and access to this area may be required to ensure that more than one pump is available for long term cooling of the reacter core.
Vital area occupancy and access dose are summarized in Table 12A.4-2.
Under these circumstances, plant personnel say require access to this area for operations such as pump seal replacement or minor maintenance. Tasks such as these require that three individuals spend approximately 4 hours in the pump
Access routes to the vital areas are described in Table 12A.4-3.
      !              rooms or at the cooling units.
i 12A.4.1 AREA A: RHR/ SPRAY PUMP ROOMS AND COOLING UNITS i
p3           Sources of exposure in this area are the RHR and spray system piping in the j       system train that is operating. This piping is located in the adjacent pump room and in the valve and piping area located above at elevation 397'0". Piping in the train requiring maintenance or repair is assumed to be flushed and drained.
'~~ N Area "A" as identified on Figure 12A.4-1 is the location of the residual heat removal (RHR) pumps, reactor building spray pumps and the common pump room l23 cooling units. The reactor building spray pump is only required for short term cooling (2 hours). Failure of an RHR pump following an accident will result in a minimum safeguard condition and access to this area may be required to ensure that more than one pump is available for long term cooling of the reacter core.
    ,                Access to this area is not required immediately since only long term operation need be considered. One day after the accident, the exposure rate is 230 mr/hr in the pump rooms and 576 mr/hr at the cooling units. The calculated dose to an individual for 4 hours of occupancy is 0.85 rem and 2.06 rem, respectively.
Under these circumstances, plant personnel say require access to this area for operations such as pump seal replacement or minor maintenance. Tasks such as these require that three individuals spend approximately 4 hours in the pump rooms or at the cooling units.
p3 Sources of exposure in this area are the RHR and spray system piping in the j
system train that is operating. This piping is located in the adjacent pump room and in the valve and piping area located above at elevation 397'0".
Piping in the train requiring maintenance or repair is assumed to be flushed and drained.
Access to this area is not required immediately since only long term operation need be considered. One day after the accident, the exposure rate is 230 mr/hr in the pump rooms and 576 mr/hr at the cooling units. The calculated dose to an individual for 4 hours of occupancy is 0.85 rem and 2.06 rem, respectively.
Table 12A.4-2 shows that 4 hours occupancy in this area is possible prior to one day following the accident.
Table 12A.4-2 shows that 4 hours occupancy in this area is possible prior to one day following the accident.
I                                                       12A-13 I.
I 12A-13 I.
  .i
. i


The access route to area "A"     is route "1" described in Table 12A.4-3. This access route will add a total of 0.02 rem to the worker dose if the task is started one day after the accident.
The access route to area "A" is route "1" described in Table 12A.4-3.
12A.4.2     AREA B: CHARGING /SI PUMP ROOMS Area "B"   is the location of the charging / safety injection (SI) pumps and is identified on Figure 12A.4-2. Failure of one of these pumps following an accident will result in a minimum safeguards condition and access to this area may be required to ensure that all pumps are av=ilable for long term cooling of the reactor core. Under these circumstances, plant personnel may require access to this area for operations such as pump seal replacement or minor maintenance.
This access route will add a total of 0.02 rem to the worker dose if the task is started one day after the accident.
12A.4.2 AREA B: CHARGING /SI PUMP ROOMS Area "B" is the location of the charging / safety injection (SI) pumps and is identified on Figure 12A.4-2.
Failure of one of these pumps following an accident will result in a minimum safeguards condition and access to this area may be required to ensure that all pumps are av=ilable for long term cooling of the reactor core. Under these circumstances, plant personnel may require access to this area for operations such as pump seal replacement or minor maintenance.
Tasks such as these require that three individuals spend approxima:ely 4 hours in '
Tasks such as these require that three individuals spend approxima:ely 4 hours in '
the pump rooms.
the pump rooms.
i Sources of exposure in this area are from the charging /SI pump piping for the pumps that are optional and are located in the adjacent pump rooms. Piping in the pump room where maintenance or repair is required is assumed to be flushed and drained. Access to this area is not required immediately since only long term operation need be considered. Two days after the accident, the exposure rate is 630 mr/hr. The calculated dose of o'cupancy c        is 2.39 rem. Table 12A.4-2 shows that 4 hours occupancy in this area is possible prior to two days following the accident.                                                                       y j                                                                                       \
i Sources of exposure in this area are from the charging /SI pump piping for the pumps that are optional and are located in the adjacent pump rooms. Piping in the pump room where maintenance or repair is required is assumed to be flushed and drained. Access to this area is not required immediately since only long term operation need be considered. Two days after the accident, the exposure rate is 630 mr/hr. The calculated dose of o'cupancy is 2.39 rem. Table 12A.4-2 c
The access routes to area "B" are routes "3' and "S" and are described in
shows that 4 hours occupancy in this area is possible prior to two days following the accident.
      ,    Table 12A.4-3. These access routes will add 0.13 rem and 0.05 rem to the dose if the task is started two days after the accident.
y j
12A.4.3     AREA C: CHARGING /SI PUMP C AUXILIARIES LOCAL CONTROL PANEL               f;3 Area "C" as identified on Figure 12A.4-2 is the location of charging / safety injection pump C auxiliaries local control panel. Failure of one of the               l23 i           charging /SI pumps will result in minimum safeguards condition and access to this area may be required for manual switching of the charging /SI pumps. This task would require that two workers spend approximately 2 minutes at the control panels.
\\
The access routes to area "B" are routes "3' and "S" and are described in Table 12A.4-3.
These access routes will add 0.13 rem and 0.05 rem to the dose if the task is started two days after the accident.
12A.4.3 AREA C: CHARGING /SI PUMP C AUXILIARIES LOCAL CONTROL PANEL f;3 Area "C" as identified on Figure 12A.4-2 is the location of charging / safety injection pump C auxiliaries local control panel. Failure of one of the l23 i
charging /SI pumps will result in minimum safeguards condition and access to this area may be required for manual switching of the charging /SI pumps. This task would require that two workers spend approximately 2 minutes at the control panels.
i 12A-14 i
i 12A-14 i


                  -            ~
~
The major source of exposure in this area is a 3 inch safety injection line located inside the shield labyrinth at the entrance to cubicles 88-23 and 88-24.
The major source of exposure in this area is a 3 inch safety injection line located inside the shield labyrinth at the entrance to cubicles 88-23 and 88-24.
A direct line of sight is possible from this source to the immediate vicinity of the pump C transfer switch. This line will not become a source of exposure until recirculation of containment sump liquid is initiated. Additional exposure in this area results from charging /SI piping in pump room 88-23.
A direct line of sight is possible from this source to the immediate vicinity of the pump C transfer switch. This line will not become a source of exposure until recirculation of containment sump liquid is initiated. Additional exposure in this area results from charging /SI piping in pump room 88-23.
Access to this area could be required immediately after the accident. Access at 30 minutes is assumed in order to evaluate the worst case of containment sump liquid in the 3 inch safety injection line at the start of recirculation.
Access to this area could be required immediately after the accident. Access at 30 minutes is assumed in order to evaluate the worst case of containment sump liquid in the 3 inch safety injection line at the start of recirculation.
i
Assuming that the workers are in a direct line of sight with the unshielded i
            . . -          Assuming that the workers are in a direct line of sight with the unshielded safety injection line, the exposure rate in the area is 87 .em/hr which results in an occupancy dose of 2.90 rem for the 2 minute time period.
safety injection line, the exposure rate in the area is 87.em/hr which results in an occupancy dose of 2.90 rem for the 2 minute time period.
      ,                  The access route to area "C"   is route "7" described in Table 12A.4-3. This
The access route to area "C" is route "7" described in Table 12A.4-3.
                          , access route will add a total of 1.39 rem to the worker dose if the task is started 30 minutes after the accident.
This
12A.4.4   AREA D: SPENT FUEL PIT HEAT EXCHANGER Area "D" is the location of the spent' fuel pit heat exchangers (see
, access route will add a total of 1.39 rem to the worker dose if the task is started 30 minutes after the accident.
                                                                                                            ~
12A.4.4 AREA D: SPENT FUEL PIT HEAT EXCHANGER Area "D" is the location of the spent' fuel pit heat exchangers (see
Figure 12A.4-2). Access to this area is not required to aid in the mitigation of
~
              )           or recovery from an accident, but should conditions dictate, access may be needed l                       to service the heat exchanger to maintain cooling of the spent fuel. Under these l 23 circumstances, post-accident operations in this area require only long-term periodic surveillance.
Figure 12A.4-2).
Access to this area is not required to aid in the mitigation of
)
or recovery from an accident, but should conditions dictate, access may be needed l
to service the heat exchanger to maintain cooling of the spent fuel. Under these l 23 circumstances, post-accident operations in this area require only long-term periodic surveillance.
The exposure rate in this area following an accident is negligible since there are no post-accident sources of activity in the vicinity of the heat exchangers.
The exposure rate in this area following an accident is negligible since there are no post-accident sources of activity in the vicinity of the heat exchangers.
This permits unlimited access (40 hours / week) in this area.
This permits unlimited access (40 hours / week) in this area.
The access route to area "D" La route "9" described in Table 12A.4-3.     This       ;
The access route to area "D" La route "9" described in Table 12A.4-3.
access route will add a total of 0.02 rem to the worker dose if the task is started one day after the accident.
This access route will add a total of 0.02 rem to the worker dose if the task is started one day after the accident.
12A-15 1
12A-15 1


12A.4.5     AREA E: RADVASTE GAS HANDLI.4G CONTROL PANELS Area,"E" as identified in Figure 12A.4-2 is the location of the radwaste gas     .
12A.4.5 AREA E: RADVASTE GAS HANDLI.4G CONTROL PANELS Area,"E" as identified in Figure 12A.4-2 is the location of the radwaste gas tecombiner analyzer and control panels. Access to this area is not required following an accident since it is not planned to start-up the radwaste gas 23 handling system. If degassing of the primary coolant system becomes necessary following an accident, the operation will be accomplished by utilizing the reactor head vent system.
tecombiner analyzer and control panels. Access to this area is not required following an accident since it is not planned to start-up the radwaste gas           23 handling system. If degassing of the primary coolant system becomes necessary following an accident, the operation will be accomplished by utilizing the reactor head vent system.
12A.4.6 AREA F: SPENT FUEL PIT CCOLING PL?!PS AND LOCAL CONTROL PAhTLS Area "F" as identified on Figure 12A.4-3 is the location of the spent fuel pit cooling pumps and local control panels. Access to this area is not required to aid in the mitigation of or recovery from an accident, but should conditions 3
12A.4.6     AREA F: SPENT FUEL PIT CCOLING PL?!PS AND LOCAL CONTROL PAhTLS Area "F" as identified on Figure 12A.4-3 is the location of the spent fuel pit cooling pumps and local control panels. Access to this area is not required to 3            aid in the mitigation of or recovery from an accident, but should conditions dictate, access to this area may be needed in order to maintain cooling of the         ,
dictate, access to this area may be needed in order to maintain cooling of the spent fuel. Under these circumstances, plant personnel may require access to this area for operations such as pump seal replacement or minor maintenance.
spent fuel. Under these circumstances, plant personnel may require access to this area for operations such as pump seal replacement or minor maintenance.
Tasks such as these require that three individuals speed approximately 4 hours at the pumps.
Tasks such as these require that three individuals speed approximately 4 hours at the pumps.
Dose contributors in this' area are the containment building and a 3 inch safety injection line located approximately 20 feet away above the shield slab at elev.
Dose contributors in this' area are the containment building and a 3 inch safety injection line located approximately 20 feet away above the shield slab at elev.
426'6". The time at which access to this area is required ia based on the j         minimum time it takes to reach maximum spent fuel pool temperature with loss of
426'6".
,            both cooling pumps. This time is 12.5 hours. Eight hours after the accident, l           the exposure rate is 1.16 rem /hr. The calculated dose to an individual for 4 1
The time at which access to this area is required ia based on the j
minimum time it takes to reach maximum spent fuel pool temperature with loss of both cooling pumps. This time is 12.5 hours. Eight hours after the accident, l
the exposure rate is 1.16 rem /hr. The calculated dose to an individual for 4 1
hours of occupancy is 3.03 rem.
hours of occupancy is 3.03 rem.
The access route to area "F"   is route "6" described in Table 11A.4-3. This access route will add a total of 0.11 rem to the worker dose if the task is started 8 hours after the accident.
The access route to area "F"
f                                               12A-16 I
is route "6" described in Table 11A.4-3.
This access route will add a total of 0.11 rem to the worker dose if the task is started 8 hours after the accident.
f 12A-16 I
i
i
-w
--- m a


1 12A.4.7     AREA G: ENGINEERED SAFETY FEATURE MOTOR CONTROL CE.YTER Area "G" is the location of the Engineered Safety Feature (EST) Motor Control Center IDA2Y and is identified on Figure 12A.4-3.       It is not expected that access to this area would be required since all ESF control functions are performed from the control room. However, access may be required in the unlikely event that a safety-related component loses remote control power. Should such a component
1 12A.4.7 AREA G: ENGINEERED SAFETY FEATURE MOTOR CONTROL CE.YTER Area "G" is the location of the Engineered Safety Feature (EST) Motor Control Center IDA2Y and is identified on Figure 12A.4-3.
    ,                lose remote centrol power and fail in the unsafe position, in conjunction with a simultaneous failure of its redundant counterpart, it may ee deemed necessary to gain access to this area for manual control of the component. This task would require that two workers spend approximately 2 to 5 minutes in this area.
It is not expected that access to this area would be required since all ESF control functions are performed from the control room. However, access may be required in the unlikely event that a safety-related component loses remote control power. Should such a component lose remote centrol power and fail in the unsafe position, in conjunction with a simultaneous failure of its redundant counterpart, it may ee deemed necessary to gain access to this area for manual control of the component. This task would require that two workers spend approximately 2 to 5 minutes in this area.
Dose contributors to this rea are spray system, safety injection system and chemical and volume contrr,1 system piping located below and adjacent to this area. Access to this area could be required immediately after the accident.
Dose contributors to this rea are spray system, safety injection system and chemical and volume contrr,1 system piping located below and adjacent to this Access to this area could be required immediately after the accident.
Access at 30 minutes is assumed in order to evaluate the worst case which is the initiation of the recirculation of containment sump liquid in the spray and safety injection systems. The exposure rate in this area is 23 rem /hr resulting in calculated exposures to an individual of 0.77 rem and 1.92 rem for occupancy         l23
area.
    ,                times of 2 minutes and 5 minutes, respectively.
Access at 30 minutes is assumed in order to evaluate the worst case which is the initiation of the recirculation of containment sump liquid in the spray and safety injection systems. The exposure rate in this area is 23 rem /hr resulting in calculated exposures to an individual of 0.77 rem and 1.92 rem for occupancy l23 times of 2 minutes and 5 minutes, respectively.
The access route to area "G"     is route "4" described in Table 12A.4-3. This access route will add a total of 0.26 rem to the worker dose if access is I y'             required 30 minutes after the accident.
The access route to area "G" is route "4" described in Table 12A.4-3.
  ,                12A.4.8     AREA H: WASTE PROCESSING SYSTEM CONTROL PANEL Area "H"   is the location of the waste processing system panel (see Figure 12A 4-3). The waste gas system is not intended r           used for degassing the primary coolant system in post-accident conditions.         ess to this area may be needed since the waste gas compressor are controlled from this panel. This task will required two persons to occupy this area for one minute.
This access route will add a total of 0.26 rem to the worker dose if access is I y' required 30 minutes after the accident.
12A.4.8 AREA H: WASTE PROCESSING SYSTEM CONTROL PANEL Area "H" is the location of the waste processing system panel (see Figure 12A 4-3).
The waste gas system is not intended r used for degassing the primary coolant system in post-accident conditions.
ess to this area may be needed since the waste gas compressor are controlled from this panel. This task will required two persons to occupy this area for one minute.
12A-17 i-
12A-17 i-


Sources of exposure in this area are the contain=ent building, and a 2 inch CVCS line located approximately 10 feet away and above the 2 foot thick concrete
Sources of exposure in this area are the contain=ent building, and a 2 inch CVCS line located approximately 10 feet away and above the 2 foot thick concrete shield slab at elevation 426'0".
      .          shield slab at elevation 426'0". Immediately after the accident, the dose rate from these sources in areas "H" is 3.74 rem /hr. The calculated dose for the one minute occupancy time is 0.06 rem.
Immediately after the accident, the dose rate from these sources in areas "H" is 3.74 rem /hr. The calculated dose for the one minute occupancy time is 0.06 rem.
The access route to area "H" is route "5" described in Table 12A.4-3. This route will add a total of 0.98 rem to the worker dose in this area for access
The access route to area "H" is route "5" described in Table 12A.4-3.
  }'             immediately after the accident.
This route will add a total of 0.98 rem to the worker dose in this area for access
12A.4.9     AREA I: CHARGING / SAFETY INJECTION PUMP CC0 LING UNITS Area "I"   is the location of the charging / safety injection pump rocm cooling units -
}'
and is identified on Figure 12A.4-4. Failure of one of these cooling units following an accident will result in a minimum safeguards condition and access to the area may be required to ensure that more th'n   a one of the charging / safety injection pumps are available for the long. term cooling of the reactor core.
immediately after the accident.
Under these circumstances, plant personnel cay require accers to cne of the aress, for operations such as manual switchover, maintenance, or repair. Tasks such as these require that two persons spend five minutes at the cooling units for manual         ,
12A.4.9 AREA I: CHARGING / SAFETY INJECTION PUMP CC0 LING UNITS Area "I" is the location of the charging / safety injection pump rocm cooling units -
switchover, or three persons spend four hours for the maintenance or repair of a cooling unit.
and is identified on Figure 12A.4-4.
4 The major sources of exposure in this area are the charging / safety injection pump I'                                                                                                          )@3 cubicle piping, the piping area immediately west of the cooling units on                 ''
Failure of one of these cooling units following an accident will result in a minimum safeguards condition and access to the area may be required to ensure that more th'n one of the charging / safety a
elevation 400'-0", and a 3-inch chemical and volume control system (CVCS) pipe located inside the room containing cooling units 1 and 2. Access to this area could be required immediately af ter the accident for manual realignment of valves for the cooling units. Access at the time of accident occurrence (i.e.g, 0 hr.)
injection pumps are available for the long. term cooling of the reactor core.
Under these circumstances, plant personnel cay require accers to cne of the aress, for operations such as manual switchover, maintenance, or repair. Tasks such as these require that two persons spend five minutes at the cooling units for manual switchover, or three persons spend four hours for the maintenance or repair of a cooling unit.
The major sources of exposure in this area are the charging / safety injection pump
)@3 4
I' cubicle piping, the piping area immediately west of the cooling units on elevation 400'-0", and a 3-inch chemical and volume control system (CVCS) pipe located inside the room containing cooling units 1 and 2.
Access to this area could be required immediately af ter the accident for manual realignment of valves for the cooling units. Access at the time of accident occurrence (i.e.g, 0 hr.)
is assumed to evaluate the worst case of worker exposure.
is assumed to evaluate the worst case of worker exposure.
Prior to the installati     m of the shielding additions, the exposure rates in this area varied for t' ' individual cooling units between 426 and 6260 rem /hr, which results in 5 minute occupancy doses of 33.5 to 522.7 rem, immediately after the accident. For the maintenance and repair activities after the accident, the~
Prior to the installati of the shielding additions, the exposure rates in this m
    !                                                    12A-13 I"
area varied for t' ' individual cooling units between 426 and 6260 rem /hr, which results in 5 minute occupancy doses of 33.5 to 522.7 rem, immediately after the accident. For the maintenance and repair activities after the accident, the~
12A-13 I"
6
6
;I                                                                                                   .
;I


