Text

Proposed Tech Specs Re Auxiliary Bldg Filtered Ventilation Exhaust Sys & Radwaste Gaseous Effluent Monitoring Instrumentation
	ML20246K113
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/11/1989
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20246K090	List: ML20246K085; ML20246K113;
References
	NUDOCS 8905170242
	Download: ML20246K113 (39)
	v • d • e

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PLANT SYSTEMS 3/4.7.7 AUXILIARY BUILDING FILTEREO VENTILATION EXHAUST SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 The Auxiliary Building Filtered Ventilation Exhaust System shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the Auxiliary Building Filtered Ventilation Exhaust System inoperable, restore the inoperable system to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .*

(4 SURVEILLANCE REQUIREMENTS 4.7.7 The Auxiliary Building Filtered Ventilation Exhaust System shall be demonstrated OPERABLE:

a.

At least once per 31 days, by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at.least 15 minutes; b.

At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system, by:

1)

Verifying that the cleanup system satisfies the in place pene-tration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance of Regulatory UM Positions C.S.a, C.5.c and C.S.d of Regulatory Guide 1.52, /cfm :

Revision 2, March 1978, and the system flow rate is SA,00?

10% (both fans operating - Unit 1) or d?,0^^ cfm + 10% (both fans operating - Unit 2);

40;500

Until 11:59 p.m. September 7, 1983, HOT STANDBY conditions may be maintained on Unit 1 without proceeding to COLD SHUTDOW.

If the system is not restered to

)

OPERABLE status by that time, be in COLD SHUTDOW within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s-s 8905170242 890511 PDR ADOCK 05000369 P

PDC McGUIRE - UNITS 1 and 2 3/4 7-16 A:nendme n t So, %g ((Unit Unit 1) 2)

No.

Amendment

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p' PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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Verifying within.31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.~a of Regulatory Gu8de 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%; and Vi*

Verifying a system flow rate of M,y90

.00 cfm i 10% (both fans 3) 3 operating - Unit 1) or Q cfm + 10% (both fans operating -

Unit 2) during system operation when tested in-accordance with ANSI N510-1975.

g c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation, by verifying,

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within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;

d.

At least once per 18 months, by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than 6 inches Water Gauge while operating the system at a flow rate of q s, y e o 5',0^^ cfm -

10% (both fans operating - Unit 1) or -4h000 cfm +

10% (both fans operating - Unit 2), and Hojsad 2)

Verifying that the system starts on a Safety Injection test signal and directs its exhaust flow through the HEPA filters and charcoal adsorbers.

After each complete or partial replacement of a HEPA filter bank, by e.

verifying that the HEPA filter bank satisfies the in place penetration and bypass leakage testing criteria of less than 1% in accordance with ANSI N510-1975 for a 00P test aerosol while operating the system at a flow rate of 64,000 cfm 10% (both fans operating - Unit 1) or 43,000 cfm + 10% both fans operating - Unit 2); and

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After each complete or partial replacement of a charcoal adsorber bank, by verifying that the charcoal adsorber satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1975 for a halogenated hydro-carbon refrigerant test gas while operating the system at a flow rate of 5%600 cfm i 10% (both f ans operating - Unit 1) or 4;006 cfm 10%

(both fans operating - Unit 2).

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McGUIRE - UNITS I and 2 3/4 7-17 Ambed Ah.

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6 Cknys INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring inst,umentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure.that the limits of Specification 3.11.2.1 are not exceeded.

The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 3.3-13.

ACTION:

a.

With a radioactive gaseous effluerit monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, in lieu of a Licensee Event Report, explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

The provisions of Specification 3.0.3 are not applicable.

l c.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous ef fluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL. CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies sh5wn in Table 4.3-9.

MCGUIRE - UNITS 1 and 2 3/4 3-71 Amendment No. 87 (Unit 1)

Amendment No. 68 (Unit 2)

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n TABLE 3.3-13,(Continued)

TABLE NOTATION n

At all times.

AA During WASTE GAS HOLDUP SYSTEM operation.

- - During gaseous effluent releases.

t ACTION STATEMENTS ACTION 35 -

With the number of channels GPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

?

At least two independent samples of the tank's contents a.

are analyzed, and b.

At least two technically qualified members of the facility staff independently verify the discharge valve lineup:

1)

The manual portion of the computer input for the release rate calculations performed on the computer, or 2)

The entire release rate calculations if such calcula-tions are performed manually.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 37 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via thi.s pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 38 -

With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, immediately suspend PURGING or VENTING of radioactive effluents via this pathway.

ACTION 39 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days.

With two channels inoperable, be in at least HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 40 -

With the number of channels OPERABLE less than required by ne Minimum Channels OPERA 8LE requirement, effluent releases sia the effected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.1:-2.

ACTION 41 -

With the number of channels OPERA 8LE one less than requirec by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.

Amendment No. 1 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-74 Amendment No. 20 (Unit 1>

4/13/83

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TABLE 4.3-9 (Continued) w i

TABLE NOTATION I

At all times except when the isolation valve is closed and locked.

During WASTE GAS HOLDUP SYSTEM operation.

(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm / Trip Setpoint, b.

Circuit failure (alarm only), and c.

Instrument indicates a downscale failure (alarm only).

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

i a.

Instrument indicates measured levels above the Alarm Setpoint, b.

Circuit failure, and c.

Instrument indicates a downscale failure.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) The, CHANNEL CALIBRATION shall include the use of standard gas samples corresponding to alarm setpoints in accordance with the manufacturer's recommendations.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommendations.

In addition, a standard gas sample of nominal 4 volume percent oxygen, balance nitrogen, shall be ured in the calibration to check linearity of the oxygen analyzer.

l Amendment No.10 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-77 Amendment No. 29 (Unit 1) l

b 4 Aje.s O

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.10 The Loose-Part Detection System shall be OPERABLE.

