ML20215J801
| ML20215J801 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/10/1986 |
| From: | Dugger C, Richardson J, Sibley E DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20215J795 | List: |
| References | |
| MCSD-2211.00-35, MCSD-2211.00-35-R01, MCSD-2211.00-35-R1, NUDOCS 8705080259 | |
| Download: ML20215J801 (16) | |
Text
.=
Duke Power Company.
McGuire Nuclear Station, Unit 2 System
Description:
MCSD-2211.00-35 Equipment. Staging Building Heating, Ventilating and Air Conditioning System .VK/YK Drawing Numbers: MC-2522-11.85-00 MC-2522-11.89-00 MC-2522-11.86-00 MC-2522-11.90-00 MC-2522-11.86-01 MC-2522-11.91-00 MC-2522-11.87-00 MC-2522-11.92-00 MC-2522-11.88-00 MC-2525-11.85-00 -
Flow Diagram Numbers: MC-2557-5 MC-2557-6 Date: June 10, 1986 Revision: 1 This document includes engineering design in which quality has been assured, in accordance with established procedures.
[h f b 7/8/26 D6te '
Inspected By 7 s -H Date Originated By
&XB M n/ 7/r/r?
DAte' odc Insp teo By wAwea Date Cpckec1y
& 7 S~bl A>ck M C/d 4
- 6'8 G KFiiroveABy/u Date nspettiuM Waivea Date By: R. H. Burley Mechanical Division - HVAC 8705080259 870504 PDR ADOCK 05000369 p PDR 4
-M.
t McGuire Nublear Station.
~
=-
fSyshem-Description: .MCSD-2211.00 Equipmen't Staging Building Heating,
' Ventilating and Air Conditioning System - VK/YK
.Revi$ionLog: -
-1. Revision 0 -Initial Approved Release.- June 10, 1986
'2. Revision 1 - Revised to Supersede Original Office Building System Description of tne similar Number e
)
s TABLE OF CONTENTS Page Number Section Title EQUMPMENT STAGING BUIL)ING 3
- 1. 0 i EFI 9G . if E 9TE ATI iG AND AI RCONDl" ION 4G SYSTE ' .
3 1.1 ' SYSTEM PURPOSE 3
1.2 SYSTEM DESCRIPTION COMPONENT DESIGN PARAMETERS 4
- 1. 3 5
1.4 INSTRUMENTATION AND CONTROL 5
1.5 SYSTEM OPERATION Rev. O MCSD-2211.00-35
1.0 E0JMPMEN" STAGING Li MING HEATING.
V TILAT NG AND AI RCMDITIONING SYSTEM 1.1 SYSTEM PURPOSE The purpose of the Equipment Staging Building Heating, Ventilating and Air Conditioning System is to prevent an unmonitored release of_ radioactivity from the building, to provide air filtration, and to maintain the building tempera-ture below 78 F in summer and above 68 F in winter. This system performs no function during a LOCA and is not Nuclear Safety Related.
1.2 SYSTEM DESCRIPTION The Equipment Staging Building Heating, Ventilating and Air Conditioning System consists of the following major components:
a) A filter unit containing prefilters, HEPA filters and cooling coils b) A centrifugal fan to recirculate building air c)- A vane-axial fan for building exhaust d) An air-cooled reciprocating chiller e) A horizontal split-case chilled water pump f) Electric duct and unit heaters The systen is in no way intended to mitigate the consequences of an accidental release of radioactivity inside containment. Administrative control of the reactor building equipment hatch must be maintained in accordance with the
' plan
- Technical Specifications to ensure that an accidental release does not occur with the equipment hatch open.
The reactor building purge system should be operated to maintain airflow from the equipment staging ~ building to the upper containment when the reactor building equipment hatch is open. Reference MCSD-2211.00-20.
The building exhaust fan should be ON when operations are_being performed which could result in the release of radioactivity within the building. This will ensure that any release is monitored since the exhaust airstream is continuous-ly sampled by 2 EMF 59. The total volume of air exhausted from the building is totalized and displayed on the face of 2ESB-CP-1. The building exhaust fan continues to operate when radioactivity is detected so that the total release can be determined.
