ML20059F047
| ML20059F047 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/31/1993 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20059F040 | List: |
| References | |
| NUDOCS 9311040103 | |
| Download: ML20059F047 (100) | |
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1 ENCLOSURE 1 r
PDMS SAR AMENDMENT 18 i
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. AMENDMENT 18 - AUGUST 1993 l
CHAPTER 6 TABLE OF CONTENTS (Cont'd)
.i SECTION TITLE PAGE 6.3.36 CONTROL ROD DRIVE SYSTEM 6.3-13 6.3.37 MISCELLANEOUS INSTRUMENTATION SYSTEM 6.3-14 6.3.38 CONDENSER AIR EXTRACTION FILTRATION SYSTEM 6.3-15 6.3.39 SEAL OIL SYSTEM - GENERATOR SYSTEM 6.3-15 6.3.40 TEMPORARY NUCLEAR SERVICES CLOSED COOLING 6.3-15 SYSTEM 6.3.41 DELETED 6.3-15 I
6.3.42 DELETED 6.3-15 6.3.43 RIVER WATER PUMP HOUSE HEATING AND 6.3-15 VENTILATION 6.3.44 CIRCULATION WATER PUMP HOUSE HEATING &
6.3-16 VENTILATION 6.3.45 FIRE PUMP HOUSE HEATING AND VENTILATION 6.3-16 SYSTEM 6.3.46 COAGULATOR BUILDING HEATING AND 6.3-16 l
VENTILATION SYSTEM 6.3.47 CHLORINATOR HOUSB HEATING AND VENTILATION 6.3-16
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SYSTEM 6.3.48 DELETED 6.3-16 6.3.49 TURBINE BUILDING HEAUNG AND VENTILATION 6.3-16 SYSTEM 6.3.50 EARTHQUAKE DETECTION SYSTEM 6.3-17 j
6.3.51 REACTOR COOLANT PUMPS MOTOR OIL DRAIN 6.3-17 SYSTEM j
TC-xiii AMENDMENT 18 - AUGUST 1993
CHAPTER 6 TABLE OF CONTENTS (Cont'd) l l
PAGE SECTION ILL12 6.3-17 6.3.52 DEFUEUNG TEST ASSEMBLY 6.3-17 GRAY AND WHITE DIESELS SYSTEM 6.3.53 6.3-17 6.3.54 DIESEL GENERATORS CHEMICAL LABORATORY TRAIL 191 EXHAUST SYSTEM 6.3-18 6.3.55 6.3-18 6.3.56 POLAR CRANE 6.4-1 6.4 DELETED 6.5-1 6.5 SYSTEM REFERENCES AMENDMENT 18 - AUGUST 1993 TC-xiv
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CHAPTER 5 TABLE OF CONTENTS (Cont'd) l LIST OF TABLES TABLE NO.
TITLE PAGE 5.1-1 BASELINE RADIOLOGICAL CRITERIA - REACTOR 5.1 BUILDING 5.1-2 BASELINE RADIOLOGICAL CRITERIA - AFHB 5.1-6 5.2-1 SPECIFIC DECONTAMINATION GOALS - REACTOR 5.2-3 BUILDING l
5.2-2 SPECIFIC DECONTAMINATION GOALS - AFHB 5.2-4 t
5.2-3 SPECIFIC DECONTAMINATION GOALS - OTHER 5.2-10 BUILDINGS 5.3-1 PDMS RADIOLOGICAL CONDITIONS - REACTOR 5.3-3 BUILDING 5.3-2 PDMS RADIOLOGICAL CONDITIONS - AFHB 5.3-4 5.3-3 PDMS RADIOLOGICAL CONDITIONS - OTHER 5.3-10 BUILDINGS 5.3-4 SURFACE CONTAMINATION - REACTOR BUILDING 5.3-11 5.3-5 SURFACE CONTAMINATION - AFHB 5.3-12 l_
5.3-6 SURFACE CONTAMINATION - OTHER BUILDINGS 5.3-21 j'
1 l
l iv AMENDMENT 18 - AUGUST 1993
l 5.1 GENERE DECONTAMINATION ACTIVITIES The decontamination of TMI-2 was accomplished in two phases. The initial phase improved the rar'Jological conditions in the facility such that the dose rates were acceptably low to permit the necessary accident cleanu_p activities. The second phase was a decontamination program initiated for the purpose of systematically improving radiological conditions in the plant regardless of whether access was required for cleanup activities.
In order to establish goals for the TMI-2 decontamination program, decontamination criteria were established for the RB, AFHB, and specific portions of other buildings, whem relevant.
i' The primary consideration in establishing the criteria for the initial phase was the anticipated need for personnel access during the cleanup and post-cleanup timeframe. Table 5.1-1 presents the Baseline Radiological Criteria for the RB and Table 5.1-2 provides the Baseline Radiological Criteria for the AFHB.
The general decontamination criteria for piping systems, equipment, and components were based solely on their contribution to area dose rates. It should be emphasized that these criteria were intended as guidelines rather than absolute criteria. The guidelines wem used in conjunction with common sense and good radiological practices.
5.1.1 GENERAL DECONTAMINATION OBJECTIVES The general decontamination program objectives were assigned primarily by area. The general objectives established for each area were based on initial contamination levels, the need for personnel access, and the possibility of release of radioactivity to the environment.
The facility was categorized into the following areas:
a.
Reactor Building 1.
Reactor Building elevation 282'
~
2.
Reactor Building elevations 305' and 347' 3.
Reactor Building D-Rings 4.
Refueling Canal b.
Auxiliary and Fuel Handling Buildings 1.
Auxiliary Building Cubicles (total of 99) 2.
Fuel Handling Building Cubicles (total of 37) c.
Other Buildings 1.
Diesel Generator Building (elevation 281')
2.
Service Building (elevation 281', Tendon Access Gallery) i 5.1-1 AMENDMENT 18 - AUGUST 1993
+
j
-l of the RV and the refueling canal has increased the dose rates in the refueling canal such that I
the PDMS general area dose rate goal had to be increased to 100 mR/hr.-
'5.1.3 AUXILIARY AND FUEL HANDLING BUILDINGS 5.1.3.1 Auxiliary Building The Auxiliary Building was categorized into 99 separate cubicles, which accounted for l
essentially all of the walls, floors, and overhead amas in the building.
The general decontamination objective for the contaminated cubicles was to suppon ongoing cleanup activities. The Baseline Radiological Criteria referenced in Table 5.1-2 were applied to each Auxiliary Building cubicle as a guideline for the decontamination efforts.
5.1.3.2 Fuel Handling Building t
i The Fuel Handling Building was categorized into 37 separate areas or cubicles which accounted l
for essentially all of the walls, floors, and overhead areas in the building. The general decontamination objectives for the contaminated areas within the Fuel Handling Building were established to support ongoing cleanup activities and to stabilize localized contamination. As in the Auxiliary Building, the Baseline Radiological Criteria referenced in Table 5.1-2 were applied to each Fuel Handling Building cubicle for use as guideline for the programmatic decontamination effort.
5 5.1.4 OTHER BUILDINGS 5.1.4.1 Service Building (Elevation 281', Tendon Access Gallery) i The general decontamination objective in the Service Building was to identify hot spots and remove or shield contamination.
One specific objective was the partial removal of the contaminated cork seal material from a building constniction joint.
5.1.4.2 Service Building (Elevation 305')
The general decontamination objective in the Service Building (elevation 305') was to identify hot spots and remove or shield contamination.
5.1.4,3 Control Building Area (M-20 Area, M-20 Area Sump)
The general decontamination objective in this portion of the Control Building Area was to identify hot spots and remove or shield contamination.
5.1-3 AMENDMENT 18 - AUGUST 1993 1
TABLE 5.2-2 t
- SPECIFIC DECONTAMINATION GOAL.S - AFHB SPECIFIC DECONTAMINATION GOALS GENERALAREA SURFACE CONTAMINATION f
CUBICLE DOSE RATE
< 7'/ Overheads 2
NUMBER AREA DESCRIPTION (mR/hr)
(dom /100 cm )
AX001 RB Emerg. Cooling Booster Pumps Area 2.5
< 1,000/< 10,000 AX002 Access Corridor 2.5
< 1,000/_< 10,000 AX002a N Piping System 2.5
< 1,000/< 10,000 2
AX003 Access Area 2.5_
< 1,000/ < 10,000 AX004 Seal Injection Valve Rm
< 1000
< 50,000/< 50,000 AX005 MUP Pump IC Rm
< 500
< 50,000/< 50,000 l
AX006 MUP Pump 1B Rm
< 503
< 50,000/< 50,000 l
AX007 MUP Pump 1A Rm
< 500
< 50,000/< 50,000 l
AX008 Spent Resin Storage Tank 1B Rm
< 500 "AS IS" AX009 Spent Resin Stomge Tank 1A Rm
< 500 "AS IS" AX010 Spent Resin Transfer Pump Rm
< 500 "AS IS" AX011 Aux Bldg Sump Tank Pumps and Valve
< 50
< 5,000/ < 50,000 I
Room AX012 Aux Bldg Sump and Tank Rm
< 50
< 5,000/< 50,000 l
AX013 Evap Cond Tanks, Pumps and Demins Rm < 500
< 1,000/< 10,000 l
AX014 RC Evaporator Rm
< 500
< 50,000/< 50,000 AX015a Cleanup Filters Rm
< 500
< 50,000/< 50,000 l
AX015b Cleanup After Filters Rm
< 500
< 50,000/< 50,000 AX016 Cleanup Demineralizer 2A Rm
< 500
< 50,000/< 50,000 AX017 Cleanup Demineralizer 2B Rm
< 500
< 50,000/< 50,000 AX018 Waste Transfer Pumps Rm
< 500
< 50,000/ < 50,000 AX019 Waste Disposal Liquid Valve Rm
< 500
< 50,000/< 50,000 l
AX020 RC Bleed Holdup Tanks 1B and 1C Rm
< 500
< 50,000/< 50,000 AX021 RC Bleed Holdup Tank 1 A Rm
< 500
< 50,000/< 50,000 J
5.2-4 AMENDMENT 18 - AUGUST 1993 -
1
I TABLE L2-2 (Cont'd)-
)
SPECIFIC DECONTAMINATION GOALS - AFHB 1
SPECIFIC DECONTAMINATION GOALS l
GENERALAREA SURFACE CONTAMINATION CUBICLE DOSE RATE
< 7'/ Overheads NUMBER AREA DESCRWITON (mR/hr)
(dpm/100 cm )
2 AX022 North Stairwell 2.5
< 1,000/ < 10,000 AX023 Elevator Shaft 10
< 50,000/< N/A AX024 Aux Bldg Sump Filters Rm
< 500
< 50,000/ < 50,000' AX025 Area Between Service, Control, and RB
< 500
< 1,000/< 10,000 AX026 Seal Injection Filters Rm
< 500
< 50,000/< 50,000 l
AX027 South Stairwell 2.5
< 1,000/< 10,000 AX101 Radwaste Disposal Control Panel Area 2.5
< 1,000/< 10,000 AX102 RB Sump Pumps Filters Rm
< 1000
< 50,000/< 50,000 AX103 Motor Control Center 2-11EB Rm 2.5
< 1,000/ < 10,000 AX104 Motor Control Center 2-21EB Rm 2.5
< 1,000/ < 10,000 -
AX105 Substation 2-11E Rm 2.5
< 1,000/ < 10,000 -
AX106 Substation 2-21E Rm 2.5
< 1,000/< 10,000 i
AX107 Motor Control Center 2-11EA Rm 2.5
< 1,000/< 10,000 AX108 Motor Control Center 2-21EA Rm 2.5
< 1,000/< 10,000 AX109 Nuclear Services Coolers and Pumps Area <
2.5
< 1,000/< 10,000 AX110 Intermediate Coolers Area 2.5
< 1,000/< 10,000 l
AX111 Intermed Cooling Pumps and Filters Rm
< 50
< 1,000/< 10,000 l
AX112 Seal Return Coolers and Filter Rm
< 1000
< 50,000/< 50,000 AX113 Waste Gas Analyzer Rm
< 50
< 50,000/< 50,000 AX114 MUP Deminemlizer 1 A Rm "AS IS" "AS IS" AX115 MUP Demineralizer IB Rm "AS IS"
" AS IS".
AX116 Makeup Tank Rm
< 500
< 50,000/< 50,000 AX117 MUP Filters Rm
< 1000 "AS IS" AX118 Spent Fuel Coolers and Pumps Area 2.5
< 1,000/< 10,000 1
r 5.2-5 AMENDMENT 18 - AUGUST 1993 j
TABLE 5.2-2 (Cont'd)
SPECIFIC DECONTAMINATION GOALS - AFHB SPECIFIC DECONTAMINATION GOALS GENERAL AREA SURFACE CONTAMINATION CUBICLE DOSE RATE
< 7'/ Overheads 2
NUMBER AREA DESCRIPTION (mR/hr)
(dom /100 cm )
AX211 Fuel Handling Bldg Exhaust Unit A 50 N/A AX212 Decay Heat Surge Tk and Substation Area <
2.5
< 1,000/< 10,000 AX213 Unit Substations and Access Area 2.5
< 1,000/ < 10,000 AX214 Decon Facility 2.5
< 1,000/ < 10,000 AX215 Fuel Handling Bldg Supply Unit 2.5 N/A AX216 Aux Bldg Supply Unit 2.5 N/A AX217 Access Area 2.5
< 1,000/ < 10,000 AX218 Concentrated Waste Storage Tank Rm
< 500
< 50,000/ < 50,000 AX219 Inst Racks and Atmospheric Monitor Area <
2.5
< 1,000/ < 10,000 AX220 Caustic Liquids Mixing Area
< 500
< 1,000/< 10,000 7
AX221 Caustic Liquids Mixing Area Corridor
< 500
< 1,000/ < 10,000 AX222 South Stairwell 2.5
< 1,000/ < 10,000 AX223 Air Handling Units General Area 2.5
< 5,000/ < 10,000 AX301 Elevator Shaft and Elevator Machine Rm 2.5
< 1,000/ < 10,000 AX302 North Stairwell 2.5
< 1,000/ < 10,000 i
AX303 Elevator and Stairwell Access 2.5
< 1,000/< 10,000 I
AX304 Aux. Bldg. Exhaust Fan #8 2.5
< 1,000/ < 10,000 AX305 Fuel Handling Bldg. Exhaust Fan #10 2.5
< 1,000/ < 10,000 AX401 Roof 2.5
< 1,000/ N/A AX402 Cooling Water Surge Tanks Rm
< 500
< 50,000/< 50,000 AX403 Damper Rm
< 500
< 50,000/ < 50,000 AX501 RB Spray Pump 1 A Rm 25
< 5,000/ < 50,000 AX502 RB Spray Pump 1r, Rm 25 "AS IS" AX503 Decay Heat Remov Clr and Pump 1 A Rm <
25
< 50,000/< 50,000 AX504 Decay Heat Remov Clr and Pump 1B Rm 25
< 50,000/< 50,000 FH001 Makeup Suction Valve Rm
< 500
< 50,000/ < 50,000 FH002 Access Corridor 2.5
< 1,000/ < 10,000 5.2-7 AMENDMENT 18 - AUGUST 1993
TABLE 5.2-2 (Cont'd)
SPECIFIC DECONTAMINATION GOALS - AFHB SPECIFIC DECONTAMINATION GOALS GENERAL AREA SURFACE CONTAMINATION CUBICLE DOSE RATE
< 7'/ Overheads NUMBER AREA DESCRIPTION (mR/hr)
(dpm/100 cmh FH003a Makeup Discharge Valve Rm
< 1000
< 50,000/ < 100,000 FH003b Makeup Discharge Valve Rm
< 1000
< 50,000/ < 100,000 FH004 Westinghouse Valve Rm
< 500
< 50,000/< 50,000 FH005 Mini Decay Heat Vault
< 500
< 50,000/< 50,000 FH006 Decay Heat Service Coolers Area
< 500
< 1,000/< 10,000 FH007 Neutrl and Recl Boric Acid Access Area
< 500
< 1,000/< 10,000 FH008 Neutralizer Tanks Pumps Rm
< 500
< 50,000/< 50,000 FH009 Neutralizer Tanks Rm
< 500
< 50,000/< 50,000 FH010 Reclaimed Boric Acid Tank Rm
< 500
< 50,000/< 50,000 FH011 Reclaimed Boric Acid Pump Rm
< 500
< 50,000/< 50,000 FH012 Neutralizer Tanks Filters Rm
< 500
< 50,000/< 50,000 FH013 Oil Drum Storage Area
< 500
< 1,000/< 10,000 FH014 Annulus
< 500
< 50,000/ < 50,000 -
FH101 MUP Valve Rm
< 500
< 50,000/< 50,000 FH102 East Corridor 2.5
< 1,000/ < 10,000 FH103 Sample Rm
< 50
< 50,000/< 50,000 FH104 West Corridor 2.5
< 1,000/< 10,000 FH105 Model Rm 2.5
< 1,000/< 10,000 FH106 Monitor Tanks and Sample Sink Area 2.5
< 1,000/ < 10,000 FH107 Trash Compactor Area 2.5
< 1,000/< 10,000 FH108 Truck Bay 2.5
< 1,000/< 10,000 FH109 Spent Fuel Pool A 2.5 "AS IS" (Under fuel pool cover) l FH110~
SDS Spent Fuel Pool 2.5
< 1,000/< 10,000 FH111 Fuel Cask Storage
< 1000
< 1,000/< 10,000 FH112 Annulus
< 100
< 50,000/< 50,000 FH201 East Corridor 2.5
< 1,000/< 10,000
^
FH202 West Corridor 2.5
< 1,000/ < 10,000 i
5.2-8 AMENDMENT 18 - AUGUST 1993 I
J
TABLE 5.2-2 (Cont'd)
SPECIFIC DECONTAMINATION GOALS - AFHB SPECIFIC DECONTAMINATION GOALS GENERALAREA SURFACE CONTAMINATION CUBICLE DOSE RATE
< 7'/ Overheads 2
NUMBER AREA DESCRIPTION (mR/hr)
(dpm/100 cm )
FH203 Surge Tank Area
< 500
< 50,000/< 50,000 FH204 Standby Pressure Control Area
< 500
< 1,000/< 10,000
+
FH205 Annulus
< 100
< 50,000/ N/A FH301 Upper Spent Fuel Pool A Area (Above fuel pool cover) 2.5
< 1,000/< 10,000 FH302 SDS Operating Area 2.5
<: 1,000/ < 10,000-FH303 Upper Standby Pressure Control Area 2.5
< 1,000/< 10,000 FH304 Annulus
< 500
< 50,000/< 50,000 FH305 Spent Fuel Pool Access Area 2.5
< 1,000/< 10,000 t
5.2-9 AMENDMENT 18 - AUGUST 1993
TABLE 5.3-1 PDMS RADIOLOGICAL CONDITIONS - REACTOR BUILDING AREA DESCRIPTION SPECIFIC DECONTAMINATION GOALS PDMS RADIOLOGICAL CONDITIONS
- GENERAL AREA SURFACE GENERAL AREA SURFACE DOSE RATE CONTAMINATION DOSE RATE CONTAMINATION 2
2 fmR/hr) fdom/100 cm )
fmR/hri fdom/100 cm )
Elevation 305' to 347
<100
< 50,000 150 2,000,000 Elevation 347' and Above
< 30
< 50,000 50 710,000 Refueling Canal
<100
< 50,000 120 670,000 D-Ring Interior, El. 349' and above "A" D-Ring "AS IS" "AS IS" 300 280,000 "B" D-Ring "AS IS" "AS IS" 200 220,000 Top of D-Rings
<100
< 50,000 40
'270,000
("A" D-ring) 50 190,000
("B" D-ring)
Basement, El. 282*
Note 1 i
The radiological conditions in this table reflect rounded-off, average PDMS survey data.
o on This is the decay-corrected dose rate taken by ROVER (TPB 85-3 Rev. O, February 1985.)
NOTES:
1.
This area is inaccessible; no meaningful data exists.
5.3-3 AMENDMENT 18 - AUGUST 1993
TABLE 5.3-2 PDMS PADIOLOCICAL CONDITIONS - AFRS SPECIFIC DECONTAMINATION GOALS PDMS RADIOLCCICAL CONDITIONS
- GENERAL AREA SURFACE CONTAMINATION GENERAL AAEA SURFACE CONTAMINATION CUBICLE DOSE RATE
<7'/ Overheads DCSE P. ATE-
< 7'/ Overheads NUMBER AREA DESCRIPTION tmR/hrt (dem/100 cm')
imR/hrt idem /2 00 em'l LX001 e3 Emerg. Cooling Booster Pumps Area 2.5 1,000/< 10,000 2.4 81,000/
6,500
. AX002 Access Corridor 2.5 1,000/< 10,000 1.5 110/
1,300 AX002a N, Piping System 2.5 1,000/< 10,000 AX003 Access Area 2.5 1,000/< 10,000 AX004 Seal Injection Valve Rm
< 1000
< $0,000/< 50,000 120 68,000/ 750,0GO 63005 MVP Pump 1C Ra
< $00
< 50,000/< 50,000 8
40,000/
30,000 AX006 MVP Pump 1B Ra
< 500
< 50,000/< 50,000 60 88,000/
29,000 AXOG7' MVP Pump 1A Rm
< 500
< 50,000/< 50,000 40 9,000/
21,000 AX009 Spent Resin Storage Tank 1B Rm
< $00 "A3 IS*
110 960,000/3,400,00s AX009 Spent Resin Storage Tank 1A Ra A
500 "AS IS' 1,700 3,000,000/6,000,000 LX010 Spent Resin Transf er Pua.y Rm
< $00
- AS IS*
180 1,400,000/5,100,000 t
, LX011 Aux Bldg Sump Tank Pumps and Valve Rm 50
< 5,000/< 50,000 8
3,200/
4,900 AX012 Aux Bldg Sump and Tank Rm
$0 5,000/< 50,000 560 390,000/
67,000 AX013 Evap Cond Tanks, Pumps and Demins Rm
< $00 1,000/< 10,000 10 130/-
140 AX014 RC Evaporator Rm
< 500
< $0,000/< $0,000 18 20,000/
8,100 AX015a cleanup Filters Rm
< 500
< $0.000/< 50,000 110 10,000/
8,700 AX015b
. Cleanup Af ter Filters Rm
' < 500
< $0,000/< 50,000 38 21,000/
13,000 AX016 Cleanup Demineralizer 2A Rm
< 500
< 50,000/< 50,000 -
38 21.000/
13,010 AX017 Oleanup Demineralizer 2B Rm
< 500
< 50,000/< 50,000 110 10,000/
8,700 AX018 Waste Transfer Pumps Rm
< 500'
< 50,000/< 50,000 10 17,0001 14,000 1
AX019 Waste Disposal Liquid Valve Ra
< 500
< 50,000/< 50,000 19 7,800/
5,700
- Tho radiological conditions in this table reflect rounded-of f, average PDMS survey data. All blank entries will be filled in prior to entry into PDMS.