APPLICABILITY:

H0 DES 1 and 2 ACTION:

a.

With one'or more Loose-Part Detection System channels inoperable for more than 30 days, prepare and submit a Special. Report to the Commission pursuant to Specification 6.9.2.within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b.

The provisions of. Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each channel of the Loose-Part Detection Systems shall be demonstrated OPERABLE by performance of:

I a.

A CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and b.

An ANALOG CHANNEL OPERATIONAL TEST except for verification of Setpoint at least once per 31 days, and c.

A CHANNEL CALIBRATION at least one per 18 months.

McGUIRE - UNITS 1 and 2 3/4 3-78 Amendment No. 87 (Unit 1)

Amendment No. 68 (Unit 2)

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RADI0ACTXVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS g~

DOSE RATE LIMITING CONDITION FOR OPERATION l

3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents frem the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

j a.

For noble gases:

Less than or equal to 500 mrem /yr to the whole body and less than or equal to 3000 mrem /yr to the skin, and b.

For Iodine-131 and 133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days:

Less than or equal to 1500 mrem /yr to any organ.

APPLICABILITY:

At all times.

ACTION:

With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

MCGUIRE - UNITS 1 and 2 3/4 11-9 Amendment No. 52 ; Unit :)

Amendment No. 33 (Unit :)

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TABLE NOTATION i

(1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

J For a particular measurement system (which may include radiochemical separation):

4'

$ D LLD =

E V

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exp (-Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

is the standard deviation of the background counting rate or of s htne counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 x 108 ic the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclides, and t

at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

Typical values of E, V, Y, and at shall be used in the calculation.

l It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

McGUIRE - UNITS 1 and 2 3/4 11-11

ko b4M (5 TABLE 4.11-2 (Continued)

TABLE NOTATION o

(2) Sampling and analysis shall also be performed following shutdown, STARTUP, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

(3)

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(4)_ Samples shall be changed.at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

(5) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) The ratio of the sample flow volume to the sampled stream flow volume shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

(7) The principal gamma emitters for which-the LLD specification. applies include the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137,and Cegl41 in iodine and particulate releases.

The LLO for Ce-144 is 5x10 pCi/ml.

This list does nat mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Sem_iannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7.

(8) The composite filter (s) will be analyzed for alpha activity by analyzing one filter per week to ensure that at least four filters are analyzed per collection period.

I 4

"cGUIRE - U.1ITS 1 and 2 3/4 11-12 i

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$1TE SOUNDARY FCA CASECUS EFFLUENT $

McGUIRE NUCt. EAR STATIQN FIGURE 5.1-3 McGUIRE - UNITS I and 2 5-4 A: endment No.

(Unit 14 Amendment No.

(Unit 2)

betyds O

BASES v

STANOBY NUCLEAR SERVICE WATER POND (Continued)

The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply to safety-related equipment without exceeding their design basis temperature and is consistent with the recommend-ations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants,"

March 1974.

The Surveillance Requirements specified for the dam inspection will conform to the recommendations of Regulatory Guide 1.127, Revision 1, March 1978 3/4.7.6 CONTROL AREA VENTILATION SYSTEM The OPERABILITY of the Control Area Ventilation System ensures that:

(1) the ambient air temperature does not exceed the allowable temperature for o

continuous duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.

This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR 50.

ANSI N510-1975 will be used as a procedural guide for surveillance testing.

3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM The OPERABILITY of the Auxiliary Building Filtered Ventilation Exhaust System ensures that radioactive materials leaking from the ECCS equipment within the auxiliary building following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations were assumed in the accident analyses. ANSI N510-1975 will be used as a procedural guide for surveillance testing.

The methyl iodide penetration test criteria for the carbon samples have been made

, more restrictive than required for the assumed iodine removal in the accident analysis because the humidity may be greater than 70% under normal operating conditions.

l 1

i McGUIRE - UNITS 1 and 2 B 3/4 7-4 s

b*

' Docdment Control Desk j

May 11, 1989 i

ATTACHMENT No. 2 1

McGUIRE NUCLEAR STATION PROPOSED TECHNICAL SPECIFICATION REVISION BACKGROUND INFORMATION SUPPORTING THE PROPOSED CHANGES

[Doctimenf Control Desk

~

May 11, 1989 Page 1 of 5 Waste Handling Modification NSM MG-11202, known as the Waste Handling Modification, will add a new addition to the north end of the Auxiliary Service Building and will:

1.

Increase Radwaste storage and compacting areas; 2.

Increase Chemistry laboratory and Health Physics office areas; 3.

Reduce the total volume of low-level radwaste by installing new laundry and equipment decontamination equipment, and new waste compacting equipment; and, 4.

Enclose and provide ventilation for the Waste Solidification (WS) building.

By installing a high density waste shredder / compactor at McGuire, we will be able to reduce radwaste disposal volume and holding area space. The physical layout of the addition will include an additional area to house a storage area for packaged compacted /non-compacted waste, a shipping dock, and an area for a high density shredder / compactor on elevation 760. The current waste shipping dock will be converted into a shielded waste drum storage area. The present waste drum storage area will be converted to a bagged waste storage area.

A second floor will house the new Chemistry labs which will replace the existing labs. Additional office space will also be provided for Health Physics.

The existing decontamination equipment at McGuire is designed for use with aggressive cleanir.g chemicals and are not compatible with the materials of construction and process media in the radwaste system. The chemicals have long since been banned at the station; therefore, rendering the existing decontamination equipment ineffective. Also, the existing equipment was not designed for the decontamination of electrical equipment. There has been an increase of electrical equipment used in contaminated areas over the years resulting in about 30% of the equipment requiring decontamination being electrical. Decontamination also requires the ability to remove oil, grease, paint, and adhesive residues from surfaces.