The building exhaust fan may be turned 0FF if there is no possibility of releasing radioactivity within the building. The building supply fan and chilled water system may continue to operate to control building temperature.
The maintenance area temperature is controlled between 78 F during the cooling season and 65 F during the heating season. Cooling is provided by an air cooled chilled water system which delivers 45 F water to 2MVKFU0005. Cooling is controlled based on return air temperature by modulating flow to 2MVKFU0005 with a three-way valve. Heating is~provided by electric duct and unit heaters.
Unit heaters are controlled with integral thermostats and duct heat is con-trolled based on return air temperature. A booster heater in the change room area supply duct prevents the temperature in this area from falling below 72 F.
MCSD-2211.00-35 Rev. O
1.3 COMPONENT DESIGN PARAMETERS 1.3.1 SUPPLY FAN (MCM 1211.00-1862, 1863, 1864, MCM 2211.00-0147) a)- Tag Number 2MVKSF0001 b) Fan Type SWSI Centrifugal c) 'Desigri Flow 16,900 cfm d) Design Fan Static Pressure 8.0'in..w.g.
e) Design Speed 1640 rpm f) Motor HP .
40 hp g) Motor Electrical Data 575V/30/60 cy 1.3.2 EXHAUST FAN (MCM 1211.00-1850, 1858, 1859) a) Tag Number 2MVKXF0002 b) Fan Type Vane Axial c) Design Flow . . _
5000 cfm d) Design Fan Total Pressure 7.0 in. w.g.
e) Design Speed' 3500 rpm f) Motor HP 15 hp g) Motor Electrical Data 575V/30/60 cy 1.3.3 RECIPROCATING CHILLER (MCM 1211.00-1851) a) Tag Number 2MYKCH0001 b) Type Air Cooled c) Design Flow 125 gpm d) Entering Water Temperature 55 F e) Leaving Water Temperature 45 F f) Entering Air Temperature 95 F g) Capacity 51.8 tons h) Electrical Data -
575V/30/60 cy 1.3.4 CHILLED WATER PUMP (MCM 1211.00-1852, 1853) a) Tag Number 2MYKPU0001 b) Type Horiz. Split Case c) GPM 125-d) Head 75 ft.
e) RPM 1750 f) Horsepower 5 575V/30/60 cy g) Electrical Data 1.3.5 COOLING COILS (MCM 1211.00-1868)
-a) Quantity 2 b) Entering Air Condition 78 F db, 65 F wb c) Leaving Air Condition 53 F db, 52 F wb d) Sensible Capacity 448,000 BTU /HR e) Latent Capacity 174,000 BTU /HR f) Total Capacity 622,000 BTV/HR g)- Area 38 ft.2 h) Rows 6 i) Fins / inch 8 MC50-2211.00-35 Rev. O
-F --- w- rwyp-r,a__m , _,_ . _ . _ _
/
.j) GPM _
-125 k). Air Quantity 16,900 CFM 1): .
Velocity- 445 fpm 1.3.6 FILTERS (MCM 1211.00-Later)'
a) Total Air Flow 16,900 cfm b) Filter Area _ 64 ftz ,
c) -Prefilter Size . 24 x,24 x 12 d)_ HEPA' Filter Size 24 x 24 x 12 e) Filter Quantity 16 1.3.7 MAINTENANCE AREA DUCT HEATER (MCM 1211.00-1861) a) Tag Number 2MVKDH0003 b) Air Flow 16,700.
c) Duct Size- 42 x 30-d)' -KW .60 e) Entering Air 68 F.
f) Leaving Air 72.2 F g) No. Steps 2 _
h) Voltage 600 volts /3' phase 1.3.8 CHANGE ROOM DUCT HEATER (MCM 1211.00-1861) a) Tag Number 2MVKDH0004
.b) Air Flow 700 c) Duct Size 12 x 9 d) KW 3 e) Entering Air 79.2 f) Leaving Air 89.7 g) No. Steps . 2 h) Voltage- 208 volts /3 phase 1.3.9 PORTABLE FILTER /EXHAUSTERS (MCM 1211.00-tater) a) Tag Number 2MVKFU0006, 2MVKFU0007 b) Air Flow 680 cfm c) Horsepower 1
.d) Voltage 120V e) Filter Type. Disposable phenolic-resin coated cartridge 1.4 INSTRUMENTATION AND CONTROL
'For detailed information concerning instrumentation and control, refer to Duke file number MCM-2211.00-0148.
