ML20097D052

Interim Guidelines for Containment Purge Operation Clinton Power Station - Unit 1

ML20097D052
Person / Time
Site:	Clinton
Issue date:	06/30/1984
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20097D048	List: ML20097D045 ML20097D052
References
PROC-840630, NUDOCS 8409170355
Download: ML20097D052 (16)

Text

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- TABLE OF CONTENTS a Page

1.0 INTRODUCTION

1 2.0.1 CONSIDERATIONS FOR CONTAINMENT PURGE OPERATION 1

~

2.1 -Airborne-Radioactivity Levels' 1 2.2 Nonradioactive Pollutants 3 3.0 FACTORS AFFECTING CONTAINMENT AIRBORNE

. RADIOACTIVITY LEVELS 3 3.1 Sources of Airborne Radioactivity 3 3.2 Containment Purge Operation 4 4.0 INDICATORS OF CONTAINMENT AIRBORNE RADIOACTIVITY 4 4.1 Airborne Radioactivity Measurement 4 4.2 Reactor Coolant Radioactivity Concentration 5 5.0 INTERIM GUIDELINES FOR PURGE OPERATION 6

-5.1 Bases and Discussion 6 5.2 - Description 7

6.0 REFERENCES

8 LIST OF TABLES AND FIGURES TABLE 1 - RADIATION CUBICLES WITHIN THE CONTAINMENT 9 -

TABLE 2 - ORIGINS OF CONTAINME T AIRBORNE RADIOACTIVITY 10 FIGURE 1 - Buildup of Airborne ~ Iodine in Containment After Continucus Containment Purge System Isolation 11 FIGURE 2 - Containment General Arrangement at Elevation 755'-0" 12 L ' FIGURE 3 - Containment General Arrangement at Elevation 778'-0" and.789'-1" 13 FIGURE 4 - Containment General Arrangement at-El'evatioli 803'-3"~and 816'-7" 14 w

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I INTERIM GUIDELINES FOR CONTAINMENT PURGE OPERATION

1.0 INTRODUCTION

The Clinton Power Station-(CPS) containment-purge system design consists of a high volume Containment Building HVAC System (CBHS) .and a low volume Continuous Containment Purge System (CCPS), as described in CPS Final Safety Analysis Report (Reference 1) . It is proposed that the use of the

_.30,000 cfm CBHS will be limited to 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year during plant operating modes 1 through 3. The CBHS can be utilized on an unlimited basis during plant operating modes 4 and 5.

The 8,000.cfm CCPS will be used continuously during operating modes l'through 3 except during the operation of CBHS.

Gaseous effluents based upon a continuous ~ containment purge are found to be well within the applicable limits, as seen in CPS-FSAR Tables 11.3-9 and 11.3-11.

In accepting the CPS containment purge system design, the NRC has required that IPC develop and implement during plant operation prior to the first refueling outage, interim guidelines for containment purge operations (~ Reference 2, Section 6. 2.4.1) . It is intended that the, guidelines ~will address the possibility of a reduction in the use of CCPS with due consideration given to containment airborne activity 1,evels, and overall containment air quality.

- 2,0 CONSIDERATIONS h0R CONTAINMENT PURGE OPERATION The containment purge system is designed to enhance personnel habitability in the containment, exclusive of the drywell,

- during all modes of operation. Control of environment for

. equipment and other considerations is not dependent upon

'the containment purge operation, in accordance with Branch

. Technical Position (BTP) CSB 6-4 (Reference 2).

.The scope of the-conta'inment purge system in relation to habitability is control of radioactive and nonradioactive pollutants in the air to within the' acceptable levels. Heat removal is accomplished through area coolers, which are de-signed to control local temperatures independent of CCPS or CBHS operation.

s 2.1 Airborne Radioactivity Levels The. containment airborne radioactivity level.must be controlled and maintained 1,n accordance with 10CFR20 and Regulatory Guide 8.8.

. The airborne radioactivity limitations are discussed in 10CFR, Sections 20.103 (a) (1) , 20.13 0 (a) ( 3) and 20.203(d). These regulations can be interpreted into

, the following guidelines:

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a. If the airborne radioactivity in. work areas is maintained.below 1/4 MP.C *, the workers occupying these areas will not be $equired to undergo an assessment of radioactivity. intake. ,

b. Work areas where the airborne radioactivity exceeds 1/4 MPC , will have to be designated as " Airborne Rahioactivity Areas."