Seventy-five percent of all materials require this process. At this time the equipment at McGuire falls short in this area. The addition of newer trnhnology will aid in this area.

Our existing laundry decontamination facility uses conventional water wash machines. The new laundry dry cleaning system will result in a reduction in waste water by using a dry cleaning solvent that can be distilled and re-used in the system.

The WS building was originally designed to provide an area for waste solidification and was designed with partially open walls to permit an abundant ventilation flow due to the volatile waste solidification media that McGuire intended to use for waste solidification. Subsequently, McGuire decided not to use this solidification media and now uses a de-watering system.

The WS building is also used to house portable demineralized units.

The WS building was originally designed as a separate structure from the Auxiliary Service Building and required that personnel exit the Auxiliary Service Building to get to the WS building. Therefore, the building has been enclosed and attached to the Auxiliary service building.

, ' Document Control Desk Hay 11, 1989 Page 2 of 5 Attaching the WS building to the Auxiliary Service Building will incorporate it into the RCA and allow personnel access without exiting the RCA. Also, the WS building will be serviced by Radwaste Building Ventilation system.

In summary, the Waste Handling modification will provide the facilities needed to safely sort, handle, compact, and store (temporarily) solid radioactive waste.

Implementation of the NSM will result in a significant reduction in the volume of contaminated materials to be disposed of as low-level waste. Benefits of this NSM are consistent with NRC policy on volume reduction, INPO Good Practices, and are consistent with ALARA guidelines. Additionally, these radwaste reductions will allow McGuire to meet the State Compact Allocation limits. Reduction of radioactive waste volume is ever increasingly important due to the impending closure of the Barnwell Low-Level Waste Facility.

The modification will also require changes to the existing HVAC equipment as well as add new equipment. A summary of the major changes is presented below.

A.

Provide a new air handling unit with roof-mounted air intake to serve the existing labs and new labs, along with the new office space. This unit will be served with chilled water from new air cooled chillers to provide comfort conditioning. This unit is identified as OMVAAH047. The HP office, HP storage, conference room, and other areas that are not potentially contaminated and require comfort conditions are served by OMVAAH047.

B.

Provide two (2) new 50% capacity heating and ventilating units in a roof mounted penthouse to serve the ventilated areas. These units are identified as OMVAAH108 and OMVAAH109. The built-up units consist of a housing with filter, heater, and evaporative cooler. Areas served by these units include the Hot Machine Shop, shipping area, contaminated box area, and others.

C.

Existing equipment on raw water cooling (ABRWS-1, CMH-AHU-1, and CMH-AHS-1) will be modified to operate on chilled water.

D.

Preheat for the new supply units will be provided by resistance heaters.

E.

New exhaust fans and HEPA filters will be provided to serve all radwaste areas except the Contaminated Materials Handling (CMH) area. All potentially contaminated radwaste areas are exhausted through filter unit OMVAFU0110.

The air is drawn through this unit by two large vane axial exhaust fans OMVAXF0111 and OMVAXF0112. The new exhaust fans will be tied in with CMH-XF-1.

All air is monitored for radiation and a continuous count is maintained of the total exhaust air.

F.

The Chemistry Office Area, Locker Rooms, First Aid, and areas that are potentially contaminated, and require total comfort conditions, are served by 0MVAAH0003.

OMVAAH0003 is a built up unit furnished with a fan, chilled water cooling coil, large preheating coil, and filters. This unit uses 100%

outside air, with all areas being exhausted through the system described in section E.

G.

Chilled water coils identified in this description are served by three new 33% capacity air cooled chillers and two new 100% capacity pumps. In addition there is one air cooled chiller and one pump that provide cooling to the dry cleaning condensers. Both systems are inter-piped for backup.

, ' Document Control Desk May 11, 1989

. Attachment 2 Page 3 of 5 l

Auxiliary Building System Description The design basis for the Auxiliary Building Ventilation system as discussed in FSAR Section 9.4.2 are to:

Provide a suitable environment for the operation of equipment and personnel access as required for inspection, testing and maintenance.

Maintain the building at a slightly negative pressure to minimize out leakage.

Provide purging of the building to the unit vent. The air exhausted to the environment from potentially contaminated areas is monitored and filtered, as required, so that the limits of 10 CFR 20 and the Technical Specification are not exceeded.

Provide a suitable environment for the operation of vital equipment during an accident.

The Auxiliary Building Ventilation System is composed of the following subsystems:

A.

Fuel Handling Ventilation System Makeup air from outdoors for the fuel handling area is provided for each station unit by a separate supply subsystem (FSAR Figure 9.4.2-3) consisting of one 100 percent capacity fan with heating and cooling coils and a medium efficiency air filter. This subsystem is not impacted by the implementation of NSM MG-11202.

B.

Fuel Handling Ventilation Exhauster The fuel handling ventilation exhaust subsystem consists of two 100 percent capacity fans, ductwork, bypass and filters. Exhaust air is directed either through the filter system or through the bypass and then to the unit vent. This operation affords a minimum of ten air changes per hour over toc fuel pool to continuously purge the area of any heat, humidity, gaseous or particulate matter. This subsystem is not impacted by the implementation of NSM MG-11202.

C.

Auxiliary Building General Ventilation Supply Makeup air from the atmosphere for the general ventilation supply subsystem in the Auxiliary Building is provided for each station unit.

Each unit is supplied by two air handling units ccalisting of pro-filters, heating and cooling coils and supply fan. The supply units l

do not have standby capacity. Normally, both fans operate at their design speed with the air distributed throughout the building aided by the suction of the various exhaust ventilation systems. This subsystem is not affected by implementation of NSM MG-11202 although the associated exhaust system is affected (see F below).