N/L = Not Applicable 5,3-4 AMENDMENT 18 - AUGUST 1993 s
,,m_
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TABLE 5. 3-2 (Cont *d)
PDMS RADIOLOGICAL CONDITIONS - A'HB SPECIFIC DECONT?JtINATICN coals PDMS RADIOLOGICAL CONDITIONS
- GENERAL AREA SURFACE CONTAMINATION CUDICLE DOSE RATE
<7*/ Overheads GENERAL ARIA SURFACE CONTAMINATION DOSE RATE
< 7*/ Overheads 18 UMBER AJt!A DESCRIPTION t rJt / hr t idpm/100 em')
(mR/hrt (dom /100 cm*1 AX020 RC Bleed soldup Tanks 15 and 1C Rm
< 500 c.50,000/< 50,000 160 520,000/200,000 AX021 RC Bleed Holdup Tank 1A Rm
< 500
< $0,000 /< 50,000 AX022 Morth Stairvell 2.5
< 1,000/C 10,000 0.3 440/
470 AXO23 Elevator Shaf t (Inside cab) 10
< 50,000/
N/A 14 9,700/
480 '
2 LX024 Aux Bldg Sump Filters Rm
< 580
< 50,000/< $0,000 15 6,400/ 11,000 aK025 Area Between Service, Control, and RB
< 500 1,000/< 10,061 3.5 100/
310
' AX026 Seal Injection Filters Rm
< 500
< 50,000/< 50,000 12 9,000/ 1,000 A1027 South Stairwell.
?.5 1,000/< 10,000 0.2 480/
. AX101 Redwaste Disposal Control Fa al h ee 4.i 1,000/< 10,000 AX102' RB Samp Pumps Filters Rm
- 1000
< 50,000/< 50,000 47 9.300/ 4,200 AX103 Motor control Center 2-11EB Rm 2.5 1,000/< 10,000 0.2 470/
480 AX104 Motor. Control Center 2-21EB Rm 2.5 1,000/< 10,000 0.2 470/
4?0 LX105 Substation 2-11E Rm 2.5 1,008/< 10,000 0.2 480/
530 LX106 Substation 2-21E Rm 2.5 1,000/< 10,000 0.2 480/
530 AX107 Motor Control Center 2-11EA Rm 2.5 1,000/< 10,000 0.2 460/
530
' AX108 Motor Control Center 2-21EA Rm 2.5 1,000/< 10,000 0.2 480/
500 AX109 Nuclear Services coolers and Pumps Area <
2.5 1,000/< 10,000 0.2 100/
130 AX110 Intermediate Coolers Area.
2.5 1,000/< 10,000 0.2 100/
130 AX111 Intermed cooling Pumps and Filters Ra SS 1,000/< 10,000 0.7 440/
410 AX112 Seal Return Coolers and Filter Rm
- < 1000
< 50,000 /< 50,000 AX113 Weste cas Analyser Rm 50
< 50,000/< 50,000 19
'22,000/ 6,400 i
i
't QX114 MUP Demineralizer lA Ra
- AS IS*
"AS IS*
73,000 9,800/
- AX115 MVP Demineraliser 1B Rm
- AS IS*
- AS IS*
68,000 31,000/
AX116 Makeup Tank Rm
< 500
< 50,000 /< 5 0,0 00 51 50,000/ 13,000 AX117 MUP Filters Ra
< 1000
- AS IS*
QX118
' Spent Fuel Coolers and Pumps Area
- 2. 5' 1,000/< 10,000 1.1 1,000/ 3,000 5 3-5 AMENDMENT 18 - AUGUST 1993 t.
.. ~...
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n i. n-a
- v.,.,L
,, a L.,
n,.,..
~,n, c.,.-n..
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.., ~..
- ~..
I TABLE 5.3-2 (Cont'd)
POMS RADICI.0CICAL CONDITIONS - AFH3 SPECIFIC DECONTAMINATION GOALS PDMS RADIOLOGICAL CONDITIONS
- GENERAL AREA SURFACS CONTAMINATION GENERAL AREA SURFACE CONTAMINATION CUBICLE DOSE RATE
< 7'/ Overheads DOSE RATE
< 7'/ Overheads 8
NUMEER AREA DESCRIPTION tmR/hrt (dom /100 m1 imR/hrt (dDm/100 em')
L1119 Spent ruel Demineraliser Rm 2.5 1,000/< 10,000 0.4 480/
330 CX120 Spent Fuel Filters Rm 2.5 1,000/< 10,000 0.6 360/ 1,000 AX121 Elevator Shaf t (Inside cab) 2.5 1,000/< 10,000 0.2 620/
AX122 porsk Stairwell 2.5 1,000/< 10,000 0.2 460/
390 DX123 Access Area 2.5 1,000/< 10,000 AX124 Concentrated Liquid Waste Pump Ra
< 500
< 50,000/< 50,000 3.3 3,300/ 1,900 AX125 waste ces Decay Tank 1B Rm
< 500
< 50,030/< 50,000 DX126 wasta Cas Filter Rm
< 500
< 50,000/< 50,000 0.2 100/
160 LX127-waste Gas Decay Tank 1A Rm
< 500
< 50,000/< $0.000 AE128
. Valve and Instrument Rm
< 500
< 50,000/< 50,000 2.7 1,000/ 1,300 AX129 Deborating Domineraliser IB Rm
< 500
< 50.000/< 50,000 0.3 1,000/
600 LX130 Deborating Demineralizer IA Rm
< $00
< 5 0,000/< 50,000 0.5 540/
520 AX131 Miscellaneous waste Holdup Tank Rm
$0 5,000/< 50,000 120 1,900/ 6,500 AX132 Corridor Detween Unit I and Unit 2 2.5 1,000/< 10,000 Qu133 South Stairwell 4
2.5 1,000/< 10,000 0.2 500/
500 AE134 Miscellaneous waste Tank Pumps Rm
<' 50
< 50,000/< 50,000 13 13,000/ 45,000 A1135 Radwaste Disposal Control Panels 2.5 1,000/< 10,000 0.2 130/
120 AX201 North Stairwell 2.5 1,000/< 10,000 0.2 450/
470 LX202 Elevatot Shaft 2.5 1,000/< 10,000 0.2 620/.
960
' AX203 4160V Switchgear 2-1E Rm 2.5 1,000/< 10,000 0.2 480/
460 LE204 4160V Switchgear 2-2E Rm -
2.5 1,000/< 10,000 0.2 480/
480 82205-RB Purge Air Sup. and By Ctrl Exh Area 2.5 1,000/< 10,000 0.7
. 100/-
130 L1206 RB Purge Air Exhaust Unit B 50 N/A.10-200,000/100,000 AX207 RB Purge Air Exhaust Unit A 50 N/A 13 200,000/600,000 At208 Aux Bldg Exhaust Unit B 50 N/A 0.4 3,900/ 3,000 5.3-6' AMENDMENT 18 - AUGUST 1993
~
TABLE 5. 3-2 (Cont'd)
PDMS RADICLCGICAL CONDITIONS - AFBB SPECIFIC DECONTAMINATION GOALS PDMS RADIOLOGICAL CONDITIONS
- GENERAL AREA SURFACE CONTAMINATION GENERAL AREA SURFACE CONTAMINATION CUBICLE DOSE RATE 47'/ Overheads DOSE RATE
< 7*/ Overheads 4
. N"MPER AREA DESCRIPTION feR/hrt i dem/100 cm'l imR/hr) t dem/10 0 em'n QX209 Aux Bldg Exhaust Unit A 50 N/A 0.7 10,000/ 13,000 L1210 Fuel Handling Bldg Exhaust Unit B 50 N/A 0.9 12,00t/ 2 3,000 ax211 Fuel aandling Bldg Exhaust Unit A 50 N/A 0.3 7,200/ 3,900 AX212 Decay Heat Surge Tk and Substation Area <
2.5 1,000/< 10,000 0.2 100/
90 A1213 Unit substations and Access Area 2.5 1,000/< 10,000 0.2 130/
120 AX214 Decon Facility 2.5 1,000/< 10,000 0.3 150/
100 A1215 Fuel Bandling Bldg Supply Unit 2.5 N/A 0.2 450/
450 LX216 Aux Bldg Supply Unit 2.5 N/A 0.2 450/
450 AX217 Access Area 2.5 1,000/< 10,000 0.2 100/
130 A1218 concentrat'ed waste Storage Tank Rm
< 500
< 50,000/< 50,000 15 1,900/ 1,000
' I AI219 Inst Racks and Atmospheric Monitor Area 2.5 1,000/< 10,000 0.3 400/ 5,900 AX220 Caustic Liquids Mixing Area
< SCO 1,000/< 10,000 1.4 450/
360 Q2221 Caustic Liquids Mixing Area corridor
< 500 1,000/< 10,000 0.8 450/
880 AX222 South Stairwell 2.5 1,000/< 10,000 0.2 100/
880 AK223 Air Handling Unita General Area 2.5 5, G00/< 10,000 0.8 490/
450 42301 Elevator Shaft and Elevator Machine Rm 2.5 1,000/< 10,000 0.2 100/
170 4
AK302 North Stairvell 2.5 1,000/< 10,000 0.2 480/
480 A1303 Elevator and Stairwell Access 2.5 1,000/< 10,000 0.2 510/
500 Ax304 Aux. Bldg. Exhaust Fan OS.
2.5 1,000/< 10,000' O.6 753/
500 AI305 Fuel Handling Bldg. Exhaust Fan 010 2.5 1,000/< 10,000 0.2 650/
390 A2401 Roof 2.5
< 1,000/
N/A AI402 Cooling water Surge Tanks Rm.
< $00
< 50,000/< 50,000 0.2 110/
230 i
AI403.
Damper Rm '
< 500
< $0,000/< $0,000~
0.2 120/
130
- A1501 RB Spray Pump 1A Rm 25 5,000/< 50,000, AZ502 RB Spray Pump 1B Ra
<' 25 "As IS" A1503 Decay Esat Remot Cooler and Pump 1A Ra 25-
< $0,000/< 50,000
+
5.3-7 AMENDMENT 18 - AUGUST 1993 L
a 4
..h.m e..m.s
.) ~.
.E
...-y.
,s-.
.,m,.y-y
TABLE 5. 3-2 (Cont'd)
PDMS PADIOLOGICAL CONDITIONS + AFBB SPECIFIC DECONTAMINATION COALS PCMS RADIOLOGICAL CONDITIONS
- GENERAL AAEA SLTRP ACE CONTAMINATION GENERAL AREA SURFACE CONTAMINATION CUBICI.E DOSE RATZ
<7*/ Overheads DOSE RATE
< 7*/ Overheads NUMBER AREA DESCRIPTION imR/hrt-Idom/100 cm n imR/hrt (dom /100 em')
AX504 Decay Seat Remov Cooler and Pump 1B Rm 25
< 50,000/4 50,000 FH001 Makeup Suetion valve Rm
< 500
< 50,000/< 50,000 19 70,000/
89,000 FH002 Access Corridor 2.5 1,000/< 10,000 1.5 1,000/
1,500 FH003a Makeup Discharge valve Rm
< 1000
< 50,000/<100,000 69 140,000/
77,000 FH003b Makeup Discharge Valve Ra
< 1000
< 50,000/4100,000 220
$10,000/ 5,000,000
~ FH00 4,
. Westinghouse valve Rm
< 500
< 50,000/< $0,000 59 38,0001 1,100,000 FH005 Mini Decay seat Vault
< 500
< 50,000/C 50,000 2.4 2,700/
1,500
-FH006 Decay Heat Service Coolers Area
< 500 1,000/< 10,000 j'
FS007 Neutri and Reci Boric Acid Access Area
< 500 1,000/< 10,000 FH000 Neutraliser Tanks Pumps Rm
< 500
< 50,000/< 50,000 100 62,000/
1,700 FH003 Neutralizer Tanks Rm
< 500
< 50,000/< $0,000 150 20,000/
8,300 FB010 Reclaimed Boric Acid Tank Ra
< 500
< $0.000/< 50,000 4.3 2,400/
6,300 FH011 Reclaimed Boric Acid Pump Rm
< 500
< 50,000/< $0,000 9,1 14,000/
20,000 FH012 Neutraliser Tanks Filters Rm -
< 500
< 50,000/< 50,000 31 2,800/
'1,200 F5013 011 Drum Storage Area
< $00 1,000/< 10,000 0.2 100/
100 FH014 Annulus
< 500
< 50,000/< 50,000 110 35,000/
7,500 FH101 MUP Vaive Rm
< 500
< 50,000/< 50,000 200 850,000/14,000,000 FH102 East corridor 2.5 1,000/< 10,000 1.1 200/
31,000 FH103 Sample Rm
$0
< 50.000/4 50,000 1.2 4,000/
1,600 PH104 West Corridor 2.5 1,000/< 10,000 0.2 120/
100 FH105 Model Rm 2.5 1,000/< 10,000 0.2 100/
100 FH106 Monitor Tanks and Sample Sink Area 2.5 1,000/<-10,000 0.7 330/
110 a
F FH107 Trash compactor Area 2.5
<. 1,000/< 10.000 0.2 100/
130 FH108 Truck Bay -
2.5 1,000/< 10.,000 0.2 70/
70 FH109-Spent Fuel Pool A 2.5
- AS IS*
-(Under fuel pool cover)
S.3-8 AMENDMENT 18'- AUGUST 1993
... ~. _.,
a--
i TABLE 5. 3-2 (Cont *d)
PDMS RADIOLOCICAL CONDITIONS - D?HB SPECIFIC DECONTAMINATION GCALS PDMS RADIOLOGICAL CONDITIONS
- CUBICLE.
GENERAL AREA SURFACE CONTAMINATION GENERAL AREA SUREACE CONTAMINATION DOSE RATE
<7'/ Overheads DCSE BATE
< 7'/ Overheads NUMBER AREA DESCRIPTION feR/hr)
(dom /100 em*)
imR/hr) f dom /100 cm'l FH110 SDS Spent Puel Pool 2.5 1,000/< 10,000
. F8111 Fuel Cask Storage
< 1000
< 1;000/< 10,000 FH112 Annulus
< 100
. < 50,000/< 50,000 19 3,500/
840 FE201 East Corridor 2.5 1,000/< 10,000 1.0 420/ ' 9,400 FH202 West Corridor.
2.5 1,000/< 10,000 0.2 400/
490 FE203 Surge Tank Area.
< 500
< 50,000/< 50,000 28 1,000/
N/A FR204 Standby Pressure Control Area
< 500 1,000/< 10,000 0.2 1,000/
1,000 F8205 Annulus
< 100
< 50,000/
N/A 9
700/
8,400 FH301 -
Upper Spent Fuel Pool A Area (Above fuel pool cover) 2.5
< 1,000/c 10,000 4.0 240/
300 FE302 SDS Operating Area 2.5 1,000/< 10,000 1.2 400/
400 FE303 Upper Standby Pressure Control Area 2.5 1,000/< 10,000 0.2 300/
160 FE304 Annulus.
< 500
< $0,000/< 50,$00 0.6 2,200/
2,200 FE305 Spent Fuel Pool Access Area 2.5 1,000/< 10,000 1.3 390/
900 4
)
' i
'5.3 AMENDMENT 18 - AUGUST 1993
~v
=-'O.t' e
sw
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c
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T
TABLE 5.3-3 PDMS PADIOLOGICAL CCNDITICNS - OTHER BUILDINGS SPEC 1PIC DECONTAMINATION GOALS PDMS PADIOLOGICAL CONDITIONS
- GENERAL AREA SURFACE CCNTAMINATION GENERAL AREA SURFACE CONTAMINATION CUBICLE DOSE RATE
< 7"/ Overheads DOSE RATE
< 7'/ Overheads Nt.MBER AREA DESCRIPTION imp /hr)
(dem/100 ed)
ImR/hr)
(dom /100 cm*)
S9000 Service Building El. 281' 2.5 1,000/< 10,000 SB500 Tendon Access Gallery 2.5 1,000/< 10,000 Service Building El. 305' 2.5 1,000/< 10,000 39002 M-20 Area 2.5 1,000/< 10,000 SC002 M-20 Area Sump 2.5 1,000/< 10,000 Turbine Building El. 281' 2.5 1,000/< 10,000 CACE Building 2.5 1,000/< 10,000 Rn101 Proc. H 0 Storage Tank Sump 2.5 1,000/< 10,000 3
Rn104 Borated H,0 Storage Tank Area 2.5 1,000/< 10,000
- The radiological conditions in this table reflect rounded-off, average PDMS survey data. All blank entries will be filled in prior to entry into PDMS.
5.3-10 AMENDMENT 18 - AUGUST 1993
+
.. s
TABLE 5.3-4 SURFACE CONTAMINATION - REACTOR BUILDING AREA DESCRIPTION PRINCIPLE ISOTOPES CURIES Elevations 305' to 347 '
Cs-137 9.7 E-1 Sr-90 1.9 E-1 Elevation 347' and Above Cs-137 6.7 E-1 Sr-90 3.3 E-1 Refueling Canal Cs-137 2.8 E-2 Sr-90 2.2 E-2 D-Ring Interior Cs-137 3.2 E-2 Elevation 349' and Above Sr-90 2.0 E-3 Basement, Elevation 282' Cs-137 6.5 E+2 i
Sr-90 5.9 E+2 i
- I 5.3-11 AMENDMENT 18 - AUGUST 1993
-m M
g,
--?
w
TABLE 5.3-5 SURFACE CONTAMINATION - AFHB CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPES m CURIES m AX001 RB Emerg. Cooling Booster Pumps Area A
AX002 Access Corridor A
7.32E-7 AX002a N Piping System A
2 AX003 Access Area A
AX004 Seal Injection Valve Rm C
1.08E-4 AX005 MUP Pump IC Rm B
5.05E-5 AX006 MUP Pump IB Rm B
- 1. l lE-4 AX007 MUP Pump 1A Rm B
1.16E-5 AX008 Spent Resin Stomge Tank 1B Rm A
1.93E-3 AX009 Spent Resin Storage Tank 1 A Rm A
2.94E-3 AX010 Spent Resin Transfer Pump Rm A
1.50E-3 AXOll Aux Bldg Sump Tank Pumps and Valve Rm B
1.37E-6 AX012 '
Aux Bldg Sump and Tank Rm A
4.60E-4 AX013 Evap Cond Tanks, Pumps and Demins Rm A
2.68E-7 AX014 RC Evaporator Rm A
2.63E-5 AX015a Cleanup Filters Rm A
4.38E-6 5.3-12 AMENDMENT 18 - AUGUST 1993 l
TABLE 5.3-5 (Cont'd)
SURFACE CONTAhUNATION - AFHB CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPES
- CURIES m AX015b Cleanup After Filters Rm A
8.93E-6 AX016 Cleanup Demineralizer 2A Rm A
1.57E-5 AX017 Cleanup Demineralizer 2B Rm A
7.70E-6 AX018 Waste Transfer Pumps Rm A
1.22E-5 AX019 Waste Disposal Liquid Valve Rm A
9.20E-6 AX020 RC Bleed Holdup Tanks IB and IC Rm B
3.54E-3 AX021 RC Bleed Holdup Tank 1 A Rm A
AX022 North Stairwell A
2.84E-7 AX023 Elevator Shaft A
4.95E-6 AX024 Aux Bldg Sump Filters Rm B
2.06E-6 AXO25 Area Between Service, Control, and RB A
2.23E-7 AX026 Seal Injection Filters Rm C
1.58E-6 AX027 South Stairwell A
2.12E-7 AX101.
Radwaste Disposal Control Panel Area A
AX102
3.02E-6 AX103 Motor Contrul Center 2-11EB Rm
'A 3.34E-7 5.3-13 AMENDMENT 18 - AUGUST 1993
TABLE 5.3-5 (Cont'd)
SURFACE CONTAMINATION - AFHB CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPES
- CUPJES
- AX104 Motor Contml Center 2-21EB Rm A
3.51E-7 AX105 Substation 2-11E Rm A
8.22E-7 AX106 Substation 2-21E Rm A
9.31 E-7 AX107 Motor Control Center 2-11EA Rm A
1.04E-6 AX108 '
Motor Control Center 2-21EA Rm A
7.48E-7 AX109 Nuclear Services Coolers and Pumps Area A
3.97E-7 AX110 Intermediate Coolers Ama A
4.27E-7 AX111 -
Intermed Cooling Pumps and Filters Rm A
8.30E-7 AX112 Seal Return Coolers and Filter Rm B
AX113 Waste Gas Analyzer Rm A
3.44E-5 AX114 MUP Demineralizer I A Rm A
6.94E-6 AX115 MUP Demineralizer IB Rm A
3.22E-5 AX116
. Makeup Tank Rm B
3.99E-5 AX117 MUP Filters Rm B
AXII8 Spent Fuel Coolers and Pumps Area A
3.35E-6 5.3-14 AMENDMENT 18 - AUGUST 1993
TABLE 5.3-5 (Cont'd)
SURFACE CONTAMINATION - AFHB CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL-ISOTOPES m CURIES A AX119
' Spent Fuel Demineralizer Rm A
2.82E-7 AX120 Spent Fuel Filters Rm A
1.08E-7 AX121 Elevator Shaft A
3.33E-7 AX122 North Stairwell A
3.51E-7 AX123 Access Ama A
AX124 Concentrated Liquid Waste Pump Rm A
1.26E-6 AX125 Waste Gas Decay Tank 1B Rm A
AX126 Waste Gas Filter Rm A
5.51E-8 AX127 Waste Gas Decay Tank 1 A Rm A
AX128 Valve and Instrument Rm A
9.30E-7 AX129 Deborating Demineralizer IB Rm A
6.72E-7 AX130 Deborating Demineralizer lA Rm A
3.72E-7 AX131 Miscellaneous Waste Holdup Tank Rm A
3.11E-6 AX132.