1.5' SYSTEM OPERATION All switches necessary to operate the system are located-on 2ESB-CP-1. The location of'this control panel is shown on MC-2522.11-86-00.
To start the system supply fan, place 2VKHS5060 in the ON position. This switch is labeled " SUPPLY FAN 2MVKSF0001."
MCSD-2211.00-35 Rev. O
To start the system exhaust fan, place 2VKH55070 in the ON position. This switch is labeled " EXHAUST FAN 2MVKXF0002."
To start she chilled water system, place 2YKH55100 in.the AUTO position. This switch is labeled " CHILLED WATER SYSTEM 2MYKPU0001, 2MYKCH0002." Placing this switch in.the' AUTO position starts the chilled water pump ano gives the chiller ,
a' start permissive. The chiller starts automatically as necessary to maintain- l a return water temperature of 55 F.
The building exhaust flow rate is shown on magnehelic gauge 2VKPG5000. The.
gauge is labeled " EXHAUST FLOW 5000 cfm." The design flow rate is 5000 cfm.
The actual flow rate will vary between 4000 cfm and 6000 cfm depending on filter loading. ,
The total volume of air exhausted from the building is shown on a six digit totalizer (2VKP5001) located on 2ESB-CP-1. The totalizer is labeled " TOTAL EXHAUST VOLUME FT.3 x 1000."
Filter differential pressure is shown on a 0-5 in, w.g. magnehelic gauge Filter differential pressure (2VKPG5030) mounted on filter unit 2MVKFU0005.
should not be allowed to exceed 4.0 in. w.g.
l' l
l
.MC50-2211.00-35 Rev. O
..- . - - . .. . ~-
- 4) An evaluation of.the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or qu'antity of r solid waste that differ from those previously predicted in the License application and amendments thereto;
, RESPONSE:
The McGuire Equipment Staging Building'(ESB), by itself, will not signifi-cantly impact overall station liquid and gaseous affluents or solid waste generation. This conclusion is based mainly a the fact that the staging,.
maintenance, and contaminated material handling activities to be performed in
- the ESB would likely be performed elsewhere in the plant (i.e. containment, Hot Machine Shop, contaminated material handling areas, etc.) if the ESB were
, not available.
t Liquid waste generation resulting from ESB use will be negligible when com-pared to other liquid waste sources at the station. The ESB provides con-taminated parts wash down areas,with provisions to route potentially con-taminated liquids to existing station liquid radweste treatment systems; this capability will be used to reduce both airborne effluent and personnel expo-sures resulting from working on contaminated equipment. The volume of liquid effluent generated will vary. with ESB usage, but will always be negligible when compared to other processes generating liquid radwaste in the plant.
Additionally,.the liquid effluent resulting from ESB contaminated equipment wash down activities would be generated.regardless of ESB availability since 4
these same activities would -likely be performed elsewhere in. the plant.
7 Gaseous effluent releases predicted previously for the station will not be affected by ESB usage. As stated above, the staging, maintenance, and con-taminated materials handling activities to be performed in the ESB would normally be performed elsewhere in the plant if the ESB were not available.
Since the ESB HVAC exhaust is filtered . (i.e. pre-filter and HEPA) prior to release, gaseous effluents generated by the above activities being performed in the ESB will be ALARA and not significantly different form releases pre-dicted previously.
, The quantity of solid waste generated by the station will not be significantly affected by ESB usage. The only solid waste generated as a direct result of ESB usage, that would not have been generated otherwise, is associated with the periodic changeout of pre-filter and HEPA filter units. Changeout of ESB filters units has been estimated to add less than 100 cubic feet per year.of potentially radioactive solid waste to McGuire's total solid waste generation.