      -      ..  . ~ .
. ~.
3... _._.
3...
exposure rates in the area vill vary between 20.3 and 284 rem /hr one day af ter the accident, and 5.86 to 84.0 rem /br five days af ter the accident. These dose rates will result in maintenance and repair occupancy doses of between 76.4 and 1070 rem one day after the accident, and between 23.2 and 333 rem five days after the accident.
exposure rates in the area vill vary between 20.3 and 284 rem /hr one day af ter the accident, and 5.86 to 84.0 rem /br five days af ter the accident. These dose rates will result in maintenance and repair occupancy doses of between 76.4 and 1070 rem one day after the accident, and between 23.2 and 333 rem five days after the accident.
The access rout eto Area "I" is route "10" described in Table 12A.4-3. For the manual valve switchover procedure, the access route will add a total of 1.02 rem to the worker dose at the time of the accident (i.e. , O hr. ) . For the m'intenance and repair activities after the accident, the access route will contribute 0.02 rem one dry after the accident to the worker dose, and becomes       23 I                 negligible five days after the accident.
The access rout eto Area "I" is route "10" described in Table 12A.4-3.
The resultant dose levels in this area have been reduced to acceptable values by the addition of concrete and lead shielding around the charging / safety injection .
For the manual valve switchover procedure, the access route will add a total of 1.02 rem to the worker dose at the time of the accident (i.e., O hr. ). For the m'intenance and repair activities after the accident, the access route will contribute 0.02 rem one dry after the accident to the worker dose, and becomes 23 I
and CVCS piping located within the charging / safety injection pump cooling unit cubicle. The new configuration allows personnel access in accordance with the occupancy requirements of Table 12A.4-2 and the occupancy ' guidelines for vital access areas requiring infrequent occupancy as contained in YUREG-0737.             ,]
negligible five days after the accident.
12A.4.10 AREA J: ENGITLEEED SAFETY FEATURE SUBSTATlaN ' BUS AND MOTOR CONTE 0L CEFIER f<                 Ares "J"     is the location ci the engineered safety feature 480 volt unit l \/
The resultant dose levels in this area have been reduced to acceptable values by the addition of concrete and lead shielding around the charging / safety injection and CVCS piping located within the charging / safety injection pump cooling unit cubicle. The new configuration allows personnel access in accordance with the occupancy requirements of Table 12A.4-2 and the occupancy ' guidelines for vital access areas requiring infrequent occupancy as contained in YUREG-0737.
substation bus IDB1 tud motce control center 10Y2Y (see Figure 12A.4-6).
,]
12A.4.10 AREA J: ENGITLEEED SAFETY FEATURE SUBSTATlaN ' BUS AND MOTOR CONTE 0L CEFIER f<
l \\/
Ares "J" is the location ci the engineered safety feature 480 volt unit substation bus IDB1 tud motce control center 10Y2Y (see Figure 12A.4-6).
Occupancy in this area following an accident will be the same as explained for area "G".
Occupancy in this area following an accident will be the same as explained for area "G".
Dose contributors to tais area are the volume control tank (cubicle 63-02), and       '
Dose contributors to tais area are the volume control tank (cubicle 63-02), and
                                                                                                                .3
'.3 the valve gallery located in cubicle 63-03.
!                        the valve gallery located in cubicle 63-03.
Access to this area could be required immediately after the accident. With the assumption that :ero hour entry occurs, the exposure rate in this area will result in calculated exposures of 3.33 and 8.33 rem to an individual for the j
Access to this area could be required immediately after the accident. With the assumption that :ero hour entry occurs, the exposure rate in this area will result in calculated exposures of 3.33 and 8.33 rem to an individual for the j                         occupancy periods of 2 and 5 minutes, respectively. However, the resultant dose i
occupancy periods of 2 and 5 minutes, respectively. However, the resultant dose i
levels in'this area are reduced to acceptable levels quickly as shown in l
levels in'this area are reduced to acceptable levels quickly as shown in l
i
i
;  .i
.i 12A-19
;  '                                                            12A-19
(
(   5 l'
5 l'


        ^
^
Table 12A.4-2, and the resultant integrated doses meet the dose requirements of 10CFR50, Appendix A, General Design Criteria 19 as outlined in NUREG-0737.
Table 12A.4-2, and the resultant integrated doses meet the dose requirements of 10CFR50, Appendix A, General Design Criteria 19 as outlined in NUREG-0737.
23 The access route to area   "J" is route "14" described in Table 12A.4-3. This access route will add a total of 2.16 rem to the worker dose immediately after the accident.
23 The access route to area "J" is route "14" described in Table 12A.4-3.
12A.4.11 AREA K: HYDROGEN RECOMBI.M CONTROL AND POWER SUPPLY PANELS Area "K" as identified on Figure 12A.4-6 is the general location of the hydrogen recombiner control and power supply panels. Post-accident hydrogen formation in the reactor building may require operation of the hydrogen recombiner system.
This access route will add a total of 2.16 rem to the worker dose immediately after the accident.
12A.4.11 AREA K: HYDROGEN RECOMBI.M CONTROL AND POWER SUPPLY PANELS Area "K" as identified on Figure 12A.4-6 is the general location of the hydrogen recombiner control and power supply panels. Post-accident hydrogen formation in the reactor building may require operation of the hydrogen recombiner system.
The system is started and controlled by operator action at the recombiner control ~
The system is started and controlled by operator action at the recombiner control ~
panel. This task requires that two workers spend 10 minutes in this area per hour over a 3 hour period.
panel. This task requires that two workers spend 10 minutes in this area per hour over a 3 hour period.
Dose contributors in this area are the personnel access hatch and a 3 inch chemical and volume control system pipe located below at elevation 450'6".
Dose contributors in this area are the personnel access hatch and a 3 inch chemical and volume control system pipe located below at elevation 450'6".
Access to the control panels could be required shortly after an accident. The exposure rate at one hour after the accident in this area is 21.1 rem /hr. The calculated dos ~e to an individual in this area for 10 minutes of occupancy is 3.!2 rem. If occupancy is required at one day after the accident, the exposure rate is calculated to be 1.12 rem /hr which results in a 10 minute dose of l       0.19 rem.                                                                         s The access route to area "K" is route "13" described in Table 12A.4-3. The calculated dose to an individual travelling this route is 3.23 rem I hour after the accident and 0.28 rem 1 day after the accident.
Access to the control panels could be required shortly after an accident. The exposure rate at one hour after the accident in this area is 21.1 rem /hr. The calculated dos ~e to an individual in this area for 10 minutes of occupancy is 3.!2 rem.
I 12A.4.12 AREA L: HYDROGEN RECCMBINER CONTROL AND POWER SUPPLY PANELS Area "L", as identified on Figure 12A.4-6, is the general location of the hdyrogen recombiner control and power supply panels. Occupancy in this ares following an accident will be the same as explained for area "K".
If occupancy is required at one day after the accident, the exposure rate is calculated to be 1.12 rem /hr which results in a 10 minute dose of l
t
0.19 rem.
    .                                                12A-20 I
s The access route to area "K" is route "13" described in Table 12A.4-3.
The calculated dose to an individual travelling this route is 3.23 rem I hour after the accident and 0.28 rem 1 day after the accident.
I 12A.4.12 AREA L: HYDROGEN RECCMBINER CONTROL AND POWER SUPPLY PANELS Area "L", as identified on Figure 12A.4-6, is the general location of the hdyrogen recombiner control and power supply panels. Occupancy in this ares following an accident will be the same as explained for area "K".
t 12A-20 I


Dose contributors in this area are the reactor building located approximately 40 feet away and a 10 inch spray line located below the 2 f t. concrete floor at elevation 436'-0" Access to the control panels could be required shortly after an accident. The exposure rate at one hour after the accident in this area is 1.5 rem /hr. The calculated dose to an individual in this area for 10 minutes of occupancy is 0.25 rem. If occupancy is required at one day after the accident, the exposure rate is calculated to be 16.0 mrem'/hr which results in a 10 minutes j                       dose of 0.003 rem.
Dose contributors in this area are the reactor building located approximately 40 feet away and a 10 inch spray line located below the 2 f t.
The access route to area "L" is route "11" described in Table 12A.4-3. This     l 23
concrete floor at elevation 436'-0" Access to the control panels could be required shortly after an accident. The exposure rate at one hour after the accident in this area is 1.5 rem /hr. The calculated dose to an individual in this area for 10 minutes of occupancy is 0.25 rem.
              ,~           access route wil add a total of 0.76 rem to the worker dese 1 hour af ter the accident and 0.02 rem 1 day after the accident.
If occupancy is required at one day after the accident, the exposure rate is calculated to be 16.0 mrem'/hr which results in a 10 minutes j
12A.4.13 AREA M: REACTOR BUILDING ATMOSPHERE SAMPLE COLLECTION POINT AND           l 23 J .R In~DROGEN GAS ANALY''
dose of 0.003 rem.
Area "M" as identified in Figure 12A.4-6 is the location where a reactor building l 23 air sample will be collected following an accident. It is also the location of the reactor building atmosphere hydrogen analy:er. The hydrogen analyzers are designed to continuously monitor the reactor building atmosphere following an accideat. Access to the analyzer is not required since they are redundant (the other analyzer is located at elevation 4'63'-0" of the Auxiliary Building between -
The access route to area "L" is route "11" described in Table 12A.4-3.
column lines L, M, 7.7 and the reactor building) and all necessary functions are l C' ' ,,,              controlled remotely from the Control Room. However, access to this area is required to collect a reactor building air sample. The time required to collect the air sample has been estimated to be 10 minutes.
This l 23
Dose contributors to this area are the reactor building located approximately 10 ft. away, 3/8" gas sample lines for the sample cylinder and the hydrogen analyzer, and the gas sample cylinder itself. Access to this area could be required shortly after the accident. Access at 30 minutes is assumed. The exposure rate-in this area 30 minutes after the accident is 12.9 rea/hr. This results in a calculated dose of 2.15 rem for 10 minutes of occupancy.                 23 i
,~
access route wil add a total of 0.76 rem to the worker dese 1 hour af ter the accident and 0.02 rem 1 day after the accident.
12A.4.13 AREA M: REACTOR BUILDING ATMOSPHERE SAMPLE COLLECTION POINT AND l 23 In~DROGEN GAS ANALY''.R J
Area "M" as identified in Figure 12A.4-6 is the location where a reactor building l 23 air sample will be collected following an accident. It is also the location of the reactor building atmosphere hydrogen analy:er. The hydrogen analyzers are designed to continuously monitor the reactor building atmosphere following an accideat. Access to the analyzer is not required since they are redundant (the other analyzer is located at elevation 4'63'-0" of the Auxiliary Building between -
column lines L, M, 7.7 and the reactor building) and all necessary functions are l C' '
controlled remotely from the Control Room. However, access to this area is required to collect a reactor building air sample. The time required to collect the air sample has been estimated to be 10 minutes.
Dose contributors to this area are the reactor building located approximately 10 ft. away, 3/8" gas sample lines for the sample cylinder and the hydrogen analyzer, and the gas sample cylinder itself. Access to this area could be required shortly after the accident. Access at 30 minutes is assumed. The exposure rate-in this area 30 minutes after the accident is 12.9 rea/hr. This results in a calculated dose of 2.15 rem for 10 minutes of occupancy.
23 i
12A-21 I
12A-21 I


The access route to area "M"   is route "12" described in Table 12A.4-3. This access rour.e will add a total of 1.14 rem to the worker dose for access to and from this area 30 minutes after the accident.
The access route to area "M" is route "12" described in Table 12A.4-3.
12A.4.14 AREA N: TECHNICAL SUPPORT CENTER Area "N" as identified in Figure 12A.4-7 is the location of the technical support j         center. The cechnical support center is located adjacent to the control room on elevation 463'-0" of the control building. Continuous occupancy is required in this area following an accident. A major direct dose contributor to this aea is the reactor building. The direct radiation from the reactor building will result ..
This access rour.e will add a total of 1.14 rem to the worker dose for access to and from this area 30 minutes after the accident.
12A.4.14 AREA N: TECHNICAL SUPPORT CENTER Area "N" as identified in Figure 12A.4-7 is the location of the technical support j
center. The cechnical support center is located adjacent to the control room on elevation 463'-0" of the control building. Continuous occupancy is required in this area following an accident. A major direct dose contributor to this aea is the reactor building. The direct radiation from the reactor building will result..
in exposure rates in the c ntrol room of approximately 2.7 mrem /hr immediately after the accident, quickly droppina off to 0.6 mrem /hr 1 hour after the accident and to near background levels shortly thereafter.
in exposure rates in the c ntrol room of approximately 2.7 mrem /hr immediately after the accident, quickly droppina off to 0.6 mrem /hr 1 hour after the accident and to near background levels shortly thereafter.
A complete analysis of post-accident radiation' doses in the control room and     ,
A complete analysis of post-accident radiation' doses in the control room and technical support center is presented in Section 15.4.1.
technical support center is presented in Section 15.4.1. Dese contributors include (1) direct radiation from the reactor building, (2) direct radiation from the radioactive cloud outside the control room which results from reactor building leakage, and (3) exposure to radioactive materials which may leak into the technical support center. The post-accident integrated doses (30 days) to         ,
Dese contributors include (1) direct radiation from the reactor building, (2) direct radiation from the radioactive cloud outside the control room which results from reactor building leakage, and (3) exposure to radioactive materials which may leak into the technical support center. The post-accident integrated doses (30 days) to persons in the technical support center area 26.6 rem inhalation dose to the thyroid, 4.87 rem whole body gama dose, and 21.6 rem beta skin dose. The
persons in the technical support center area 26.6 rem inhalation dose to the
-23 l
      -    thyroid, 4.87 rem whole body gama dose, and 21.6 rem beta skin dose. The                 -23 l           majority of this dcse comes within the first few days of the accident.
majority of this dcse comes within the first few days of the accident.
12A.4.15 AREA 0: CONTROL ROCM Area "0" as identified in ligure 12A.4-7 is the location of the control room.
12A.4.15 AREA 0: CONTROL ROCM Area "0" as identified in ligure 12A.4-7 is the location of the control room.
Continuous occupancy is required in this area following an accident. A major direct dose contributor to this trea is the reactor building. The direct radiation from the reactor building will result in exposure rates in the control room of approximately 2.7 mrem /hr immediately after the accident, quickly ueopping off to 0.6 mrem /hr 1 hour af ter the accident and to near background levels shortly thereafter.
Continuous occupancy is required in this area following an accident. A major direct dose contributor to this trea is the reactor building. The direct radiation from the reactor building will result in exposure rates in the control room of approximately 2.7 mrem /hr immediately after the accident, quickly ueopping off to 0.6 mrem /hr 1 hour af ter the accident and to near background levels shortly thereafter.
Line 430: Line 447:
h
h


A complete analysis of post-accident radiation doses in the control room is presented in Section 15.4.1.         Dose contributors include (1) direct radiation from
A complete analysis of post-accident radiation doses in the control room is presented in Section 15.4.1.
                        -the reactor building, (2) direct radiation from the radioactive cloud outside the control room which results from reactor building leakage, and (3) exposure to radioactive materials which may leak into the control room. The post-accident integrated doses (30 days) to operators in the control room are 26.6 res 23 inhalation dose to the thyroid, 4.87 rem whole body gamma dose, and 21.6 rem beta skin dose. The majority of this dose comes within the first few days of the accident.
Dose contributors include (1) direct radiation from
            ..            12A.4.16 AREA P: SAMPII ROOM                                                                     '
-the reactor building, (2) direct radiation from the radioactive cloud outside the control room which results from reactor building leakage, and (3) exposure to radioactive materials which may leak into the control room. The post-accident integrated doses (30 days) to operators in the control room are 26.6 res 23 inhalation dose to the thyroid, 4.87 rem whole body gamma dose, and 21.6 rem beta skin dose. The majority of this dose comes within the first few days of the accident.
Area "P"     as identified in Figure 12A.4-7 is the location of the sample room.
12A.4.16 AREA P: SAMPII ROOM Area "P" as identified in Figure 12A.4-7 is the location of the sample room.
Access to this area is required to ubtain the primary system liquid and gas               '
Access to this area is required to ubtain the primary system liquid and gas samples following an accident for assessing the extent of fuel damage and to evaluate the primary coolant chemistry. The samples shall consist of fluids
samples following an accident for assessing the extent of fuel damage and to evaluate the primary coolant chemistry. The samples shall consist of fluids             ~
~
taken from the primary coolant hot leg, the pressurizer liquid and steam spaces, and residual heat removal loop. These samples are collected by a pre-defined-               .
taken from the primary coolant hot leg, the pressurizer liquid and steam spaces, and residual heat removal loop. These samples are collected by a pre-defined-procedure in sample vessels at a sink located in the sample room.
procedure in sample vessels at a sink located in the sample room.
23 The post-accident sampling system shall provide a means for the collection of post-accident samples in the sample room and will be designed to maintain the
                                      .                                                                                  23 The post-accident sampling system shall provide a means for the collection of post-accident samples in the sample room and will be designed to maintain the
[# -
[# -
_ resultant dose levels in the area at acceptable values. This will be achieved by IIs/               a combination of radiation shielding and sample collection procedures.
_ resultant dose levels in the area at acceptable values. This will be achieved by IIs/
The radiation shielding design and personnel exposure estimates shall.be provided
a combination of radiation shielding and sample collection procedures.
,                        at a later date upon completion of their design review.
The radiation shielding design and personnel exposure estimates shall.be provided at a later date upon completion of their design review.
The access route to area "P" is route "15" described in Table 12A.4-3.
The access route to area "P" is route "15" described in Table 12A.4-3.
12A.4.17 AREA Q: RADI0 CHEMISTRY I.AB l                       Area "Q" as identified in Figure 12A.4-7 is th,e location of the radiochemistry la bo ra to ry. Access to this area is required for the radiological and chemical             23 analyses of the post-accident samples following their transfer to this location.
12A.4.17 AREA Q: RADI0 CHEMISTRY I.AB l
i                                                                                                                           l l
Area "Q" as identified in Figure 12A.4-7 is th,e location of the radiochemistry 23 la bo ra to ry.
    ?
Access to this area is required for the radiological and chemical analyses of the post-accident samples following their transfer to this location.
j
i l
    !                                                              12A-23                                                   l 6                                                                                                                       j i
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?
j 12A-23 6
j i