Corridor Between Unit I and Unit 2 A
AX133 South Stairwell A
3.79E-7 AX134 Miscellaneous Waste Tank Pumps Rm A
9.73E-6 5.3-15 AMENDMENT 18 - AUGUST 1993 l
l
TABLE 5.3-5 (Cont'd)
SURFACE CONTAMINATION - AFHB CUBICLE NUMBER-AREA DESCRIPTION PRINCIPAL ISOTOPES
- CURIES S AX135 Radwaste Disposal Control Panels A
5.34E-8 AX201 North Stairwell A
2.95E-7 AX202 Elevator Shaft A
3.25E-7 AX203 4160V Switchgear 2-lE Rm A
1.22E-6 AX204 4160V Switchgear 2-2E Rm A
1.27E-6 AX205 RB Purge Air Sup. and Hy Ctrl Exh Area A
4.58E-7 AX206 RB Purge Air Exhaust Unit B A
1.64E-4 AX207.
RB Purge Air Exhaust Unit A A
1.81E-4 AX208 Aux Bldg Exhaust Unit B A
2.80E-6 AX209 Aux Bldg Exhaust Unit A A
7.23E-6 AX210 Fuel Handling Bldg Exhaust Unit B A
7.02E-6 AX211 Fuel Handling Bldg Exhaust Unit A A
4.12E-6 AX212 Decay Heat Surge Tk and Substation Area A
8.87E-7 AX213 Unit Substations and Access Area A
9.39E-7 AX214 Decon Facility A
2.37E-7 AX215 Fuel Handling Bldg Supply Unit A
3.25E-7 5.3 AMENDMENT 18 - AUGUST 1993
TABLE 5.3-5 (Cont'd)
SURFACE CONTAAUNATION - AFHB t
CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPES
- CURIES m AX216 Aux Bldg Supply Unit A
3.90E-7 AX217 Access Area A
7.06E-7 AX218 Concentrated Waste Storage Tank Rm A
1.67E-6 AX219 Inst Racks and Atmospheric Monitor Area A
7.40E-7 AX220 Caustic Liquids Mixing Area A
4.95E-7 AX221 Caustic Liquids Mixing Area Corridor A
1.30E-6
' AX222 South Stairwell A
5.66E-8 AX223 Air Handling Units General Area A
4.40E-6 AX301 Elevator Shaft and Elevator Machine Rm A
6.57E-8 AX302 North Stairwell A
2.79E-7 AX303 Elevator and Stainvell Access A
5.60E-7 AX304 Auxiliary Building Exhaust Fan #8 A
AX305 Fuel Handling Building Exhaust Fan #10 A
AX401 Roof A
AX402 Cooling Water Surge Tanks Rm A
1.80E-7 AX403 Damper Rm.
A 1.46E-7 5.3-17 AMENDMENT 18 - AUGUST 1993
=
TABLE 5.3-5 (Cont'd)
S1JRFACE CONTAMINATION - AFHB CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPES m CURIES
- AX501 RB Spmy Pump 1A Rm B
AX502 RB Spray Pump 1B Rm A
AX503 Decay Heat Remov Cooler and Pump 1A Rm A
AX504 Decay Heat Remov Cooler and Pump 1B Rm A
FH001 Makeup Suction Valve Rm B
1.68E-4 FH002 Access Corridor B
2.51E-6 FH003a Makeup Discharge Valve Rm B
8.35E-5 FH003b Makeup Discharge Valve Rm B
4.68E-4 FH004 Westinghouse Valve Rm A
7.71E-5 FH005 Mini Decay Heat Vault A
1.67E-6 FH006 Decay Heat Service Coolers Area A
FH007 Neutrl and Rect Boric Acid Access Area A
- FH008 Neutrahzer Tanks Pumps Rm B
7.09E-5 FH009 Neutralizer Tanks Rm B
3.41E-5 FH010 Reclaimed Boric Acid Tank Rm A
2.28E-6 5.3-18 AMENDMENT 18 - AUGUST 1993
~-
TABLE 5.3-5 (Cont'd)
SURFACE CONTAMINATION - AFHB CUBICLE -
NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPES m CURIES
- FH011 Reclaimed Boric Acid Pump Rm A
1.06E-5 FH012 Neutralizer Tanks Filters Rm A
9.64E-7 FH013 Oil Dmm Storage Ama A
5.20E-8 FH014 Annulus A
6.05E-5 FH101 MUP Valve Rm A
1.33E-3 FH102
. East Corridor A
8.32E-7 FH103 Sample Rm A
2.85E-6 FH104 West Corridor A
3.71E-7 FH105 Model Rm A
5.59E-7 FH106 Monitor Tanks and Sample Sink Area A
8.29E-7 FH107 Trash Compactor Ama A
1.62E-7 FH108-Truck Bay A
5.53E-7 FH109 Spent Fuel Pool A A
FH110 SDS Spent Fuel Pool A
FHill Fuel Cask Storage A
FH112
' Annulus B
1.14E-5 FH201 East Corridor
-A
- 1.75E-6 FH202 West Corridor.
A 1.48E-6 5.3-19 AMENDMENT 18 - AUGUST 1993
TABLE 5.3-5 (Cont'd)
SURFACE CONTAMINATION - AFHB CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPES (D CURIES
- FH203 Surge Tank Area A
5.22E-7 FH204 Standby Pressure Control Area A
2.74E-6 FH205 Annulus B
1.33E-6 FH301 Upper Spent Fuel Pool A Ama A
6.14E-7 FH302 SDS Operating Area A
2.86E-6 FH303 Upper Standby Pressure Control Area A
2.54E-6 FH304 Annulus B
6.26E-6 FH305 Spent Fuel Pool Access Area A
3.07E-6 NOTES:
(1) The principal isotopes and their mlative distribution are defined below.
A B
C
- Sr-90 7.44E-2 Sr-90 3.94E-1 Sr-90 8.25E-1 Cs-137 9.26E-1 Cs-137 6.09E-1 Cs-137 1.75E-1 Pu-238 2.00E-6 Pu-238 5.97E-7 Pu-239 2.34E-5 Pu-239 6.95E-6 Pu-240 6.19E-6 Pu-240 1.84E-6 Pu-241 2.88E-4 Pu-241 8.42E-5 Am-141 4.47E 6 Am-141 1.33E-6 (2) These are calculated values based on the specific decontamination values given on Table 5.3-2. All blank entries will be filled '
in prior to entry into PDMS.
5.3-20 AMENDMENT 18 - AUGUST 1993
TABLE 5.3-6 SURFACE CONTAMINATION - OTHER BUILDINGS CUBICLE NUMBER AREA DESCRIPTION PRINCIPAL ISOTOPESl" CURIESm SB000 Service Building El. 281' A
SB500 Tendon Access Gallery A
Service Building El. 305' A
SB002 M-20 Area A
SB002
.M-20 Ama Sump A
Turbine Building El. 281' A
CACE Building A
RA101 Proc. H O Storage Tank Sump A
2 RA104 Borated H O Storage Tank Area A
2 NOTES:
_(1) The principal isotopes and their relative distribution are defined below.
(2) These are calculated values based on the specific decontamination values given on Table 5.3-3. All blank entries will be filled in prior to' entry into PDMS.
A Sr 7.44E-2 Cs-137 9.26E-1 5.3 AMENDMENT 18 - AUGUST 1993
1 CHAPTER 6 TABLE OF CONTENTS (Cont'd)
SECTION TITLE PAGE 6.3.22 PENETRATION PRESSURIZATION SYSTEM 6.3-9 6.3.23 GLAND STEAM SYSTEM 6.3-10 6.3.24 MOISTURE SEPARATOR SYSTEM 6.3-10 6.3.25 REACTOR BUILDING SUMP RECIRCULATION SYSTEM 6.3-10 6.3.26 SCREEN WASH SYSTEM 6.3-10 6.3.27 FEEDWATER HEATER NITROGEN BLANKETING 6.3-11 SYSTEM 6.3.28 DIESEL FUEL - EMERGENCY DIESEL GENERATOR 6.3-11 SYSTEM c
6.3.29 LABORATORY GAS SYSTEMS 6.3-11 6.3.30 MAKEUP WATER TREATMENT AND CONDENSATE 6.3-12 POLISHING SYSTEM 6.3.31 AMMONIA SYSTEM 6.3-12 6.3.32 REACTOR BUILDING CHILLED WATER SYSTEM 6.3-13 1
6.3.33 SAFETY FEATURES ACTUATION SYSTEM 6.3-13 6.3.34 BREATHING AIR SYSTEM 6.3-13 6.3.35 CONTAINMENT AIR CONTROL ENVELOPE HVAC 6.3-13.
6.3.36 CONTROL ROD DRIVE SYSTEM 6.3-13 6.3.37 MISCELLANEOUS INSTRUMENTATION SYSTEM 6.3-14
-6.3.38 CONDENSER AIR EXTRACTION FILTRATION SYSTEM 6.3-15 6.3.39 SEAL OIL SYSTEM - GENERATOR SYSTEM 6.3,
6.3.40 TEMPORARY NUCLEAR SERVICES CLOSED COOIJNG 6.3-15 SYSTEM 6.3.41 DELETED ix AMENDMENT 18 - AUGUST 1993
CHAPTER 6 TABLE OF CONTENTS (Cont'd)
SECTION TITLE PAGE 6.3.42 DELETED 6.3.43 RIVER WATER PUMP HOUSE HEATING AND 6.3-15 l
VENTILATION 6.3.44 CIRCULATION WATER PUMP HOUSE HEATING AND 6.3-16 VENTILATION 6.3.45 FIRE PUMP HOUSE HEATING AND VENTILATION 6.3-16 SYSTEM 6.3.46 COAGULATOR BUILDING HEATING AND 6.3-16
-l VENTILATION SYSTEM 6.3.47 CHLORINATOR HOUSE HEATING AND VENTILATION 6.3-16 6.3.48 DELETED 6.3-16 6.3.49 TURBINE BUILDING HEATING AND VENTILATION 6.3-16 SYSTEM 6.3.50 EARTHQUAKE DETECTION SYSTEM 6.3 6.3.51 REACTOR COOLANT PUMPS MOTOR OIL DRAIN 6.3-17 SYSTEM 6.3.52 DEFUELING TEST ASSEMBLY 6.3-17 6.3.53 GRAY AND WHITE DIESELS SYSTEM 6.3-17 6.3.54 DIESEL GENERATORS 6.3-17 6.3.55 CHEMICAL LABORATORY TRAILER. EXHAUST 6.3-18 SYSTEM 6.3.56 POLAR CRANE 6.3-18 l
6.4 DELETED 6.4-1 6.5 SYSTEM REFERENCES 6.5-1 x
AMENDMENT 18 - AUGUST 1993
CHAPTERJ TABLESF CONTENTS (Cont'd)
LIST OF TABLES TABLE NO.
TITLE PAGE 6.1-1 DEACTIVATED FACILITIES 6.1-5 6.2-1 DEACTIVATED PASSIVE SYSTEMS 6.2-26 6.3-1 DEACTIVATED SYSTEMS 6.3-19 6.4-1 DELETED 6.4-2 S
i i
~J
_j 4
xi AMENDMENT 18 - AUGUST 1993
6.1 DEACTIVATED FACILITIES Table 6.1-1 provides a listing of deactivated facilities for TMI-2. Also listed are the status of internal contamination and relevant remarks regarding the final layup of the facility. The following sections address the facility description and the PDMS function of the facility.
6.1.1 TURBINE BUILDING The Turbine Building houses the main turbine, a portion of its Steam Supply System, and Condensate and Feedwater Systems. It also contains the main condenser and a part of the Circulating Water and Air Extraction Systems. The Water Treatment System is located in this facility.
During PDMS, this facility serves no active or passive function and as such is designated deactivated. However, electric distribution remains configured to power the fim detectors and half the low voltage (120/208 VAC) lighting loads. In addition, one sump pump will mmain operational and domestic water will be available.
6.1.2 DELETED i
I l
i 6.1-1 AMENDMENT 18 - AUGUST 1993
']
6.1.3 CONTAINMENT AIR CONTROL ENVELOPE The CACE was installed during the cleanup period and provided space to mobilize equipment and materials needed to support the in-containment activities through defueling. Location of the CACE at the equipment hatch allows equipment and materials to be moved into and out of the Cor.tainment Building with a minimum of difficulty through the equipment hatch airlock doors.
The CACE served as an aid in the control of the spread of contamination and airborne radioactivity during those times when the airlock doors were opened.
During PDMS, this facility serves no active function and as such is designated deactivated.
Certain types of RB entries require the CACE to be in a closed condition; thus, the CACE serves a passive function.
6.1.4 CIRCULATING WATER PUMP HOUSE The Circulating Water Pump House contains the six circulating water pumps and their controls _
which provide a flowpath from the circulating water flume to the main condenser.
During PDMS, this facility serves no active or passive function and as such is designated.
deactivated.
6.1.5 CIRCULATING WATER CHLORINATOR HOUSE The Circulating Water Chlorinator House contains the chlorine evaporator, chlorinator and ejector 1
and storage tanks in addition to the sulfuric acid storage tank. This facility supported the chemical treatment of the Circulating Water System.
During PDMS, this facility serves no active or passive function and as such is designated deactivated.
6.1.6 NATURAL DRAFT COOLING TOWERS Two cooling towers were provided to cool the total combined plant circulating water flow. The towers are natural draft type with a ring of water cooling cells surrounding the perimeter of the hyperbolic stack. The purpose of the cells was to mechanically mix the water and air. The water flowed through distribution nozzles in the top of the cells to splash through the fill, falling to the tower collecting basin. The fill was composed of horizontal splash bars supported in a grid system, which broke up the water flow to increase the heat transfer rate. From there, the water l
flowed by gravity to the circulating water fiume.
6.1-2 AMENDMENT 18 - AUGUST 1993
During PDMS, these towers serve no active or passive function and as such are designated deactivated. Therefore, the combustible material from this facility has been removed. The aircraft warning lights will remain operational.
6.1.7 MECHANICAL DRAFT COOLING TOWER The original design of the Mechanical Draft Cooling Tower was to remove the heat added by the Service Cooling Water Systems, which included the Secondary Services River Water, before it was returned to the river. Incoming hot water was pumped from a hot water collecting basin beneath the tower to the hot water distribution basins at the top of the towers. Air entered through inlet air louvers on both sides of the tower to mix with the water falling through the fill.
The cooled water was collected in the water basin under the tower.
This facility has been dismantled and the combustible material has been removed.
6.1.8 PROCESSED WATER PUMP HOUSE The Processed Water Pump House is located between the processed water storage tanks and houses the transfer pumps, sample sink ard tank isolation valves. This system and facility was installed during the cleanup period and was used to collect water from the Auxiliary Building Emergency Liquid Cleanup System.
During PDMS, this facility serves no active or passive function and as such is designated deactivated.
6.1.9 TENDON ACCESS GALLERY The Tendon Access Gallery pmvided access for initial positioning and tightening of the Tendon Post-Tensioning System during construction. The Tendon Post-Tensioning System is grouted and as such does not require periodic torquing.
During PDMS, this facility serves no active or passive function and as such is designated deactivated. However, one sump pump will remain operational.
6.1.10 RIVER WATER AND FIRE PUMP HOUSE The River Water Pump House provided a structure for intake water supplied to the various nuclear and service water systems and the Unit 2 diesel fire pump (FS-P-1) in the adjacent Fire Pump House structure.
During PDMS, these facilities and the systems within these facilities serve no active or passive function and as such are designated deactivated.
6.1-3 AMENDMENT 18 - AUGUST 1993
6.1.11 BWST PIPE CHASE The Borated Water Storage Tank (BWST) Pipe Chase is an underground tunnel extending from the BWST into the Auxiliary Building on the east side. It encloses piping in the Decay Heat Removal System related to the borated water supply for the plant. During PDMS, this area serves no active or passive function and is designated deactivated.
6.1.12 CONTROL BUILDING (M-20) AREA EAST The Control Building Area is the plant area below elevation 305' between the Turbine, Reactor, and Service Buildings. The east ponion is separated from the west by a barrier wall and houses the motor-driven Emergency Steam Generator Feed Pumps. This area provides access to the Tendon Access Gallery on the east side and the Control and Service Buildings from the Turbine Building.
During PDMS, this area serves no active or passive function and is designated deactivated.
6.1.13 CONTROL BUILDING (M-20) AREA WEST The Control Building Area west ponion houses the turbine-driven Emergency Steam Generator Feed Pump, Main Steam Isolation, Relief and Atmospheric Vent Valves, the Control Building Area Sump, and Unit Substations 2-34 and 2-44. This area also provides access to the Tendon Access Gallery on the west side.
During PDMS, this area serves no active or passive function and is designated deactivated.
However, one sump pump will remain operational.
6.1.14 EMERGENCY DIESEL GENERATOR BUILDING The Emergency Diesel Genemtor Building houses the diesel generators, diesel fuel oil storage tanks, diesel fuel oil day tanks, associated switchgear, and sump pumps. The' entire building and its contents have been turned over to Unit 1.
l 6.1-4 AMENDMENT 18 - AUGUST 1993 i
i i
)
TABLE 6.1-1 DEACTIVATED FACILITIES PDMS INTERNAL FACILITY DESCRIPTION FUNCTION CONTAMINATION REMARKS Turbine Building NONE YES Residual contamination in some floor areas, floor drains, condensate polisher sump piping and regeneration station, and some secondary systems; one sump pump operational; domestic water available.
CACE NONE YES Residual fixed contamination in some floor areas.
Circulating Water Pump House NONE NO Circulating. Water Chlorinator House NONE NO Natural Dmft Cooling Towers NONE NO Airemft warning lights are operational.
Mechanical Draft Cooling Tower NONE N/A Dismantled.
Pmeessed Water Pump House NONE YES Residual contamination in the pump house piping.
Tendon Access Gallery NONE YES Residual contamination in sump; one sump pump l
operational.
River Water and Fire Pump House NONE NO BWST Pipe Chase NONE YES Residual contamination in pipe chase and decay heat removal piping.
6.1-5 AMENDMENT 18 - AUGUST 1993
TABLE 6.1-1 (Cont'd)
DEACTIVATED FACILITIES PDMS INTERNAL FACIIlTY DESCRIPTION FUNCTION CONTAMINATION REMARKS Control Building (M-20) Ama East NONE YES Residual contamination in access tmnk to tendon access gallery.
Control Building (M-20) Area West NONE YES Residual contamination in main steam lines and control building area sump; one sump pump operational.
Emergency Diesel Genemtor Building NONE NO Turned over to Unit 1.
6.1-6 AMENDMENT 18 - AUGUST 1993
6.2.20 TEMPORARY NUCLEAR SAMPLING SYSTEM 6.2.20.1
System Design
This system was designed and installed during the TMI-2 cleanup peric,d. The temporary nuclear sampling system provided representative liquid and gas samples from selected points containing post-accident waste. The analyses of these samples detennined the condition of the plant. The temporary sampling system provided a location for remote sampling of the sources of radioactive water within Unit 2.
The Temporary Nuclear Sampling System provided recirculation and purging of the sample lines, backi' lushing with deminemlized water to reduce activity levels, and transferring the sampling waste back to the storage system. The sampling system also provided the capability to take pressurized and depressurized primary coolant samples.
6.2.20.2 PDMS Function This system provides no active function during PDMS. However, a small portion of the system will remain in service to sample the MWHT. The passive function provided by this system i
during PDMS is contamination control. Contamination within the system is controlled by the isolation of the boundary valves for the contaminated portions of the system.
6.2.21 OTSG CHEMICAL CLEANING SYSTEM 6.2.21.1
System Design
The OTSG Chemical Cleaning System was designed to chemically remove corrosion products and contaminants from selected portions of the Condensate, Feedwater, Emergency Feedwater and Main Steam Systems prior to operation, and from the Steam Generators as needed during the life of the plant. The Feedwater, Condensate, and Main Steam Chemical Cleaning System used temporary piping and equipment connected to the existing system piping.
6.2.21.2 PDMS Function This system provides no active function during PDMS. The passive function provided by this system during PDMS is Containment isolation. The Containment isolation function is provided by valves in the Decon Service Air System, the Processed Water Storage and Recycle System, and the Temporary Decon Water System.
6.2.22 CORE FLOODING SYSTEM 6.2.22.1
System Design
The Core Flooding System was designed to flood the Reactor Vessel core with borated water in the event of a major loss of coolant accident. Release of the water, which was stored in two 1
tanks located inside the Reactor Building, was independent of actuation signals, electric power i
6.2-13 AMENDMENT 18 - AUGUST 1993
TABLE 6.2-1 (Cont'd)
DEACTIVATED PASSIVE SYSTEMS SYSTEM CONTAINMENT INTERNAL SYSTEM DESCRIPTION CODE ISOLATION CONTAMINATION REMARKS Hydrogen Recombiner HR YES NO Emergency Feedwater EF YES YES Reactor Coolant System RC NO YES Waste Disposal - Solid WDS NO YES WDS-FV-612 and 614 are considered part of Sludge Transfer System.
RC Feedwater Heat RCF NO YES SG Secondary Vent & Drain SV YES YES Dewatering System DS NO YES Fuel Transfer Canal Fill & Drain FCC YES YES Fuel Transfer System FH YES YES Temporary AFHB HVAC TWG NO YES Ductwork removed.
Vents VE NO NO Passive venting pathways for secondary systems.
Submerged Demineralizer System SDS NO YES 6.2-27.
AMENDMENT 18 - AUGUST 1993 ou-..a e--
a-u -
.mm
+-
(w-m..
w e
4
+
y w
w w
-.4+=v
1.
Electro-hydraulic Control System Fluid Coolers 2.
Turbine Lube Oil Coolers 3.
Hydrogen Coolers 4.
Hydrogen and Air Side Seal Oil Coolers 5.