, ,, .-n , , - , -
-,mm--,name,,,-,,,,.ac..-rr-n,v--mw.,.. ,,,e ,,-.n , - , - - _ . ...-,----.-,n,- -,.-,--,-,--,-,.n---~ -- . ..
. -_ _ .. . - ~ .
l l
- 5) An evaluation of the change, which shces the expected maximum exposures.
to individual in the UNRESTRICTED AREA and to the general population'that-diffsr_from those~previously estimated in the License application and amendments thereto; i
. RESPONSE: ,
As presented in our response to item #4 above, liquid and gaseous'efflu-ent releases will not differ significantly from those previously predict-ed_in the license application. The meteorological dispersion character-istics of the ESB HVAC discharge point have been reviewed and found to be consistent with assumptions currently being applied for assessing re-leases from existing McGuire. unit vent release point's. Therefore, use of the ESB will not cause expected maximum exposures to individuals or 'the general population to differ significantly from previous predictions
- i. presented to the license application.
l 1
- 6) A comparison of the predicted releases of radioactive materials, in' liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; i
RESPONSE
As presented in our response to item #4 above, use of the ESB will not significantly affect liquid and gaseous effluents or solid waste gener-ation currently resulting from plant operation.
Potential volumes of additional liquid waste generated in the ESB as a result of equipment decontamination activities, beyond those activities
^
previously performed, would have contributed negligibly to the 2.1E+07 gallons of radioactive liquid waste processed at McGuire in 1986.
[ Gaseous effluent radionuclide release rates'for the proposed new ESB
, release point have been estimated based on historical release data for the Oconee Hot Machine Shop. Activities performed in the Oconee Hot Machine Shop are basically the same as those proposed for the ESB.
Oconee Hot Mschine Shop historical release data is provided in Table 1.
Total releases for the McGuire station over the same period of time (1984
~through 1986) are provided in Table 2. A comparison of McGuire FES and historical airborne effluent releases to estimated ESB releases is ;
provided in Table 3. It should be noted that the estimated ESB releases ;
provided in Table 3 do not represent additions to total McGuire histor- l ical releases, but are indirectly considered and included in both the FES I and historical radionuclide release values listed. )
I i
1 l
r g - ww -g--e , e e , -- .-m p' u-g
The potential generation of less than 100 cubic feet of radioactive solid waste as a result of ESB HVAC filter disposal would have contributed negligibly to the 28,194 cubic feet of radioactive solid waste generated by McGuire in 1986.
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and i,
RESPONSE
Use of the ESB to perform staging, maintenance and contaminated materials handling activities will result in reduced station personnel radiological exposure. Whereas the new ESB is designed and equipped to perform the proposed activities while maintaining worker exposures ALARA, performing the same activities elsewhere in the plant (i.e. high background radia-tion dose rate areas in containment) would likely result in higher personnel exposures. The total annual personnel exposure savings will' vary with ESB usage.
- The actual dose savings cannot be numerically quantified at this time.
Reactor vessel stud cleaning is normally done in the fuel pool area which presently has a low background radiation dose level but will increase with increased spent fuel storage. Removal of the upper head injection system piping is another planned use for the ESB which will result in dose savings. While the background levels in upper containment are generally low (5-10 mR/hr) except near the vessel head, moving the piping from containment to the ESB for cutting the pipe into smaller pieces for shipping will result in dose savings.
Future tasks such as work on the reactor coolant pump motors, would result in additional dose savings if performed in the ESB instead of containment; however, again, these dose savings cannot be quantified at this time, but the exposure to plant operating personnel is reduced utilizing the ESB.
TABLE 1 'JCONEE HOT MACHINE SHOP AIRBORNE EFFLUENT RELEASES (CURIES)
NUCLIDE 1984 1985 1986 MN54 1.10E-10 8.50E-07 C057 -
2.35E-07 C058 1.85E-07 3.26E-05 C060 3.11E-07 3.37E-05 ZR95 9.56E-07 NB95 1.46E-06
-RU103 4.39E-07 AG110M .