I Since the existing radiation shield design and sample analysis procedures in this area were designed for 1% failed fuel sources, the post-accident sampling system has been designed to reduce the activity concentration of the samples to a level that will result in dose rates within the range of values normally associated with the 1% failed fuel design criteria. The post-accident sampling system will therefore allow personnel access in the radiochemistry laboratory in concurrence with the occupancy requirements of Tables 12A.4-2 and 12A.4-4, and the resultant integrated doses shall meet the dose requirements outlined in NUREG-0737.
Since the existing radiation shield design and sample analysis procedures in this area were designed for 1% failed fuel sources, the post-accident sampling system has been designed to reduce the activity concentration of the samples to a level that will result in dose rates within the range of values normally associated with the 1% failed fuel design criteria. The post-accident sampling system will therefore allow personnel access in the radiochemistry laboratory in concurrence with the occupancy requirements of Tables 12A.4-2 and 12A.4-4, and the resultant integrated doses shall meet the dose requirements outlined in NUREG-0737.
The access route to area "Q" is route "15" as described in Table 12A.4-3.
The access route to area "Q" is route "15" as described in Table 12A.4-3.
12A.4.18 AREA R: COUNT ROOM Area "R" as identified in Figure 12A.4-7 is the location of the count room.
12A.4.18 AREA R: COUNT ROOM Area "R" as identified in Figure 12A.4-7 is the location of the count room.
Access to this area is required for the radiologic'al analysis of the post-accident samples prepared in the radiochemistry laboratory.
Access to this area is required for the radiologic'al analysis of the post-accident samples prepared in the radiochemistry laboratory.
The post-accident sampling system design criteria to provide post-accident sources with a radioisotope activity level comparable to that of the 1% failed
The post-accident sampling system design criteria to provide post-accident sources with a radioisotope activity level comparable to that of the 1% failed fuel design criteria results in insignificant increases in personnel exposure above those received under normal operating conditions. The need for additional 23 shielding has been reduced to making provisions for the availabiIity of temporary shielding to be used for local hot spots, when and if such are found by l
        . fuel design criteria results in insignificant increases in personnel exposure above those received under normal operating conditions. The need for additional         23 shielding has been reduced to making provisions for the availabiIity of temporary shielding to be used for local hot spots, when and if such are found by l         personnel. Therefore, the personnel access in the count room shall be in           s accordance with the occupancy requirements of Tables 12A.4-2 and 12A.4-4, and the resultant integrated doses shall meet the dose requirements outlined in NUREG-0737.
personnel. Therefore, the personnel access in the count room shall be in s
The access route to area "R"   is route "15" as described in Table 12A.4-3.
accordance with the occupancy requirements of Tables 12A.4-2 and 12A.4-4, and the resultant integrated doses shall meet the dose requirements outlined in NUREG-0737.
12A.4.19 INTERMEDIATE BUII. DING The intermediate building was reviewed to identify post-accident radiation sources, access requirements, and the location of safety related equipment. It     23 was found that the only area of the intermediate building where exposure to 12A-24 I
The access route to area "R" is route "15" as described in Table 12A.4-3.
12A.4.19 INTERMEDIATE BUII. DING The intermediate building was reviewed to identify post-accident radiation sources, access requirements, and the location of safety related equipment.
It 23 was found that the only area of the intermediate building where exposure to 12A-24 I


            , an sr.         ,xms .
, an sr.
n                                           .
,xms.
post-accident radiation sources is possible is at the 412'-0" elevation adjacent
n post-accident radiation sources is possible is at the 412'-0" elevation adjacent to the east and west penetration access areas. At this elevation, residual heat removal (RHR), safety injection (SI), and chemical and volume control system
            ,                        to the east and west penetration access areas. At this elevation, residual heat removal (RHR), safety injection (SI), and chemical and volume control system
_(CVCS) piping containing post-accident sources is located in the east and west j
:                      _(CVCS) piping containing post-accident sources is located in the east and west j                         penetration access areas. The areas adjacent to the penetration access areas               -
penetration access areas. The areas adjacent to the penetration access areas contains component cooling pumps, motor driven emergency feedwater pumps, and 1
1 contains component cooling pumps, motor driven emergency feedwater pumps, and c
miscellaneous safety related valves and instrumentation which may require access.
miscellaneous safety related valves and instrumentation which may require access.
All other areas of the intermediate building are not exposed to -post-accident sources and receive a negligible increase in dose.
c All other areas of the intermediate building are not exposed to -post-accident sources and receive a negligible increase in dose.
I-1 3 ,.~.                    The intermediate building at elevation 412'-0" is shielded from the radioactive piping located in the penetration access areas by a 2 foot concrete wall. This
I-1 The intermediate building at elevation 412'-0" is shielded from the radioactive 3,.~.
        ,                          shield wall reduces the dose rates in this general area of the intermediate
piping located in the penetration access areas by a 2 foot concrete wall. This shield wall reduces the dose rates in this general area of the intermediate building to a level which permits limited access approximately 15 minutes immediately af ter the accident, 3 hours of access 8 hours following the accident,1 and 20 hours of access 1 day after the accident.
        ,                          building to a level which permits limited access approximately 15 minutes             .
23 In the area between the east and west penetration access areas, several pipes I
immediately af ter the accident, 3 hours of access 8 hours following the accident,1 and 20 hours of access 1 day after the accident.                  .
containing post-accident sources were found to be located above the sides of a pipe chase located at elevation 422'-3".
23 In the area between the east and west penetration access areas, several pipes       -
This allowed direct streaming of a l
I containing post-accident sources were found to be located above the sides of a pipe chase located at elevation 422'-3". This allowed direct streaming of a             -
5 12-inch RER pipe to the intermediate building floor elevation 412'-0".
l      5 12-inch RER pipe to the intermediate building floor elevation 412'-0". The resultant dose levels in this area of the intermediate building have been reduced to acceptab'e values by the modification of the pipe chas'e as follows:
The resultant dose levels in this area of the intermediate building have been reduced to acceptab'e values by the modification of the pipe chas'e as follows:
      ;]           ,/             (1) extension of the pipe chase side above the 12" RER line, (2) addition of 6"
;]
;                                  concrete shielding to the'e.41 sting i foot concrete shieldinn, (3) relocation of access ladder to prevent streaming through concrete cutout. The new configuratica allows personnel access in accordance with the occupancy i
,/
requirements of Table 12A.4-2, and the resultant integrated doses meet the dose requirements of 10CFR50, Appendix A, General Design Criteria 19 as outlined in-NUREG-0737,
(1) extension of the pipe chase side above the 12" RER line, (2) addition of 6" concrete shielding to the'e.41 sting i foot concrete shieldinn, (3) relocation of access ladder to prevent streaming through concrete cutout. The new configuratica allows personnel access in accordance with the occupancy i
,                                  12A.4.20 EMERCENCY OPERATIONS FACII.ITY P
requirements of Table 12A.4-2, and the resultant integrated doses meet the dose requirements of 10CFR50, Appendix A, General Design Criteria 19 as outlined in-NUREG-0737, 12A.4.20 EMERCENCY OPERATIONS FACII.ITY P
The radiation shielding design and personnel exposure doses shall be pro-                   -
The radiation shielding design and personnel exposure doses shall be pro-23 vided at a later date upon completion of the emergency operations facility design review. This facility will be designed to maintain the resultant dose levels in the area at acceptable levels.
vided at a                                                                               23 later date upon completion of the emergency operations facility design review. This facility will be designed to maintain the
12A-25 i'
:                            resultant dose levels in the area at acceptable levels.
 
12A-25
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                                                                                                          .s
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=
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as3'         O. eA. em.     .            N.                       .
w w
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eA.
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em.
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N.
w       as   a     m             m           e         em             w         w h        ===                           4      f*
4
3       wye,             P. em.           .            ur.         e.         d.
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N N
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*= el kN
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en 4         4                                                              .
h 3
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: wye, P.
g 4 8w
em.
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4 ur.
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e.
a led e                   4       4     8'*   m             M           N         N             se       as                                     g
d.
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VITAL. ARM kADI ATinte las5E SterlARY                                                                   -'
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pre utsasse y Acs.ea.s thse.e Ten     Total           Total             .
VITAL. ARM kADI ATinte las5E SterlARY 6
Occupaucy               Time Alter               Bhase       Aeul tree Area         sk se             those Vital Area       Seguirements                 Acc lilen t       (Ree/Fermon)   Jeger soni         Qcefretsum)         {M.ne_e _tye}
ie -
C..ollag shal t )         ) permana far                 I liour             i.4. 4           0.47               64.9           194.6 (ttelutenance ar Repair) 4 1.ouse                                                                                                                       i 8 Iwauen               9. nli         0.38                 9.19           27.6 Jay                 I . II         0.02                 8.33             5.98 5 daya                 n. 30             (I)               O. 30           n.90 to days                 u.22             (4)               0.22             u.e4 30 days                 0.us             (1)               0 . 81 6         c.24
pre utsasse y Acs.ea.s thse.e Ten Total Total Occupaucy Time Alter Bhase Aeul tree Area sk se those Vital Area Seguirements Acc lilen t (Ree/Fermon)
                                                                          ,90 days                 0.02             (t)               89 . 0 2         U. Den J     Laglueused Safety       2 permane for                 0               3.11 - 8.))           2.46         5.49 - 10.5     18.0 - 21.11 Featusu Sul.m t e t lan 2-5 minutes s es muJ natur                                      1/2 8.our                                  3.64                        7.7p - 13.nt
Jeger soni Qcefretsum)
{M.ne_e _tye}
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) permana far I liour i.4. 4 0.47 64.9 194.6 (ttelutenance ar Repair) 4 1.ouse i
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2.46 5.49 - 10.5 18.0 - 21.11 Featusu Sul.m t e t lan 2-5 minutes
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s es muJ natur 1/2 8.our 2.21 - 5.2e 3.64 1.a5 - 6.92 7.7p - 13.nt S.
M I lueur         1.41 - 1.58             1.20         2.6) - 4.73     5. 26 - 9. %
Centrol Center b
8 8.our         u.17 - 0.4 )           0.24         0.48 - 0.67     H.N2 - 8.34         23 8 day           0.004 - ts.ul         U.trui       0.ture - 0.015 p.u2 - 0.01 g     layJe ugees Nece leiner   2 persons for to               i Inn r                 1.52           1.20                 4.72             9.44 t'n.itsol auJ Peuer       minutes 1.or I.our S..pply rauels           over a 3 insur                 2 lueurs               2.82           0.42                 2.54             5.us ceeled 3 leuurs               1.50           0. })                 3.M)             3.66 4 8.ours               1.57           U.26                 8.4)             2.86 24 Iwours               0.49           0.05                 81. 2 0         0.4u 25 twaars               0.15           0.09                 0.26             11. 5 2 26 laours               55. 8 7         0.09                 (1.26           0.52 27 leossra               0.16           8 . 83 4             0.25             0.50 l
I lueur 1.41 - 1.58 1.20 2.6) - 4.73
: 5. 26 - 9. %
M 8 8.our u.17 - 0.4 )
0.24 0.48 - 0.67 H.N2 - 8.34 23 8 day 0.004 - ts.ul U.trui 0.ture - 0.015 p.u2 - 0.01 g
layJe ugees Nece leiner 2 persons for to i Inn r 1.52 1.20 4.72 9.44 t'n.itsol auJ Peuer minutes 1.or I.our S..pply rauels over a 3 insur 2 lueurs 2.82 0.42 2.54 5.us ceeled 3 leuurs 1.50
: 0. })
3.M) 3.66 4 8.ours 1.57 U.26 8.4) 2.86 24 Iwours 0.49 0.05
: 81. 2 0 0.4u 25 twaars 0.15 0.09 0.26
: 11. 5 2 26 laours
: 55. 8 7 0.09 (1.26 0.52 27 leossra 0.16 8. 83 4 0.25 0.50 l


  =   .s   _                                                                      _
=
1 Ang l* 8 2A.4-2 (ta t inue4l VITAL ARFA RADI Atlost lAGE StesukY Occupancy     Atra se in.ne 1m     1atal                 Total 4hcipancy                               Time After                       thener         And Fr us Area     these                 Ime V8tal Area               Se.tu i s tocen t s                         AsclJens                   (tce/rere d       (peo/Peseeel   graf ry seen).         (Pten py) tryJrugen setembiner                 2 persone sur lo                               I B.our                       0.26             0.76             1.02               2.84 1.
.s 1 Ang l* 8 2A.4-2 (ta t inue4l VITAL ARFA RADI Atlost lAGE StesukY Occupancy Atra se in.ne 1m 1atal Total 4hcipancy Time After thener And Fr us Area these Ime V8tal Area Se.tu i s tocen t s AsclJens (tce/rere d (peo/Peseeel graf ry seen).
thea e eI anJ ruwe r                 eleu.t ea yer 8=>ur Surely ramals                       ever a ) 8.our                                 2 I.oure                       0.12             0.52             0.64               1.28 l.ealuJ                                                                                                                                                       ,
(Pten py) 1.
1l1.uur e                     0.u7             c.)$             0.45               0.9o                             ,
tryJrugen setembiner 2 persone sur lo I B.our 0.26 0.76 1.02 2.84 thea e eI anJ ruwe r eleu.t ea yer 8=>ur Surely ramals ever a ) 8.our 2 I.oure 0.12 0.52 0.64 1.28 l.ealuJ 1l1.uur e 0.u7 c.)$
4 8.uura                       0.05             O.30             al.15               O.70 24 lioure                       0.0H27           0.02             0.0227             0.tMS4 25 lemurs                       0.tW126           0.0896           0.0222             0.0444 26 8.ouse                       0.0025           0.088             0.020%             0.tM I 2 7 8.ou r a                     0.0023           0.017             0.039)             0.0586 Bed *' tar BullJ8ag Air                                                               0                             4.22             1.17             5.59               11.2
0.45 0.9o 4 8.uura 0.05 O.30 al.15 O.70 24 lioure 0.0H27 0.02 0.0227 0.tMS4 25 lemurs 0.tW126 0.0896 0.0222 0.0444 26 8.ouse 0.0025 0.088 0.020%
[    tl                                          2 perso.in for 10 minutes g            54 ple cullection refus                                                                           1/2 hour                           2.15             1.14             1.29               6.58 t2 I bour                         4.25             0.82             2.0%               4.30 8 houta                       88. 1 I           0.I4             0.25               O.Su 3 J.sy                         0.01             0.02             0.05               0.30 in hn t e a l Si.pleos a             Cuntlenn.us                                 10 days                           -                -        Thyralda 76,6              -
0.tM I 2 7 8.ou r a 0.0023 0.017 0.039) 0.0586
N ce.,t.,                                                                                                                                           cd==a    =
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4.87 meta      -  21.6                               ,3 0                     y..u                   re..et le uu.                               20 Jay.                           -                -        T8.y e a lJ = 26.6         -
tl Bed *' tar BullJ8ag Air 2 perso.in for 0
c i r..I ca       =   4.87
4.22 1.17 5.59 11.2 g
                                                                                                                                                                      ****'=       21.6 r     S mple N. .es a
54 ple cullection 10 minutes refus 1/2 hour 2.15 1.14 1.29 6.58 t2 I bour 4.25 0.82 2.0%
tl     p eJ 8. l.culas a y lat.
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: 88. 1 I 0.I4 0.25 O.Su 3 J.sy 0.01 0.02 0.05 0.30 Thyralda 76,6 N
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in hn t e a l Si.pleos a Cuntlenn.us 10 days 4.87 cd==a
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4           e i
4 e
i TABLE 12A.4-3 ACCESS ROUTES TO VITAL AREAS Access Route                           Description
i i
: 1.     From Control Building (C.B.), 463' elev., down either 3
TABLE 12A.4-3 ACCESS ROUTES TO VITAL AREAS Access Route Description 1.
From Control Building (C.B.), 463' elev., down either 3
stairway to 412' elev. through 412' elev. to north corridor.
stairway to 412' elev. through 412' elev. to north corridor.
From C.B. , 412' elevation, enter Auxiliary Building (A.B.) at stairway tower 1, down stairway to 374' clev., through hallways 74-01 and 74-09 to rooms 74-16 and 74-17. For cooling units, ladder up from hallway 74-09 to 385' elev. to rooms 85-01 and 85-02.
From C.B., 412' elevation, enter Auxiliary Building (A.B.) at stairway tower 1, down stairway to 374' clev., through hallways 74-01 and 74-09 to rooms 74-16 and 74-17.
: 2.     From C.B., 463' elev., down e.ither stairway to 412' elev.,
For cooling units, ladder up from hallway 74-09 to 385' elev. to rooms 85-01 and 85-02.
2.
From C.B., 463' elev., down e.ither stairway to 412' elev.,
through 412' elev. to north corridor. From C.B., 412' elev. enter A.B. at hallway 12-11, through hallways 12-11 and 12-09 to stairway tower 2, down stairway to 397' elev.
through 412' elev. to north corridor. From C.B., 412' elev. enter A.B. at hallway 12-11, through hallways 12-11 and 12-09 to stairway tower 2, down stairway to 397' elev.
and through room 97-01 to stairs at column lines M and 9.5.
and through room 97-01 to stairs at column lines M and 9.5.
Down stairs to 388' elev. to room 88-13S.
Down stairs to 388' elev. to room 88-13S.
                                      ^
^
: 3.     Same as "-2" but through room 88-13S to room 88-25.
3.
              ,u l     s_.          4.     From C.B., 463' elev., down either stairway to 412' elev.,
Same as "-2" but through room 88-13S to room 88-25.
,u l
4.
From C.B., 463' elev., down either stairway to 412' elev.,
s_.
through 412' elev. to north corridor. From C.B., 412' elev.,
through 412' elev. to north corridor. From C.B., 412' elev.,
enter A.B. at hallway 12-11, north through hallway 12-11 to room 12-28.
enter A.B. at hallway 12-11, north through hallway 12-11 to room 12-28.
: 5.       Same as "4" but continues through hallway 12-11 to room 12-15.
5.
: 6.       Same as "4" but north through hallway 12-11 and east through hallway 12-11 N to room 12-18.
Same as "4" but continues through hallway 12-11 to room 12-15.
l
6.
;      4 12A-33 i
Same as "4" but north through hallway 12-11 and east through hallway 12-11 N to room 12-18.
l 4
12A-33 i
F-
F-