Exciter Air Coolers.
s 6.3.12 SECONDARY SERVICES RIVER WATER SYSTEM The Secondary Services River Water System provided a heat sink for the Secondary Services Closed Cooling System, enabling the reuse of the closed cooling water. This was achieved by-supplying river water to the tubeside of the secondary service coolers. The Closed Cooling Water System handled all nonnuclear related cooling water requirements such as main turbine lube oil coolers, hydrogen coolers, and the condensate pump and heater drain pump oil coolers.
4 In addition, the Secondary Services River Water System provided makeup water to the Circulating Water System and to the Pretreatment System.
6.3.13 DEMINERALIZED SERVICE WATER SYSTEM The Demineralized Service Water System was designed to receive demineralized water from the.
Demineralizing System. The water was processed for oxygen removal, stored under a nitrogen blanket, and distributed to service as v.eded. The distribution' headers supplied the Reactor Building, Turbine Building, Control and Service Building, the Auxiliary and Fuel Handling Building, and the Diesel Generator Building.
The Radwaste Pumps Seal Water System, a subsystem of the Demineralized Service Water System, provided seal water to pumps that handled contaminated fluid in either normal.or abnormal operations. During PDMS, this water is supplied by the Domestic Water System.
6.3.14 TURBINE LUBE OIL PURIFICATION AND TRANSFER SYSTEM The Turbine Lube Oil Purification and Transfer System was designed to provide high quality oil for lubrication of the main turbine-generator unit and the two steam generator feedpump turbine assemblies. The purification system continuously extracted oil from the turbine oil reservoirs, removed water and solid contaminants from the lube oil, and returned clean, cool oil to the reservoir. The transfer system functioned to transfer oil between the storage tank and the turbine oil mservoirs.
6.3-5 AMENDMENT 18 - AUGUST 1993 l
5
1 i
4.
Diesel Generator Coolers
~
5.-
Alternate Reactor Building Spray Pumps and Motor Cooler 1
6.
Alternate Makeup Pumps and Motor Cooler
-1 7.
Secondary Plant Sampling Water Chiller 8.
Decay Heat Service Coolers 9.
River Water Pump House Fan Coils 10.
Control Building Area Fan Coils 11.
Control Building Mechanical Room Fan Coils 12.
Control Building Liquid Chiller Condenser 13.
Alternate Supply to Emergency Steam Generator Feedwater Pump Suction.
6.3.16 REACTOR BUILDING NORMAL COOLING WATER SYSTEM -
The Reactor Building Normal Cooling Water System was designed to circulate treated water i
through the Reactor Building air cooling units and to remove the heat thus transferred to the water by passing it through an evaporative cooler.
6.3.17 REACTOR BUILDING PENETRATIONS FORCED AIR COOLING SYSTEM i
The Reactor Building Penetrations Forced Air Cooling System provided cool air to the feedwater and main steam penetrations in the Reactor Building to maintain the temperature of the concrete i
surrounding the penetations within allowable limits.
6.3.18 CIRCULATING WATER AND RIVER WATER CHEMICAL TREATMENT SYSTEM i
The Circulating Water and River Water Chemical Treatment System was designed 'to prevent scale formation in the Circulating Water System and to prevent algae growth in the Circulating.
and River Water Systems.
6.3.19' CIRCULATING WATER SYSTEM j
The Circulating Water System was designed to provide the cooling water requirement for the main condenser. The main condenser performed the following functions:
i 6.3-7 AMENDMENT 18 - AUGUST 1993
.j i
- The trash racks and traveling water screens were designed to prevent objects 3/8 in. and larger from entering the river water pump house intake structure. The trash racks and traveling screens 1
also were designed to automatically mmove the tmpped debris to prevent fouling and allow sufficient flow into the intake stmeture.
6.3.27 FEEDWATER HEATER NITROGEN BLANKETING SYSTEM The Feedwater Heater Nitrogen Blanketing System was designed to store commercial grade i
nitrogen and supply it at a reduced pressure to all of the feedwater heaters except the 14th stage feedwater heaters in the Turbine Building. Nitrogen was used as a purge gas and a noncorrosive cover gas during prolonged shutdown periods to minimize corrosion of the shell side of the
/
feedwater heaters. The feedwater heaters supplied by the nitrogen blanketing system include:
a.
FW-J-2A & B
~:
b.
FW-J-3A & B c.
FW-J-4A & B d.
FW-J-5A & B e.
FW-J-6A & B.
6.3.28 DIESEL FUEL - EMERGENCY DIESEL GENERATOR SYSTEM The diesel fuel system supplied fuel automatically, on demand, to the two emergency diesel generators. The system also maintained a fuel mserve. The diesel generators supplied power for the plant in the event that off-site power was not available. This system has been tumed '
over to Unit 1.
?
6.3.29 LABORATORY GAS SYSTEMS l
The Laboratory Gas System was comprised of a series of gas line systems through which various i
gases were provided for use in the water analysis laboratory in the Service Building. These systems were; a.
Acetylene System
+
b.
P-10 Count Gas System I
c.
Methane System d.
Nitrogen System i
6.3-11 AMENDMENT 18 - AUGUST 1993
1 e.
Nitrous Oxide System f.
Propane System g.
Vacuum System.
Acetylene and nitrous oxide lines were provided to support the operation of an atomic absorption spectrophotometer. P-10 count gas was distributed to support the calibration of radiological l
instruments. Other gases routed by the system included nitrogen, methane, and propane for i
various laboratory uses. Vacuum lines were also provided for testing of various components.
i The basic components of the laboratory gas system included a gas cylinder storage area (located along the north outside wall of the building adjacent to the Borated Water Storage Tank) and tubing runs from the cylinder storage area into the Service Building.
r The system was not designed to seismic criteria. Design pressures and temperatures for the system were based upon the maximum cylinder pressures of the various gas cylinders to be provided. These pressures ranged from 2640 psig (for nitrogen) to 110 psig (for propane). In as much as pressurized gas cylinders provided the motive force for gas transport in the system, there were no pumps associated with the system except for VIeP-1 and VL-P-2, which were the vacuum pumps for each of the two available vacuum connections. The only other major pieces of equipment associated with the system were a line heater (NO-H-1) for the nitrous oxide supply and a flash arrester (AIeV3) for the acetylene supply system.
All storage bottles have been removed for PDMS.
6.3.30 MAKEUP WATER TREATMENT AND CONDENS ATE POLISHING SYSTEM The Makeup Water Treatment System processed Susquehanna River water and provided high i
purity filtered and demineralized water for the Demineralized Service Water System. In addition, this system supplied the condensate polishing system which reduced the level of suspended and dissolved impurities in the feedwater and condensate system to acceptable levels.
6.3.31 AMMONIA SYSTEM The Ammonia System was used in the condensate polishing system to reduce the level of suspended and dissolved impurities in the Feedwater and Condensate System to acceptable levels, thereby eliminating impurities that could cause corrosion of steam generator tubes. The ammonium hydroxide and hydrazine feed to the Condensate and Feedwater Systems were used for maintaining feedwater pH and scavenging oxygen, respectively.
)
6.3-12 AMENDMENT 18 - AUGUST 1993 1
i l
q 6.3.32 REACTOR BUILDING CHITLED WATER SYSTEM This system was designed and installed during the TMI-2 cleanup period. The purpose of the i
Reactor Building Chilled Water System was to reduce the cooling water temperature in the Reactor Building Normal Cooling Water System. This reduced the air temperature in the Reactor Building improving worker health, safety, and efficiency during activities conducted in the Reactor Building.
6.3.33 SAFETY FEATURES ACTUATION SYSTEM The function of the Safety Features Actuation System (SFAS) was to detect a LOCA and automatically actuate engineered safety feature systems and other supporting plant components to control the effects of a LOCA.
6.3.34 BREATHING AIR SYSTEM This system was designed and installed during the TMI-2 cleanup period. Its purpose was to supply supplementary air in the Fuel Handling Building for use as breathing air in contaminated areas.
f 6.3.35 CONTAINMENT AIR CONTROL ENVELOPE HVAC The CACE HVAC was installed during the cleanup period to minimize the exfiltration of i
airborne >ntaminates to the outside environment and to provide heating, cooling, and ventilation for the sCE. One or both HEPA-filtered exhaust units were operated locally when the equipment hatch airlock doors were closed and when it was necessary to remove any airborne particulate contamination that may have been present in the CACE. A radiation monitor with high radiation alarm and sample pump was provided in each filter unit exhaust line.
Differential pressure across the CACE walls was limited l'y pressure relief dampers to protect the structure. Ponable heating and cooling units were operated, as required, to maintain a l
suitable environment for personnel and equipment in the CACE.
6.3.36 CONTROL ROD DRIVE SYSTEM The Contml Rod Drive System (CRDS) trip circuits interrupted power to the Control Rod Drive Motor (CRDM) stators when reactor trip was initiated either by the Reactor Protection System i
or by the operator through the use of the manual reactor trip switch. When all power was-removed from the CRDM stator, the drive mechanism roller nuts disengaged from the leadscrew and allowed the leadscrew and its attached Control Rod assembly to drop by gravity into the reactor core. The Reactor Protection System (RPS) provided power to the four CRDCS trip circuits.
6.3-13 AMENDMENT 18 - AUGUST 1993
)
1 The trip circuits consisted of four independent trip channels, a reactor trip switch and at least one trip actuation device for each channel. Each of the four trip channels received power from the RPS and was energized for the normal (non-tripped) condition. A channel was defined as tripped when it was deenergized. Two independent methods of CRDM power intermption were provide in order to assure that trips would occur when commanded. These methods were in series within the system.
The first, or primary, trip method interrupted the three phase AC power to the CRDM power supplies.
The second trip method deenergized the undervoltage coils of the associated DC breakers.
6.3.37 MISCELLANEOUS INSTRUMENTATION SYSTEM The Miscellaneous Process Instmmentation System provided the required input signals of process variables for the regulating and auxiliary systems. It performed the required process control functions in response to those systems and provided instmmentation for startup, operation and shutdown of the reactor system under normal and emergency conditions.
The non-nuclear instmmentation provided measurements used to indicate, record, alarm, interlock, and control process variables such as pressure, temperature, and level and flow in the RCS, secondary and auxiliary systems.
Process variables required on a continuous bases for the startup, operation and shutdown of the unit were indicated, recorded, and controlled in the Control Room. Alternate essential indicators were provided at other locations to maintain the reactor in a hot or cold shutdown condition if the Control Room had to be evacuated.
Response time and accuracy of measurements were adequate for reactor protection and regulating systems and other control functions. The major design criteria related to the miscellaneous control and instrumentation systems were:
a.
Regulating and control system instrumentation were sepamte from protective system equipment.
b.
Sufficient instrumentation was provided t6 enable the operator to monitor all unit operation conditions.
i c.
Instrumentation ranges were selected to measure the respective maximum process system design conditions.
1 d.
Where measurement of wide process ranges was required and precise control was also involved, both wide range and narrow range instruments were provided.
i 6.3-14 AMENDMENT 18 - AUGUST 1993 I
Pmcess parameters used by the Integrated Contml System during power operations e.
were derived from selectable redundant transmitters.
6.3.38 CONDENSER AIR EXTRACTION FILTRATION SYSTEM The Condenser Air Extraction Filtration System was designed and installed immediately after the accident to treat the effluent of the Condenser Air Extraction System. Primary to secondary leakage during the accident caused contamination of the condenser. All filter elements have been removed from this system for PDMS.
6.3.39 SEAL OIL SYSTEM - GENERATOR SYSTEM This system provided a sealing system to contain hydmgen within the main generator for all modes of operation from turning gear to full power. It was also used to lubricate the generator gland seals.
e I
6.3.40 TEMPORARY NUCLEAR SERVICES CLOSED COOLING SYSTEM This system was designed and installed during the TMI-2 cleanup period. It provided cooling for the mini-decay heat removal heat exchangers. A blank plate was installed in the inlet to spent fuel pool heat exchanger l A to divert sufficient flow through the Temporary Nuclear Services Closed Cooling System.
3 6.3.41 DELETED t
6.3.42 DELETED 6.3.43 RIVER WATER PUMP HOUSE HEATING AND VENTILATION The River Water Pump House Heating and Ventilation System circulated cooled filtemd air throughout the River Water Pump House to remove heat released from the river water pumps and electrical switchgear. The ventilation system limited the temperature in the River. Water i
Pump House to 104*F. In the event of a LOCA, the ventilation system removed the heat released due to the operation of the additional nuclear services river water pump. The heating system maintained a minimum temperature of 50*F in the building spaces without operation of the pump motors.
?
6.3-15 AMENDMENT 18 - AUGUST 1993
6.3.44 CIRCULATION WATER PUMP HOUSE HEATING & VENTILATION The Circulating Water Pump House HVAC System provided heating and ventilation for the Circulating Water Pump House. The system interfaces with the circulating water system pump motors.
6.3.45 FIRE PUMP HOUSE HEATING AND VENTILATION SYSTEM This system provided heating and ventilation for the Fire Pump House. The ventilation was sufficient to limit building temperature to 104*F with the fire pump diesel operating and an -
outside temperature of 92*F. The heating capacity was sufficient to maintain a minimum temperatum of 40 F without operation of the fire pump diesel engine. This system had no interface with any other system.
6.3.46 COAGULATOR BUILDING HEATING AND VENTILATION SYSTEM This system provided filtered air to the Coagulator Building for ventilation purposes. The system also provided heating for the Coagulator Building.
The system interfaced with instrument air required for damper operation.
6.3.47 CHLORINATOR HOUSE HEATING AND VENTILATION SYSTEM This system provided heating and ventilation in the Chlorinator House. The ventilation system minimized the buildup of chlorine fumes in the event of a chlorine leak, while the heating system was designed to maintain temperature of 60 F with an outside ambient temperature of 4 F.
6.3.48 DELETED 6.3.49 TURBINE BUILDING HEATING AND VENTILATION SYSTEM This system circulated filtered air to all parts of the Turbine Building. This system was designed to introduce fresh air to the Turbine Building as well as remove heat produced by mechanical and electrical equipment. The system provided he,st for the Turbine Building in cold weather for suitable working conditions and pipe freeze prote-tion. The system also provided for the exhaust of heat and fumes from the neutralizer tank.,. 0 the oil drum storage area.
6.3-16 AMENDMENT 18 - AUGUST 1993
6.3.50 EARTHQUAKE DETECTION SYSTEM The SMA-3 Strong Motion Accelerograph System manufactured by Kinemetrics, Inc. was installed in the basement of the Reactor Building annulus to measure the strength of seismic events. The SMA-3 was a multi-channel strong motion accelerograph. It featured central recording on magnetic tape cassettes with remote accelerometer and starter packages. The system remained in standby condition and would only activate if an earthquake caused the starter to actuate the recording circuits and tape transports.
6.3.51 REACTOR COOLANT PUMPS MOTOR OIL DRAIN SYSTEM This system was used to drain oil leakage from the RCP motors. Oil was diverted from the upper bearing oil splash shielding and lower bearing oil splash shielding to oil shield drain tanks located in the Reactor Building basement. Not all of this oil has been removed since the dose rates severely limit access to the area of the pumps and oil collection / drain systems. However, the oil collection tanks meet NFPA-30 requirements and are equipped with flame arrestors.
Therefore, the residual oil in the tanks does not present a fire hazard.
6.3.52 DEFUELING TEST ASSEMBLY The Defueling Test Assembly (DTA) was designed and installed during the TMI-2 cleanup period to facilitate mock-up training, defueling tool design, and proof-of-principle demonstrations. The DTA tank filtration system was a temporary system located in the Turbine Building. The system filtered the water in the DTA tank to maintain acceptable _ water clarity.
This system did not handle radioactively contaminated water.
6.3.53 GRAY AND WHITE DIESELS SYSTEM The Gray and White Diesel Generators were installed during the TMI-2 cleanup period. They were designed to power the steam generator cooling systems including the Secondary Services Closed Cooling Water System and the secondary services river water pumps. The objective of these units was to maintain the integrity of existing two bus balance of plant electrical distribution. The diesel generators have been removed from the site.
6.3.54 DIESEL GENERATORS i
The diesel generatcrs were used during normal reactor operation and during the cleanup period.
Upon loss of off-site power, power was supplied to the unit from the two automatic, fast startup
)
diesel generators. The diesel generators were sized so that either one could carry the required.
j safety related loads. Each diesel generator fed one of the engineered safety feamre 4160 buses, 2-lE and 2-2E, and their associated buses. Each generator was capable of feeding the entire connected safety feature load of one 4160 volt bus plus other selected unit loads continuously, 6.3-17 AMENDMENT 18 - AUGUST 1993
11 h
L following a LOCA. Each of the diesel generators was designed for local manual contrul, remote manual control, or fully automatic start. The diesel engines wem to be automatically started by their respective SFAS signal. Upon loss of voltage on either 4160 volt engineered safety feature bus and after both cin:uit breakers of the incoming feeders had been tripped, the associated diesel generator unit was automatically connected to its bus. The diesel generators have been turned over to Unit 1.
I 6.3.55 CHEMICAL LABORATORY TRAILER EXHAUST SYSTEM This system was designed and installed during the TMI-2 cleanup period. Due to the types of samples analyzed in the chemistry lab trailer (e.g., EPICOR processed water), an Exhaust Hood and Filtration System was required. This exhaust system ensured that the effluent air was filtered for particulates and iodine. The system has been dismantled and removed from the site.
6.3.56 POLAR CRANE The Reactor Building Polar Crane is an electric polar bridge crane with a single trolley. It consists of a main hoist designed to be used to lift the Reactor Vessel closure head, the reactor upper plenum assembly, and the reactor core barrel assembly, and an auxiliary hoist designed to be used to perform lifts of refueling equipment. The polar crane was extensively refurbished during the cleanup period to partial capacity of 170 tons and used a modified pendant control.
I j
l 1
6.3-18 AMENDMENT 18 - AUGUST 1993 l
TABLE 6.3-1 DEACTIVATED SYSTEMS SYSTEM PDMS CONTAINMENT INTERNAL SYSTEM DESCRIPTION CODE FUNCTION ISOLATION CONTAMINATION REMARKS -
Auxiliary Steam AS NONE NO NO Bleed Steam EX NONE NO NO Long Tenn OTSG "B" Cooling LTB NONE NO NO Secondary Hydrogen and CO2 HY NONE NO NO Short Tenn OTSG "A" Cooling STA NONE NO NO Feedwater Heater Drains HD NONE NO NO Secondary Plant Sampling SS NONE NO NO Instmment Air IA NONE NO NO Heater Vents and Misc. Drains HV NONE NO NO All bottles of gas removed from plant and all lines purged.
Condenser Air Extraction VA-NONE NO NO Secondary Services Closed SC NONE NO NO Cooling Secondary Services River Water SR NONE NO NO 6.3-19 AMENDMENT 18 - AUGUST 1993
=
TABLE 6.3-1 (cont'd)
DEACTIVATED SYSTEMS SYSTEM PDMS CONTAINMENT INTERNAL
-- SYSTEM DESCRIPTION -
CODE FUNCTION ISOLATION CONTAMINATION REMARKS
'I Demin Water DW NONE NO NO DW-V28 transferred to ' decon.
processed water (DPW) system.
Turbine Lube Oil Purif. &
LO NONE NO NO Trans.
Nuclear Services River Water NR NONE NO NO Reactor' Building Normal Cooling RB NOhE NO NO Renetration Cooling PC NONE NO NO Circulating Water and River.
CL NONE NO N/A All chlorine removed from plant.
Water Chemical Treatment
. Cire. Water CW NONE NO.
NO Condensate System CO NONE NO NO i
Environmental Barrier EB NONE NO NO Penetration Pressurization PP NONE NO NO Gland Steam GS NONE
-NO
- NO Moisture Separator.
-. MO -
NONE-NO NO.
6.3-20 AMENDMENT 18 - AUGUST 1993 -
-....z
TABLE 6.3-1 (cont'd)
DEACTIVATED SYSTEMS SYSTEM PDMS CONTAINMENT INTERNAL SYSTEM DESCRIPTION CODE FUNCTION ISOLATION CONTAMINATION REMARKS Reactor Building Sump Recire.
RRS NONE NO NO Screen Wash Water SW NONE NO NO Nitmgen Blanketing NB NONE NO N/A Diesel Fuel and Starting Air DF NONE NO NO Turned over to Unit 1.
. (Safety Related Diesels)
Acetylene Lab AL NONE NO N/A All bottles of gas mmoved from plant and all lines depressurized.
P-10 Gas Lab MA NONE NO N/A All bottles of gas removed fmm plant and all lines depressurized.- l Methane Gas Lab ML NONE NO N/A All bottles of gas removed from plant and alllines depressurized. l Nitrogen Lab NL NONE NO N/A All bottles removed fmm plant and all lines depressurized.
l.
Nitmus Oxide Lab NO NONE NO N/A All' bottles removed from plant and all lines depressurized.
-l 6.3-21 AMENDMENT 18 - AUGUST 1993.
TABLE 6.3-1 (cont'd)
DEACTIVATED SYSTEhfS SYSTEM PDMS CONTAINMENT INTERNAL SYSTEM DESCRIPTION
. CODE FUNCTION ISOLATION CONTAMINATION REMARKS Propane lab PL NONE NO N/A All bottles removed fmm plant-and all lines depressurized.
l Vacuum Lab VL NONE NO N/A Water Treatment WT NONE NO NO Ammonia AM NONE NO NO Allammonia removed from plant.
Reactor Building Chiller Water RBC NONE NO NO Engineered Safeguards ES
-NONE NO N/A (Safety Features Actuation)
Breathing Air BA NONE NO NO This system is a manifold attached to the "SA" system.
Containment Air Control CH NONE NO NO Envelope HVAC Contml Rod Drive CRD NONE NO NO Miscellaneous Instrumentation YM
.NONE NO N/A Cond. Air Extraction Filter CAE NONE NO NO This system is a post accident addition to the "VA" system.
6.3-22 AMENDMENT 18 - AUGUST 1993
7 1
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TABLE 6.3-1 (cont'd)
DEACTIVATED SYSTEMS SYSTEM PDMS CONTAINMENT INTERNAL SYSTEM DESCRIPTION CODE FUNCTION ISOLATION CONTAMINATION REMARKS Defueling Test Assembly DTA NONE NO NO Gray and Witite Diescis N/A NONE N/A N/A Removed from site.
Diesel Generators DG NONE NO NO Turned over to Unit 1.