I

Docu. -ment Control Desk May 11, 1989 Page 4 of 5 The Auxiliary building supply system is tabulated below:

AIR HANDLING UNIT CFM AFFECT DUE TO MG-11202 l

ABSU-1A 31,355 NONE ABSU-1B 31,355 NONE ABSU-2A 31,355 NONE ABSU-2B 31,355 NONE OMVAAH0003 36,490 SUPPLIES AIR TO RADWASTE AREAS WHICH ARE NOW EXHAUSTED BY OMVAFU0110 D.

Radwaste Area Supply (Descriptions as-modified by NSM MG-11202)

One multi-zone air handling unit containing hot deck hot water heating coil, cold deck cooling coil, hot water reheat coil, zone mixing dampers, roughing filters, and modified ductwork provides cooling to the chemical area, locker rooms and other potentially contaminated areas.

Air handling unit OMVAAH0003 uses 100% outside air.

NSM MG-11202 added two new 50% capacity built-up heating and ventilating units which will serve the hot machine shop, shipping area, and contaminated box area. The units, identified as OMVAAH108 and OMVAAH109, consist of a housing with filters, heating coil, evaporative cooler, and supply fan.

E.

Radwaste Area Exhaust The radwaste areas are presently exhausted by the Auxiliary Building General and Filtered Exhaust subsystems. NSM MG-11202 will separate the existing radwaste areas from the Auxiliary Building exhaust systems.

The radwaste exhaust system consists of two 50% fans, OMVAXF0111 and OMVAXF0112, which serve filter unit OMVAFUO110, which consists of pre-filters and HEPA filters. This filter unit will serve existing and new radwaste area exhaust needs, except the CMH area. The CMH area exhaust is supplied by a single 100% fan CMH-XF-1 and a HEPA filter.

F.

Auxiliary Building Ventilation Exhaust (Description as-modified by MG-11202)

Each station unit is served by two independent exhaust subsystems, Auxiliary Building filtered ventilation exhaust and Auxiliary Building general ventilation exhaust subsystems. The filtered ventilation consists of two 50% exhaust fans (ABFXF-1A,1B,2A,2B) which serve a j

filter unit (ABFU-1 and ABFU-2) consisting of pre-filters, absolute filters, carbon filters, bypass and associated duct work. The filtered ventilation exhaust serves potentially contaminated areas and maintains them under a slight negative pressure. The Auxiliary Building general l

ventilation exhaust subsystem serves areas that are not subject to contamination.

These areas have ventilation rates based upon heat loads only. Each general ventilation unit consists of two 50% capacity fans (ABUFX-1A,1B and ABUFX-2A,2B).

J

'. iDoctiment Control Desk Hay 11, 1989 Page 5 of 5

-All existing exhaust systems in the Auxiliary Building are of greater capacity than the supply systems, thus maintaining the Auxiliary i

Building at a negative pressure. Durind Operation of either unit, all associated Auxiliary Building ventilation systems are aligned to

" normal" operation. During shutdown of either unit, associated Auxiliary Building ventilation systems may operate in part or in total to suit maintenance, inspection, testing or refueling.

Continuous monitoring is provided at appropriate areas throughout the building to assure safe conditions of temperature and radioactivity, and to alert operating personnel of an abnormality (FSAR subsections 12.1.4 and 12.2.4) l 4

l I

i

i r'

, " Document Control Desk

,May 11, 1989' ATTACHMENT No. 3 McGUIRE NUCLEAR STATION PROPOSED TECHNICAL SPECIFICATION REVISION TECHNICAL JUSTIFICATION SUPPORTING PROPOSED CHANGES l

l l

I i

l l

I lW-_____.___-_-__-

' Document Control Desk May 11, 1989 Page 1 of 8 Technical Justification Auxiliary Building filtered exhaust is presently provided by two systems. The Unit 1 system consists of the Unit 1 Auxiliary Building Filter Unit and Fans (ABFXF-1A, and IB). This unit processes 53,775 CFM of exhaust air to the Unit 1 station vent from contaminated areas. The Unit 2 system consists of the Unit 2 Auxiliary Building Filter Unit and Fans (ABFXF-2A, and 2B). This unit processes 43,000 CFM of exhaust air to the Unit 2 station vent from contaminated areas.

The existing plant radwaste areas presently served by these filter units will be disconnected and served by the new filter unit OHVAFU0110.

Each filtered exhaust ventilation system serves two general areas, the lower levels of the Auxiliary Building (see Tables 5 and 6 below) and potentially contaminated portions of the radwaste area (see Tables 2 and 4 below). Similarly the general ventilation exhaust systems serve Auxiliary Building areas and radwaste areas that are not potentially contaminated.

The majority of the areas served by each exhaust ventilation system do not require carbon fi)tering.

Credit is not taken for Auxiliary Building filter units in determining the offsite consequences of ECCS leakage during a design bases accident.

Nuclear Station Modification MG-11202 will disconnect the radwaste areas from the Unit 1 and 2 filtered and unfiltered exhaust systems. This change will remove 13 rooms from the carbon filtered exhaust train and redirect the exhaust from these rooms to the HEPA (High Efficiency Particulate Absolute) filtered exhaust train 0MVAFUO110. The areas removed contain no potential ECCS leakage sources and are contaminated only by the transport of solid waste into the area. There are no sources of volatile iodine in these areas and thus no carbon filters are required.

There is no increase in offsite radiological consequences from any postulated accident as a result of this modification.

As shown in the attached partial flow diagrams, (Flow Diagrams 1 - 4) these areas will be served by the new radwaste area exhaust filter unit OMOVAFUO110. It should be noted that the net exhaust flow from these rooms has been increased as has the exhaust rate for the rooms remaining on ABFXF-1A, ABFXF-1B, -2A, and -2B; thus, reducing the worker inhalation dose hazard.

Tables 1,2,3, and 4 below compare the original design exhaust values to those that will be supplied by OMVAFUO110.