TABLE 12A.4-3 (Cont'd)
TABLE 12A.4-3 (Cont'd)
Access Route                               Description
Access Route Description 7.
: 7.       From C.B., 463' elev., down either stairway to 412' elev.,
From C.B., 463' elev., down either stairway to 412' elev.,
i through 412' elev. to north corridor. From C.B., 412' elev.,
i through 412' elev. to north corridor. From C.B., 412' elev.,
enter A.B. at hallway 12-11, north through hsilway 12-11 and
enter A.B. at hallway 12-11, north through hsilway 12-11 and
      }                                                                                 east through hallway 12-11 N to stairway tower 3. Down stairway to 338' elev. to room 88-13 NE.
}
I                                                                       8.       Same as "7" but through room 88-13 NE to rooms 88-23 and     -
east through hallway 12-11 N to stairway tower 3.
88-24.                                                          .
Down stairway to 338' elev. to room 88-13 NE.
: 9.       Same as "7" but through room 38-13 NE to room 88-13N.
I 8.
: 10.       Same as "7" but continues through room 88-13 NE to room 88-13 N. Ladder up to 400' elev.
Same as "7" but through room 88-13 NE to rooms 88-23 and 88-24.
: 11.       From C.B., 463' elev., down either stairway to 412' elev.,
9.
Same as "7" but through room 38-13 NE to room 88-13N.
10.
Same as "7" but continues through room 88-13 NE to room 88-13 N.
Ladder up to 400' elev.
11.
From C.B., 463' elev., down either stairway to 412' elev.,
through 412' elev. to north corridor. From C.B., 412' elev.,
through 412' elev. to north corridor. From C.B., 412' elev.,
enter A.B. at hallway 12-11, north through hallway 12-11 and east through hallway 12-11 N to stairway tower 3. Up stairway to 463' elev. to room 63-09 at column line 7.7.     '
enter A.B. at hallway 12-11, north through hallway 12-11 and east through hallway 12-11 N to stairway tower 3.
i
Up stairway to 463' elev. to room 63-09 at column line 7.7.
: 12.       Same as "11" but from room 63-09 enter Fuel Building (F.B.)       23 I
i 12.
Same as "11" but from room 63-09 enter Fuel Building (F.B.)
23 I
463' elev., through room 63-01S to column lines P.4-P.9 and 3.3-4.0.
463' elev., through room 63-01S to column lines P.4-P.9 and 3.3-4.0.
: 13.       From C.B., 463' elev., down either stairway to 412' elev.
13.
From C.B., 463' elev., down either stairway to 412' elev.
through 412' elev. to north corridor. From C.B., 412' elev.
through 412' elev. to north corridor. From C.B., 412' elev.
enter A.B. at hallway 12-11, through hallways 12-11 and 10-09 to stairway tower 2. Up stairway to 463' elev., through hallway 63-04 and south through hallway 63-16 to room 63-19.
enter A.B. at hallway 12-11, through hallways 12-11 and 10-09 to stairway tower 2.
Up stairway to 463' elev., through hallway 63-04 and south through hallway 63-16 to room 63-19.
12A-34 I
12A-34 I


TABII 12A.4-3 (Cont'd)
TABII 12A.4-3 (Cont'd)
Access Route                           Description
Access Route Description 14.
: 14.     Same as "13" but through room 63-09 to room 63-01.
Same as "13" but through room 63-09 to room 63-01.
: 15.     From C.S. , 463' elev. , down either stairway to 412' elev. to i                           rooms 12-09, 12-10 and 12-11.
15.
From C.S., 463' elev., down either stairway to 412' elev. to i
rooms 12-09, 12-10 and 12-11.
4
4
    .(
. (
e 12A-35
e 12A-35


F TABLE 12A.4-4 LIOUID A'ID GASEOUS SAMPLE COLLECTION AND PREPARATION 4
F TABLE 12A.4-4 LIOUID A'ID GASEOUS SAMPLE COLLECTION AND PREPARATION 4
;                                  WORKER LOCATION CODES (1) At Sampin Panni Control Board'.
WORKER LOCATION CODES (1) At Sampin Panni Control Board'.
(2) Handling Diluted Sample (Shielded).
(2) Handling Diluted Sample (Shielded).
(3) Handling Diluted Sample (Unshielded).
(3) Handling Diluted Sample (Unshielded).
(4) Sa=ple Transport in Shielded Container.
(4) Sa=ple Transport in Shielded Container.
        .                A.         ISOTOPIC ANALYSIS OF PRIMARY CdOLA}rr.
A.
                                    ~ Locations: Sample Room, Count Room.
ISOTOPIC ANALYSIS OF PRIMARY CdOLA}rr.
* WORKER TASK                           TIME     LOCATIOT
~ Locations: Sample Room, Count Room.
: 1.     Sample Purge, Collection, Dilution and           180 sec.           1 System Flush.
WORKER TASK TIME LOCATIOT 1.
: 2. Remove Diluted Sample from System.                 30 sec.           3 I
Sample Purge, Collection, Dilution and 180 sec.
: 3. Transport to Count Room                             30 sec.           4-
1 System Flush.
        .                          4. Count Sample (Count Room).                         180 sec.           2 i
2.
i B.         BORON ANALYSIS                   -
Remove Diluted Sample from System.
3
30 sec.
  ,                ,                Locations: Sample Room and Radiochemistry Lab.
3 I
e                 1. Read pH vs Na Concentration Curve on
3.
                                                          ~
Transport to Count Room 30 sec.
30 sec.           1       ,'
4-4.
  . l';                                   Control Pancl.-                                                               i Alternate Method:
Count Sample (Count Room).
: 1. A Syringe .lml of Diluted Sacple to vial.               20 sec.           3-I.                               2.A Transp rt Simple to Chemistry Lab.                     30 sec.           2'
180 sec.
              ,                    3.A Pipet 5 ul Sample into Atomic                         120 sec.       3 and 2           ,
2 i
Absorption Spectrometer (Repeat twice).                                                  .
i B.
C.       PRIMARY GAS ACTIVITT ANALYSIS                                                                     ,
BORON ANALYSIS 3
(Same as A above).                                                                             j i
Locations: Sample Room and Radiochemistry Lab.
e 1.
Read pH vs Na Concentration Curve on 30 sec.
1 l';
Control Pancl.-
i
~
Alternate Method:
: 1. A Syringe.lml of Diluted Sacple to vial.
20 sec.
3-I.
2.A Transp rt Simple to Chemistry Lab.
30 sec.
2' 3.A Pipet 5 ul Sample into Atomic 120 sec.
3 and 2 Absorption Spectrometer (Repeat twice).
C.
PRIMARY GAS ACTIVITT ANALYSIS (Same as A above).
j i
f 12A-36a
f 12A-36a


D. H9 ANALYSIS WORKER TASK                             TIME       LOCATION
D.
: 1. Draw Diluted Gas into Syringe                           20 sec.         3 (Twice) .025 cc.
H9 ANALYSIS WORKER TASK TIME LOCATION 1.
l                   2. Inject Gas into Chro=atograph (twice).                 10 sec.         3 NOTE:     (a) Time operator spends at panel during sample purge, collection, dilution and system flush is not indicative j                                       of total elapsed time for operation, 20 minutes. It is 8
Draw Diluted Gas into Syringe 20 sec.
3 (Twice).025 cc.
l 2.
Inject Gas into Chro=atograph (twice).
10 sec.
3 NOTE:
(a) Time operator spends at panel during sample purge, collection, dilution and system flush is not indicative j
of total elapsed time for operation, 20 minutes.
It is 8
the ti:ne the operator must spend in the area.
the ti:ne the operator must spend in the area.
(b) A.1 time, 180 sec. is the sa:e for B, C, and D sample
(b) A.1 time, 180 sec. is the sa:e for B, C, and D sample
        )                                       collection, which are performed concurrently from sample
)
      ,'          ,                            control panel.
collection, which are performed concurrently from sample
            ,L i
,L control panel.
E. CONTAINMENT GAS ACTIVITY                                                         -
i E.
Location:       Intermediate Building, Elev. 463' Count Room.
CONTAINMENT GAS ACTIVITY Location:
: 1. Sample Collection.                                     120 sec.         1
Intermediate Building, Elev. 463' Count Room.
        ,                  2. Sample Removal.                                         30 sec.         3
1.
: 3. Transport.                                             120 sec.         2 I
Sample Collection.
: 4. Sample Count.                                         180 sec.         2
120 sec.
              ,      F. CONTAINMENT HYDROGEN ACTIVITY l
1 2.
(Same as E above, Step 1, only read H2 at remote           120 sec.
Sample Removal.
30 sec.
3 3.
Transport.
120 sec.
2 I
4.
Sample Count.
180 sec.
2 F.
CONTAINMENT HYDROGEN ACTIVITY l
(Same as E above, Step 1, only read H2 at remote 120 sec.
readout on control panel.)
readout on control panel.)
E
E
{           -
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l i
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s 12A-36b
12A-36b s
;  I L
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                                = - - . _ _ . . . _ . . . _
= - -. _ _... _...
1 12A.5 REVIEW OF RADIATION QUALIFICATION OF SAFETY RELATED EQUIPMENT Radiation qualification of safety related equipment is provided in the SCE6G report addressing the requirements of NUREG-0588 (refer to SCE6G letter dated     23 January 15, 1981).                                                                    .
12A.5 REVIEW OF RADIATION QUALIFICATION OF SAFETY RELATED EQUIPMENT Radiation qualification of safety related equipment is provided in the SCE6G report addressing the requirements of NUREG-0588 (refer to SCE6G letter dated 23 January 15, 1981).
s 3
s 3.)
                                                                                                .)
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12A-37
12A-37


                        ~4 12A.6                 eRITERENCES I'                                             1.             E. D. Arnold and B. F. Maskervitz, "SDC - A Shield Design Calculation Code for Fuel Mandling Facilities," ORNL-3041, March 1966.
~4 12A.6 eRITERENCES I'
1.
E. D. Arnold and B. F. Maskervitz, "SDC - A Shield Design Calculation Code for Fuel Mandling Facilities," ORNL-3041, March 1966.
i
i
    \       .                                2.             C. M. Lederer, J. M. Hollander, and J. Perlman, " Table of Isotopes," Sixth Edition, John Wiley and Sons, Inc., 1967.
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1
2.
: 3.             A. Tobias, " Data for the Calculation of Gamma Radiation Spectra and Beta Heating frora Fission Products (Revision 3), RD/B/M2669, June 1973.
C. M. Lederer, J. M. Hollander, and J. Perlman, " Table of Isotopes," Sixth Edition, John Wiley and Sons, Inc., 1967.
                  ,' T                                                               {
1 3.
: 4.             Regulitory Guide 1.4, Revision 2 (6/74).
A. Tobias, " Data for the Calculation of Gamma Radiation Spectra and Beta Heating frora Fission Products (Revision 3), RD/B/M2669, June 1973.
: 5.             Regulatory Guide 1.7, Revision 2 (11/78).
,' T
: 6.             Source Term Data for Westinghouse Pressurized Water Reactors,'WCAP-3253
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4.
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6.
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Source Term Data for Westinghouse Pressurized Water Reactors,'WCAP-3253
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                                                                                                                                                                                                          ,g3
N'Ws?V4%$pf e fd i
                                                                                .1, %.3 '!!. *;.;,p c4=--? q i$                                                                                    ,y.-h, lig
l' i
                                                                                    .,                                                                                                                              I c f.
~
                    ]                                                                                              /                                                i                                            !
y I
                      =
'l h
                                                  }.I                                      h                                                      .7"                                    '
HydYg/
                                                                                                          @i !8'l'._.
Qkd i
                                                                                                                          .h.* _ _ r MM
,...,i
                                                          %                jrh                                                    --    :    -
,e my_,.--.,
                                                                                                                                                                                    ,j}Fa-                                            m
,y 7
                                                                              'Mg - N , ;!i D E ' $ S
'g i
                                  =            L N]1%jSi                                                                                                                gi' -$g M,y_vD '~ %~ .,.
@p#j r: DI ' Q97.J.f. i- > y--.J '%
D:::
W.
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=
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i
i
                    .           t
}.I h
                                                                                              .Ed W3-- f AN"k
!8'l'._.
                                                                                                                                                                                          .wwm::=. -                       3     .
.7"
                                          ---g,],Ga        I   N.                                                 4 [Nyf;hd
=
                                                                            .: y.fc[hdif a                      . .
h
                                                                                              -1 g   = e.'.g .4; j ,dl12;[g
@i.h.* _ _ r MM
                                                                                                                          -I                .
,j}Fa-N]1%j 'M Si
gt l d! l fj p .,_.:.2_is52.J
- N, ;!i D E ' $ S D::: $g M,y_v '~ %~.,
___.y i
L jr g m
4 T'I
=
                                                                                                          ~
.Ed W3-- f AN"k gi' -
                                                                                                                                                              'hJ h$,                                             1, j g m6 i- e g                  i                                                'h'~p=-   e. u_L"5J
D i
_ , ~ . _ _ ._.                               wnr3--                  ,.,, __
t
                                                                                                                                                                                                        ,,a : $"  3 .n.
.wwm::=. -
h      .
3
                                                                      )[: T~                                                                                     N$
---g, I N.
                                    '                  f                                            * ''[                                                                                                                    -
fc[hdif 4 [Nyf;hd g = e.'.g.4; j,dl [g d! l fj p.,_.:.2_is52.J
1 k.h. !               t h,' \ o 'k-M cdi j]S                                         en (f.      / 's!j             iT       9
],Ga.: y.
                      .         E!                     l[M     s                  fi               fli
-I
                            <iw          -           .s      .
-1 12; gt l a
                                                                                                                                                                                                  ^~i..2    *0w'"
___.y
r-)g $1
~
                            % a ut      s . o''
'h 4
                                                          . k.. na/AII"(g
1, J h$,
: 3. .
i T'I g m6
                                                                                            . ,i m.                         3 lI                I              a
'h'~p=- u_L"5J
                                                                                                                                                                                !!hj'q--Q d m p'. -             .a ij                         6
,, : $" h e.
                                                                                                                                                              ./ ;g { D !L 'iE.Y                 i-- 3 :
wnr3--
1
i e i j a
                            .                                                                  s b                .      i                      1  .%,                                                      --
_, ~. _ _._.
                              .aHt-L.wL%,[P~..ah
g 3.n.
                                          " I
1 f )[: T~
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k.h. !
t
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.aHt-L.wL%,[P~..ah 1'.
b f i((i s
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* I.
1'.                                b f                                                            "          '
w, c - 4;G.,.).':y.[
                                                                          <                                    w,         .
p.e.c.: m..,. --
i((i                    -                  -
-i p..
p.e.c.: m. . , . --
_::a. e=,:-g,, 'eC+d.Wg. h._ ]
cIl - 4;G. j w. ,.).':y.[
Il j
                              -i                                              .
,1
p..
=.. = - - -
                                                        ,1                                                                    '      = . ...= - - -
s - - - - - -. --
                                  .            _::a. e=,:-g ,, 'eC+d.Wg.                                                             - h ._ ]
w.
s - - - - - - . --                 c -~8
c -~8 i
        !              i         -              .
i i
i                       .        .          i           .
i i
                                                                                                                                                      .                i           .        ,      .
i         .      .
1
1