Chem 12b Tmiler Filter CLT NONE N/A N/A Removed from site.
Exhaust Polar Crata N/A NONE NO YES 6.3-24 AMENIB1ENT 18 - AUGUST 1993 -
~. - -
T l
CHAPTER 7 TABLE OF CONTENTS (Cont'd)
SECTION TITLE PAGE 7.2.1.4.3 Evaluation 7.2-7 1
7.2.2 FIRE PROTECTION, SERVICE, AND SUPPRESSION 7.2-8 7.2.2.1 PDMS Function 7.2-8 7.2.2.2
System Description
7.2-8 7.2.2.3 Evaluation 7.2-10 7.2.3 RADIOACTIVE WASTE MANAGEMENT 7.2-11 7.2.3.1 Radioactive Waste - Miscellaneous Liquids 7.2-11 7.2.3.1.1 PDMS Function 7.2-11 7.2.3.1.2
System Description
7.2-12 7.2.3.1.3 Evaluation 7.2-13 7.2.3.2 Sump Pump Discharge and Miscellaneous Sumps System 7.2-13 7.2.3.2.1 PDMS Function 7.2-13 7.2.3.2.2
System Description
7.2-14 7.2.3.2.3 Evaluation 7.2-14 7.2.4 RADIATION MONITORING 7.2-14 7.2.4.1 PDMS Function 7.2-14 7.2.4.2 Radiological Surveys 7.2-15 1
7.2.4.2.1 AFHB Radiological Surveys 7.2-15 7.2.4.2.2 Containment Radiological Surveys 7.2-15 7.2.4.3 Effluent Monitoring 7.2-15 7.2.4.3.1 AFHB Airborne Evaluation 7.2-17 7.2.4.4 General Radiological Monitoring 7.2-17 7.2,4.5 Evaluation 7.2-17 iii AMENDMENT 18 - AUGUST 1993
s CHAPTER 7 TABLE OF CONTENTS '(Cont'd)
SECTION 1]ILE PAGE a
7.2.5 ELECTRICAL SYSTEMS 7.2-17 7.2.5.1 Auxiliary Electrical Distribution System 7.2-17a 7.2.5.1.1 PDMS Function 7.2-17a 7.2.5.1.2
System Description
7.2-17a 7.2.5.1.3 Evaluation 7.2-18 7.2.5.2 Normal and Emergency Lighting 7.2-19 7.2.5.2.1 PDMS Function 7.2-19 7.2.5.2.2 Sy:; tem Description 7.2-19.
7.2.5.2.3 Evaluation 7.2-20 7.2.5.3 Communications System 7.2-20 7.2.5.3.1 PDMS Function 7.2-20 7.2.5.3.2 -
System Description
7.2 i 7.2.5.3.3 Evaluation 7.2-21 7.2.6 -
PDMS SUPPORT SYSTEMS 7.2-21 7.2.6.1 Auxiliary Building Ventilation System -
7.2-21 7.2.6.1.1 PDMS Function 7.2-21 7.2.6.1.2
System Description
7.2-22 7.2.6.1.3 Evaluation 7.2-22 7.2.6.2 Fuel Handling Building Ventilation System 7.2-22 7.2.6.2.1 PDMS Function 7.2-22 7.2,6.2.2 System Description -
7.2-22 7.2.6.2.3 Evaluation 7.2-23
- i 1
iv AMENDMENT 18 - AUGUST 1993
CHAPTER 7 TABLE OF CONTENTS (Cont'd)
SECTION TITLE PAGE 7-.2.6.3 Air Intake Tunnel Ventilation System 7.2-23 Y
7.2.6.4 Compmssed Air Supply System 7.2-23 7.2.6.4.1 PDMS Function 7.2-23 7.2.6.4.2
System Description
7.2-23 7.2.6.4.3 Evaluation 7.2-24 7.2.6.5 Building Inleakage Waterproofing System 7.2-24 7.2.6.5.1 PDMS Function 7.2-24 7.2.6.5.2
System Description
7.2-24 7.2.6.5.3 Evaluation 7.2-24 7.2.6.6 Sewers 7.2-25 7.2.6.6.1 PDMS Function 7.2-25 7.2.6.6.2
System Description
7.2-25 7.2.6.6.3 Evaluation 7.2-25 7.2.6.7 Domestic Water System 7.2-25 7.2.6.7.1 PDMS Function 7.2-25 7.2.6.7.2
System Description
7.2-25 7.2.6.7.3 Evaluation 7.2-25 7.2.6.8 Control Room Ventilation System 7.2-25a 7.2.6.8.1 PDMS Function 7.2-25a 7.2.6.8.2
System Description
7.2-25a 7.2.6.8.3 Evaluation 7.2-25a 7.2.6.9 Cable Room Ventilation System 7.2-25a 7.2.6.9.1 PDMS Function 7.2-25a v
AMENDMENT 18 - AUGUST 1993 -
CHAPTER 7 TABLE OF CONTENTS (Cont'd)
SECTION TITLE PAGE a
7.2.6.9.2
System Description
7.2-25a 7.2.6.9.3 Evaluation 7.2-25b 7.2.6.10 Service Building Ventilation System 7.2-25b 7.2.6.10.1 PDMS Function 7.2-25b 7.2.6.10.2 System Description.
7.2-25b 7.2.6.10.3 Evaluation 7.2-25b 7.2.6.11 PDMS Alarm Monitoring System 7.2-25b 7.2.6.11.1 PDMS Function 7.2-25b 7.2.6.11.2
System Description
7.2-25c 7.2.6.11.3 Evaluation 7.2-25c i
7.2.6.12 Control Building - Mechanical Equipment Room 7.2-25d Ventilation System 7.2.6.12.1 PDMS Function 7.2-25d
'7.2.6.12.2
System Description
7.2-25d 7.2.6.12.3 Evaluation 7.2-25d 7.2.6.13 Contml Building Area Ventilation System 7.2-25d 7.2.6.13.1 PDMS Function 7.2-25d 7.2.6.13.2
System Description
7.2-25d 7.2.6.13.3 Evaluation 7.2-25d 1
I 7.3 SYSTEM REFERENCES 7.3-1 i
.1 1
I vi AMENDMENT 18 - AUGUST 1993 1
1
l CHAPTER 7 TABLE OF CONTENTS (Cont'd)
LIST OF FIGURES FIGURE NO.
TITLE PAGE 7.2-1 CONTAINMENT ATMOSPHERIC BIEATHER "MOST 7.2-40 PORTABLB" PATHWAY MODEL 7.2-2 IEACTOR BUILDING VENTILATION AND PURGE 7.2-41 7.2-3 FIRE PROTECTION 7;2-42 7.2-4 FIRE PROTECTION 7.2-43 7.2-5 DELETED 7.2-44 7.2-6 DELETED 7.2-45 7.2-7 DELETED 7.2-46 7.2-8 RADWASTE DISPOSAL MISCELLANEOUS LIQUIDS 7.2-47 7.2-9 RADWASTE PUMPS SEAL WATER 7.2-48 7.2-10 SUMP PUMP DISCHARGE AND MISCELLANEOUS SUMPS 7.2-49 7.2-11 RADIATION SURVEY LOCATIONS; ELEVATION 347' 7.2.-50 7.2-12 RADIATION SURVEY LOCATIONS; ELEVATION 305' 7.2-51 7.2-13 BUILDING AIR INTAKE, EXHAUST, AND RADIATION 7.2-52 MONITORING 7.2-14 GENERATOR, 500 KV AND 230 KV SYSTEMS 7.2-53 ONE LINE DIAGRAM 7.2-15 6900V SWITCHGEAR ONE LINE DIAGRAM 7.2-54 7.2-16 4160V SWITCHGEAR ONE LINE DIAGRAM 7.2-55 7.2-17 4160V SWITCHGEAR ONE LINE DIAGRAM 7.2-56 viii AMENDMENT 18 - AUGUST 1993
The' Air Intake Tunnel also helps. prevent the spread of fire into plant ventilating systems.
Combustible material has been removed from the Air Intake Tunnel.
Additionally, heat detectors located in the Air Intake Tunnel will trip the ventilation supply fans and provide an
-)
alarm in the event of a fire. Tripping the supply fans will also cause the fan inlet and outlet
)
- dampers to shut.
j 7.1.6 UNIT 1/ UNIT 2 ' CORRIDOR 7.1.6.1 PDMS Function During PDMS, the Unit 1/ Unit 2 corridor serves as an operational facility to provide:
j a.
Heated weather enclosure for various operational system piping such as domestic water and Unit I discharge to IWTS.
b.
Access to the Auxiliary Building from the east outside yard thmugh rollup security -
1 door 10.
}
c.
Interconnecting corridor between Unit I and Unit 2.
7.1.6.2 Facility Description The Unit 1/ Unit 2 corridor is a heated passageway mnning nonh to south adjacent to the east side of the Turbine, Service and Control, and Auxiliary Buildings. It is a steel frame stmeture with metal siding over a concrete base floor, with a partial block wall up to the windows to the outside east yard. The roof consists of built up layers of felt and asphalt.
All equipment in the Unit 1/ Unit 2 corridor related to the waste shredding and' packaging operation and all radioactive material not contained in piping were removed for PDMS.
7.1.6.3 Evaluation i
The ITnit 1/ Unit 2 corridor provides sufficient heating during PDMS to prevent freezing of the enclosed operational system piping.
All contaminated equipment has been removed 'or adequately isolated to minimize spread of contamination.
-7.1.7 CONTROL AND SERVICE BUILDINGS 7.1.7.1 PDMS Function 4
The Control Building houses the Unit 2 Control Room, two battery rooms, a cable room, and j
a mechanical equipment room.
Although the PDMS Alarm Monitoring System directs i
instmment outputs to the Unit 1 Control Room, the Unit 2 Control Room will be relied upon i
to provide specific information should the need arise.
)
'7.1-7 AMENDMENT 18 - AUGUST 1993 I
I v
The Service Building houses the operational Compressed Air System compressor and associated piping. In addition, the Service Building provides access to the Reactor Building, the Auxiliary '
Building and the Unit 2 Control Room.
7.1.7.2 Facility Description i
The Control and Service Buildings are separated by a common wall. The Control and Service Buildings are rectangular buildings with a common foundation mat. The floors of the Control Building are supported by interior walls. A peripheral gap of 4 in. between edges of the floors and the inside face of the exterior walls has been provided to create a stmetural separation between the exterior stmeture and the interior stmeture. The purpose of this separation was to i
pmtect vital and sensitive Control Room equipment from dynamic aircraft impact loading to which the exterior wall: ad the roof could be subjected. Door openings and other penetrations in exterior walls of the Control Building that are susceptible to aircraft loading have been shielded by reinforced concrete shield walls.
Duritig PDMS, the Control Building Ventilation Systems (i.e., Control Room HVAC, Mechanical Equipment Room HVAC, and Cable Room HVAC) and the Service Building l
Ventilation System will be maintained in an operational condition and will be operated as required.
When the ventilation systems are not in operation, the atmosphere will be barometrically equalized with the outside environment.
Electronic distribution will remain configured to power low voltage (120/208 VAC) lighting loads and fire detectors.
7.1.7.3 Evaluation The Contml and Service Buildings configuration for PDMS minimizes sources of contamination; therefore, the potential for spread of contamination is very low.
I 7.1-8 AMENDMENT 18 - AUGUST 1993
1 s
during PDMS.
7.2.1.3' Containment Ventilation and Purge 7.2.1.3.1 PDMS Function During PDMS, the Containment Ventilation and Purge System ensures that uncontmlled l
i atmospheric migration of radioactive contamination will not create a hazard to either the public or site personnel.
7.2.1.3.2
System Description
The Containment Ventilation and Purge System will be maintained in an operational condition l
to support activities in the Containment (e.g., surveillance entries, maintenance) during PDMS.
Testing to ensure operability of the Containment Ventilation and Purge includes HEPA filter l
pressure drop, exhaust flow rate, DOP testing (guidance provided by ANSI N510-1980), and visual inspection of the filter train. The Containment Ventilation and Purge System consists of l
a single operational Containment purge exhaust unit and associated ductwork, dampers, and filters. The purge exhaust unit (maximum flow 25,000 cfm) draws air from the D-rings through HEPA filters, and discharges to the station vent. The PDMS configuration is shown on Figure 7.2-2.
t i
f P
7.2-6a AMENDMENT 18 - AUGUST 1993
x i
to complete the mlevant activity and the Reactor Bui!dir.g Purge System would be. operating, thereby. minimizing any effluent.
Natural phenomena, such as floods and high winds, are not considered to pose a safety concern because there is adequate warning to ensure that the airlock doors could be closed prior to a significant release. From a seismic standpoint, the airlocks serve no structural ftmetion,.and therefore, will not affect the seismic integrity of the Containment.
7.2.2 FIRE PROTECTION, SERVICE, AND SUPPRESSION Fire Protection is pmvided during PDMS to minimize the potential for a release of radioactive material due to a fire in a contaminated area, protect systems maintained operational during PDMS, minimize the liability and propeny risk from potential fires, and minimize any potential risk to the operating unit on the same site.
These objectives are achieved by minimizing the potential for a fire by strict control of.
combustible materials and ignition soumes and by providing a system of detection and suppression suitable to deal with any potential fire.
7.2.2.1 PDMS Function The overall fire protection objectives are achieved by providing a system of fim protection i
features designed to ensure the following primary functional requirements:
a.
Fire detection shall be provided to the extent that any credible fire will be detected.
b.
Portable fire extinguishers shall be provided in amas of the facility, as necessary, to provide adequate fire suppression capability, f
c.
Pmsence of flammable and/or combustible liquids and materials shall be minimized
~l to the maximum extent practical.
7.2.2.2
System Description
The original TMI-2 system of fire protection has been modified to address the functional' requirements for fire protection for PDMS. The Fire Detection, Service, and Suppression System as configured for PDMS are shown on Figures 7.2-3 and 7.2-4. The measures required to provide the necessary degree of fire protection are described below.
7.2-8 AMENDMENT 18 - AUGUST 1993 I
P
a.
The yard fire main will be maintained pressurized using the station fire pumps in Unit I with the altitude tank as a backup water source. The Unit 2 Fire Protection System draws its supply water from the tie-in to the yard fire main.
b.
The fire protection zone detection system originally provided at TMI-2 will remain operational throughout operational areas of the plant. Table 7.2-4 lists those areas where fire detection is operational (PDMS status "OS") or deactivated (PDMS status "DS"). Remote monitoring capabilities are provided in the TMI-1 Control Room via the PDMS Alarm Monitoring System (Section 7.2.6.11). The specific zone panel which indicates the location of the fim will be identified by that system.
The operable portion of the fire detection and alarm systems will be tested every 6 months by performing channel functional tests and supervised cirruit tests. For non-supervised circuits between the local panels and the remote monitoring station in the TMI-l Control Room, testing will be performed every 31 days to demonstrate operability.
Equipment-related fire detectors, installed on various components within the plant c.
to monitor a specific hazard and automatically trip the associated fire suppression system, have been deactivated; the related fire suppression system has also been deactivated.
d.
The Halon systems protecting the Air Intake Tunnel have been deactivated by either removing or emptying the Halon cylinders and deenergizing the ultraviolet and pressure detectors. The Halon system protecting the relay room has been deactivated by disconnecting the cylinders and either removing or emptying them.
The fim detection system will remain operational to monitor these areas.
e.
Portable fire extinguishers and self-contained breathing apparatus are staged with emergency response crew equipment.
f.
Transient combustibles inside the Containment and the AFHB have been removed to the maximum extent practical.
7.2-9 AMENDMENT 18 - AUGUST 1993
l l
i g.
The oil has been drained fmm the main turbine, feedwater pump turbines, l
emergency feedwater pump turbine, main feedwater pumps, emergency feedwater pumps, condensate pumps, condensate booster pumps, and the hydrogen seal oil I
unit.
1 h.
The chamoal filters have been removed from all HVAC systems in Unit 2.
l i.
The 12 in. fire service loop, which runs through the Diesel Generator Building, l
AFHB, Control Building area and Turbine Building (east and west), has been isolated. The Diesel Generator Building has been turned over to TMI-1. As part of the modifications to suppon TMI-l use of the Diesel Generator Building, the fire system line has been cut and blanked off at the Fuel Handling Building where the fire system line mns fmm the Diesel _ Generator Building. This modification eliminates the need for freeze protection of the fire system in the AFHB from this end of the fire system loop.
To prevent the fire system loop from repressurizing due to seat leakage through closed loop isolation valves (supplies on the east and west Turbine Building headers),1 inch drain valves have been installed. These drains are piped to the Turbine Building sumps and will remain open while the system is isolated to provide for freeze protection. These drain valves which are normally open for drainage purposes will be inspected monthly during freezing weather (October through April).
j.
All portions of the Fire Protection System located inside buildings in areas where l
the fire hazard risk is small have been deactivated. The system has been placed in a configuration which allows reactivation of the deactivated ponions by the realignment of valves if necessary.
k.
The station fire brigade has been fully trained to assure that the personnel are familiar with system configurations, plant layout, and the procedures in Unit 2.
7.2.2.3 Evaluation The scope of fire protection has been reduced for areas in which systems have been deactivated and combustibles have been significantly reduced, so that the corresponding fire hazards have been minimized.
t 7.2-10 AMENDMENT 18 - AUGUST 1993
Deluge systems in the Auxiliary and Control Buildings have been deactivated for PDMS. There l
are no deluge systems in the Containment.
Detection devices provide contacts for supervisory indicadon that each device is operational and, in the event of detector actuation, indicates which detector actuated the alarm or trip function until reset.
The station fire brigade is under the supervisory control of Unit 1. Upon detection of a fire in Unit 2, the station fire brigade will respond to the specific location in Unit 2. This response in accordance with ongoing station fire brigade training and procederes wil' erisure mitigation of a fire in Unit 2 during PDMS. The fire protection and suppression systew are configured to pmvide adequate capability to extinguish any potential fire during PDMS.
7.2.3 RADIOACTIVE WASTE MANAGEMENT Liquid mdwaste management systems that are operational during PDMS are the Radioactive Waste - Miscellaneous Liquids System and the Sump Pump Discharge and Miscellaneous Sumps System. Major portions of these two systems are operational during PDMS to prevent localized flooding and to provide proper disposal of effluents.
7.2.3.1 Radioactive Waste - Miscellaneous Liquids 7.2.3.1.1 PDMS Function During the PDMS period, portions of the WDL system remain operational. This Matus provides assurance that significant quantities of liquid wastes will not accumulate in an uncontrolled manner in the Auxiliary Building and Containment. Liquid radwaste in these buildings may result from either rainwater inleakage or PDMS activities. The WDL system achieves its objective by meeting the following criteria.
a.
Existing sumps in the Auxiliary Building and Containment will be monitored and pumped, as required.
b.
Tie-ins to the EPICOR II system will be maintained so that accumulated liquids can be processed, as necessary.
c.
Liquid storage capabilities have been provided for accumulation until sufficient quantities are available for batch processing through the EPICOR II system.
d.
Existing Unit 1 and Unit 2 WDL system tie-ins have been isolated. The capability to process Unit 2 low-level liquid radwastes through the EPICOR II system has -
been retained for PDMS in anticipation of the eventual deletion of the TMI-1 Condition of Operation prohibiting the transfer of Unit 2 liquid to Unit 1..
7.2-11 AMENDMENT 18 - AUGUST 1993
i tanks.
The Containment Sump and Sump Pumps are in an undetermined condition. Because the existing plant sump pumps WDIeP-2A and 2B have not been refurbished, an alternate flow path will be utilized to drain down the RB basement floor. A tie-in to the WDL system has been provided outside of penetration R-593. This tie-in mns from the decay heat removal pump suction header isolation valve test connection to the RB spray pump room sump.
7.2.3.1.3 Evaluation i
Because a majority of plant systems are deactivated, have been drained, and placed in a layup condition, there are a limited number of activities that can generate liquid waste during PDMS.
Liquid waste in the remaining systems and accumulated water inleakage will be adequately handled by periodic batch processing using the operationalportions of the WDL system through EPICOR II and discharged via approved pathways. This ensures minimum exposure to plant personnel and minimizes releases to the environment in accordance with 10 CFR 20 and 50.
7.2.3.2 Sump Pump Discharge and Miscellaneous Sumps System 7.2.3.2.1 PDMS Function There are a number of sumps in TMI-2 that will be maintained in an operational condition during PDMS. The various sumpe and their locations are listed in Table 7.2-3.
Maintaining the various buildir', sumps operational assures that water buildup does not cause adverse localized flooding. T' ese sumps will contain water that is either clean or slightly radioactive. Clean water is p eser.tly routed to the Industrial Waste Treatment System (IWTS).
Ra(aactive water requirio, processing will be routed to EPICOR II* and discharged via l-approved pathways; slighto radioactive water will be pumped to the nVTS and released in accordance with 10 CFR 20,10 CFR 50 and NPDES regulations. The discharge from the RVTS is monitored for radiation in accordance with the ODCM.
t The EPICOR II System will be used after the TMI-l Condition of Operation prohibiting the transfer of Unit 2 liquid to Unit 1.is rescinded.
7.2-13 AMENDMENT 18 - AUGUST 1993
7.2.3.2.2
System Description
The designs of the various sumps are delineated in the applicable documents referenced in Section 7.3. The PDMS configuration is shown on Figum 7.2-10. Sumps have pumps that were originally capable of automatic operation. The sump pumps will normally be opemted in a manual control mode, with a high level alann that annunciates in the control room and the PDMS Alarm Monitoring System. Sump level is monitored by three float switches located in the respective sumps.
The exceptions are the Circulating Water Chlorinator Building, Circulating Water Pump House, and the Air Intake Tunnel Normal Sumps which will employ portable sump pumps to pump down the sumps as necessary.
Water from the floor drains that enters these sumps is generally not contaminated, although sumps within the Turbine Building, Control Building Area, Control and Service Building, and Tendon Access Gallery have recirculation and grab sample lines to enable sampling for radioactivity.
7.2.3.2.3 Evaluation In general, the functional requirements of each sump and sump pump have been determined on an individual basis.
Monitoring oflevel in the various sumps by remote means and/or visual inspections ensures that accumulated leakage is transferred for processing in a timely manner. Sampling will be used l
to quantify radioactive content and ensure proper waste stream processing.