Table 5 below lists the Auxiliary Building lower elevation areas served by the unit 1 filtered exhaust unit and associated fans ABXF-1A and ABXF-1B. The flow values listed are the pre-modified balanced condition totalling 41,095 CFM. The present flow requirement listed in Tech Spec 4.7.7 of 54,000 CFM +/- 10% includes 12,640 CFM for radwaste area ventilation as detailed in Table 2.

This ventilation will be supplied by OMOVAFUO110 and was increased to 15,310 CFM, per NSM MG-11202.

IDocument Control Desk May 11, 1989 Page 2 of 8 A main trunk duct draws the 12,640 CFM of ventilation exhaust to the Unit 1 filtered exhaust fans. The station Performance group conducted.~ low tests with the trunk duct isolated to simulate the post-modified system conditions. Test results indicate that at the present fan speed, the exhaust fans for Unit 1 will pull either 44,811 CFM (filtered), or 48,618 CFM (through bypass) depending on the filter mode.

Our amendment request is to change the Tech Spec 4.7.7 unit 1 flow requirement of 54,000 CFM +/-10 % to 45,700 CFM +/- 10%. The area still served by the unit 1 filtered exhaust will see a net increase in exhaust flow from a pre-modified 41,095 CFM to the post modified 45,700 CFM.

Table 6 below lists the lower Auxiliary Building areas served by the Unit 2 filtered exhaust unit and associated fans ABXF-2A and ABXF-2B. The flow values listed are the pre-modified balanced condition totalling 36,400 CFM. The present flow requirement listed in the Tech Spec 4.7.7 of 45,000 CFM +/- 10% includes 5,915 CFM for radwaste area ventilation as detailed in Table 4 below. This ventilation will be supplied by 0MVAFUO110 and will be increased to 6,835 CFM, per NSM MG-11202.

A main trunk duct draws the 5,915 CFM of ventilation exhaust to the Unit 1 filtered exhaust fans. The station Performance group conducted flow tests with the trunk duct isolated to simulate the post-modified system conditions. The test results indicate that at the present fan speed, the exhaust fans for Unit 2 will pull either 39,446 CFM (filtered), or 42,046 CFM (through bypass) depending on the filter mode.

Our amendment request is to change the Tech Spec 4.7.7 Unit 2 flow requirement of 43,000 CFM +/- 10% to 40,500 CFM +/- 10%. The area still served by the Unit 2 filtered exhaust will see a net increase in exhaust flow from a pre-modified 37,480 CFM to a post modified 40,500 CFM.

The new flow rates of 45,700 CFM for the Unit 1 filtered exhaust unit and 40,500 CFM for the Unit 2 filtered exhaust unit have been evaluated. Our calculation MCC-1211.00-00-0117 predicts a post-accident temperature in the auxiliary building based on heat loads measured during normal plant operation. The calculation indicates a maximum, worst case, expected building temperature of approximately l

133 degrees-F. This result is based on extended operation at high ambient outdoor conditions, minimum ventilation rates, and with no credit taken for reduced heat loads concurrent with unit shutdown. Most electric equipment (MOVs, transmitters, etc..) located in these areas is designed for a continuous operating temperature of 120 degrees-F. Increases above this value should have no adverse effect on electrical equipment provided increases are infrequent and last a short period of time (5 days).

Motor control centers, remote starters, contactors, power panelboards, and control j

panels are designed and built under established industry standards which assumes the equipment will be located in what the Nuclear Industry has defined as a " mild environment".

This type of equipment located in the areas serviced by the ABFVE system is designed for normal operation between 40 degrees-F to 104 degrees-F.

Again limited increases above 104 degrees-F should have no effect if the increases are infrequent and last only a short period of time.

l 1

Document Control D(sk May 11, 1989 -

Page 3 of 8 The ventilation system is usually shut down once a month for preventative maintenance, with only one or two of the filtered exhaust fans remaining in operation to maintain a negative pressure in the building. No adverse temperature conditions are experienced during this operation. Normally, temperatures range from 85 degrees-F to 90 degrees-F.

A summary of calculation MCC-1211.00-00-0117 predicted post-accident building temperatures is presented below:

CASE FILTERED EXHAUST FAN STATUS AUX. BLDG. TEMP.

1)

All four filtered exhaust fans operating 108 degrees-F 2)

Two filtered exhaust fans operating, one per unit 119 degrees-F 3)

Both Unit 1 filtered exhaust fans operating 128 degrees-F 4)

Both Unit 2 filtered exhaust fans operating 133 degrees-F The Auxiliary Building supply and unfiltered exhaust are not Nuclear Safety Related and therefore are not considered operable during a LOCA or Blackout.

During normal plant operation all supply and exhaust fans operate. If a LOCA or Blackout occurs on either train of either unit, both filter trains will run in the filter mode. Failure Case 1 is based on all filtered exhaust fans operating while supply and unfiltered exhaust fans are deenergized.

In the event of a single diesel power failure during a LOCA or Blackout, one 50% fan on each filtered exhaust train will remain operating. Failure Case 2 analyses this alignment.

Failure Case 3 is based on the remote possibility of the Unit 2 filter being unavailable due to maintenance, concurrent with a LOCA or Blackout. The Unit 1 fans and filter train remain operable. Failure Case 4 is based on the remote possibility of the Unit 1 filter being unavailable due to maintenance, concurrent with a LOCA or Blackout. The Unit 2 fans and filter train remain operable.

The new Unit 1 and Unit 2 filtered exhaust flow rates have been evaluated to determine their effect on the relative humidity entering the filters. The air cleaning industry recognizes the effect of humidity on the performance of activated carbon used in filter systems.

Calculation MCC-1211.00-00-0117 indicates a maximum post-accident exhaust air humidity of 77%. The air cleaning industry has adopted the practice of limiting the relative humidity to 70%.