6.96E-07 I 131 1.13E-05 I 133 8.73E-07 SB125 1.29E-06 CS134 2.05E-08 4.81E-05 CS137 9.9 6E-07 3.40E-05 CE143 4.45E-07
TABLE 2 - McGUIRE HISTORICAL ANNUAL AIRBORNE EFFLUENT RELEASES (CURIES)
NUCLIDE 1984 1985 1986 AVERAGE H3 1.4 8E+01 5.03 E+0,1 6.54E+61 4.35E+01 C 14 -
F 18 1.73E-09 5.77E-10 NA24 3.49E-03 1.16E-03 CL38 7.33E-08 2.44E-08 K 40 2.51E-02 8.37E-03 CR51 2.23E-08 4.58E-05 4.98E-07 , 1.54E-05 MN54 9.39E-06 7.3 5E-05 4.36E-04 1.73E-04 FE59 C057 1.37E-06 4.57E-07 C058 1.48E-04 3.20E-04 6.9 5E-05 1.79E-04 C060 3.10E-05 4.79E-05 1.69E-05 3.19E-05 ZN69M 1.95E-06 6.50E-07 BR82 8.77E-08 2.92E-08 RB88 2.67E-02 8.9 0E-03 SR89 1.58E-08 2.24E-06 7.52E-07 SR90 SR92 9.39E-08 3.13E-08 Y 92 1.49E-08 4.97E-09 Y 93 1.48E-08 4.93E-09 ZR95 NB95 2.45E-10 4.34E-10 2.54E-09 1.07E-09 M099 3.63E-09 1.21E-09 TC99M 1.41E-04 4.70E-05 RU103 3.25E-10 4.50E-06 1.50E-06 RU106 2.19E-08 1.88E-07 7.00E-08 AG108M 7.46E-10 2.49E-10 AG110M IN115M 1.51E-06 5.03E-07 SB125 I 131 9.64E-03 1.61E-02 1.32E-02 1.26E-02 I 132 3.74E-03 1.25E-03 I 133 3.53E-03 8.34E-03 1.15E-02 7.79E-03 I 134 6.17E-07 2.06E-07 I 135 2.53E-03 8.43E-04 CS134 1.92E-05 2.24E-04 4.44E-05 9.59E-05 CS136 5.09E-09 1.45E-08 6.53E-09 CS137 6.06E-05 3.90E-04 8.97E-05 1.80E-04 CS138 9.46E-03 3.15E-03 BA139 1.77E-09 5.90E-10
-CE141- 6.82E-07 1.02E-06 1.78E-07 6.27E-07 CE143 1.19E-05 3.97E-06 CE144 7.59E-06 2.28E-05 4.38E-05 2.47E-05 W 187 6.06E-05 2.02E-05 BI214 1.53E-05 5.10E-06 PB212 6.40E-06 2.13E-06 PB214 1.16E-04 3.87E-05
TABLE 2 - McGUIRE HISTORICAL ANNUAL AIRBORNE EFFLUENT RELEASES (CURIES)
NUCLIDE 1984 .1985 1986 AVERAGE AR 41 3.45E+01 2.81E+01 1.57E+01 2.61E+01 KR85 1.21E+01 7.73E+0'1 5.46E+01 4.80E+01 KR85M 2.83E+00 8.13E+00 4.32E+00 5.09E+00 KR87 2.44E-01 8.83E-01 6.81E-01 6.03E-01 KR88 1.31E+00 5.67E+00 3.62E+00 3.53E+00 XE131M 9.81E+00 2.12E+01 1.58E+01 1.56E+01 XE133 2.15E+03 3.54E+03 2.15E+03 ~
2.61E+03 XE133M 2.49E+01 4.58E+01 2.34E+01 3.14E+01 XE135 4.75E+01 1.17E+02 7.43E+01 7.96E+01 XE135M 1.62E-03 1.15E-03 1.72E-02 6.66E-03 XE137 7.67E-02 2.56E-02 l
TABLE 3 - COMPARISON OF McGUIRE FES AND HISTORICAL AIRBORNE EFFLUENT RELEASES TO EQUIPMENT STAGING BUILDING ESTIMATED SOURCE TERM (CURIES / YEAR)
NUCLIDE McGUIRE McGUIRE ESB FES HISTORICAL (2) PROJECTED (3)