Therefore, operation of the sump pump discharge system ensures liquid waste streams generated 1
during PDMS are adequately transferred for ultimate processing and do not adversely affect the PDMS plant conditions.
7.2.4 RADIATION MONITORING 7.2.4.1 PDMS Punction i
During PDMS, the radiation monitoring requirements for the facility are primarily those associated with assuring the stability of the radiological conditions in the facility and effluent monitoring. The off-site dose calculations for normal time periods and unanticipated events (see l
Chapter 8) are based on assumed and measured radiological conditions associated with the 4
various areas of the facility. In order to assure that the off-site dose calculations for the various events remain bounding, the radiological conditions must be periodically monitored to assure they remain within acceptable bounds. In addition, all effluents must be monitored to assure all off-site releases are within acceptable bounds, as well as to meet regulatory requirements for 7.2-14 AMENDMENT 18 - AUGUST 1993
I effluent reporting.
Broader radiological conditions monitoring will be conducted throughout the facility to assure i
compliance with good radiological conditions practices and 10 CFR 20. These radiological monitoring activities are required to support other PDMS activities such as visual inspections, preventive maintenance or other routine tasks.
7.2.4.2 Radiological Surveys 3
7.2.4.2.1 AFHB Radiological Surveys Radiological surveys will be conducted on a periodic basis to monitor radiological conditions in the Auxiliary and Fuel Handling Buildings. These radiological surveys will be conducted quarterly except during the initial period of PDMS (minimum of 6 months) when monthly.
radiological surveys in the AFHB will be performed in order to develop an adequate data base.
j The surveys will consist of air sampling, loose surface contamination, and radiation dose rate surveys. In addition, TLDs may be placed in fixed locations and changed out periodically to monitor dose rates over a long-term period. Radiological survey results will be n: viewed and evaluated for trends to provide early detection of deteriorating radiological conditions.
7.2.4.2.2 Containment Radiological Surveys Periodic Containment radiological surveys are required to provide information regarding the stability of the radiological conditions inside the Containment. As stated in Section 7.2.4.1, this information is necessary to periodically validate the off-site releases as calculated in Chapter 8.
Radiological surveys in the Containment will be conducted quarterly, as expressed in Regulatory Guide 1.86 Position 3.C, and, as a minimum, at the approximate locations shown on Figures 7.2-11 and 7.2-12. Monthly radiological surveys in the Containment were performed after the RB was placed in its PDMS condition in order to develop an adequate data base. These surveys consisted of loose surface contamination and radiation dose rates at all survey locations and at least one air sample inside the containment.
t The quarterly surveys will collect data from the same locations. In addition, TLDs may be placed in fixed locations and changed out periodically to monitor dose rates over a long-term period. These surveys will be reviewed and evaluated for any indicated trends. This will either provide assurance that contamination conditions inside the Containment are stable or will pmvide early indication of any changing conditions which may require corrective action.
7.2.4.3 Effluent Monitoring Airborne' effluents will be monitored during active and passive ventilation of the Containment.
Periodic operation of the Reactor Building Purge and AFHB exhaust may be necessary during personnel entries. Dur.ng Reactor Building Ventilation System operation, the station ventilation i
stack monitor, HP-n-219 or HP-R-219A, will provide real time monitoring of releases. The Reactor Building cffluent monitoring system is shown on Figure 7.2-13.. During periods when the Containment ventilation systems are not operating, airborne effluents from the Containment will continue to be monitored as discussed in Section 7.2.1.2.3.
~
7.2-15 AMENDMENT 18 - AUGUST 1993
The Containment is passively vented to the Auxiliary Building through a breather pathway which will be filtered using a HEPA filtration system. During periods of Reactor Building Purge operation the breather pathway will be isolated. During passive ventilation the purge exhaust will be isolated and the Containment will be verted through the breather HEPA fiker. ' On a semi-annual basis, a sample filter paper installed downstream of the HEPA filter will be assayed for its radioactivity content to evaluate any release to the environmem during periods of inactivity.
The Containment Atmospheric Bmather System allows pressure equalization between the Containment and the environment via the Auxiliary Building. For this reason there is no motive force to cause contamination to leak out other than through the Containment Atmospheric Breather. Therefore, it is not anticipated that releases to the environment will occur through pathways other than the breather. Operating procedures for Containment isolation and inspection of airlock door seals, whenever the doors are opened, will be used during PDMS to ensure isolation is maintained.
In the AFHB, negligible airborne effluent discharges are anticipated during normal events. This conclusion is based on three factors: 1) de facto isolation of the AFHB, 2) prevention of.
airbome events within the AFHB, and 3) the periodic monitoring of radiological conditions.
Access to the AFHB is limited and controlled by site procedums. In addition, when the AFHB heating and ventilation system is not operating, the system supply dampers are shut. The system exhaust dampers, however, remain open, thereby creating a most probable pathway for AFHB airborne effluents while allowing pressure equalization with the environment. The ventilation system exhaust, as'shown in Figums 7.2-43 and 7.2-44, houses a prefilter for large particulates, and two banks of DOP-tested HEPA filters in series. With the AFHB essentially isolated, there is no motive force to generate significant airborne contamination levels, and any airborne contamination that might develop is filtered by the ventilation system exhaust pathway prior to release at the Station Vent.
Prevention of airborne contamination within the AFHB results, in part, from the lessened level r.nd frequency of plant system operations and reduced access and activities of plant personnel.
In addition, internally contaminated systems inside the AFHB are drained ofliquids, and isolated by closing the respective boundary valves. Spent fuel pool "A" was sealed since it contained I
loose contamination sufficient to pose a contamination spmading concern.
Throughout PDMS, an ongoing radiological surveillance program will monitor radiological conditions within the AFHB. By means of various surveys, as described in Section 7.2.4.2, potential degradation of mdiological conditions will be identified in order for appropriate remedial actions to be taken. A special monitoring program of AFHB airborne levels, see j
Section 7.2.4.3.1, was conducted for a one year period prior to PDMS, and will be' continued for a minimum of one year after implementation of PDMS. The information gathered during these evaluations constitutes an extensive data base that pmvides additional assurance that AFHB airborne effluent releases will be insignificant in nature. In addition to the special monitoring program, whenever the AFHB ventilation systems are opemted during PDMS, the HEPA filtered exhaust is also monitored by the mal time sampling of the Station Vent Monitor, thus assuring a controlled, monitored effluent release.
7.2-16 AMENDMENT 18 - AUGUST 1993
Considering that the AFHB has orders of magnitude less contamination than the Containment, the airborne effluent controls described above are sufficient for assuring airborne effluent releases from the AFHB during normal events will be insignificant.
A cenain amount of inleakage into sumps is anticipated during PDMS and periodic discharges will be necessary. Initial samples will be taken and analyzed to quantify radioactive effluents.
All radioactive liquid discharges will be via an approved pathway which will provide dilution and monitoring capabilities.
7.2.4.3.1 AFHB Airborne Evaluation A special monitoring program was designed to evaluate particulate airborne concentations in the AFHB prior to, and after, entry into PDMS. The purpose of the evaluation is to determine the airborne levels in the AFHB during steady state conditions.
The most representative sample point of unfiltered AFHB airborne particulates is directly upstream of the plant ventilation system HEPA filter banks.
Installed plant monitoring capabilities exist at both of these locations, i.e., HP-R-221 A for the Fuel Handling Building and HP-R-222 for the Auxiliary Building. The moving filter paper mechanisms of these plant monitors have been disabled, creating fixed filter sample points. The filter papers at these plant monitors are periodically changed out, and air sample results are reported quarterly.
The special monitoring program has been and will be, temporarily suspended whenever plant activities in the AFHB are expected to generate significant airborne levels.
7.2.4.4 General Radiological Monitoring It is anticipated that the routine radiological surveys will only be performed in areas mquiring access for visual inspection, preventive maintenance, or other routine tasks. "High radiation,"
"high contamination," and sealed areas will not normally be accessed for routine surveys unless access is required for some other purpose. Radiological suppon of work during PDMS will be conducted in accordance with Radiological Controls procedures and good radiological work practices.
7.2.4.5 Evaluation The radiological effluent and monitoring programs described above address the principal i
radiological concerns for PDMS. These programs assure the radiological conditions in the facility are monitored and any significant deteriomting conditions will be identified in a timely period and appropriate correction action taken. Also, both liquid and gaseous effluents am monitored to assure all radioactive mieases are within acceptable bounds. These monitoring j
programs, in conjunction with geneml radiological controls activities, assure that the radiological aspects of PDMS are appropriately addmssed.
7.2.5 ELECTRICAL SYSTEMS l
During PDMS, various plant systems will be required to remain operational to support the i
monitoring, protection, and surveillance activities associated with PDMS. Some systems require 7.2-17 AMENDMENT 18 - AUGUST 1993 p
7
i continuous operation while others requim only intermittent operation. Due to the need for electrical power support for these activities, portions of the Auxiliary Electrical Distribution System will be maintained operational and remain energized during PDMS.
j l
7.2.5.1 Auxiliary Electrical Distribution System j
I 7.2.5.1.1 PDMS Function i
During PDMS, portions of the TMI-2 Auxiliary Electrical Distribution System will be maintained operational and energized to provide reliable power sources for the PDMS support systems and their associated controls and instrumentation. Power will also be available for area lighting, receptacles, heating and ventilation to support PDMS surveillance activities. In some instances, systems utilized for PDMS surveillance activities may require energization from local control stations prior to commencing the surveillance activity.
7.2.5.1.2
System Description
The TMI-2 Auxiliary Electrical Distribution System is powered from a 13.2 KV offsite power source. The 13.2 KV/480 VAC transformers, in Unit Substations 2-31,2-32,2-35,2-45 and 2-37, provide 480 VAC power to locations in the Turbine, Service and Auxiliary Buildings.
Unit Substation 2-31 provides 480 VAC to bus Unit Substation 2-22E in the Control Building.
All of the PDMS electrical loads are consolidated on these six buses.
Unit Substations 2-31 and 2-32 provide 480 VAC to three Motor Control Centers (MCCs), MCC 2-31 A, MCC 2-32A and MCC 2-42C. These contain combination motor starters using molded case circuit breakers and magnetic contactors.
The low voltage 120/208-volt AC distribution system supplies control, instrumentation, and power loads requiring unregulated 120/208-volt AC power.
It consists of distribution panelboards, branch breakers, and transformers located in and powered from 480-volt MCCs thmugh 480/120-volt dry-type transfonners.
A 125-volt battery charger provides DC power to a single distribution panel. The battery charger is normally fed from Unit Substation 2-22E. In the event of a power loss, an automatic transfer switch will provide backup power from the Unit 1 Station Blackout bus. All PDMS DC control and fire detector loads have been consolidated on this panel.
The vital 120-volt AC system consists of two distribution panels,2-12R and 2-22R, fed fmm regulated transformers. They receive power from Unit Substation 2-22E through 480/120-volt step-down-transformers. An automatic transfer switch provides backup power to panel 2-12R fmm the Unit 1 Station Blackout bus in the event primary power is lost. The regulated 120-volt AC power system supplies control and instrumentation loads as well as power for fire detection, communication and annunciators.
7.2-17a AMENDMENT 18 - AUGUST 1993
7.2.5.2 Normal and Emergency Lighting 7.2.5.2.1 PDMS Function TMI Unit 2 is provided with normal lighting systems using mercury-vapor, fluorescent and incandescent luminaries. These systems provide illumination for PDMS support activities and for personnel safety. All lighting not required for security and monitoring activities will be turned off. Lighting will be energized as needed for maintenance activities.
Installed emergency lighting will be maintained during PDMS. Normal lighting as originally designed and installed is available throughout TMI-2 except in the RB. Normal lighting within the RB is provided by strings of lights installed on the 305' and 347' elevations. The lighting is adequate to support PDMS inspection and test activities without additional illumination fmm permanently installed building lighting. Eight-hour portable emergency lighting will be carried by emergency personnel crews entering the buildings. This lighting will be staged with emergency response crew equipment. Routine entry crews will carry flashlights.
7.2.5.2.2
System Description
The normal lighting system is powered from normal AC power sources; an exception to this is the RB lighting system discussed below. This system utilizes three types. of luminaries:
mercury-vapor, fluorescent and incandescent. The mercury-vapor luminaries are powered fmm 480/277-volt systems directly from the 480-volt unit substations or fmm 480-volt motor contml centers. The fluorescent and incandescent luminaries are powered from 208/120-volt sys evn utilizing 30 KVA step-down transformers which are supplied from the.480-volt sources. In general, the mercury-vapor luminaries are used in high ceiling areas, the fluorescent luminaries in almost all other areas, and the incandescent luminaries where environmental conditions require their use. Exit signs are powered from the normal lighting system; there is no backup battery for these signs.
The RB normal lighting system consists of lights on the 305' and 347' elevations fed from Portable Power Distribution Centers (PPDC) or " power buggies." These power supplies were originally installed in the RB to support defueling activities. Two power buggies are located on the 305' elevation and two are located on the 347' elevation. The power feed is fmm either USS 2-35 or USS 2-45 and is configured such that the two power buggies on each elevation are energized from different sources, i.e., on each elevation, one-half of the lighting is fed from one source and the other half is fed from the other source. In the event one source of power is lost during an entry, adequate lighting would remain to assist in the safe evacuation of personnel.
Emergency lighting consists of sealed beam lamps powered by batteries which initiate operation upon loss of the normal lighting system. This lighting is provided to ensure safe egress for personnel. Additional exit information will be provided by postings.
7.2-19 AMENDMENT 18 - AUGUST 1993 m
d.
Commercial Telephone System This system's trunk lines, handsets and switching equipment are installed by, and '
l leased from, the Bell Telephone Company. This system provides links with the TMI-l Control Room, service buildings,230 KV substation control house, 500 KV l
substation control house and off-site locations.
e.
Evacuation Alann System J
The tone generator in the Normal Paging - Party Line System can generate j
different tones through the paging system for: fire alann, Reactor Building evacuation alarm, and the radiation emergency alarm.
The tone pulses and frequencies are identical to those used for TMI Unit 1.
)
)
7.2.5.3.3 Evaluation The communication system will remain in an operational condition during PDMS to provide the following capabilities:
a.
Communications throughout Unit 1 and Unit 2.
b.
Communication for identification of fire, injury, and flood.
c.
Communication for evacuation of normally unoccupied areas. Some of the areas identified may be used for storage of equipment and thus require occasional ingress and egmss.'
7.2.6 PDMS SUPPORT SYSTEMS The operational systems discussed in this section provide the necessary measures to support PDMS activities. Although they do not directly ensure protective functions, their operation is necessary to carry out anticipated operation, inspection, surveillance, and maintenance activities through PDMS.
7.2.6.1 Auxiliary Building Ventilation System 7.2.6.1.1 PDMS Function The Auxiliary Building Ventilation System will be maintained in an operational condition to i
support PDMS activities. When in operation, this system performs the following functions:
a.
Provides fresh, filtemd, heated air in sufficient quantity to maintain room temperatures suitable for personnel and equipment.
b.
Minimizes the spread of contamination by providing air flow from clean areas to potentially contaminated areas and to the exhaust.
c.
Filters exhaust air.
The system will also operate to provide freeze protection, as necessary, for liquid systems inside the Auxiliary Building.
7.2-21 AMENDMENT 18 - AUGUST 1993
7.2.6.1.2
System Description
The Auxiliary Building Ventilation System is a forced-flow heating and ventilating system consisting of supply and exhaust subsystems, with exhaust HEPA filter train, which provides once-through ventilation with no recin ulation.
When the ventilation system is not operating, it provides a passive, filtered pathway for equalization to atmospheric pressure. The PDMS configuration is shown on Figures 7.2-43 and 7.2-43A.
7.2.6.1.3 Evaluation During PDMS, Auxiliary Building ven.ilation and air handling equipment provide a filtered pathway for active or passive operation to meet industrial and radiological requirements.
Sources of contamination have been minimized (e.g., fuel removed, fuel pool drained, layup of deactivated systems); therefore, spread of potential contamination during PDMS has been greatly reduced.
7.2.6.2 Fuel Handling Building Ventilation System 7.2.6.2.1 PDMS Function Fuel Handling Building Ventilation System will be maintained in an operational condition to support PDMS activities. When in operation, this system performs the following functions:
a.
Provides fresh, filtered, tempered air in sufficient quantity to maintain room temperatures suitable for personnel and equipment.
i b.
Minimizes the spread of contamination by providing air flow fmm clean areas to potentially contaminated areas, and then to the exhaust.
c.
Filters exhaust air.
d.
Maintains the lower elevations (328', 305', and 281') of the Fuel Handling Building sepamte from the operating deck, which is maintained at a slightly negative pressure by the Unit I ventilation system.
The system will also operate to provide freeze protection, as necessary, for liquid systems inside the Fuel Handling Building.
7.2.6.2.2
System Description
i The Fuel Handling Building Ventilation System is a forced flow heating and ventilating system consisting of supply and exhaust subsystems, with exhaust HEPA filter train, which provide l
once-through ventilation with no recirculation. The operating deck and Fuel Handling Building truck bay are separated from the remainder of the Fuel Handling Building and are ventilated by i
the Unit i ventiktion system.
7.2-22 AMENDMENT 18 - AUGUST 1993
opentional to transfer accumulated water to minimize potential spread of contamination due to localized flooding.
7.2.6.6 Sewers 7.2.6.6.1 PDMS Function The basic function of the sewage collection system is to transpon sewage from TMI-2 stmetures
-l to the Sewage Tn:atment Plant. The PDMS configumtion is shown on Figure 7.2-47.
7.2.6.6.2 System Desciiption Sewage from TMI-2 is routed to the Sewage Treatment Plant which serves both TMI-l and TMI-2. The major operational portion of the Sewer System is underground gravity flow piping
. that provides for the transport of sewage from the Unit 2 support facilities to the STP.
7.2.6.6.3 Evaluation The Sewage Treatment Plant will process sewage from the Unit 2 suppon facilities. The majority of TMI-2 sewage piping is underground below the frost line.
l 7.2.6.7 Domestic Water System 7.2.6.7.1 PDMS Function l
During PDMS, portions of the existing domestic water system will remain operational to provide domestic water services required during PDMS.
7.2.6.7.2
System Description
The domestic water system is maintained as a modified opentional system. Unit 2 is supplied with domestic water from Unit I which is then distributed to Unit 2 support facilities. Domestic water is provided to the radwaste seal water unit in the Auxiliary Building, to the temporary personnel _ access facility in the Turbine Building, and to several outbuildings. The PLitS configuration is shown on Figures 7.2-47 and 7.2-48.
r 7.2.6.7.3 Evaluation Since personnel access into the plant will be infrequent, only one source of domestic water is required in the Turbine Building. The Auxiliary Building header is isolated but, if necessary, can be repressurized to supply domestic water to the seal water unit by opening one valve. Unit I and Unit 2 suppon facilities will remain operational; therefore, domestic water will continue l
to be supplied to them.
7.2-25 AMENDMENT 18 - AUGUST 1993
7.2.6.8 Control Room Ventilation System 7.2.6.8.1 PDMS Function The Control Room Ventilation System will be maintained in an operational condition to support PDMS activities. This system provides fresh, filtered, heated or cooled air in sufficient quantity to support personnel occupancy.
7.2.6.8.2
System Description
The Control Room Ventilation System is a forced flow heating and ventilation system consisting of a supply and exhaust subsystem which provides once-through ventilation with partial l
recirculation.
When the ventilation system is not operating, it provides a passive, filtered pathway for equalization to atmospheric pressure. The PDMS configuration is shown on Figure 7.2-49, 7.2.6.8.3 Evaluation During PDMS, Control Room ventilation and air handling equipment provide a filtered pathway for active and passive operation to meet industrial and radiological requirements. The Control Room Ventilation System is maintained operational for the occasional maintenance and surveillance entries into the TMI-2 Control Room and in response to off-normal conditions.
7.2.6.9 Cable Room Ventilation System 7.2.6.9.1 PDMS Function The Cable Room Ventilation System will be maintained in an operational condition to support PDMS activities. When in operation, this system provides fresh, filtered, heated or cooled air
. in sufficient quantity to maintain room temperatures suitable for personnel and equipment.
7.2.6.9.2
System Description
The Cable Room Ventilation System is a forced flow heating and ventilation system consisting of a supply and exhaust-return subsystem which provides ventilation with partial recirculation.
When the ventilation system is not operating, a damper in the bypass duct will open, allowing free passage of air in the exhaust-return duct system. The PDMS configuration is shown on Figure 7.2-49.
!t 7.2-25a AMENDMENT 18 - AUGUST 1993
-., ~.
7.2.6.9.3 Evaluation During PDMS, Cable Room ventilation and air handling equipment provide a filtered pathway for active and passive operation to meet industrial mquimments. This system is maintained operational to provide the appropriate environment for the battery room and the Instrument Air System (IAS) compressor.
7.2.6.10 Service Building Ventilation System 7.2.6.10.1 PDMS Function The Service Building Ventilation System will be maintained in an operational condition to support PDMS activities. When in operation, this system perfonns the following functions:
a.
Provides fmsh, filtered, heated air in sufficient quantity to maintain room-tempemtures suitable for personnel and equipment.
b.
Minimizes the spread of contamination by providing air flow from clean amas to potentially contaminated areas, and then to the exhaust.
c.
Filters exhaust air.
7.2.6.10.2
System Description
The Service Building Ventilation System is a forced flow heating and ventilation system consisting of supply and exhaust subsystems, with exhaust HEPA filter trains, which provides once-through ventilation with no recirculation.
When the ventilation system is not operating, it provides a passive, filtered pathway for equalization to atmospheric pressure. The PDMS configuration is shown on Figure 7.2-50.
7.2.6.10.3 Evaluation During PDMS, Service Building ventilation and air handling equipment provide a filtered pathway for active and passive opemtion to meet industrial and mdiological requirements..This system is maintained operational for personnel ingress and egress to the Reactor Building, Auxiliary Building, and Unit 2 Control Room, for the occassional maintenance and surveillance entries into the Service Building, and to supplement the Cable Room HVAC System in providing ventilation for the IAS compressor.