If the humidity did become excessive and caused degradation of the filter bed, the postulated off-site dose is still within the acceptance criteria of 10CFR100. A dose calculation was performed which evaluated the LOCA dose due to a gross failure of a passive component, and added the results to the FSAR Case 1 &nalysis dose results.

(Nuclear power plants that do not provide an ESF atmosphere filtration system are required by Standard Review Plan (SRP) 15.6.5 Appendix B to include in the design basis LOCA assessment the leakage from a gross failure of a passive component.) The calculated total Low Population Zone (LPZ) dose of 83 Rem is below the 10 CFR 100 allowable value of 300 Rem.

1 l

1. m DocNe'nt.'ControlDesk May 11, 1989 l Attachment &3 Page 4 of 8

. A summary of_ calculation'MCC-1211.00-00-0117 predicted post-accident filter inlet humidity values.are presented below:

OUTSIDE AIR ESUPPLY AIR

FILTER EXHAUST FAN STATUC CONDITIONS CONDITIONS HUMIDITY 1.A11 4 exhaust fans opera. 95 Fdb, 80 Fwb 50.0%

2. Unit 2 exhaust fans only 95 Fdb, 80 Fwb 34.0%

3.A11 4 exhaust fans opera. 80 Fdb, 78 Fwb 77.0%

' 4. Unit 2 exhaust fans only 80 Fdb, 78 Fwb 51.0%

~

5.All supply & exhaust fans 75 F, 95%

61.0%

6.A11 supply & exhaust fans 45 F, 95% '61.0%

To support these' calculated air conditions, data recorded at the Unit 1 ABFVE inlet was collected between June and October 1987. The temperature and relative humidity of air entering the filter package was measured during this period, at which time, the Auxiliary Building Ventilation system operating configuration

. was varied to allow for preventative maintenance. Review of the accumulated data shows no temperature in excess of 92 degrees-F (normally ranged from 85 - 90 degrees-F) and no relative humidities in excess of 70% (normally ranged from 40 -

60%).

A comparison of the' Auxiliary Building filtered ventilation exhaust subsystem

' designed to Regulatory Guide'1.52 is presented in FSAR table 9.4.2-3.

This comparison is still valid and all values of filter train flow quantities will be updated to the new flow values.

The following tables compare the exhaust flow rates in CFM that were provided by the existing Unit 1 exhaust fans, to that now provided through the new Filter Unit OMVAFUO110.

Table 1. : Unit 1 Unfiltered Exhaust Portion served by Filter Unit OMVAFUO110 EXHAUST ROOM DESCRIPTION OLD (CFM)

NEW (CFM) 1002 Corridor 1,590 1,730 1101 Ventilation Equipment Rm.

4,610 5,680 1107 Cold Lab 1,370 1,200 1014.

Clean Toilet Rm.

275 360 1015 Clean Towel Rm.

220 120 1017 Clean Locker Rm.

1,435 1,255 1019 Clean Clothing 480 190 9,980 10,535 I

01.D - Ventilation by ABUFX-1A AND ABUFX-1B NEW - Ventilation by OHVAFU0110 I

b

/ i' IpochentControl-Desk llay 11, 1989.

' Attachment 3 Page 5 of 8 Table 2': Unit'l Filtered Exhaust Portion served by Filter Unit ONVAFUO110 EXHAUST

' ROOM DESCRIPTION OLD (CFM)

NEW (CFM)

'1004 First Aid.

590 540 1006 Receiving Room 205 100 1009 Laundry (New name Storage) 1,665 920 1011 Waste Shipping 3,195 3,000 1012 Drum Storage 745 700

.1012A-Aisle 60 1105 Hot Lab (New # 1115) 5,680 9,600 1106.

A A Rm. (New # 1116) 500 450 12,640 15,310

-The following tables compare the exhaust flow rates in CFM that were provided by the existing Unit 1 exhaust fans, to that now provided through the new filter unit OMVAFUO110.

Table 3: Unit 2 Unfiltered Exhaust Portion served by filter unit OMVAFUO110.

EXHAUST ROOM DESCRIPTION OLD (CFM)

NEW (CFM)'

1024 Hot Machine Shop 13,375 1102 Mens Toilet (new name is 305 600 Mens /Womens) 1103 Womens 195 13,875 600 OLD - Ventilation previously provided by ABUXF-2A, ABUXF-2B NEW - Ventilation provided by 0MVAFUO110 See value listed below for NEW total exhaust for Room 1024.

Table 4: Unit 2 Filtered Exhaust Portion served by filter unit ONVAFUO110 EXHAUST ROOM DESCRIPTION OLD (CFM)

NEW (CFM) l 1022 Contaminated Shower 475 405 1023A Mens Contaminated Change Rm.

340 260 1023B Womens Contaminated Change 270 200 1023C Womens Clean Toilet 150 270 1024 Hot Machine Shop 4,680 5,700 5,915 6,835 OLD - Ventilation previously provided by ABFXF-2A, ABFXF-2B NEW - Ventilation provided by 0MVAFUO110

I

-Document'Contrcl Dack

.-1+ Mny 11, 1989

Attachment 3

. Page 6 of 8 3

3 I

l Table 5: Unit 1 Filtered Exhaust Area 8 Flow Values are Premodification Flows Room Name-Supply Direct Supply Indirect Exhaust

'I All Pipe Chases 3115 CFM 3115 CFM i

C.S. & R.H.R Heat Exchanger Rooms 4500 CFM 500 CFM 5000 CFM Mechanical Penetration Rooms 5125 CFM 255 CFM 5380 CFM Waste Drumming Area 1620 CFM 400 CFM 2020 CFM Reciprocating Charging Pump Rooms 294L CFM 330 CFM 3270 CFM Centrifugal Charging Pump Rooms 675 CFM 80 CFM 755 CFM S.I. Pump Rooma 235 CFM 225 CFM 460 CFM Fuel Pool Cooling Heat Exchanger Rooms 1500 CFM 1500 CFM Letdown Heat Exchanger 420 CFM Rooms 420 CFM All Filter and Heat Exchanger Rooms Not