g
g l
                      ,i           .        i           -          i             -          i               .          i l
,i i
                                                                                                                                          .            4    . i     .            .              .              .            -      i       .      .        t
i i
                                                                                                      !l                                                                                                   I h'C                                                                                                                                     a=       l 3in3                                A                                                                                                   s_i 32 eI      .
i 4
:n     :
i i
                                        ;- Jh.!,I TT'l4x,                                                                                                                I.l                                                      e"
t
                                                    ~                                                                                                                                                                                         ,
!l I
                                                    -                                              ,t i..             ,n a                                                        u n u.5
h'C a=
                                                                                                                                                                                                                                    =         -
l e
Nl .j                                                         l \ 9!
3in A
I If             li                                                         35 N =y    *'
s_i 32 3
                        .             ol ON,gl i .Mq1.drkeiM%B:anM%W:.W ge n- gdl'ij /l ccc w ;r _:wi
:n I
                                                                                            -~
Jh.!,I TT'l I.
                                                                                                                                      -'i         n,g,      i M        "fh i ...j d
e" l
                                                                                                                                                                                                                                    =a       n. c .,if
a u
                                  ;C                      -
n u.5
                                                                                                                                                  ~
~
                                                                                                                                                      ' ::'                                                                          5a       t .:     6 g, u"j             -am 4uj..spri                      m e jp +w-
4x,
                                                                                                                                                                                                                                    .          2
,t ol ON,gl gdl'ij /l i..
.                              i'      ,
,n
25'     =* z y
=
q                                                     .
35 N =y Nl.j l \\ 9!
I If "fh d
: n. c.,if li ccc w ;r wi
..spri
-'i n,g, M i...j i.Mq1.drkeiM%B:anM%W:.W n
ge -
i
=a
-~
5a t.:
6
;C u"j m uj m e jp + -
~
25' =* z 2
i'
-a w q g,
:s 3
:s 3
s i      i Mm                /                     :ul                   li               ,i i 6
4 s
I                                       idj/l          g'                                                                                                         plr
Mmidj/l y
                                                                                        ,            i    o I! INi!.
/
                                                                                                                                    - . .            ,                    j ai                           .
:ul li
8                                         $            $            G                       @                                                                                            - - - - -
,i i i
      '                                                                                                                                                                    l I      vl                                               lIr-l                l i
i 6
t K  ,
I g'
                                                                                                                                                                      @-url    u!D useum:m-                                    1
o I! INi!.
                                                                                                                            ~      , . .
plr j
                                                                                                                                        @                                  ll
ai i
                                                                                                                                                                      .-                  ll            ll                      .'
8 G
                      .                                4                            tv .'                                    /      N                            *                    '
vl l
: i. (                          h I-i n t.                                                                                                              .l -*;'
lI l l
e                                                                                          %n.\14                              2
                                ,)                                                il                                                                                                                                                                            '
u, w s w w,s                                                                                I.
                        -                                                                                                                                                                                                                I i                                            ,.
i            io
                                      @ ---m=su O<E. . . . .
G i-h-.rus-M G M F 2.. 03in a"9k61gi{                    g.
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            ,/_                                         Je ' ' ='-de 'Jidi T'"-6, s.Z.dNdilt6-Z--                                                                                                       (3}I                I,               .
Je
                              ~
' ' ='-de 'Jidi T'"-6, s.Z.dNdilt6-Z-- (3}II,
                                                        -A                   r,,, . y tz::r 1 si                   l , --           -2~
-A r,,,. y tz::r 1 si l, --
gW, N,,,=+
-2~
                                                              ~
~
4
pgAQn-g jg g, N,,,=+
(                    "'@                      1 4 ygn.
(
4 G m$i~!
1
                                                                                                                        -*h
~
                                                                                                                                              "'              l                            W pgAQn-g                                   jg   ~
W 4 ygn. 4 m$i~
2,                         ali i tum-mm {m; a
-*h W
                                                                                                                                                                            ~
C Y llii ,__: -
d"eN'I G/'5            / !I MT                                                                    .
a ,r_,-m===ma .$
of,,.qp j m[ y
                              ,              . i                                                                                                                                              i i
D VIM _f5Ef i                                  !
Eff/-
      -          Il'I ti 3 412aN                            W=SE'Y    1c                    .   !    fb'i u
                                                                                                                    .J ii'n:!!F'oc
                                                                                                                                                =r            s%.c_qs.:m aEE
                                                                                                                                                                                                  --J'A            ' EM
                                                                                                                                                                                                                          >asl n: 15 .bbU s.-- d.c d'd::!.y i Nr-----                                                          3
                                                                                                          ".ti i                                                -
I~
l
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i 9
i 2 7~
i.i
: t.        2pr.:r-~"d i-t
                                                                                                                $hbhhf$fhb$h.$'$h.
g gy.0$."$.'%'p n Q.._;dt->!.t[h;,i;
:i;.;97 j[              -
                                                                                                                                                                                                                                              -f'
  ?                                                                                                                                                                                                .
i 7 1
l
l
~
4 2,
ali G
i tum-mm {m; a d"eN'I C
G/'5 !I MTllii,__: -
~
/
Y D,,.qp j m[
. i a,r_,-m===ma.$
i i
of y
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Il'I 412aN W=SE'Y. ! fb'i.J ii'n:!!F'oc s%.c_qs.:m >asl n: 15.bb
--J' Eff/-
' EM 1c
=r aEE A
Nr----- s.-- d.c d'd::!.y i ".ti i 3
u ti 3 a'n g$!h'h I~
!!$d
$hbhhf$fhb$h.$'$h.
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9 2 7~
t.
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i i
i.i i-t
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                -              ' ,~-                               ,.,                                  ..,.                                          .,.,.
',~-
il l i                                       r                    t
il l i t
_'                                                        I j
r I
l illIV
illIV
                                                                                                                                          'I l l!!
!! i l 'I l l!!
                                                                                                                                                                                !! i ss ae
ss ae j
                                                                                                                                                                                !! lib 25 l1
                                                      - --~-
m a
1 jjjj I
llhli!!
llhli!!
it-l            !!'                                Gd!
!! lib 25 1
W ;Q                                      .3                                                                                                  -
I l1
M                      i
- --~-
                                                                          'd T~r-led '_
it-l a
Ei.*5E! U g . .;;:: :2
jjjj Ei.*5E! U Gd!
                                                                                                                                                                                                          ~
                                                                                                        ~---'] -
                                                                                                      ~''
e.l s
5$  2 e.:          s g
T- - -                                          $$  3 l' g,,                  /              . ,, ' !                                J 4 --          "p'          *            *"
i                      l. ra_ gj                                f Il              l JUj r!.      ! i..              '-'-.6'!$_ . .l'
                              , . . .                                                                                      i I e !!! fi :u M                                          I y g'
                                                                                                                                                      ~
l k Me'SYS8!                                                                                    ?1e iJ                                                                            I
                                @nu/w                  _vk h' S1
              -      mc=-g                                                          l .4            -
ji. igg,v . m.I
      ,                                                                                                                                      /y                                                        -
                    .i 3pj
[n
                                                    ~
                                                          -ll+ll !:!(gE l                          .
                                                                                            ;f*-
i IjAi N                                    !
                                                                                                                                              'n@;$,!0
:  y                  i o i*JwJi
: a.                                              'D                                b w-[p) . !!3iT.I -uigg s/;ku-n " '                                                                  d' ''
Dig'iL' 7'                                                h\\M            '
a                                  -                      '
m
m
                  ;Mr kppa k,
.3 W ;Q T~r-led '
              ~
'd
w         ,; 2        9 ]n4:q           Mee i                                   :ge                                   4                     'i , Q l       N I,1                   I                                     !$                                                      ?I a                                                        fE s                                                                                          yJ y
~
              >U!i' &l p   ;,p,.
-M i
Jr               L             yljjl_; g jM s,
g..;;:: :2
* gT                                                      "jj
~---'] -
                                                                                                                                                                                              ~r @
l s
                                      ,!F dbbA '
e.:
                                                                                                                                                                                                      ~
s
                .                  s                                                                                                                  ;pH ~.--                             a y9pidyh$' . %3i*g
~''
        .    ;i    [ M j k MM 1[R i W i e t M Ng                                                                                                                                       d A,3
5$ 2 e.
_lq>i..,;r0i.su._.mjp. w np u ~ is y a y. bi            ;&gamo                     ww a.
T- - -
as                  m=c?c       i 3,.
$$ 3 g
wy    w a,
l' g,,
                                                                                        "                                               w't
g
                                                                                                                                                                      .         w,-
/
    .                  h.~
J 4 --
                        %. - % f _
"p' I e !!! fi :u M. ! i.. '-'-. _..
h h . . . ~l          E      !
: l. ra_ j f Il l
Oh          L c. 9 h hp::,3h                                     ~,I       3:i i         kMk3l J,1
i JUj 6'!$
                *                      ,^          t  '            '
i r!
Q["** *'                                               3k       i dh%                 h* y g                       WG           y 4j s %     4 e
I l'
hb                       l--        Y                                         N     y                        }!$
~
                                                                                                                                        ,,                  m mf . _-!!n               a         _
y g' k @nu/w k h' S1 Me'SYS8!
                                                    +l t-+!u;:                                   1       A       6,.)pr                         Qf
?1e iJ I
_'*                                                                                                                                      h5                      (          '
l l.4 m
i
ji. igg,v. m.I
                                                                                                                                                ]                           j i! ,r I ' 4L i u,ij--> Mih!!./M.gsg4 9;        i,        ,,      -
-ll+ll !:!(gE c=-g
                .                         e    U..d4                       .-
_v
ii,ij%i -.          g
/y 3pj [n N
                                                                                                                                                                                          . 3
IjAi 'n@;$,!0
              ~
;f*-
e                   e                 a               e . .9 e i
l
                *                                                                                                                                  ,                  e,             e
.i
: --                                yj                    -
~
{l N n!:!
Dig'iL' 7' w-[p). !!3iT.I -uigg s/;ku-n " '
imyjgpi$.
i y
iumu ia!
i i wJi
wsms jji  gyiwiapp=s                                                        pgg.<l1!
'D h\\\\M b
                                                                                                                                                                  =r                                - -
a.
,                * !Mpl;ji, lib:!n w:!!ug.... n.
d' a
n
o
                                                                  !w Ji! iib.;;;i;   u! op!!A .uj;ju.......,.
*J
_,.g . itaie!;s;;ishpMW;ggJ@
;Mr kppa m
i                   ,        .                    .              .,
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;pH ~.--
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;&gamo m=c?c wy w
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iumu wsms
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!w w:!!ug
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i 1
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'lii'
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i 9
2


                                                                                                                                                                                      .                      .              .                          .                                                                        .                    j 1 j:      l                                                                          .}t .
==
                                  ' ' '4 . ' 'l.e'lii' j                                                                                                                    1      'h,                                          6, i                '
i;;I b "g"t y.
y "n                                                                                                                  f                                                                ==
,- t...... h.. e. i.
                                                                                                                                                                                  . ', IQ'f,g r!. M'                                        i;;I"g!                                    2 9
".! ! 'U!jv.s,.;,;.j n'$n.u@o ghm1 pot.typ ihl;w;;,ND"i:n::n;j!yI g.:
                            . ... . . h. . e. i. u.
gg i
                    ,- t u.imi
u.
                                                                          ' '" de o i .N.g.                :f g "ni 2            :
y a,,d u.imi
                                                                                                                                    ;.jjt.,T
: h. to.H d.[
                                                                                                                                    .,1        . b',"g"t              '%y.3,,                              ..
;h
                                                                                                                                                                                                                                                                        *h            ge, .: ;v.         gg ,i ;;        g< g.,
-( W ill ;
t      i y a, ,d                                        =-
J
ghm1 T g s                  pot.typ                                 ihl;w;;,ND"i:n::n;j!yI
=-
: h. to.H d.[ " .!                                  ;h
r :. ? j I-s
                                                                                                                                                                                !  'U!jv.s
".J...caf, n,-
                                                                                                                                                                                          -(                     W           ,.;       ,;.j ill J
uJ a;
                                                                                                                                                                                                                                              ;    n'$n.u@o                          uJ                  a; sr .
- vin..an;+"p" m.;g;m..no::in!,u.3!j,i'om""8il !.
I-r   :. ?     .j
;;;"kca.
                                                                                    ;;;"kca.                                                                                                                                                        ".J...caf, n eE
T g
        - vin.               .an;+"p" ...                  m.;g;m..no::in!,u.3!j,i'om""8il bi il
.r. ""i"U.,r * }"y"n.',*pu t..p;p.wmnM"l"t H":t N"t !!!!
                                                                                                          .n,        ""i"U.,r             b r ' *y }"y"n.',*pu '! ut:1 P((t.!.p
sr.
                                                                                                                                                                                          !      .                  t..p;p.wmnM"l"t "4
eE b
                                                                                                                                                                                                                                      '                                              a H":t""g              N"t !!!!
il af h)).r]'"ijHihil"d" a:
                                                                                                                                                                                                                                                                                                                            ^ *
.n,
* af h)).r]'"ijHihil"d"
^ *
                                                                                                            .r.
* ut:1 P((t.!.p "4
: al . . .,n -                                                          1i:m                    =g                                 i.*, d 3 r.... .... .. ...a. . ., ,,. rjg...n 4
=g
                                  ; ;;na:aamnjj                                                            . .n ni . ,c:..-
""g i.*, d 3 r ' y '!
m:h: ...
3r. o., r............., rjg...n n : f :a.:
n i:..fm:a.:                m gn , .... n nun. , ....,                                           ...n n . . m . ,,,                             t.                  -.                _--
a bi
3r . o. ,
: al..
                  ?,! i,il;illi!!!!!!!!!!ililiiillGiiH!iniillnindW                                                                                                                                       lii!!ili!!!llii!!illimWSil!!!!!!!!!!!!!I!                                           e ii           O if
.,n -
                                                                            .m...............................m.....
1i:m 4
m . m.....,..w............. ....... ..
m:h:
: n. u. : .
t.
I                      '. %.,,                                                  :                                %                        (~'(, k. . , di ,' . $, ._ <N.,                                                                    $        $!-"
...,,...n ni.,c:..- i.. m m gn,.... n nun.,....,...n n.. m.,,,
                                                                                                              .. uI's.::':," c                                                                                                                                                                            n s                                                                                                            ,-                                                          .
; ;;na:aamnjj
                                  . fr~.                     r-                                                                          e-JeyI+            e                .                     . -_                                                                    o*
?, i,il;illi!!!!!!!!!!ililiiillGiiH!iniillnindW lii!!ili!!!llii!!illimWSil!!!!!!!!!!!!!I!
                                                , @n ..,-,.dM !Sii'i                                                            - Til'I f                                                                                                                            M"T'TM'                                          '
ii O if
so_ j'!O                                                    e% )f,:W ;djj, !
: n. u. :.
i~                      (C                    1
.m...............................m.....
:d l
m. m.....,..w......................
                                                                                                                                                                                                    .. %'Q[@l[WhE 9 I
I                          .
                                                                                                                                                                                                                                          *I
                                                                                                                                                                                                                                      ~'~~
                                                                                                                                                                                                                                                                  'k $ l ,'
i.
: l.                     .~_                        E; }.J.Jd'li)Y *isOn                                              f,                      .                         J
                                                                                                                                                                                            - 4.?#                                                    ,1C~a.:W ld                              fl                ID . '                                                                                                          .               N
                                                                                                                                                                                                                                    , , ; _ ; _ ],f ,,5[( W} ,
l                s j.,,
g'-                          ,,,g. .lyc                        t                ;}                                                                                                                                                      ~
1[ 4 }l. 3                                                                                                    *        !                                                E                                                              i                        a l.
:.Mi y" - h%- 4 7.
                                                                                                                                              . .i -pj - - l r '1 1_f.                      .*Y. .__ _ .                m'"ar'          a                1I._s.
3,;  k
: t. lM'lt e .p l,
                              >                                                                                -O "d" u.ii o.
1        _
                                                                                                                                                                                                                                                              ~
s t                                f YikY          'y'- .                       .N k  *                          {                            I            )              I*  h I              b. hh' y=~231                      s;: 7            ss:
I,      i
                                                                                                                                                                                                  .r I
M *s                                                        4.
e i                                                  fg i                      v: n, s cr s-                            'i                        C.:                  .i                      p                          -
i i
3'fi . c h.                                                                                                                                                                                                                                                 -._.3 p( };In q
                                                                  ===4'                                                                                t
            .nm l            .
y]                    Ii . m%. r. n sri l
                .                     p.-.                 c =._ na , i=,i., :a.=                                    , .:-= . . < ,                                      ~ai-.                           __
e
e
                                                                                                                                                                                                                                    , ='                                         ,
(~'(, k.., di,'. $,._ <N.,
i s
I I's.::':,"
w;!; g'4qbi aq- , 1 12; M, i.m                         p       sy.,                    .     -;t       y1                    g, l                ,                                                  Wi          y.                     ,              8 f 'J M:         s .+.
n s
A
.. u c
                                                                                      .:              na               n 9            ,ir.
, @n..,-,.dM !Sii'i - Til'I o*
p i                 t.
JeyI+
r _y:e                          -ay',ey mm:- b i                   ! ._ n a u n..                                 ,;;
e e-
                                                                                                                    ,              L,                    d              ,
. fr~.
i.. --,. 's.y 7
M"T'TM'
                                                                                                                                                                                                                                                                                                    )g I,                                                                                                                                                                                                                                                                                                                     ~
.. %'Q[@l[Wh 9 i.
            ~)   g
r-j'!O e% )f,:W ;d !
(-l I            !i-
d f
                                                                                                    . **'v_= -..}{ Y             -=
I
                                                                                                                                                }  Eb 5 Q. l} \         l..,
- so_
1 at _
E; }.J.Jd'li)Y
s 1
* f, jj,
t
'k $ l,'
                                                                                                                                                                                                                                                  .='..-7 1% #
I
x         -
*I l
                                                                                                                                                                                                                                                                                                                                      +*
i~
            ?
(C 1
                                                                                            &                            &                  b                                    'Ci                                      n
J - 4.?#
                                                                                                                                                                                                                                *= g .                  --            , r                   ~.
,1C~a.:W E
y e n. tec                                                                s ee s '-
~'~~
i                               gr               L i                                                                                             _
isOn.
_'                                          8 *"-
l.
. ~ _
,, ; _ ; _ ],f,,5[ W},
ld fl ID. '
N
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s g'-
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;}
E j.,,
1I
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-7* h, G,
              . !.                                                                        G.                           S.                 C.
'!. )g
                                                                                                                                                                                          'I
'I 3
                                                                                                                                                                                                                                          -7* h,                    G,                                ;                                  .
*I G.
t                   i             ,                            i. i ._.                                                     t              i                  I .
S.
                                                                                                                                                                            ;                                                                                                                      -+._
C.
                                                                                                                                                                                                                                                                            .b.
t i
                                                                                                                                                                                                                                                                                                                                        ~
: i. i._.
                                                  + IrG-lh ?55
I.
:; ll $.iha.                            h' Ib .'IM                   '-
i t
5'"5                                                 l D""-                  -"'                                            l'i                                                                                                                                                                          ,
+ IrG-lh ?55 :; ll $. h' b.'IM
DI                                                                  dl                                      jI.I;l'O[lN$.k                                              I i    ;. - l
-+._
                                                                                                                                                                                                    @I { (g 7                        Mj-'I''d(        '
5'"5
T I'h s -                                                                                                      (8'                                          lII                  E Hy N N -a1 iL W E11d, ;lit lft. ~ZM.;i, 3 %''*"'AL) d
.b.
                                                                                              !Y a) .Q l'I. 4","l M D'C>g                                                            &-{                  -
: l.                                                                                                                                                                                                    '                              s.                          -
t                  MP ej nu
_. c _ _ ._....- ,r-                                                                  fk                                      _
l
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(                                                                               ,
~
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l'i iha. I I
                                                                                                                                                                                                                                                              .'5,.1,h..
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l 13 k'F*J n! r 1                  ' -          ~y                   ---
;. - l Mj-'I''d( T 'h s -
es          s..         -1                                                                   l 'll I'            '
@I { (g Q 'I. (8' D""-
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DI dl jI.I;l'O[lN$.k lII 7
                                    *.                                  ''                              :.:Y E                                       ,
E lft. ~ZM.;i, 3 %''*"'AL) 'd a).
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l 4","l M D'C>g I
                                                                            .. W 4mrk?h                                                                                                         ,_$.-r$                               @-lR..mp,W_                             D                  _A .g_                                   -
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                                                                                            ' rd {a                  4 1;n                                    o
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                                                                                                                                                                                                  .,a
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JII ',.,U
ip.4                -:
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                                                  ;                                        .+2                   ht . C a, .                                     ;
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t':
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8
                                                                                                                                                                                                                                                                                                                        ' { }gIiini.g t':    -
* %;l I}_ 8is, a__e!i_ gr :,4.:! !
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l t
              -                                                                                                                                                                                                                                          ,-                  c
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2,4"
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d pi.,,)nnit6
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=
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't-L aa q
* I; l ds j'y b *- . s-I l .'..                                                               /"h""q"',                       x      f- h.!'h1  '*ll!!%
I l j'y b *-.
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' 's l '4 8 I 1",
di nn-                 fp>                  c 9 _ pn                                 + ,n.v -
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                                                                                                              ,,y'_,!                     F!
$ h. '*ll!!
J.i . ?!F A I                                                                                                                                          !! t L 49 C ,_ 4 q                                                                                             [!!!!!!!!!!!!!                 .
..n 3
1 i                                                                                                                               '                                                                                       ;    s s             5, I          p                                              _
I.
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I
* I IN,i !N'i.I\ill                                        *
?
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9 x f- !'h1 %
                        '                                                                                                                                                                                                                                              eg!i
i.ntI'" x.
                                                                                                                                                                                                                                                                      $s i!NI . s N. .g
; ds s-J nn-c
                                                                                                                                                                                                                                                                            -~-
_ pn +,n.v -
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Latest revision as of 22:33, 16 December 2024