7.2.6.11 PDMS Alarm Monitoring System 7.2.6.11.1 PDMS Function The function of the plant computer alarm system is to notify plant operations personnel of an abnormal plant condition which requires operator action to correct or which represents a threat to plant, personnel or equipment safety. The PDMS Alarm Monitoring System provides' the means to remotely monitor select TMI-2 7.2-25b AMENDMENT 18 - AUGUST 1993
l i
7.2.6.12 ~
Control Building-Mechanical Equipment Room Ventilation System 7.2.6.12.1 PDMS Function j
i Part of the Control Building 4fechanical Equipment Room Ventilation System will be maintained j
in an operational condition to support PDMS. The modified system provides fresh, filtered, heated air in sufficient quantity to maintain room temperatures suitable for personnel and equipment.
7.2.6.12.2
System Description
The Control Building 4fechanical Equipment Room Ventilation System is a forced flow heating ventilation system consisting of a supply and exhaust subsystem which provides once-through ventilation with no recirculation.
7.2.6.12.3 Evaluation During PDMS, the Control Building-Mechanical Equipment Room Ventilation and air handling equipment provide a filtered pathway for active and passive operation to meet industrial and radiological requirements. The Control Building-Mechical Equipment Room Ventilation System is maintained operational for the occasional maintenance and surveillance entries into the mechanical equipment room and in response to off-normal conditions. During the winter it provides pipe freeze protection.
7.2.6.13 Contml Building Area Ventilation System 7.2.6.13.1 PDMS Function The Control Building Area Ventilation System will be maintained in an opemtional condition to support PDMS. When in operation, the system provides fresh, filtered, heated air in sufficient j
quantity to maintain room temperatures suitable for personnel and equipment.
'l 7.2.6.13.2
System Description
)
The Control Building Area Ventilation System is a forced flow heating and ventilation system
)
consisting of a supply fan, air filter, and duct heater unit, which provides heated (when required) fresh air into the Control Building Area.
1 7.2.6.13.3 Evaluation i
During PDMS, the Control Building Area Ventilation and air handling equipment provides an active filtered pathway that meets industrial requirements.
The Control Building Area Ventilation System is maintained operational for the occasional maintenance and surveillance entries into the Control Building Area and to provide pipe freeze protection.
~
7.2-25d AMENDMENT 18 - AUGUST 1993 j
l 1
i e
TABLE 7.2-1 OPERATIONAL SYSTEMS CONTAINMENT INTERNAL SYSTEM DESCRIPTION SYS. CODE ISOLATTON CONTAMINATION REMARKS CONTAINMENT ATMOSPHERIC N/A YES YES PASSIVE SYSTEM; PERIODIC INSPECTION BREATHER OF HEPA PILTER AND ASSAY OF SAMPLE FILTER PAPERS.
CONTAINMENT VENTILATION AND AH YES YES OPERATED IN PURGE MODE TO SUPPORT PURGE CONTAINMENT ENTRIES.
CONTAINMENT AIRLOCKS AND N/A YES N/A AIRLOCKS FOR PERSONNEL / EQUIPMENT ACCESS; EQUIPMENT HATCH EQUIPMENT HATCH WILL REMAIN IN PLACE.
FIRE PROTECTION FP N/A N/A ZONE FIRE DETECTION SENSORS SHALL BE OPERATIONAL THROUGHOUT OPERATIONAL PLANT AREAS.
FIRE SERVICE FS YES N/A FIRE SERVICE WILL BE ISOLATED AND PIPING DRAINED INSIDE THE UNIT 2
BUILDINGS.
PROVISIONS HAVE BEEN MADE AND EQUIPMENT HAS BEEN STAGED TO UTILIZE LOOP HYDRANTS.
FIRE SUPPRESSION EQUIPMENT FE N/A N/A PORTABLE FIRE SUPPRESSION EQUIPMENT ARE STAGED WITH EMERGENCY
RESPONSE
CREW EQUIPMENT.
WASTE DISPOSAL - LIQUID WDL YES YES NECESSARY EQUIPMENT TANKS TO PROCESS WATER WILL BE MAINTAINED OPERATIONAL.
ONLY THE BUILDING SUMP PUMPS, THE MISC. WASTE HOLDUP TANK (WDL-T-2),
THE ABST (WDL-T-5)
AND EPICOR II INTERCONNECTING PIPE SHALL REMAIN OPERATIONAL FOR WATER REMOVAL FUNCTIONS REQUIRED TO SUPPORT THE PROCESSING OF DECON LIQUID BY EPICOR II.
SUMP PUMP DISCHARGE AND SD N/A YES FACILITIES WILL BE SEALED TO PREVENT EXTERIOR MISCELLANEOUS SUMPS WATER INGRESS.
PERIODIC SUMP PUMP OPERATIONS WILL PREVENT ACCUMULATION OF DRAINAGE AND INADVERTENT IN-LEAKAGE.
7.2-26 AMENDMENT 18 - AUGUST 1993
~ - -..
f r
.. - =..
t
.)
TABLE 7.2 OPERATIONAL SUMP SYSTEMS FOR PDMS f
1 Sumns Associated With SD System i
Sump Location Turbine Building Sump Turbino Building s
t Control. Building Area Sump M-20 Area West Control & Service-Building Sump Service' Building Tendon Access Gallery Sump Tendon Access Gallery Air Intake Tunnel Normal Sump Air Intake' Tunnel Egmns Associated With WDL System Sump Location f
Containment Basement Sump Containment Building Auxiliary Building Sumps (2)
Auxiliary Building.
l Decay Heat Removal Pump Room Auxiliary Building i
'l.-
i Reactor Building Spray Pump Auxiliary Building f
Room Sump
{
a 1
I l
3 l
i 7.2-39 AMENDMENT 18 - AUGUST 1993-l I
4 l
-i f
t FIGURE '7.2-6 Deleted.
1 J
l 7.2-45 AMENDMENT 18 - AUGUST 1993 1
1
FIGURE 7.2-7 Deleted.
i 7.2-46 AMENDMENT 18 - AUGUST 1993
-1 1
3/4.4 ACCIDENT GENERATED WATER
. LIMITING CONDITIONS FOR PDMS 3.4.1 Deleted.
2 4
t t
I i
3/4.4-1 AMENDMENT 18 - AUGUST 1993
g J
c-3/4.4 ACCIDENT GENERATED WATER BASES Deleted.
c I
t t
B3/4.4-1 AMENDMENT 18 - AUGUST 1993 W
41
1 i
1 6.0 ADMINISTRATIVE CONTROLS i
6.1 RESPONSIBILITY 6.1.1 The PDMS Manager is responsible for the management of overall unit operations at Unit
)
2 and shall delegate in writing the succession to this msponsibility during absence.
6.2 ORGANIZATION
)
GPU NU. CLEAR ORGANIZATION 6.2.1 The GPU Nuclear Corporation (GPUNC) organization for unit management and technical support shall be as in Section 10.5 of the PDMS SAR.
TMI-2 ORGANIZATION 6.2.2 The unit organization shall be as described in Section 10.5 of the PDMS SAR and an individual qualified in radiation protection procedures shall be on site whenever Radioactive
]
Waste Management activitbs am in progress.
6.3 UNIT STAFF OUALIFICATIONS j
6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions unless otherwise noted in the Technical Specifications. The 1
requirements of ANSI N18.1-1971 that pertain to operator license qualifications for unit staff shall not apply.
6.3.2 The management position responsible for radiological control'or his deputy shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977.
Each Radiological Controls Technician in a responsible position shall meet or exceed the qualifications of ANSI N18.1-1971, 1
paragraphs 4.5.2 or 4.3.2, or be formally qualified through an NRC-approved TMI Radiation l
Controls training program. All Radiological Controls Technicians will be qualified through i
tmining and examination in each area or specific task related to their radiological controls i
functions prior to their performance of those tasks.
6.4 TRAINING 6.4.1 A retmining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requimments and recommendations of Regulatory Guide 1.8 of 1977.
6-1 i
AMENDMENT 18 - AUGUST 1993
ADMINISTRATIVE CONTROLS'
.)
- 6.5.3 AUDITS (con't) g.
The ODCM and implement!ng procedures at least once per 24 months.
i h.
Any other ama of unit operation considered appropriate by the PDMS Manager i
er the Office of the President - GPUNC.
]
RECORDS 6.5.3.2 Audit reports encompassed by Section 6.5.3.1 shall be forwarded for action to the management positions responsible for the areas audited and the IOSRG within 60 days after completion of the audit. Upper management shall be informed in accordance with the TMI-2 PDMS QA Plan.
6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP (IOSRS)
R FUNCTION 6.5.4.1 The IOSRG shall be a full-time group of engineers, independent of the unit staff, and located onsite.
ORGANIZATION 6.5.4.2 a.
The IOSRG staff shall be as specified in the TMI-1 Tech. Specs. (License No.
DPR-50).
b.
The IOSRG shall report to the director msponsible for nuclear safety i
assessment and will perform their function for both TMI Unit I and Unit 2.
RESPONSIBILITY 6.5.4.3 The periodic myiew functions of the IOSRG shall include the following on a selective and overview basis:
i a.
The independent review activities stated in Section 6.5.2.5 which may be performed after the fact.
b.
Assessment of unit operations and performance and unit safety programs from a nuclear safety perspective.
c.
Any other matter involving safe operations of the nuclear power plant that the onsite IOSRG manager or the PDMS Manager deems appropriate for consideration, j
6-6 j
' AMENDMENT 18 - AUGUST 1993 1
1
.i...
ADMINISTRATIVE CONTROLS
'6.7 PROCEDURES.AND PROGRAMS (con't) 6.7.2 Each procedure required by Section 6.7.1, and SUBSTANTIVE CHANGES thereto, shall be reviewed and approved as described in Section 6.5.1 prior to implementation and shall be myiewed periodically as required by ANSI N18.7-1976.
6Property "ANSI code" (as page type) with input value "ANSI N18.7-1976.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..7.3 Temporary changes to procedures in Section 6.7.1 above may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the responsible organization qualified in accordance with Section 6.5.1.9 and knowledgeable in the area affected by the procedure. For changes which may affect the operational status of unit systems or equipment, at least one of these individuals shall be a member of unit management or supervision; and c.
The change is documented, reviewed and appmved as described in Section 6.5.1 within 14 days of implementation.
6.7.4 The following programs shall be established, implemented, and maintained:
a.
Radioactive Effluent Controls Program A progmm shall be provided conforming with 10 CFR 50.36a for the control of mdioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The.
program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include mmedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
1.
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2.
Limitations on the concentrations of mdioactive material released in liquid effluents to UNRESTRICTED AREAS conforming _to 10 CFR Part 20, Appendix B, Table 2, Column 2, 3.
Monitoring, sampling, and analysis of radioactive liquid and ' gaseous effluents in accordance with 10 CFR 20.1301 and with the methodology and parameters in the ODCM, 6-8 AMENDMENT 18 - AUGUST 1993 -
i ADMINISTRATIVE CONTROLS 6.8 REPORTING REOUIREMENTS (con't)
ANNUAL REPORTS' 6.8.1.3 Annual repons covering the activities of the unit as described below during the pmvious calendar year shall be submitted prior to March 1 of each year.
Reports required on an annual basis shall include:
A tabulation of the number of station, utility and other personnel (including contractors) a.
for whom monitoring was required, receiving exposures greater than 100 mrem /yr and their associated person-rem exposure according to work and job functions, e,g,,
2 surveillance, routine maintenance, special maintenance (the dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements). Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose mceived from external sources shall be assigned to specific major work functions.
BIENNIAL REPORTS 6.8.1.4 Biennial reports (i.e., once every two years) covering the activities of the unit as described below during the previous two calendar years shall be submitted prior to March 1 of every other year.
Reports required on a biennial basis shall include:
a.
All changes made to the PDMS SAR during the previous two calendar years.
b.
All changes, tests, or experiments meeting the requirements of 10 CFR 50.59.
SPECIAL REPORTS 6.8.2 Special repons shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each repon.
6.8.3 NONROUTINE REPORTS A repon shall be submitted in the event that an Exceptional Occurmnce as specified in Section 6.13 occurs. The report shall be submitted under one of the report schedules described below.
2 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
2 This tabulation supplements the requirements of Anicle 20.2206 of 10 CFR 20.
6-11 I
AMENDMENT 18 - AUGUST 1993
ADMINISTRATIVE CONTROLS 6.9 RECORD RETENTION (Con't) e.
Records of changes made to the procedures required by Recovery Technical Specification 6.8.1 and PDMS Technical Specification 6.7.1.
l f.
Radiation Safety Program Reports and Quarterly Recovery Progress Reports on the March 28,1979 incident.
i g.
Records of radioactive shipments.
h.
Records and logs of radioactive waste systems operations.
i i.
Records and drawing changes reflecting facility. design modifications made to systems and equipment described in the Safety Analysis Repozt, TER, SD, or Safety Evaluation previously submitted to NRC.
j.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
k.
Records of transient or opemtional cycles for those unit components designed for a limited number of transients or cycles.
1.
Records of reactor tests and experiments.
i m.
Records of tmining and qualification for current members of the unit staff.
n.
Records of in-service inspections previously required by the Technical Specifications.
o.
Records of Quality Assurance activities required by the Operating, Recovery, or PDMS Quality Assurance Plans.
p.
Records of reviews perfonned for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.-
4 q.
Records of meetings of the Plant Operation Review Committee (PORC) and the f
Generation Review Committee (GRC), and reports of evaluations prepared by the IOSRG, if applicable to TMI 2.
r.
Records of the incident which occurred on March 28,1979.
jj s.
Records of unit radiation and contamination surveys.
t.
Records of radiation exposure received by all individuals for whom monitoring _
was required.
6-13 AMENDMENT 18 - AUGUST 1993
y ADMINISTRATIVE CONTROLS 6.9 RECORD RETENTION (Con't) u.
Records of gaseous and liquid radioactive material released to the environs.
v.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL.
bjD RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
6.11 IUGH RADIATION AREA In lieu of the " control device" or " alarm signal" requimd by paragraph 20.1601 of 10 CFR 20, each high radiation area shall be controlled as specified in the Radiation Pmtection Plan.
6.12 OFFSITE DOSE CALCULATION MANUAL (ODCM)
SUBSTANTIVE CHANGES to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2 v. This documentation shall contain:
1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1301,40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by GPU Nuclear management, c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
6-14 AMENDMENT 18 - AUGUST 1993
CHAPTER 10 ADMINISTRATIVE FUNCTIONS TABLE OF C_QNTENTS i
SECTION
. TITLE PAGE
10.0 INTRODUCTION
10.0-1 10.1 QUALITY ASSURANCE PLAN 10.1-1 10.2 SECURITY PLAN
.10.2-1 10.3 EMERGENCY PLAN 10.3-I 10.4 RADIATION PROTECTION PLAN 10.4-1 10.5 ORGANIZATION 10.5-1 10.5.1 CORPORATE ORGANIZATION 10.5-1 10.5.1.1 President - GPU Nuclear 10.5-1 10.5.1.2 TMI-2 Division 10.5-1 10.5.1.3 Technical Functions Division 10.5-1 10.5.1.4 Services Division 10.5-2' 10.5.1.5 Administration and Finance Division 10.5-2 10.5.1.6 Nuclear Assurance Division 10.5-2 10.5.1.7 Cther Functions 10.5-2 10.5.2 ONSITE ORGANIZATION 10.5-2 1
l 10.5.2.1 Manager, TMI-2 Department 10.5-3 1
i AMENDMENT 18 - AUGUST 1993 i
1
i 10.5 ORGANIZATION 10.5.1 CORPORATE ORGANIZATION The corporate organizational elements responsible for the PDMS phase of TMI-2 are shown on Figure 10.5-1. The specific responsibilities are discussed below. Additionally, the PDMS Technical Specifications prescribe specific requirements for staff qual.ifications, training, and the review and audit of TMI-2 activities.
10.5.1.1 President - GPU Nuclear l
The President - GPU Nuclear has the overall responsibility for the management of TMI-2 during PDMS. This responsibility is administered through the management staff, including:
Director, TMI-2 Division Director, Technical Functions Division Director, Services Division Director, Administration and Finance Division Director, Nuclear Assurance Division 10.5.1.2 TMI-2 Division
- The TMI-2 Division has overall responsibility for the TMI-2 plant. The Director, TMI-2 Division is charged with assuring consistent implementation of policies and procedures at TMI-2.
10.5.1.3 Technical Functions Division The Division of Technical Functions provides a centralized technical capability to support GPU Nuclear facilities and, when requested, will provide such support to maintain the PDMS condition. The division provides the general mechanical, civil, electrical and instrumentation, engineering mechanics, and chemistry / materials disciplines. Further, the division also provides technical support in the areas of nuclear fuel management, computer applications, human engineering, risk analyses, environmental qualification, and plant analysis.
A GPU Nuclear reorganization will occur upon entry or shortly after entry into PDMS,
.At that time, a new division (the TMI Division) will be formed which 'will assume responsibility for operations and maintenance of both TMI-1 and TMI-2; the TMI-I and TMI-2 Division will be deleted.
The corporate organizational elements for TMI-2 following this reorganization are shown in Figure 10.5-la.
j 10.5-1 AMENDMENT 18 - AUGUST 1993
-i
t 10.5.1.4 Services Division
- The Division of Services provides senral corporate-wide functions, including licensing and regulatory affairs, human resources, long-range planning, and strategic planning. The Services Division also provides security services, and the planning, scheduling, and directing of plant modifications, construction pmjects, and major maintenance activities for planned and forced outages, or as otherwise required, at GPU Nuclear facilities.
10.5.1.5 Administration and Finance Division The Administration and Finance Division pmvides corporate-wide support in the areas of materials management, operations analysis, accounting, budget and rate case suppon.
10.5.1.6 Nuclear Assurance Division The Nuclear Assumnce Division provides the radiological and environmental controls, emergency preparedness, quality assurance, occupational safety, and training and education-functions in support but independent of the GPU Nuclear operational divisions.
10.5.1.7 Other Functions Ir 'idition to the divisions lis%d above, the following four smaller independent functions report to ihe Office of the President:
Independent Safety Review - including the General OfGce Review Board (GORB),
Nuclear Safety Analysis Department (NSAD), Ombudsman, and Risk Assessment; Communications; Corporate Counsel and Secretary:
Continuous Improvement 10.5.2 ONSITE ORGANIZATION The onsite organizational elements responsible for the PDMS phase of TAU-2 are shown on Figure 10.5-2.
Following the GPU Nuclear reorganization discussed on page 10.5-1, the Services Division responsibilities will include TMI-2 dismantlement activities and waste management and i
shipping (See Figure 10.5-2a).
l i
10.5-2 AMENDMENT 18 - AUGUST 1993
10.5.2.1 PDMS Manager
- The PDMS Manager has the first-level management msponsibility for maintaining the TMI-2 PDMS condition.
The PDMS Manager is directly responsible for the operations and maintenance activities associated with the TMI-2 PDMS. Reporting to the PDMS Manager are i
the subordinate managers msponsible for execution of the above~ listed functions.
b b
Following the GPU Nuclear reorganization discussed on page 10.5-1, the waste-management activities for TMI-2 will be transferred to the Services Division and the engineering activities for TMI-2 will be transferred to the Technical Functions Division and the Plant Engineering section of the TMI Division (See Figure 10.5-2a).
1 10.5-3 AMENDMENT 18 - AUGUST 1993
?
GPU NUCLEAR CORP.
ORGANIZATION PLAN r -
ICE OF THE PRESIDENT 0FF GPU NUCLEAR CORPOR ATION I
I PRESIDENT l
I
,__________I I
I g
CORPORATE l
l CONTINU0US INDEPENDENT COMMUNICATIONS COUNSEL AND g
IMPROVEMENT SAFETY REVIEW SECRETARY g
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i TMl-1 TMI-2 OYSTER CREEK l
l 1
I TECHNICAL ADMINISTRATION NUCLEAR SERVICES FUNCTIONS
& FINANCE ASSURANCE sDIN TMI '
cru NGCU:AR CORP.
ORGAMZATION PLAN PDMS SAR FIGLEE: 10.5 -1 PAGE 10.5-4
GPU NUCLEAR CORP.
ORGANIZATION PLAN
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FFICE OF THE PRESIDENT 0
g GPU NUCLEAR CORPORATION I
I PRESIDENT l
g L_________
,__________I I
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CORPORATE I
l CONTINUOUS INDEPENDEtiT COMMUNIC ATIONS COUNSEL AND l
g IMPROVEMENT SAFETY REVIEW SECRETARY i
i TMI OYSTER CREEK i
l l
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TECHNICAL ADMINISTRATION NUCLEAR SERVICES FUNCTIONS
& FINANCE ASSURANCE eid4Nescieer TMI-2 GPU NUCLEAR CORP, ORGANZATION PLAN POMS SAR F10t K : 10.5-1 a PAGE 10.5-4a
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ORGANIZATION PLAN PRESIDENT TM-2 GPU NUCLEAR
- DIRECTOR, DIRECTOR,
- DIRECTOR, SERVICES TMI TECH FUNCTIONS I
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SITE SERVICES DIRECTOR, OPERATIONS PLANT ENGINEERING DIRECTOR, TMI
& MAINTENANCE, TMI DIRECTOR, TMl i
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MANAGER MANAGER PDMS CONSTRUCTION, TMI WASTE MANAGEMENT MANAGER RAD STE OPERATIONS /
DISMANTLEMENT ENGINEERING ENGINEERING MANAGER SUPPORT SUPPORT MANAGER 4d490eclear TMI-2 ORGMZADON PUW TM-2 POMS SAR FIGLRE: 1).5-2 a PAGE 105-5a E-----. u e-------.
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SUPPLEMENT 1
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Section 7.1.2.2. The auxiliary building ventilation system will be operational and used part of the time during PDMS. What will prevent air back-flow from becoming a pathway for unfiltered and unmonitored release, during the time the ventilation system is not operating?
RESPONSE
The Auxiliary Building air supply fan has automatic, quick-closing inlet and outlet dampers that remain isolated during periods when supply air is not in i
operation. These closed dampers will prevent back-flow. The dampers in the air intake tunnel have been removed for PDMS.
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i SI-6 AMENDMENT 18 - AUGUST 1993 1
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SUPPLEMENT 1 15.