-Listed above 4925 CFM 4925 CFM

' Volume Control Tank Rooms 350 CFM 350 CFM Boric Acid Tank Rooms 2560 CFM 2560 CFM Waste Gas Tank Room 1890 CFM 1890 CFM 1685 CFM Sampling Rooms 1685 CFM Hydrogen Recombiner Rooms 880 CFM 880 CFM Waste Gas Compressor Rooms 4000 CFM 4000 CFM Mixing and Settling Tank 120 CFM Rooms 120 CFM Mixing and Settling Tank Muqp Rooms 400 CFM 400 CFM Spent Resin Storage Tank 400 CFM Rooms 400 CFM Laundry and Hot Shower 650 CFM Tank Rooms 650 CFM 1290 CFM j

C.S. and RHR Pump Rooms 1290 CFM NS-ND Sump 25 CFM 25 CFM

{

TOTAL 41095 CFM

= _ _ _ _ _ _.

..(-

Document Control Dstk

,Mr.y 11, 1989 Attechmeat 3 Page 7. of 8 Table 6: Unit 2 Filtered Exhaust Area 4 Flow Valuus are Premodification Flows Rocm Name Supply Direct

. Supply Indirect.

Exhaust 3270 CFM All Pipe Chases 3270 CFM C.S. & R.H.R Heat Exchanger Rooms 4500 CFM 500 CFM 5000 CFM Mechanical Penetration Rooms 5125 CFM 255 CFM 5380 CFM Reciprocating Charging Pump Rooms 2940 CFM 330 CFM 3270 CFM Centrifugal Charging Pump Rooms 675 CFM 80 CFM 755 CFM S.I. Pump Rooma 235 CFM 225 CFM 460 CFM Fuel Pool Cooling Heat 1500 CFM Exchanger Rooms 1500 CFM Letdown Heat Exchanger 420 CFM Rooms 420 CFM All Filter and Heat Exchanger Rooms Not, 4280 CFM Listed above' 4280 CFM volume Control Tank 350 CFM Rooms 350 CFM Boron Recycle Evaporator 935 CFM Package Rooms 835 CFM Waste Evaporator Package 910 CFM Rooms 910 CFM Waste Evaporator Feed 220 CFM Tank Pump Rooms 220 CFM Waste Evaporator Feed 235 CFM Tank Pump Rooms 235 CFM Waste Drain Leakage 235 CFM Holding Tank Rooms 235 CFM Chemical Drain Tank Pung 440 CFM Rooms 440 CFM 1685 CFM Sample Rooms 1685 CFM 1290 CFM C.S. and RHR Pump Rooms 1290 CFM 25 CFM NS-ND Sump 25 CFM Boron Recycle Holdup 5880 CFM Tank Rooms 5880 CFM TOTAL 36440 CFM 1

' ' Document Control Desh

~

May 11, 1989 Page 8 of 8 Environmental Assessment The existing ventilation system releases gaseous effluents at three locations, the Unit 1 vent stack, the Unit 2 vent stack, and the discharge of fan CMH-XF-1.

Each of these locations is monitored.

NSM MG-11202 will relocate the radiation monitor EMF 53, and relocate the release point associated with CMH-XF-1.

The new location for the vent stack is 60 feet from the existing location. Radiation monitor EMF 53 will be used at the new vent stack location which will handle all exhaust associated with exhaust fans OHVAXF0110, OMVAXF0111, and CMH-XF-1, or Radwaste Area Vent. The new radwaste handling area will be vented through the Radwaste Area Vent along with ventilation from 13 rooms in the Auxiliary Building that formerly discharged through the Station Unit Vents. As a result of the modification, the total Auxiliary Building ventilation exhaust is increased from 187,985 CFM to 214,650 CFM. The Auxiliary Building exhaust through the Unit 1 Vent is reduced from 91,925 CFM to 73,020 CFM and the Unit 2 Vent is reduced from 81,545 CFM to 64,775 CFM. The Radwaste Area Vent exhaust will be increased from 14,515 CFM to 76,855 CFM.

A worst case accident associated with failure of liquid radioactive piping in the post modified waste handling area has been evaluated and it was determined that the current range of EMF 53 is adequate to monitor all potential releases from the area. This potential accident was present prior to the modification and was reanalyzed since its release path will change from the unit vent to EMF 53 per the waste handling modification.

EMF 53 will still terminate releases on receipt of a high radiation alatm following the modification and all release areas from the waste handling area that could be potentially radioactive will continue to be monitored.

The gaseous curie release from plant operations will not increase as a result of this modification. The improved solid waste handling capability will reduce solid radwaste volume while the improved laundry facilities will reduce liquid radwaste volume.

Offsite dose calculation methodology as given in the Offsite Dose Calculation Manual (0DCM) will not be changed as a result of this modification; however, effluent monitor (EMF) setpoints will be changed prior to operation of the modified ventilation system to account for the revised discharge flow rates mentioned above. Offsite doses are calculated based on measured releases in microcuries per second from all gaseous release points using the GASPAR (NUREG 0597) computer code. Flow rates from each release point are measured and totaled to obtain the correct input data. Offsite dose will not increase as a result of this modification; therefore, no changes to the GASPAR computer code are required as a result of this modification. Monitor setpoints are established to warn if any release point is excessive in terms of dose limits using the design release rates from the vent. Typical set point calculations are provided in the ODCM.

The modification to the ventilation systems as described, and the relocation of the existing release point will not increase the existing offsite dose analysis or j

the environmental consequences of operating the plant.