Forwards Design Review of Plant Shielding & Environ Qualification of Equipment for Spaces/Sys Which May Be Used in post-accident Operations Outside Reactor Bldg.Info Will Be Incorporated in Amend 23 of FSAR
ML20062L113
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 01/09/1981
From: Nichols T
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8101150183
Download: ML20062L113 (46)
v • d • e


Text

{{#Wiki_filter:. .~ r SOUTH CAROLH4A ELECTRIC & GAS COMPANY ,ou cerier so.,.. CotuMe:A. Souin CAnoLINA 29818 i T. C. Nicuots, Jn. January 9, 1981 V<t P.g sset.f.W G4wp CAECvmt nau. c..,.. Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commicsion [ Washington, D. C. 2055$

Subject:

Virgil C. uclear Station Docket No /395 } Shielding Review I (

Dear Mr. Denton:

s_ e South Carolina Electric & Cas Company acting for itself and as agent for the South Carolina Public Service Authority, provides forty-five (45) copies of the Design Review of Plant Shielding and Environmenta.1 Qualification of Equipment for Spaces / Systems which may be used in post accident operations outside the reactor building at the Virgil C. Synser Nuclear Station. This information will be incorporated in Amendment 23 of FSAR. If you have any questions, please let us know, i Very truly yours, t h f L= ,p s A' S' l_sk T. C. Nichols, Jr. NEC:TCN:glb I

Enclosures:

cc: V. C. Summer w/o enclosures G. H. Fischer w/o enclosures T. C. Nichols, Jr. w/o enclosures E. H. Crews, Jr. O. W. Dixon, Jr. D. A. Nauman O. S. Bradham W. A. Williams, Jr. A. A. Smith-A. R. Koon E3? ~ R. B. Clary J. B. Knotts, Jr. J. L. Skolds I" C'.U ' ' B. A. Bursey NPCF/Whitaker File Ni;. I 8 013 5 o gg, 1 l t A

O 12A DESIGN REVIEW OF PLANT SHIELDING AND ENVIRONMENTAL QUALIFICATION OF EQUIPMENT FOR SPACES / SYSTEMS WHICH MAY BE USED IN POST ACCIDENT OPERATIONS OUTSIDE THE REACTOR BUILDING AT THE VIRGIL C. SUMMER NUCLEAR STATION t 12A.1 INTRODUCTION l This report has been prepared in response to the September 13, 1979, letter from Darrel G. Eisenhut of the NRC to all operating nuclear power plants. This, letter prerented an implementation schedule for the recommendations presented in "TMI-2 i j Less ons Learned Task Force Status Report and Short-Term Recommendations" s (NUB:G-0578). The requirements defined in the September 13th letter were subs equently clarified in a letter from Harold R. Denton to all operating nuclear powtr plants dated October 30, 1979. Among the requirements defined in the two NRC letters is a review to determine whether post-accident radiation fields unduly limit personnel access to areas necessary for mitigation of or recovery from an accident or unduly degrade the proper operation of safety equipment. Corrective actions for problems identified as a result of the review are also to be determined. This report presents the results of such a review for the Virgil C. Summer Nuclear Station. 1 The review was based on the following guidelines: a) The post-accident dose rate in areas requiring continuous occupancy should 23 not exceed 15 mr/hr. b) The post-accident dose rate in areas which do not requi.:e continuous l 23 occupancy should be such that the dose to an individual during a required access period is less than 5 Rem whole body or its equivalent, in order to maintain compliance with General Design Criterion 19. c) The integrated dose to safety equipment.as a result of the accident should be less than the dose for which the equipment has been qualified to ensure 11A-1 4 i

s that the capability of the equipment to perform its safety function.has not been degraded, in order to maintain compliance with General Design 23 Criterion 4. d) The minimum radioactive source term used in the evaluation should be equivalent to the source terms recensnended in Regulator / Guides 1.3 and 1.4. I 1 i 4 r u 6 m h i l h 12A-2 l i

9 s 12A.2

SUMMARY

This report provides a review of the Virgil C. Summer Nuclear Power Plant to determine whether post-accident radiation fields unduly limit personnel access to areas necessary for mitigation of or recovery from an accident, or unduly degrade the proper operation of safety equipment. This review was accomplished using the recommendations and guidelines of NUREG-0578 and subsequent clarifications as l provided by the NRC. A detailed discussion of the evaluation of plant vital areas and equipment qualification for post-accident conditions is presented in Sections 4.0 and 5.0. .! k,! Results indicated that certain areas of the plant required additional radiation shielding to reduce the post-accident radiation fields. These areas and the shielding modifications utilized are described in the following paragraphs. Area "A" is the location of the residual heat removal (RER) pumps, reactor building spray pumps, and the pump room cooling units. The RER/ Spray piping is adequately shielded and does not restrict post-accident access to this area. However, a significant potential source of exposure to plant personnel can result a from the RER/ Spray pump room sump line. This line was unshielded and located in 23 the ha'11way between pump room B and the waste holdup tank, and resulted in a potentially high radiation ares during both normal and accident operating conditions. The resultant dose levels in the subject area have been reduced to l / acceptable values by the re-routing and venting of the line to permit the line to drain during sump pump shutdown periods, and the placement of lead shielding to i prevent streaming to the operating floor 374'-0". The new pipe configuration and radiation shielding allows personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737. Following an accident, personnel access to the auxiliary building is controlled at the 412'-0" elevation from the control building. As a result, the use of the stairway and elevator located in cubicle 12-09 as an access route to vital areas 12A-3 i 1

above and below the 412'-0" elevation is important. A 10-inch RER line penetrates the south and east shield walls of cubicle 12-09 at elevation 429'-6" resulting in significant doses to workers in this area. Shortly after the accident, the integrated dose to a worker transversing this area would be of the order of 1 rem. The resultant dose levels in the subject area have been reduced to acceptable values by the addition of lead shielding. The new configuration allows personnel access in accordance with the occupancy requirements of l Table 12A.4-2, and the resultant integrated dose meets the dose requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737. ~ Area "I" is the location of the charging / safety injection pump room cooling units. This area was found to contain high radiation levels due to unshielded CVCS piping located at several places within the area. In order to permit the required occupancy time in the area for aanual valve alignment or maintenance, the resultant dose levels in the area have been reduced to acceptable values by the addition of lead and concrete shielding. The new configuration allow's personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose require =ents of 10CFR50, 23 Appendix A, General Design Criterion 19 as outlined in NUREG-0737. ~. r In the area of the intermediate building between the east and west penetration access areas, there were several RHR, safety injection, and CVCS lines which were routed above the sides of an open pipe chase at elevation 422'-3". This } permitted direct streaming from the piping to reach the floor area of intermediate building floor elevation 412'-0" which contains safety related f equipment. The resultant dose levels in this area of the intermediate building have b'een reduced to acceptable values by the modification of the pipe chase as follows: (1) extension of the pipe chase side above the 12" RER line, (2) addition of 6" concrete shielding to the existing i foot concrete shiciding, (3) re-location of an access ladder to prevent streaming through a concrete cutout. The new configuration allows personnel access in accordance with the occupancy requirements of Table 12A.4-2, and the resultant integrated dose meets the dose. requirements of 10CFR50, Appendix A, General Design Criterion 19 as outlined in NUREG-0737. I a 12A-:. 1 I

12A.3 SOURCE TERMS AND CALCULATIONAL METHODOLOGY t 12A 3.1 SOURCE TERMS 12A.3.1.1 Basis for the Source Terms The activity releases assumed in this review are based on the assumptions and l regulatory positions contained in the Regulatory Guides 1.4 and 1.7. The activity assumed for liquid source term calculation is based on 100 percent of j the noble gas inventory, 50 percent of the halogen core inventory and 1 percent of all other nuclides in the core inventory. The activity assumed for gaseous source term calculation is based on 100 percent of the noble gas core inventory and 25 percent of the halogen core inventory. 12A.3.1.2 Liquid Source Terms 23 Two liquid sources are considered in the design review: (1) the undiluted fluid as found within the reactor coolant system, and (2) the diluted fluid as found within the reacter building recirculation sump. The first source term, undiluted reactoc coolant, is required in the examination of those systems whose flow originates from either the Reactor Coolant System or an auxiliary system containing the undiluted primary fluid. The source terms are based on the j dilution of the liquid activity inventory discussed in the first paragraph with I '~d the fluid volume of the Reactor Coolant System. This source is used for the examination of the reactor coolant fluid sampling section of the Nuclear Sampling System, and those portions of the Chemical and Volume System associated with the degasification of the reactor coolant fluid. In the second liquid source term, consideration is given for the dilution of the liquid activity inventory discussed in the first paragraph with the fluid volume contained in the reactor building recirculation sump. The minimum fluid volume expected in the sump, and the individual contributors to that volume, are given in Table 12A.3-1. These source terms are utilized in the examination of,those 12A-5 i i

systems which receive their fluid supply from the reactor building recirculation sump. Those systems which are considered in the review are: Residual Heat Removal System Reactor Building Spray System Safety Injection System Nuclear Sampling System (RHR process fluid sample) {

  • 2A.3.1.3 Gas Source Terms I

The gaseous source terms were determined for containment and the waste gas system using the activity releases described in Section 12A.3.1.1. The containment airborne source term was based on the dilution of the gaseous activity inventory by the containment free volume atmosphere. Although not designed for reactor coolant degasification under post-accident conditions, the waste gas system was evaluated for the exposures emitted and received under the post-accident conditions. The waste gas system is designed to remove the fissica product gases from the reactor coolant contained in the Volume Control Tank (VCT). The amount of fission gases renoved from the reactor coolant in the VCT and collected by the waste gas system can be related to the amount entering the VCT as follows: l \\ (1) Stripping Efficiency (SE): C -C p t SE = C -C R L eq i (2) Stripping Fraction (SF): l C -C a t SF = CR l 12A-6 4 i

9 where C = R the gas concentration in the reactor coolant liquid entering the Volume Control Tank, C = g the gas concentration in the reactor coolant liquid leaving the Volume Control Tank, C. the gas concentration in the reactor coolant liquid leaving = u l '9 the Volume Control Tank, assuming the ratio of the gas concentration in the liquid and gas phases in the Volume Control Tank follows Henry's Law. /-' s I The waste gas system source terms were determined for the degasification of the reactor coolant liquid by calculation of the quantity of activity entering the Volume Control Tank via the normal letdown path. For the sake of conservatism, the stripping efficiency of this process is assumed to be 100 percent. Therefore, in the previous equation of the stripping fraction, C7=C7 , and the stripping fraction is: 'S C -C R 7 SF = gg Thus, the separation of the fission gases from the reactor coolant liquid in the (, VCT will follow Henry's Law. This results in the maximum theoretical gas 1 concentration in the vapor phase of the VCT and, hence, the maximum quantity of gas enters the waste gas system. t 12A.3.2 METHODOLOGY 12A.3.2.1 Calculation of Dose Rates Dose cates for the areas of interest in this review were calculated by determining the potential contributing sources at a representative location and using the appropriate source term from Table 12A.3-2 adjusted for decay as required. The dose rate at the representative location was used as the general 12A-7 1 i

ares dose rate for the area. The SDC computer code (Ref. 1) was used in performing the dose rate calculations. Energy groups re' quired as input to the computer code were determined using the gansna ray energy and intensity data in Refs. 2 and 3 for the nuclides in Table 12A.3-2. 12A.3.2.2 Calculation of Doses to Personnel During Post Accident Access to Vital Areas i Personnel doses received in performing a specific task in a given vital area are calculated as the sum of the doses received during travel to and from the vital area and the dose received while performing the given operation in the vital area. The doses received during travel are determined by calculating dose rates at selected locations (or at a single location if the dose rate along the travel route is relatively uniform) along the travel route using the methodology discussed in Section 12A.3.2.1 and multiplying the dose rates by the appropriate travel time for each selected location along the travel route. Doses received while performing a given operation are determined by multiplying the dose rate for the given area by the time required to perform the operation. Dose estes for the given vital ares are determined using the methodology discussed in Section 12A.3.2.1. -g l '] 12A.3.2.3 Calculation of Integrated Doses to Safety Equipment i The integrated dose to a given item of safety equipment is determined by integrating the dose rate appropriate for the given item over the time period that it is required to be available to perform its safety function. Dose estes are calculated using the methodology discussed in Section 12A.3.2.1. I 4 12A-3 t J l I

TABLE 11A.3-1 CONTAINMENT SUMP MINIMUM LIQUID INVENTORY Liquid Source Liquid Volume (ft3) Refueling Vater Storage Tank 46,791* Safety Injection Accumulators 3,000 i Boron Injection Tank 120 Sodium Hydroxide Storage Tank 408* Reactor Coolant System 9,146 3 Minimum containment Sump Volume = 59,465 ft w i NOTES: (a) Refueling Water Storage Tank at minimum operating water level at start of drawdown of the tank. The tank drawdown will be terminated at LO-LO level upon the automatic initiation of recirculation via the RER system. (b) The three (3) Safety Injection Accumulators have individual capacities of 3 1000 ft each. (c) The minimum usable volume of liquid in the Sodium Hydroxide Storage Tank. v8 l y.- t b 4 i 12A-9 9 I

~ _ _ -. _. -. -_. _ - - TABLE 12A.3-2 V. C. SUMMER SHIELDING S0t:RCE TERMS (T=0) L Liquid ( Caseous ( } Containment Reactor Containment Source Source Susp Coolant Airborne Waste Gas Activity Activity Concentration Concentration Concentration Concentration i Isotope (Ci) (CL) (uci/ce) (pci/ce) (pCi/ce) (pci/ce) a Be-84 7.5 + 6 3.75 + 6 4.46 + 3 2.90 + 4 7.20 + 1 6.67 + 3 Kr-87 3.70 + 7 3.70 + 7 2.20 + 4 1.43 + 5 7.10 + 2

1. 30 + 6. -

Te-133 4.40 + 5 2.62 + 2 1.70 + 3 Cs-134 1.70 + 5 1.01 + 2 6.56 + 2 Cs-136 4.70 + 4 2.80 + 1 1.81 + 2 Cs-137 7.03 + 4 4.18 + 1 2.71 + 2 Ba-139 1.50 + 6 8.93 + 2 5.79 + 3 Be-83 3.20 + 6 1.60 + 6 1.90 + 3 1.24 + 4 3.07 +-1 2.85 + 3 Kr-83m 6.30 + 6 6.30 + 6 3.75 + 3 2.43 + 4 1.21 + 2 2.09 + 5 Kr-85m 1.90 + 7 1.90 + 7 1.13 + 4 7.34 + 4 3.65 + 2 5.06 + 5 Kr-85 7.42 + 5 7.42 + 5 4.42 + 2 2.36 + 3 .1.42 + 1 1.15 + 4 i Kr-88 5.50 + 7 5.50 + 7 3.27 + 4 2.12 + 5 1.06 + 3 1.63 + 6 Rb-88 5.41 + 5 3.22 + 2 2.09 + 3 I Rb-89 6.80 + 5 4.05 + 2 2.63 + 3 Sr-89 7.40 + 5 4.40 + 2 2.36 + 3 St-90 5.00 + 4 2.98 + 1 1.93 + 2 Y-90 5.00 + 4 2.98 + 1 1.93 + 2 Sr-92 9.10 + 5 5.42 + 2 3.51 + 3 Y-92 1.00 + 6 5.95 + 2 3.86 + 3 Sr-93 1.10 + 6 6.55 + 2 4.25 + 3 Y-93 1.10 + 6 6.55 + 2 4.25 + 3 Mo-99 1.50 + 6 8.93 + 2 5.79 + 3 J Tc-99m 1.30 + 6 7.74 + 2 5.02 + 3 ) Ru-103 1.10 + 6 6.55 + 2 4.25 + 3 Rh-103m 1.10 + 6 6.55 + 2 4.25 - 3 Ru-106 4.10 + 5 2.44 + 2 1.58 + 3 12A-10 1 4 - l.