Section 7.1.5.3 - Air Intake Tunnel - indicates that "In the event of a fire in the air intake pathway, the fire dampers will be closed by operator action from a remote location." What mechanism will be used to indicate a fire? Does " operator" refer to a person, is it considered the automatic operation or is there another device such as a smoke detector or fire alarm trip that automatically shuts the damper?
RESPONSE
There are heat-actuated detectors (IIADs) still in operation in the air intake tunnel that will detect any fire. The operator action referred to is not a person, but the detection and subsequent automatic quick-closing inlet and outlet dampers that remain in operation. The only fire reasonably postulated to occur in the air intake tunnel is as a result of a hypothetical airplane crash and subsequent fuel fire. The probability of an airplane crash impacting the air intake tunnel is negligible. Assuming that the target area includes l
touchdown and skid areas in the vicinity of the air intake tunnel, the probability of either a small or large aircraft hit is estimated to be less than 2E-7/ year. Therefore, no additional protection is required considering the low probability of an airplane crash impacting the ventilation systems and the immediate plant response to this catastrophic occurrence. The quick-closing dampers mentioned above are ventilation dampers associated with the vent fans, not fire dampers.
f S1-16 AMENDMENT 18 - AUGUST 1993
l SUPPLEMENT 1 9
22.
Section 7.2.2.2 - System Description - Paragraph (d) - What is the justification for removal of the halon systems in the air intake tunnel?
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RESPONSE
The justification for removal of the halon systems in the air intake tunnel is based on the following:
1.
There are dampers that quick-close and isolate the air intake tunnel from each building during periods when supply air is not in operation. These are ventilation dampers associated with the vent fans, not fire dampers.
2.
Them is a low probability of an airplane crash. See msponse to Question No.15.
S1-23
' AMENDMENT 18 - AUGUST 1993
I SUPPLEMENT 1 30.
Figure 7.2 The left hand portion of the drawing indicates the instrumentation that has been disabled or de-energized. How will this affect the fire damper action?
RESPONSE
Each building has isolation dampers that close when supply air is not in operation. These are quick-closing inlet and outlet dampers. These closed dampers will prevent back-flow into the air intake tunnel. The dampers are ventilation dampers associated with the vent fans, not fire dampers.
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s S1-31 AMENDMENT 18 - AUGUST 1993
SUPPLEMENT 2 i
A.3. What are the locations of the fire system hose and reels that will be operational during PDMS7 t
RESPONSE
The fire service hoses and hose reels will not be operational during PDMS nor will they be maintained. The fire brigade will primarily rely on hose lines from exterior hydrants with back-up assistance from offsite fire departments.
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S2-3 AMENDMENT 18 - AUGUST 1993 i
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SUPPLEMENT 4 1.
Provide an estimate of the total quantity of contamination (in curies) in the Auxiliary and Fuel Handling Buildings. Include both fixed and removable contamination.
RESPONSE
The msponse to PDMS SAR Supplement 2, Question B.8. provided the estimated total activity present as loose surface contamination in the AFHB and the seven other contaminated facilities at TMI-2. The current question extends that request for information to also include fixed contamination. The data necessary to provide a response to this request has not been obtained.
An assessment of the quantity of fixed contamination in two AFHB cubicles was submitted for NRC review in GPU Nuclear letter C312-93-2063, dated September 15, 1993. If the methodology used is acceptable, the fixed contamination in the rest of the AFHB will be estimated.
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l S4-1 AMENDMENT 18 - AUGUST 1993 l
i SUPPLEMENT 5 i
22.
Section 3.9.13, Accident Generated Water, of the existing Technical Specifications requires that the licensee dispose of the Accident Generated Water (AGW) per NRC approved procedures. The licensee has proposed deleting this requirement. The staff recommends retaining this requirement until the AGW evaporation is completed. The l
staff would also entertain a separate license amendment modifying this requirement.
RESPONSE: AGW evaporation was completed on August 12, 1993. Therefore, this PDMS Technical Specification was deleted.
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1 S5-21 AMENDMENT 18 - AUGUST 1993
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ENCLOSURE 2
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LIST OF PDMS 4
REQUIREMENTS AND COMMITMENTS.
REVISION 2:
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ENCLOSURE 2 3
Additional Reauirements/L.icensee Commitments A.
Removal of Water from Reactor Coolant System and Fuel Transfer Canal 1.
Remove water to the extent reasonably achievable.
Reactor Vessel; drained to less than 10 gallons (38 liters) of water. (SAR 6.2.27.2; TER 5-9)
Reactor Building Fuel Transfer Canal. (TER 5-9) 2.
Isolate the fuel transfer tubes. (SAR 1.1.2.1).
3.
Drill holes in canal seal plate to prevent refueling canal from filling. (TER 5-9) 4.
Cover the Reactor Vessel to minimize water entry. (SAR 6.2.27.2) 5.
Drain the Submerged Demineralizer System to the extent reasonably achievable.
(SAR 6.2.36.2) 6.
Drain and cover the "B" spent fuel pool to the extent reasonably achievable.
(SAR 6.2.36.2) 7.
Drain and cover the "A" spent fuel pool to the extent reasonably achievable.
(SAR 6.2.3.2)
B.
Radiation Safety & Reduction of Potential for Releases 1.
Ship offsite or package and stage for shipment remaining mdioactive waste from -
the major TMI-2 decontamination activities. (SAR 1.1.2.1; TER xiv) 2.
Reduce radiation levels within the facility, to the extent reasonably achievable and consistent with ALARA, to allow plant monitoring, maintenance, and inspection.
Apply shielding in critical locations after reactor vessel draindown to reduce dose rates. (TER 5-23) 4.
Define and establish an overall surveillance program plan for PDMS environmental protection systems to ensure public health and safety. (TER xiv) 1 Revision 2
C.
Ventilation 1.
Verify that a surveillance program exists to ensure AFHB ventilation and filtration operability, maintenance and testing. (SAR 7.1.2 and 7.1.3; TER 6-26) 2.
Verify that the licensee has procedures in place to continue to operate the AFHB ventilation system until the Accident Generated Water is no longer being pmcessed or tmnsfermd in the AFHB. (TER 6-28) 3.
Ensure that penetation R-626 has been upgraded to 5 psi. (SAR Supp. 3, Item B.2; TER 6-17) 4.
Ensure that the reactor building breather system is the predominant pathway for effluent and influent to the building during those times that the reactor building ventilation system is not being operated; and that the effluent is filtered and monitored. (SAR 7.2.1.2; TER 6-25).
5.
DOP test the HEPA filter in breather prior to entry into PDMS. (SAR 7.2.1.2.2 and Supp. 3, Item B.3; TER 6-25) 6.
Ensure installation, actuation setting, and routine surveillance testing of the isolation valve between containment and HEPA filter in the reactor building bmather (to automatically close upon receipt of a containment pressure increase of 0.25 psi). (SAR 7.2.1.2; TER 5-10,5-11, and 6-24) 7.
Develop and implement a reactor building entry procedure that requires an evaluation of the reactor building atmospheric conditions prior to personnel ent.ry.
(SAR 7.2.1.3) i 8.
Develop and implement procedures for maintaining HEPA filter banks for the Reactor Building Purge System.(SAR 7.2.1.3) 9.
Develop and implement procedures for monitoring the Reactor Building vent during reactor building purge. (SAR 7.2.1.3)
D.
Plant Contamination Survey 1.
Licensee will meet established contamination level goals for entrance into PDMS for each area of the AFHB. If the decontamination goals cannot be met because of the unique situation at TMI-2 or ALARA considerations, the licensee will provide an evaluation of the specific situation to the NRC. (SAR 5.3.1 and Supp.
3, Item A.11; TER p. 4-2) 2 Revision 2-J
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Update information in the following tables from the SAR as final decontamination results become available. (SAR 5.3.2)
- Table 5.3-2 (SAR) "PDMS Radiological Conditions - AFHB"
- Table 5.3-4 " Surface Contamination - Reactor Building"
- Table 5.3-5 ' Surface Contamination - AFHB"
- Table 5.3-6 " Surface Contamination - Other Buildings" 3.
Perform survey of the service building, elevation 305 ft.; the turbine building, elevation 281 ft. and the containment air control envelope building and provide information in the PDMS SAR before entry into PDMS in order to establish a radiological baseline for the facility. (SAR.5.3.2; TER 4-2) 4.
Ensure that a progmm exists for periodic measurement of radiation and contamination levels to verify radiological conditions. (SAR 7.2.4.1 and 7.2.4.2; TER 6-42 and 6-43).
E.
Physical Maintenance in Reactor Building and Vessel 1.
Have the capability of insening a video camera into the reactor vessel to verify fuel location if it is determined at a later time that such an examination is required. (TER 6-3) 2.
Create a program plan to perform monthly entries into the reactor building for at least 6 months after placing it into its PDMS condition. (PDMS SAR 7.2.4; TER 5-23)
F.
Physical Maintenance in AFHB 1.
Create a program plan to perform monthly entries into the AFHB for at least 6.
months after placing it into its PDMS condition. (SAR 7.2.4; TER 5-23) 2.
Ensure that both fuel pool structures remain intact (SAR 7.1.3.2)
G.
P_hysical Maintenance in other Buildings 1.
Ensure that the Contml Room Ventilation Systems (i.e., Control Room HVAC i
and Cable Room HVAC) and the Service Building Ventilation System are -
maintained in an operational condition and will be operated as' required. (SAR 7.2.6.8,9,10) j 3
Revision 2
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Maintain the capability to process potentially contaminated liquids.
H.
Electrical Related 1.
In reactor containment, reactor building electric power circuits will be deenergized except those necessary for PDMS monitoring, inspection, and surveillance equipment and other PDMS suppon requirements. (SAR 7.1.1.4; Supp.1, Item 17; TER 6-34 and 6-38) 2.
In the auxiliary building, the power to lighting, fim detectors, and sump level indication circuits will be energized and will remain operational. The auxiliary sump, auxiliary sump tank and associated level indication will also remain operational. (SAR 7.1.2.2; TER 6-37) 3.
In the fuel-handling building, low voltage circuits to lighting and fire detection will be energized. (SAR 7.1.3.2; TER 6-37) 4.
In the Control and Service Buildings, verify that the electrical distribution will remain configured to power low voltage lighting loads and fim detectors. (SAR 7.1.7.2) 5.
Portions of the TMI-2 electrical distribution system will be operational and energized to provide power for the PDMS support systems and their associated controls and instrumentation.
Power will be available for area lighting, receptacles, heating, and ventilation to suppon PDMS activities. (SAR 7.2.5.1.1; TER 6-37) 6.
Emergency lighting (8-hr portable emergency lights) is staged with emergency response crew equipment. (SAR 7.2.5.2.1; TER 6-37) 7.
Verify that exit signs are powered from the normal lighting system. (SAR 7.2.5.2.2) 8.
DC power during PDMS will be available. Enads have been consolidated whem practicable to reduce the number of energizeA circuits. (SAR 7.2.5.1.3; TER 6-38) 9.
Deleted i
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Fire Protection 1.
Have procedures in place to ensure that the fire mains within the reactor building will be closed with valves drained to the extent reasonably achievable within 30 days following entry into PDMS to minimize the potential for introduction of-water into the reactor vessel. (SAR 7.2.2.2i.; TER 6-2) l 2.
Deleted.
3.
Ensure that either the TMI-2 control room or some other location is continuously manned with a fully qualified person or that remote monitoring capabilities are available in TMI-1 control room to identify the specific zone panel which indicates the location of the fire in the TMI-2 facility. Ensure that procedural control exists to delineate the location of the monitoring activity. (TER 6-29; SAR 7.2.2.2b.)
4.
Demonstrate that TMI-1 Operations has accepted responsibility for maintaining the fire service system in operable areas of the plant as required to support operations in the waste-handling and packaging facility, the respirator cleaning l
facility and the administration building. (TER 6-29) 5.
Deactivate deluge systems in the auxiliary building and the control building. (S AR 7.2.2.3; TER 6-29) 6.
Ensure that all Halon systems have been deactivated by disconnecting the cylinders and either emptying or removing them. (SAR 7.2.2.2d.)
7.
Verify that portable fire extinguishers are staged with emergency response crew -
equipment. (SAR 7.2.2.2e.)
8.
Verify that self-contained breathing apparatus are staged with emergency msponse crew equipment. (SAR 7.2.2.2c.)
9.
Ensure that the fire detection system remains operational in the AirIntake Tunnel and the relay room. (SAR 7.2.2.2d.)
)
10.
- Deleted, l
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11.
To the extent that fire protection is not required in work or storage areas, ensure isolation of the 12-inch fire service loop, which runs through the AFHB, the j
control building area and the turbine building (east and west). (SAR 7.2.2.21.,
TER 6-32)
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Ensure that the fire system line is cut and blanked off at the fuel-handling building, where the fire system line runs from the diesel generator building. (SAR 7.2.2.2i.; TER 6-32) 13.
Deactivate the river water pump house. (SAR 6.1.10; TER 6-33) i 14.
Deactivate the fire pump house. (SAR 6.1.10 and Supp.1, Item 14; TER 6-33) i 15.
Ensure that transient combustibles have been removed from inside the containment and the AFHB to the extent practicable. (SAR 7.2.2.2f.; TER 6-33)
This includes most plant items installed after the accident. Fire loading must be less than a 1-hour loading of 80,000 BTU / square foot. (SAR Supp.1, Item 17) 16.
Drain oil to the extent reasonably achievable from the main turbine, feedwater-pump turbines, emergency feedwater pump turbine, main feedwater pumps, emergency feedwater pumps, condensate pumps, condensate booster pumps and hydrogen seal oil unit. (SAR 7.2.2.2g.; TER 6-34) 17.
Taken as an aggregate, demonstrate that no more than 57 percent of the original total volume of reactor coolant pump lubricating oil remains in the upper and lower reservoirs of the four reactor coolant pump reservoirs. (SAR Supp.1, Item 33; TER 6-34) 18.
Charcoal filters have been removed from all HVAC systems in TMI-2. (SAR 7.2.2.2h.; TER 6-34) l 19.
Train and familiarize station fire brigade with the TMI-2 system configurations, plant layout and procedures for TMI-2. (SAR 7.2.2.2k.; TER 6-35) l 20.
Procedure in place for reactivation of the deactivated portions of the fire protection system if necessary. (SAR 7.2.2.2j.; TER 6-29) h 21.
Verify that the procedure for inspection of the fire loop drain valves during freezing weather is in place. (SAR 7.2.2.2i.; TER 6-32) 22.
Verify that the procedures and system are in place for testing of the operable portion of the fire detection and alarm system. (SAR 7.2.2.2b.; TER 6-34) 6 Revision 2 i
23.
Verify that procedures for manual suppression of fire by the fire brigade are provided as stated in the FPPE. (TER 6-35)
J.
Flood Protection 1.
Ensure that flood panels are provided for all entrances to the control building, and to the entmnce of the auxiliary building. (TER 6-36) Doors and entrances to the Control Building Area that are not flood-protected are either watertight or are provided with flood panels. All openings that are potential leak paths (i.e., ducts, pipes, conduits, cable trays) are sealed. (SAR 7.1.4) l 2.
Verify that the containment basement and auxiliary building sumps level ind: cations will be maintained. (SAR 7.2.3.1.2) 3.
Verify that the auxiliary building sump pumps are maintained operational and placed in a manual control mode. (SAR 7.2.3.1.2).
4.
Verify that the Miscellaneous Waste Holdup Tank and the Auxiliary Building Sump Tank (ABST) have been isolated from the Radwaste Disposal Gas System and vented via HEPA filters to protect against air' orne releases from these tanks.
o (SAR 7.2.3.1.2) 5.
Ensure that a flow path exists to drain down the reactor building basement floor.
(SAR 7.2.3.1.2) 6.
Deleted 7.
Deleted 8.
Ensure that the active sumps have a high level alarm that annunciates in the control room and the PDMS Alarm Monitoring System. (SAR 7.2.3.2.2)
K.
_ Procedures and Programs 1.
Include a surveillance program under which a limited number of rodent carcasses will be analyzed for gamma-emitting isotopes as part of the non-routine Radiological Environmental Monitoring Program. (SAR Supplement 3, A.16)
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STANDARDS FOR SATISFYING REOUIREMENTS AND COMMITMENTS The staff recognizes that many of the above requirements and commitments have been acted upon by the licensee. Once this list is finalized, the licensee will submit a letter that documents which of the listed requirements and commitments have been satisfied.
The letter will reference primary documentation (UWIs, procedure numbers, drawings, etc.) that demonstrate that the work was completed or the requirement or commitment met. It will not be necessary to submit the primary reference documents but only have them accessible at the TMI-2 site. The staff will verify by reviewing the primary documentation and/or inspection of the actual modification. Once the staff has conducted its review and determined that the requirement or commitment has been satisfied, the staff will close out the item. As other items are completed, the licensee will continue to notify the staff in writing of the completed status and identify the appropriate primary references. The staff and licensee plan to agree prior to notification of completion of an item what constitutes the standard for demonstrating completion of the item.
M.
PROCEDURES FOR CHANGING THE ABOVE REOUIREMENTS AND COMMITMENTS During the remainder of the current cleanup effort, conditions may change n:sulting in a change in the licensee's ability to satisfy the above requirements and commitments.
Licensee's request for deviations to the above list of requirements and conditions must-be made in writing, as an amendment to the SAR, providing a description of the old requirement or commitment and a description of the change. The deviation request must include a safety analysis evaluating the proposed change. Requests for deviations to the above list must be timely and allow for staff review (typically 60 days). The NRC staff will either approve or disapprove the licensee's request in writing based on the results of the staff review. The licensee understands that PDMS was evaluated and received staff approval based on the requirements and commitments made by the licensee through SAR Amendment 17. Significant changes to the requirements and commitments may invalidate, or require a reevaluation of the staff's Safety Evaluation and Technical Evaluation Report.
8 Revision 2
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.i ENCLOSURE 3 j
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SAFETY EVALUATION OF PROPOSED CHANGES 1
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PDMS REQUIREMENTS AND COMMITMENTS-
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ENCLOSURE 3 Safety Evaluation of Proposed Changes Additional Requirement / Licensee Commitment - II.7.
Descriotion of Proposed Chance The exit signs are powered fmm the normal lighting system, but there is no backup battery.
Therefom, the phrase discussing battery backup is being deleted.
Safety Evaluation of Prooosed Changg Section 7.2.5.2 of the PDMS SAR is being revised to indicate that the installed emergency lighting will be maintained. This change in philosophy at TMI-2 pmvides sea?ed beam lamps powered by batteries which initiate operation upon loss of the normal lighting system. This lighting is provided to ensure safe egress for personnel. Additional exit information will be provided by postings. This proposed change does not constitute an Unreviewed Safety Question (USQ) nor does it impact the conclusions of the NRC PDMS Safety Evaluation Report (SER).
Additional Requirement / Licensee Commitment - I.1.
Description of Proposed Change The reference to the SAR subscription is being corrected.
Additional Requirement / Licensee Commitment - I.2.
Description of Prooosed Change Automatic fire suppression is not provided to any portion of TMI-2. Therefore, this requirement of the Fire Protection System is being deleted.
Safety Evaluation of Proposed Change Automatic fire suppression was originally provided to areas of the facility and systems which contained significant amounts of combustibles and possible ignition sources. However, the extensive cleanup and removal of combustibles in the TMI-2 facility obviate the need for 1
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automatic fire suppression.~ Further, the ongoing electrical distribution modification, scheduled for completion in early 1994, will reduce the number of possible ignition sources. In summary,~
J no location contains a significant amount of combustibles nor is there a'possible ignition source j
near a moderate amount of combustibles.
This proposed change does not constitute an 1
Unreviewed Safety Question (USQ) nor does it impact the conclusions of the NRC PDMS Safety Evaluation Repon (SER).
Additional Requirement / Licensee Commitment - I.3.
Descriotion of Proposed Change The zone panel (i.e., the local control panel) which indicates the location of the fire will be identified by the PDMS Alarm Monitoring System as shown on PDMS SAR Table 7.2-5. The local panel would then be consulted to determine the exact location of the fire. The SAR wording is being revised to reflect the proper situation.
Safety Evaluation of Proposed Change This change corrects a slight misrepresentation of the true situation. The PDMS Alarm Monitoring System provides remote monitoring capabilities in the TMI-1 control room j
to direct site personnel in the performance of their duties. The purpose of the fire abrms ponion of that system was to indicate the general location of the fire-which is accomplished by reference to the zone panel. This proposed change does not constitute an Unmviewed Safety Question (USQ) nor does it impact the conclusions of the NRC PDMS Safety Evaluation Report (SER).
Additional Requirement / Licensee Commitment - L4.
Description of Proposed Change Minor typographical correction.
Additional Requirement / Licensee Commitment - L7. and L8, Description of Prooosed Change The portable fire extinguishers and self-contained breathing apparatus (SCBA) will be staged with the emergency response crew equipment and controlled by an approved fire protection procedure. In addition, Figures 7.2-6 and 7 are being deleted.
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Safety Evaluation of Proposed Change Figums 7.2-6 and 7 wem limited in scope and incorrect as shown. Rather than correct the figums, the SAR statements were revised to present a more general description of the location of the portable fire extinguishers and SCBA. This pmposed change does not constitute an Unreviewed Safety Question (USQ) nor does it impact the conclusions of the NRC PDMS Safety Evaluation Report (SER).
Additional Requirement / Licensee Commitment - L11.
Descriotion of Proposed Change The reference to the SAR subsection is being corrected.
Additional Requirement / Licensee Commitment - L12.
Description of Proposed Changg The reference to the SAR subsection is being corrected.
Additional Requirement / Licensee Commitment - L15.
Description of Proposed Change The reference to the SAR subsection is being corrected.
Additional Requirement / Licensee Commitment - L16.
Description of Proposed Change The reference to the SAR subsection is being corrected.
Additional Requirement / Licensee Commitment - L18.
Description of Proposed Change i
The reference to the SAR subsection is being corrected.
3 Revision 2 H
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Additional Requirement / Licensee Commitment - I.19.
Description of Proposed Change The reference to the SAR subsection is being corrected.
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Additional Requirement / Licensee Commitment - I.20.
Description of Proposed Change The reference to the SAR subsection is being corrected.
Additional Requirement / Licensee Commitment - L21.
Description of Pron 2 sed Change The reference to the SAR subsection is being corrected.
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. Revision 2