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l locument Control Desk May 11, 1989 ATTACHMENT No. 4 McGUIRE NUCLEAR STATION PROPOSED TECHNICAL SPECIFICATION REVISION SIGNIFICANT HAZARDS CONSIDERATION DISCUSSION SUPPORTING CHANGES l

l-

~

B Document Control Desk May 11, 1989 Page 1 of 3 Significant Hazards Consideration Discussion The proposed change to the ABFVE system flowrates does not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated; 2) Create the possibility of a new or different kind of accident from any previously analyzed; or 3) involve a significant reduction in a margin of safety.

The new flow rates for the Unit 1 and Unit 2 filtered exhaust unit have been evaluated and our calculation predicts a post-accident temperature in the auxiliary building based on heat loads measured during normal plant operation.

The calculation indicates a maximum, worst case, expected building temperature of approximately 133 degrees-F. This result is based on extended operation at high ambient outdoor conditions, minimum ventilation rates, and with no credit taken for reduced heat loads concurrent with unit shutdown.

Most electric equipment (MOVs, transmitters, etc.,) located in these areas is designed for a continuous operating temperature of 120 degrees-F. Increases above this value should have no adverse effect on this electrical equipment provided increases are infrequent and last a short period of time (5 days). Motor control centers, remote starters, contactors, power panelboards, and control panels are designed and built under established industry standards which assumes the equipment will be located in what the Nuclear Industry has defined as a " mild environment". This type of equipment located in the areas serviced by the ABFVE system is designed for normal operation between 40 degrees-F to 104 degrees-F.

Again limited increases above 104 degrees-F should have no effect if the increases are infrequent and last only a short period of time (5 days).

The ventilation system is usually shut down once a month for preventative maintenance, with only one or two of the filtered exhaust fans remaining in operation to maintain a negative pressure in the building. No adverse temperature conditions are experienced during this operation. Normally, temperatures range from 85 degrees-F to 90 degrees-F.

The new Unit 1 and Unit 2 filtered exhaust flow rates have been evaluated to determine their effect on the relative humidity entering the filters. The air cleaning industry recognizes the effect of humidity on the performance of activated carbon used in filter systems. Our calculation indicates a maximum post-accident exhaust air humidity of 77%. The air cleaning industry has adopted the practice of limiting the relative humidity to 70%.

If the humidity did become excessive and caused degradation of the filter bed, the postulated off-site dose is still within the acceptance criteria of 10CFR100. A dose calculation was performed which evaluated the LOCA dose due to a gross failure of a passive component, and added the results to the FSAR Case 1 analysis dose results.

(Nuclear power plants that do not provide an ESF atmosphere filtration system are required by Standard Review Plan (SRP) 15.6.5 Appendix B to include in the design basis LOCA assessment the Icakage from a gross failure of a passive component.)

The calculated total Low Population Zone (LPZ) dose of 83 Rem is below the 10 CFR 100 allowable value of 300 Rem.

s e

e..

Document Control Desk May 11, 1989 i

Page 2 of 3 The ABFVE system will continue to provide a suitable environment for the operation of equipment and provide personnel access as required for inspection, testing and maintenance.

The ABFVE system will provide a suitable environment f or the operation of vital equipment during and following an accident. The ABFVE system will maintain the building at a slightly negative pressure to minimize out-leakage. The ABFVE system will provide purging of the building to the unit vents. The air exhausted to the environment from potentially contaminated areas is continuously monitored, and filtered as required, so that the limits of 10 CFR 20 and the Technical Specification are not exceeded.

The proposed change to relocate the existing gaseous release point, currently identified as the Contaminated Parts Warehouse vent, does not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated; 2) Create the possibility of a new or different kind of accident from any previously analyzed; or 3) involve a significant reduction in a margin of safety.

As previously stated, the existing vent is located at the discharge of fan CMH-XF-1 and is monitored by EMF 53.

The relocation of the radiation monitor EMF 53, and the release point associated with CMH-XF-1 is necessitated by the waste handling modification.

The new location for the release point is 60 feet from the existing location. Radiation monitor EMF 53 will be used at the new release point location which will handle all exhaust associated with exhaust fans OMVAXF0110, ONVAXF0111, and CMH-XF-1.

The new radwaste handling area will be vented through the relocated release point along with ventilation from 13 rooms in the Auxiliary Building that formerly discharged through the Station Unit Vents. A worst case accident associated with failure of liquid radioactive piping in the modified waste handling area has been evaluated and it was determined that the current range of EMF 53 is adequate to monitor all potential releases from the area. This potential accident was present prior to the modification and was reanalyzed since its release path will change from the unit vent to EMF 53 per the waste handling modification.

EMF 53 will still terminate releases on receipt of a high radiation alarm following the modification and all release areas from the waste handling area that could be potentially radioactive will continue to be monitored.

The gaseous curie release from plant operations will not increase as a result of this amendment. Offsite doses are calculated based on measured releases in microcuries per second from all gaseous release points using the GASPAR (NUREG 0597) computer code. No changes to the GASPAR computer code are required as a result of this amendment. Monitor setpoints are established to warn if any release point is excessive in terms of dose limits using the design release rates from the vent. Typical set point calculations are provided in the Offsite Dose Calculation Manual and may be revised as needed.

Therefore, the relocation of the existing release point will not increase the existing offsite dose analysis or the environmental consequences of operating the plant.

p

,4....

Document Control Desk Hay 11, 1989 Page 3 of 3 The proposed changes to the affected tables have been submitted to rename the

" Contaminated Parts Warehouse" designation for the relocated radiation monitor to read " Waste Handling Area" to reflect the new location of the monitor and the building ventilation system which it is used to monitor. This change is intended to provide a better description of the monitor and its use.

These changes are administrative and do not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated; 2) Create the possibility of a new or different kind of accident from any previously analyzed; or 3) involve a significant reduction in a margin of safety.

- - - _ - _ - _ _ _ _ _ - _ - _. _ _.. _ _ _ _ _ _ _. _ _ _ _.

ML20246K113

Text

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