I i TABII 12A.3-2 (Cont'd) Liquid (I) Gaseous (2) Containment Reactor Containment Source Source Sump Coolant Airborne Waste Gas Activity Activity Concentration Concentration Concentration Concentration Isotone (Ci) (CL) (pCi/cc) (pCi/cc) (pCi/cc) (pCi/cc) ~Rh-106 4.10 + 5 2.44 + 2 1.58 + 3 Te-132 1.10 + 6 6.55 + 2 4.25 + 3 I-132 5.90 + 7 2.95 + 7 3.51 + 4 2.28 + 5 5.66 + 2 5.24 + 4 Te-134 1.60 + 6 9.52 + 2 6.18 + 3 [ 'i I-134 8.90 + 7 4.45 + 7 5.30 + 4 3.44 + 5 8.54 + 2 7.88 + 4 Xe-138 1.50 + 8 1.50 + 8 8.93 + 4 5.79 + 5 2.88 + 3 6.64 + 6 Cs-138 1.50 + 6 8.93 + 2 5.79 + 3 Ba-140 1.40 + 6 8.33 + 2 5.41 + 3 La-140 1.50 + 6 8.93 + 2 5.79 + 3 Ce-143 1.20 + 6 7.14 + 2 4.63 + 3 Pr-143. 1.20 + 6 7.14 + 2 4.63 + 3 Ce-144 9.20 + 5 5.48 + 2 3.55 + 3 Pr-144 1.20 + 6 7.14 + 2 4.63 + 3 Sr-91 9.20 + 5 5.48 + 2 3.55 + 3 y.91m Y-91 9.60 + 5 5.71 + 2 3.71 + 3 Zr-95 1.30 + 6 7.74 + 2 5.02 + 3 Nb-95m Nb-95 1.10 + 6 7.74 + 2 5.02 + 3 Zr-97 1.30 + 6 7.74 + 2 5.02 + 3 Nb-97m Nb-97 1.30 + 6 7.74 + 2 5.02 + 3 Ru-105 8.60 + 5 5.12 + 2 3.32 + 3 Rh-105m 8.60 + 5 5.12 + 2 3.32 + 3 Rh-105 5.50 + 5 3.27 + 2 2.12 + 3 Te-131 7.20 + 5 4.29 + 2 2.78 + 3 I-131 4.10 + 7 2.05 + 7 2.44 + 4 1.58 + 3 3.93 - 2 3.64 + 4 Xe-131m 6.51 + 5 6.51 + 5 3.88 + 2 2.51 + 5

1. 25 + 1 1.15 + 4 I-133 7.30 + 7 3.90 + 7 4.64 - 4 3.01 - 5 7.49 + 2 6.91 - 4 l

12A-11 'l

e.e a-er s r-TABII 12A.3-2 (Cont'd) Liquid ( } f) Gaseous Containment Reactor. Containment Source' Source Sump Coolant Airborne Waste Gas Activity Activity Concentration Concentration Concentration Concentration Isotooe (Ci) (Ci) (mci /ce) (mci /ce) (mci /ce) (mci /ce) Xe-133m 3.80 + 6 3.80 + 6 2.26 + 3 1.47 + 4 7.29 + 1 7.24 + 4 Xe-133 1.50 + 8 1.50 + 8 8.93 + 4 5.79 + 5 2.88 + 3 2.72 + 6 I-135 6.90 + 7 3.45 + 7 4.11 + 4 2.66 + 5 6.62 + 2 6.09 + 4 Xe-135m 4.20 + 7 4.20 + 7 2.50 + 4 1.62 + 5 8.06 + 2 1.77 + 6, 7.18 +.', ) Xe-135 2.90 + 7 2.90 + 7 1.73 + 4 1.12 + 5 5.57 + 2 Ba-141 1.30 + 6 7.74 + 2 5.02 + 3 La-141 1.30 + 6 7.74 + 2 5.02 + 3 Ce-141 1.40 + 6 8.33 + 2 5.41 + 3 NOTES: (1) Based on 100% noble gas core inventory, 50% halogen core inventory, and 1% of all others core inventory. I (2) Based on 100% noble gas core inventory and 25% halogen core inventory. \\ 3rh I 4 12A-12 l a -

12A.4 REVIEW OF AREAS REQUIRING ACCESS FOR POSTACCloENT OPERATIONS A vital area is defined as any area which will or may require occupancy to permit an operator to aid in the mitigation of or recover from an accid'ent. Vital areas for the Virgil C. Summer Nuclear Station are shown in Figures 12A.4-1 through 12A.4-7. Calculated exposure rates as a function of time after the accident are given in Table 12A.4-1. Vital area occupancy and access dose are summarized in Table 12A.4-2. Access routes to the vital areas are described in Table 12A.4-3. i 12A.4.1 AREA A: RHR/ SPRAY PUMP ROOMS AND COOLING UNITS i '~~ N Area "A" as identified on Figure 12A.4-1 is the location of the residual heat removal (RHR) pumps, reactor building spray pumps and the common pump room l23 cooling units. The reactor building spray pump is only required for short term cooling (2 hours). Failure of an RHR pump following an accident will result in a minimum safeguard condition and access to this area may be required to ensure that more than one pump is available for long term cooling of the reacter core. Under these circumstances, plant personnel say require access to this area for operations such as pump seal replacement or minor maintenance. Tasks such as these require that three individuals spend approximately 4 hours in the pump rooms or at the cooling units. p3 Sources of exposure in this area are the RHR and spray system piping in the j system train that is operating. This piping is located in the adjacent pump room and in the valve and piping area located above at elevation 397'0". Piping in the train requiring maintenance or repair is assumed to be flushed and drained. Access to this area is not required immediately since only long term operation need be considered. One day after the accident, the exposure rate is 230 mr/hr in the pump rooms and 576 mr/hr at the cooling units. The calculated dose to an individual for 4 hours of occupancy is 0.85 rem and 2.06 rem, respectively. Table 12A.4-2 shows that 4 hours occupancy in this area is possible prior to one day following the accident. I 12A-13 I. . i

The access route to area "A" is route "1" described in Table 12A.4-3. This access route will add a total of 0.02 rem to the worker dose if the task is started one day after the accident. 12A.4.2 AREA B: CHARGING /SI PUMP ROOMS Area "B" is the location of the charging / safety injection (SI) pumps and is identified on Figure 12A.4-2. Failure of one of these pumps following an accident will result in a minimum safeguards condition and access to this area may be required to ensure that all pumps are av=ilable for long term cooling of the reactor core. Under these circumstances, plant personnel may require access to this area for operations such as pump seal replacement or minor maintenance. Tasks such as these require that three individuals spend approxima:ely 4 hours in ' the pump rooms. i Sources of exposure in this area are from the charging /SI pump piping for the pumps that are optional and are located in the adjacent pump rooms. Piping in the pump room where maintenance or repair is required is assumed to be flushed and drained. Access to this area is not required immediately since only long term operation need be considered. Two days after the accident, the exposure rate is 630 mr/hr. The calculated dose of o'cupancy is 2.39 rem. Table 12A.4-2 c shows that 4 hours occupancy in this area is possible prior to two days following the accident. y j \\ The access routes to area "B" are routes "3' and "S" and are described in Table 12A.4-3. These access routes will add 0.13 rem and 0.05 rem to the dose if the task is started two days after the accident. 12A.4.3 AREA C: CHARGING /SI PUMP C AUXILIARIES LOCAL CONTROL PANEL f;3 Area "C" as identified on Figure 12A.4-2 is the location of charging / safety injection pump C auxiliaries local control panel. Failure of one of the l23 i charging /SI pumps will result in minimum safeguards condition and access to this area may be required for manual switching of the charging /SI pumps. This task would require that two workers spend approximately 2 minutes at the control panels. i 12A-14 i

~ The major source of exposure in this area is a 3 inch safety injection line located inside the shield labyrinth at the entrance to cubicles 88-23 and 88-24. A direct line of sight is possible from this source to the immediate vicinity of the pump C transfer switch. This line will not become a source of exposure until recirculation of containment sump liquid is initiated. Additional exposure in this area results from charging /SI piping in pump room 88-23. Access to this area could be required immediately after the accident. Access at 30 minutes is assumed in order to evaluate the worst case of containment sump liquid in the 3 inch safety injection line at the start of recirculation. Assuming that the workers are in a direct line of sight with the unshielded i safety injection line, the exposure rate in the area is 87.em/hr which results in an occupancy dose of 2.90 rem for the 2 minute time period. The access route to area "C" is route "7" described in Table 12A.4-3. This , access route will add a total of 1.39 rem to the worker dose if the task is started 30 minutes after the accident. 12A.4.4 AREA D: SPENT FUEL PIT HEAT EXCHANGER Area "D" is the location of the spent' fuel pit heat exchangers (see ~ Figure 12A.4-2). Access to this area is not required to aid in the mitigation of ) or recovery from an accident, but should conditions dictate, access may be needed l to service the heat exchanger to maintain cooling of the spent fuel. Under these l 23 circumstances, post-accident operations in this area require only long-term periodic surveillance. The exposure rate in this area following an accident is negligible since there are no post-accident sources of activity in the vicinity of the heat exchangers. This permits unlimited access (40 hours / week) in this area. The access route to area "D" La route "9" described in Table 12A.4-3. This access route will add a total of 0.02 rem to the worker dose if the task is started one day after the accident. 12A-15 1

12A.4.5 AREA E: RADVASTE GAS HANDLI.4G CONTROL PANELS Area,"E" as identified in Figure 12A.4-2 is the location of the radwaste gas tecombiner analyzer and control panels. Access to this area is not required following an accident since it is not planned to start-up the radwaste gas 23 handling system. If degassing of the primary coolant system becomes necessary following an accident, the operation will be accomplished by utilizing the reactor head vent system. 12A.4.6 AREA F: SPENT FUEL PIT CCOLING PL?!PS AND LOCAL CONTROL PAhTLS Area "F" as identified on Figure 12A.4-3 is the location of the spent fuel pit cooling pumps and local control panels. Access to this area is not required to aid in the mitigation of or recovery from an accident, but should conditions 3 dictate, access to this area may be needed in order to maintain cooling of the spent fuel. Under these circumstances, plant personnel may require access to this area for operations such as pump seal replacement or minor maintenance. Tasks such as these require that three individuals speed approximately 4 hours at the pumps. Dose contributors in this' area are the containment building and a 3 inch safety injection line located approximately 20 feet away above the shield slab at elev. 426'6". The time at which access to this area is required ia based on the j minimum time it takes to reach maximum spent fuel pool temperature with loss of both cooling pumps. This time is 12.5 hours. Eight hours after the accident, l the exposure rate is 1.16 rem /hr. The calculated dose to an individual for 4 1 hours of occupancy is 3.03 rem. The access route to area "F" is route "6" described in Table 11A.4-3. This access route will add a total of 0.11 rem to the worker dose if the task is started 8 hours after the accident. f 12A-16 I i -w --- m a

1 12A.4.7 AREA G: ENGINEERED SAFETY FEATURE MOTOR CONTROL CE.YTER Area "G" is the location of the Engineered Safety Feature (EST) Motor Control Center IDA2Y and is identified on Figure 12A.4-3. It is not expected that access to this area would be required since all ESF control functions are performed from the control room. However, access may be required in the unlikely event that a safety-related component loses remote control power. Should such a component lose remote centrol power and fail in the unsafe position, in conjunction with a simultaneous failure of its redundant counterpart, it may ee deemed necessary to gain access to this area for manual control of the component. This task would require that two workers spend approximately 2 to 5 minutes in this area. Dose contributors to this rea are spray system, safety injection system and chemical and volume contrr,1 system piping located below and adjacent to this Access to this area could be required immediately after the accident. area. Access at 30 minutes is assumed in order to evaluate the worst case which is the initiation of the recirculation of containment sump liquid in the spray and safety injection systems. The exposure rate in this area is 23 rem /hr resulting in calculated exposures to an individual of 0.77 rem and 1.92 rem for occupancy l23 times of 2 minutes and 5 minutes, respectively. The access route to area "G" is route "4" described in Table 12A.4-3. This access route will add a total of 0.26 rem to the worker dose if access is I y' required 30 minutes after the accident. 12A.4.8 AREA H: WASTE PROCESSING SYSTEM CONTROL PANEL Area "H" is the location of the waste processing system panel (see Figure 12A 4-3). The waste gas system is not intended r used for degassing the primary coolant system in post-accident conditions. ess to this area may be needed since the waste gas compressor are controlled from this panel. This task will required two persons to occupy this area for one minute. 12A-17 i-

Sources of exposure in this area are the contain=ent building, and a 2 inch CVCS line located approximately 10 feet away and above the 2 foot thick concrete shield slab at elevation 426'0". Immediately after the accident, the dose rate from these sources in areas "H" is 3.74 rem /hr. The calculated dose for the one minute occupancy time is 0.06 rem. The access route to area "H" is route "5" described in Table 12A.4-3. This route will add a total of 0.98 rem to the worker dose in this area for access }' immediately after the accident. 12A.4.9 AREA I: CHARGING / SAFETY INJECTION PUMP CC0 LING UNITS Area "I" is the location of the charging / safety injection pump rocm cooling units - and is identified on Figure 12A.4-4. Failure of one of these cooling units following an accident will result in a minimum safeguards condition and access to the area may be required to ensure that more th'n one of the charging / safety a injection pumps are available for the long. term cooling of the reactor core. Under these circumstances, plant personnel cay require accers to cne of the aress, for operations such as manual switchover, maintenance, or repair. Tasks such as these require that two persons spend five minutes at the cooling units for manual switchover, or three persons spend four hours for the maintenance or repair of a cooling unit. The major sources of exposure in this area are the charging / safety injection pump )@3 4 I' cubicle piping, the piping area immediately west of the cooling units on elevation 400'-0", and a 3-inch chemical and volume control system (CVCS) pipe located inside the room containing cooling units 1 and 2. Access to this area could be required immediately af ter the accident for manual realignment of valves for the cooling units. Access at the time of accident occurrence (i.e.g, 0 hr.) is assumed to evaluate the worst case of worker exposure. Prior to the installati of the shielding additions, the exposure rates in this m area varied for t' ' individual cooling units between 426 and 6260 rem /hr, which results in 5 minute occupancy doses of 33.5 to 522.7 rem, immediately after the accident. For the maintenance and repair activities after the accident, the~ 12A-13 I" 6

I

. ~. 3... exposure rates in the area vill vary between 20.3 and 284 rem /hr one day af ter the accident, and 5.86 to 84.0 rem /br five days af ter the accident. These dose rates will result in maintenance and repair occupancy doses of between 76.4 and 1070 rem one day after the accident, and between 23.2 and 333 rem five days after the accident. The access rout eto Area "I" is route "10" described in Table 12A.4-3. For the manual valve switchover procedure, the access route will add a total of 1.02 rem to the worker dose at the time of the accident (i.e., O hr. ). For the m'intenance and repair activities after the accident, the access route will contribute 0.02 rem one dry after the accident to the worker dose, and becomes 23 I negligible five days after the accident. The resultant dose levels in this area have been reduced to acceptable values by the addition of concrete and lead shielding around the charging / safety injection and CVCS piping located within the charging / safety injection pump cooling unit cubicle. The new configuration allows personnel access in accordance with the occupancy requirements of Table 12A.4-2 and the occupancy ' guidelines for vital access areas requiring infrequent occupancy as contained in YUREG-0737. ,] 12A.4.10 AREA J: ENGITLEEED SAFETY FEATURE SUBSTATlaN ' BUS AND MOTOR CONTE 0L CEFIER f< l \\/ Ares "J" is the location ci the engineered safety feature 480 volt unit substation bus IDB1 tud motce control center 10Y2Y (see Figure 12A.4-6). Occupancy in this area following an accident will be the same as explained for area "G". Dose contributors to tais area are the volume control tank (cubicle 63-02), and '.3 the valve gallery located in cubicle 63-03. Access to this area could be required immediately after the accident. With the assumption that :ero hour entry occurs, the exposure rate in this area will result in calculated exposures of 3.33 and 8.33 rem to an individual for the j occupancy periods of 2 and 5 minutes, respectively. However, the resultant dose i levels in'this area are reduced to acceptable levels quickly as shown in l i .i 12A-19 ( 5 l'

^ Table 12A.4-2, and the resultant integrated doses meet the dose requirements of 10CFR50, Appendix A, General Design Criteria 19 as outlined in NUREG-0737. 23 The access route to area "J" is route "14" described in Table 12A.4-3. This access route will add a total of 2.16 rem to the worker dose immediately after the accident. 12A.4.11 AREA K: HYDROGEN RECOMBI.M CONTROL AND POWER SUPPLY PANELS Area "K" as identified on Figure 12A.4-6 is the general location of the hydrogen recombiner control and power supply panels. Post-accident hydrogen formation in the reactor building may require operation of the hydrogen recombiner system. The system is started and controlled by operator action at the recombiner control ~ panel. This task requires that two workers spend 10 minutes in this area per hour over a 3 hour period. Dose contributors in this area are the personnel access hatch and a 3 inch chemical and volume control system pipe located below at elevation 450'6". Access to the control panels could be required shortly after an accident. The exposure rate at one hour after the accident in this area is 21.1 rem /hr. The calculated dos ~e to an individual in this area for 10 minutes of occupancy is 3.!2 rem. If occupancy is required at one day after the accident, the exposure rate is calculated to be 1.12 rem /hr which results in a 10 minute dose of l 0.19 rem. s The access route to area "K" is route "13" described in Table 12A.4-3. The calculated dose to an individual travelling this route is 3.23 rem I hour after the accident and 0.28 rem 1 day after the accident. I 12A.4.12 AREA L: HYDROGEN RECCMBINER CONTROL AND POWER SUPPLY PANELS Area "L", as identified on Figure 12A.4-6, is the general location of the hdyrogen recombiner control and power supply panels. Occupancy in this ares following an accident will be the same as explained for area "K". t 12A-20 I

Dose contributors in this area are the reactor building located approximately 40 feet away and a 10 inch spray line located below the 2 f t. concrete floor at elevation 436'-0" Access to the control panels could be required shortly after an accident. The exposure rate at one hour after the accident in this area is 1.5 rem /hr. The calculated dose to an individual in this area for 10 minutes of occupancy is 0.25 rem. If occupancy is required at one day after the accident, the exposure rate is calculated to be 16.0 mrem'/hr which results in a 10 minutes j dose of 0.003 rem. The access route to area "L" is route "11" described in Table 12A.4-3. This l 23 ,~ access route wil add a total of 0.76 rem to the worker dese 1 hour af ter the accident and 0.02 rem 1 day after the accident. 12A.4.13 AREA M: REACTOR BUILDING ATMOSPHERE SAMPLE COLLECTION POINT AND l 23 In~DROGEN GAS ANALY.R J Area "M" as identified in Figure 12A.4-6 is the location where a reactor building l 23 air sample will be collected following an accident. It is also the location of the reactor building atmosphere hydrogen analy:er. The hydrogen analyzers are designed to continuously monitor the reactor building atmosphere following an accideat. Access to the analyzer is not required since they are redundant (the other analyzer is located at elevation 4'63'-0" of the Auxiliary Building between - column lines L, M, 7.7 and the reactor building) and all necessary functions are l C' ' controlled remotely from the Control Room. However, access to this area is required to collect a reactor building air sample. The time required to collect the air sample has been estimated to be 10 minutes. Dose contributors to this area are the reactor building located approximately 10 ft. away, 3/8" gas sample lines for the sample cylinder and the hydrogen analyzer, and the gas sample cylinder itself. Access to this area could be required shortly after the accident. Access at 30 minutes is assumed. The exposure rate-in this area 30 minutes after the accident is 12.9 rea/hr. This results in a calculated dose of 2.15 rem for 10 minutes of occupancy. 23 i 12A-21 I