H3 1.92E+03 6.40E+02 C 14 1.60E+01 F 18 8.14E-09 NA24 2.79E-03 CL38 5.15E-06 K 40 5.77E-05 CR51 1.52E-07 HN54 9.40E-03 3.19E-03 9.00E-07 FES9 3.20E-03 C057 1.06E-05 2.00E-07 C058 3.20E-02 1.0 7E-02 3.00E-05 C060 1.4 6E-02 4.87E-03 3.00E-05 ZN69M 2.97E-03 BR82 2.51E-07
- RB88 1.04E-08 SR89 6.80E-04 2.27E-04 SR90 1.24E-04 SR92 1.64E-09 Y 92 3.58E-10 Y 93 4.03E-10 ZR95 1.00E-06 NB95 1.57E-05 1.00E-06 M099 5.00E-07 TC99M 2.33E-08 RU103 8.29E-11 4.00E-07 RU106 1.68E-07 AG108M 4.22E-03 AG110M 7.00E-07 IN115M 4.16E-04 SB125 1.00E-06 I 131 6.60E-02 2.4 6E-02 1.00E-05 I 132 6.86E-08 I 133 9.60E-02 3.23E-02 9.00E-07 I 134 3.20E-05 I 135 2.18E-09 CS134 9.40E-03 3.19E-03 5.00E-06 CS136 -
1.05E-03 CS137 1.56E-02 5.20E-03 3.00E-05 CS138 2.09E-0 7 BA139 1.32E-06 CE141 8.24E-06 CE143 6.73E-06 4.00E-07 CE144 1.70E-06 W 187 7.11E-07 BI214 1.29E-05
r:
TABLE 3 - COMPARISON OF McGUIRE FES AND HISTORICAL AIRBORNE EFFLUENT RELEASES TO EQUIPMENT STAGING BUILDING ESTIMATED SOURCE TERM (CURIES / YEAR)
NUCLIDE McGUIRE McGUIRE ESB FES HISTORICAL (2) PROJECTED (3)
PB212 8.70E+00 PB214 1.60E+01 AR41 5.00E+01 1.84E+01 KR85 5.20E+02 1.74E+02 KR85M 6.00E+00 3.18E+00 ,
KR87 2.00E+00 5.8 7E+00 KR88 1.40E+01 8.76E+02 XE131M 2.00E+01 1.71E+01 XE133 1.86E+03 6.47E+02 XE133M 2.00E+01 6.67E+00 XE135 2.80E+01 9.34E+00 XE135M 0.00E+00 XE137 0.00E+00 NOTES:
(1) NUREG-0063, " Final Environmental Statement Related to the Operation of William B. McGuire Nuclear Station Units 1 and 2," April, 1976, Table 3.4.
(2) Average annual t'otal site airborne releases reported for years 1984 through 1986.
(3) . Based on maximum Oconee Hot Machine Shop annual airborne releases for years 1984 through 1986.
.n_. . -
e ,
u DUKE POWER COMPANY Mc6ylRE NUCLEAR STATION P.O. ses see CORNELlWS, N.C. 153310480 tgLgemong,ayogiepgtss?
May 5, 1987 N. A. Rutherford, System Engineer Licensing Section Nuclear Production Department Duke Power Company Charlotte, N.C. 28242 Attentions J. B. Day
-Subjects Equipment Staging Building Ventilation Commitments
Dear Sir:
The managsment of McGuire Nuclear Station has reviewed the proposed conunitments for testing and operation of the ESB Ventilation Package, and finds it fully acceptable.
Yours truly, 2< @W=* f T. L. McConnell, Manager McGuire Nuclear Station TLM/RFB/chl cc: M.F. 1.3.2.10 i
i
_ . _ _ _ _ . - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ . _ _ _ _ . _ _ _ _ . . _ _ , _ _ _ _ _ _ _ _ _ _ - - . _ . . _ _ . . . _ __ _ . _