The access route to area "M" is route "12" described in Table 12A.4-3. This access rour.e will add a total of 1.14 rem to the worker dose for access to and from this area 30 minutes after the accident. 12A.4.14 AREA N: TECHNICAL SUPPORT CENTER Area "N" as identified in Figure 12A.4-7 is the location of the technical support j center. The cechnical support center is located adjacent to the control room on elevation 463'-0" of the control building. Continuous occupancy is required in this area following an accident. A major direct dose contributor to this aea is the reactor building. The direct radiation from the reactor building will result.. in exposure rates in the c ntrol room of approximately 2.7 mrem /hr immediately after the accident, quickly droppina off to 0.6 mrem /hr 1 hour after the accident and to near background levels shortly thereafter. A complete analysis of post-accident radiation' doses in the control room and technical support center is presented in Section 15.4.1. Dese contributors include (1) direct radiation from the reactor building, (2) direct radiation from the radioactive cloud outside the control room which results from reactor building leakage, and (3) exposure to radioactive materials which may leak into the technical support center. The post-accident integrated doses (30 days) to persons in the technical support center area 26.6 rem inhalation dose to the thyroid, 4.87 rem whole body gama dose, and 21.6 rem beta skin dose. The -23 l majority of this dcse comes within the first few days of the accident. 12A.4.15 AREA 0: CONTROL ROCM Area "0" as identified in ligure 12A.4-7 is the location of the control room. Continuous occupancy is required in this area following an accident. A major direct dose contributor to this trea is the reactor building. The direct radiation from the reactor building will result in exposure rates in the control room of approximately 2.7 mrem /hr immediately after the accident, quickly ueopping off to 0.6 mrem /hr 1 hour af ter the accident and to near background levels shortly thereafter. 12A-22 i h

A complete analysis of post-accident radiation doses in the control room is presented in Section 15.4.1. Dose contributors include (1) direct radiation from -the reactor building, (2) direct radiation from the radioactive cloud outside the control room which results from reactor building leakage, and (3) exposure to radioactive materials which may leak into the control room. The post-accident integrated doses (30 days) to operators in the control room are 26.6 res 23 inhalation dose to the thyroid, 4.87 rem whole body gamma dose, and 21.6 rem beta skin dose. The majority of this dose comes within the first few days of the accident. 12A.4.16 AREA P: SAMPII ROOM Area "P" as identified in Figure 12A.4-7 is the location of the sample room. Access to this area is required to ubtain the primary system liquid and gas samples following an accident for assessing the extent of fuel damage and to evaluate the primary coolant chemistry. The samples shall consist of fluids ~ taken from the primary coolant hot leg, the pressurizer liquid and steam spaces, and residual heat removal loop. These samples are collected by a pre-defined-procedure in sample vessels at a sink located in the sample room. 23 The post-accident sampling system shall provide a means for the collection of post-accident samples in the sample room and will be designed to maintain the [# - _ resultant dose levels in the area at acceptable values. This will be achieved by IIs/ a combination of radiation shielding and sample collection procedures. The radiation shielding design and personnel exposure estimates shall.be provided at a later date upon completion of their design review. The access route to area "P" is route "15" described in Table 12A.4-3. 12A.4.17 AREA Q: RADI0 CHEMISTRY I.AB l Area "Q" as identified in Figure 12A.4-7 is th,e location of the radiochemistry 23 la bo ra to ry. Access to this area is required for the radiological and chemical analyses of the post-accident samples following their transfer to this location. i l l ? j 12A-23 6 j i

Since the existing radiation shield design and sample analysis procedures in this area were designed for 1% failed fuel sources, the post-accident sampling system has been designed to reduce the activity concentration of the samples to a level that will result in dose rates within the range of values normally associated with the 1% failed fuel design criteria. The post-accident sampling system will therefore allow personnel access in the radiochemistry laboratory in concurrence with the occupancy requirements of Tables 12A.4-2 and 12A.4-4, and the resultant integrated doses shall meet the dose requirements outlined in NUREG-0737. The access route to area "Q" is route "15" as described in Table 12A.4-3. 12A.4.18 AREA R: COUNT ROOM Area "R" as identified in Figure 12A.4-7 is the location of the count room. Access to this area is required for the radiologic'al analysis of the post-accident samples prepared in the radiochemistry laboratory. The post-accident sampling system design criteria to provide post-accident sources with a radioisotope activity level comparable to that of the 1% failed fuel design criteria results in insignificant increases in personnel exposure above those received under normal operating conditions. The need for additional 23 shielding has been reduced to making provisions for the availabiIity of temporary shielding to be used for local hot spots, when and if such are found by l personnel. Therefore, the personnel access in the count room shall be in s accordance with the occupancy requirements of Tables 12A.4-2 and 12A.4-4, and the resultant integrated doses shall meet the dose requirements outlined in NUREG-0737. The access route to area "R" is route "15" as described in Table 12A.4-3. 12A.4.19 INTERMEDIATE BUII. DING The intermediate building was reviewed to identify post-accident radiation sources, access requirements, and the location of safety related equipment. It 23 was found that the only area of the intermediate building where exposure to 12A-24 I

, an sr. ,xms. n post-accident radiation sources is possible is at the 412'-0" elevation adjacent to the east and west penetration access areas. At this elevation, residual heat removal (RHR), safety injection (SI), and chemical and volume control system _(CVCS) piping containing post-accident sources is located in the east and west j penetration access areas. The areas adjacent to the penetration access areas contains component cooling pumps, motor driven emergency feedwater pumps, and 1 miscellaneous safety related valves and instrumentation which may require access. c All other areas of the intermediate building are not exposed to -post-accident sources and receive a negligible increase in dose. I-1 The intermediate building at elevation 412'-0" is shielded from the radioactive 3,.~. piping located in the penetration access areas by a 2 foot concrete wall. This shield wall reduces the dose rates in this general area of the intermediate building to a level which permits limited access approximately 15 minutes immediately af ter the accident, 3 hours of access 8 hours following the accident,1 and 20 hours of access 1 day after the accident. 23 In the area between the east and west penetration access areas, several pipes I containing post-accident sources were found to be located above the sides of a pipe chase located at elevation 422'-3". This allowed direct streaming of a l 5 12-inch RER pipe to the intermediate building floor elevation 412'-0". The resultant dose levels in this area of the intermediate building have been reduced to acceptab'e values by the modification of the pipe chas'e as follows:

]

,/ (1) extension of the pipe chase side above the 12" RER line, (2) addition of 6" concrete shielding to the'e.41 sting i foot concrete shieldinn, (3) relocation of access ladder to prevent streaming through concrete cutout. The new configuratica allows personnel access in accordance with the occupancy i requirements of Table 12A.4-2, and the resultant integrated doses meet the dose requirements of 10CFR50, Appendix A, General Design Criteria 19 as outlined in-NUREG-0737, 12A.4.20 EMERCENCY OPERATIONS FACII.ITY P The radiation shielding design and personnel exposure doses shall be pro-23 vided at a later date upon completion of the emergency operations facility design review. This facility will be designed to maintain the resultant dose levels in the area at acceptable levels. 12A-25 i'

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~ % 'f = } j E I F k TAtl E 3 2A.4-2 (Ibest lu .8) VITAL. ARM kADI ATinte las5E SterlARY 6 ie - pre utsasse y Acs.ea.s thse.e Ten Total Total Occupaucy Time Alter Bhase Aeul tree Area sk se those Vital Area Seguirements Acc lilen t (Ree/Fermon) Jeger soni Qcefretsum) {M.ne_e _tye} C..ollag shal t ) ) permana far I liour i.4. 4 0.47 64.9 194.6 (ttelutenance ar Repair) 4 1.ouse i 8 Iwauen

9. nli 0.38 9.19 27.6 Jay I. II 0.02 8.33 5.98 5 daya
n. 30 (I)

O. 30 n.90 to days u.22 (4) 0.22 u.e4 30 days 0.us (1) 0. 81 6 c.24 ,90 days 0.02 (t) 89. 0 2 U. Den J Laglueused Safety 2 permane for 0 3.11 - 8.)) 2.46 5.49 - 10.5 18.0 - 21.11 Featusu Sul.m t e t lan 2-5 minutes [ s es muJ natur 1/2 8.our 2.21 - 5.2e 3.64 1.a5 - 6.92 7.7p - 13.nt S. Centrol Center b I lueur 1.41 - 1.58 1.20 2.6) - 4.73

5. 26 - 9. %

M 8 8.our u.17 - 0.4 ) 0.24 0.48 - 0.67 H.N2 - 8.34 23 8 day 0.004 - ts.ul U.trui 0.ture - 0.015 p.u2 - 0.01 g layJe ugees Nece leiner 2 persons for to i Inn r 1.52 1.20 4.72 9.44 t'n.itsol auJ Peuer minutes 1.or I.our S..pply rauels over a 3 insur 2 lueurs 2.82 0.42 2.54 5.us ceeled 3 leuurs 1.50

0. })

3.M) 3.66 4 8.ours 1.57 U.26 8.4) 2.86 24 Iwours 0.49 0.05

81. 2 0 0.4u 25 twaars 0.15 0.09 0.26
11. 5 2 26 laours
55. 8 7 0.09 (1.26 0.52 27 leossra 0.16 8. 83 4 0.25 0.50 l

= .s 1 Ang l* 8 2A.4-2 (ta t inue4l VITAL ARFA RADI Atlost lAGE StesukY Occupancy Atra se in.ne 1m 1atal Total 4hcipancy Time After thener And Fr us Area these Ime V8tal Area Se.tu i s tocen t s AsclJens (tce/rere d (peo/Peseeel graf ry seen). (Pten py) 1. tryJrugen setembiner 2 persone sur lo I B.our 0.26 0.76 1.02 2.84 thea e eI anJ ruwe r eleu.t ea yer 8=>ur Surely ramals ever a ) 8.our 2 I.oure 0.12 0.52 0.64 1.28 l.ealuJ 1l1.uur e 0.u7 c.)$ 0.45 0.9o 4 8.uura 0.05 O.30 al.15 O.70 24 lioure 0.0H27 0.02 0.0227 0.tMS4 25 lemurs 0.tW126 0.0896 0.0222 0.0444 26 8.ouse 0.0025 0.088 0.020% 0.tM I 2 7 8.ou r a 0.0023 0.017 0.039) 0.0586 [ tl Bed *' tar BullJ8ag Air 2 perso.in for 0 4.22 1.17 5.59 11.2 g 54 ple cullection 10 minutes refus 1/2 hour 2.15 1.14 1.29 6.58 t2 I bour 4.25 0.82 2.0% 4.30 8 houta

88. 1 I 0.I4 0.25 O.Su 3 J.sy 0.01 0.02 0.05 0.30 Thyralda 76,6 N

in hn t e a l Si.pleos a Cuntlenn.us 10 days 4.87 cd==a = ce.,t., 21.6 meta ,3 0 c i r..I y..u re..et le uu. 20 Jay. T8.y e a lJ = 26.6 4.87 ca = 21.6

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4 e i i TABLE 12A.4-3 ACCESS ROUTES TO VITAL AREAS Access Route Description 1. From Control Building (C.B.), 463' elev., down either 3 stairway to 412' elev. through 412' elev. to north corridor. From C.B., 412' elevation, enter Auxiliary Building (A.B.) at stairway tower 1, down stairway to 374' clev., through hallways 74-01 and 74-09 to rooms 74-16 and 74-17. For cooling units, ladder up from hallway 74-09 to 385' elev. to rooms 85-01 and 85-02. 2. From C.B., 463' elev., down e.ither stairway to 412' elev., through 412' elev. to north corridor. From C.B., 412' elev. enter A.B. at hallway 12-11, through hallways 12-11 and 12-09 to stairway tower 2, down stairway to 397' elev. and through room 97-01 to stairs at column lines M and 9.5. Down stairs to 388' elev. to room 88-13S. ^ 3. Same as "-2" but through room 88-13S to room 88-25. ,u l 4. From C.B., 463' elev., down either stairway to 412' elev., s_. through 412' elev. to north corridor. From C.B., 412' elev., enter A.B. at hallway 12-11, north through hallway 12-11 to room 12-28. 5. Same as "4" but continues through hallway 12-11 to room 12-15. 6. Same as "4" but north through hallway 12-11 and east through hallway 12-11 N to room 12-18. l 4 12A-33 i F-

TABLE 12A.4-3 (Cont'd) Access Route Description 7. From C.B., 463' elev., down either stairway to 412' elev., i through 412' elev. to north corridor. From C.B., 412' elev., enter A.B. at hallway 12-11, north through hsilway 12-11 and } east through hallway 12-11 N to stairway tower 3. Down stairway to 338' elev. to room 88-13 NE. I 8. Same as "7" but through room 88-13 NE to rooms 88-23 and 88-24. 9. Same as "7" but through room 38-13 NE to room 88-13N. 10. Same as "7" but continues through room 88-13 NE to room 88-13 N. Ladder up to 400' elev. 11. From C.B., 463' elev., down either stairway to 412' elev., through 412' elev. to north corridor. From C.B., 412' elev., enter A.B. at hallway 12-11, north through hallway 12-11 and east through hallway 12-11 N to stairway tower 3. Up stairway to 463' elev. to room 63-09 at column line 7.7. i 12. Same as "11" but from room 63-09 enter Fuel Building (F.B.) 23 I 463' elev., through room 63-01S to column lines P.4-P.9 and 3.3-4.0. 13. From C.B., 463' elev., down either stairway to 412' elev. through 412' elev. to north corridor. From C.B., 412' elev. enter A.B. at hallway 12-11, through hallways 12-11 and 10-09 to stairway tower 2. Up stairway to 463' elev., through hallway 63-04 and south through hallway 63-16 to room 63-19. 12A-34 I

TABII 12A.4-3 (Cont'd) Access Route Description 14. Same as "13" but through room 63-09 to room 63-01. 15. From C.S., 463' elev., down either stairway to 412' elev. to i rooms 12-09, 12-10 and 12-11. 4 . ( e 12A-35

F TABLE 12A.4-4 LIOUID A'ID GASEOUS SAMPLE COLLECTION AND PREPARATION 4 WORKER LOCATION CODES (1) At Sampin Panni Control Board'. (2) Handling Diluted Sample (Shielded). (3) Handling Diluted Sample (Unshielded). (4) Sa=ple Transport in Shielded Container. A. ISOTOPIC ANALYSIS OF PRIMARY CdOLA}rr. ~ Locations: Sample Room, Count Room. WORKER TASK TIME LOCATIOT 1. Sample Purge, Collection, Dilution and 180 sec. 1 System Flush. 2. Remove Diluted Sample from System. 30 sec. 3 I 3. Transport to Count Room 30 sec. 4-4. Count Sample (Count Room). 180 sec. 2 i i B. BORON ANALYSIS 3 Locations: Sample Room and Radiochemistry Lab. e 1. Read pH vs Na Concentration Curve on 30 sec. 1 l'; Control Pancl.- i ~ Alternate Method:

1. A Syringe.lml of Diluted Sacple to vial.

20 sec. 3-I. 2.A Transp rt Simple to Chemistry Lab. 30 sec. 2' 3.A Pipet 5 ul Sample into Atomic 120 sec. 3 and 2 Absorption Spectrometer (Repeat twice). C. PRIMARY GAS ACTIVITT ANALYSIS (Same as A above). j i f 12A-36a

D. H9 ANALYSIS WORKER TASK TIME LOCATION 1. Draw Diluted Gas into Syringe 20 sec. 3 (Twice).025 cc. l 2. Inject Gas into Chro=atograph (twice). 10 sec. 3 NOTE: (a) Time operator spends at panel during sample purge, collection, dilution and system flush is not indicative j of total elapsed time for operation, 20 minutes. It is 8 the ti:ne the operator must spend in the area. (b) A.1 time, 180 sec. is the sa:e for B, C, and D sample ) collection, which are performed concurrently from sample ,L control panel. i E. CONTAINMENT GAS ACTIVITY Location: Intermediate Building, Elev. 463' Count Room. 1. Sample Collection. 120 sec. 1 2. Sample Removal. 30 sec. 3 3. Transport. 120 sec. 2 I 4. Sample Count. 180 sec. 2 F. CONTAINMENT HYDROGEN ACTIVITY l (Same as E above, Step 1, only read H2 at remote 120 sec. readout on control panel.) E { l i,- 12A-36b s I L

= - -. _ _... _... 12A.5 REVIEW OF RADIATION QUALIFICATION OF SAFETY RELATED EQUIPMENT Radiation qualification of safety related equipment is provided in the SCE6G report addressing the requirements of NUREG-0588 (refer to SCE6G letter dated 23 January 15, 1981). s 3.) \\ w ~ E n l l

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~4 12A.6 eRITERENCES I' 1. E. D. Arnold and B. F. Maskervitz, "SDC - A Shield Design Calculation Code for Fuel Mandling Facilities," ORNL-3041, March 1966. i \\ 2. C. M. Lederer, J. M. Hollander, and J. Perlman, " Table of Isotopes," Sixth Edition, John Wiley and Sons, Inc., 1967. 1 3. A. Tobias, " Data for the Calculation of Gamma Radiation Spectra and Beta Heating frora Fission Products (Revision 3), RD/B/M2669, June 1973. ,' T { 4. Regulitory Guide 1.4, Revision 2 (6/74). 5. Regulatory Guide 1.7, Revision 2 (11/78). 6. Source Term Data for Westinghouse Pressurized Water Reactors,'WCAP-3253 . 't, it (May 1974). \\v s s M. w s' .l g P f ', ~ YI l. u., = h a Q -W q. e \\ 1 3*

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