The ALARA design guidance provided by the R.G. 8.8 with regard to the-control of airborne radfoactivity is summarized'as follows:

a. The source terms used in the design shall be those corresponding to an offgas release rate of 100,000 pCi/sec, at 30 min decay, for BWR's.

b. The airborne radioactivity control systems (i.e.,

HVAC and' leakage control) shall be designed to maintain airborne radioactivity in work areas well below MPC R 's.

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c. Designs that permit repeated. release of radioactiv_ity material into work areas are contrary to ALARA philosophy. -

d. Routine provisions of. protection through use of individual respirators is generally unacceptable.

e. The spread of contamination shall be limited by maintaining air pressure gradients and airflows from the areas of low potential airborne contamina-tion to areas of higher potential contamination.

The containment purge syst'em design and' operation should be thus based upon two main objectivcc, which are consistent with the ALARA philosophy. These objectives are as follows:

a. To maintain air pressure gradients and airflows from general access areas to radiation. cubicles, where ,

the potential for contamination is higher.

b. To maintain airborne radioactivity concentrations below 41/4 MPC in general areas, and below N1 MPC n ra a on cubicles.

R ,

• Maximum permissible concentrations per 10CFR20, Appendix "B",

LTable I, column 1.

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4 2.2- Nonradioactive Pollutants There.are no stored sources of toxic material in the

-containment, - the leakage of which may impair habitability.

The fumes generated from chemicals used during cleaning and from welding operations during maintenance activity would be of concern.

3.0 FACTORS AFFECTING CONTAINMENT AIRBORNE RADIOACTIVITY LEVELS The containment airborne radioactivity level is affected by the sources of airborne radioactivity and the operation and' air flow volume of the containment purge system.

3.1 Sources of Airborne Radioactivity There are three distinct sources of radioactivity that will contribute to the airborne activity in the general areas of the containment. They are the re-

-fueling pool, suppression pool and leakage of reactor coolant within the containment (outside the drywell) .

a. The refueling pool may contribute significantly onJy during refueling operation. During such times, presumably,-the high volume CBHS will be used. Hence the refueling pool is not used as a contributing' source in developing these guide-lines for the CCPS operation.

b. .The suppression pool is exposed to areas of person- .

nel access, in the Mark III containment , and hence

. - contributes to the airborne radioactivity. During normal power operation the suppression pool is, contaminated by leakage of steam and reactor water.

This aspect, and the resultant airborne radioactivity levels in the containment genaral areas have been analyzed in the General Elect;-ic Company Document 22A5718, " Containment Dose Reduction Study." The results of this study, which was prepared for the standard GE Mark III design, are approximately true for Clinton. They indicate that under expected operating conditions the suppression pool could contribute an airborne level of about 0.1 MPC R*

The suppression pool can also contribute heavily

.to - the airborne radioactivity levels following the safety / relief valve blowdown. This condition

- is expected to be of a transient nature, and is not included in this evaluation. Further, Clinton's design includes a suppression pool cleanup system, which can be used when necessary.

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c. The leakage of reactor coolant and steam within the primary containment (outside the drywell? also con-a _ tributes to the airborne radioactivity. It is found to-be the largest contributor during normal power

. operation. The leakage is expected to occur primarily

.e owithin the cubicles which house the reactor water cleanup system components.

3.2 Containment Purge Operation -

The effects of the low volume CCPS operation only will be considered here. The use of the purge system has two effects on the containment airborne radioactivity level.

-a. It. established pressure boundaries and prevents, to ,

a great extent, the spread of airborne contamination from radiation cubicles to general areas.

b. It removes the airborne radionuclides, thus reducing their levels in containment areas. '

If the contaimnent purge is isolated, the airborne j radioactivity in the containment starts building  ;

~

up cowards an asymptotic value. The projected buildup of iodine activity in Clinton containment is depicted in Figure 1, based upon a design basis reactor coolant

• concentration and a rate of coolant leakage outside the drywell of 1.0 gpm'with a partition factor of 0.01.

(The coolant leakage assumed is equivalent to that determined by the total offsite release considerations

-of Appendix I to 10CFR50. This is not to be confused with the total coolant leakage. permissible, per t'he

, technical specifications, because most of the latter occurs inside the drywell.) It is seen from Figure 1 that the iodine activity ~ builds up to 1/2 of-the asymptotic value in about 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> and to its asymptotic value of 93 MPC in about 1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. The iodine level

p exceeds 1/4 MPC in about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following CCPS isolation.

4.0 INDICATORS OF CONTAINMENT AIRBORNE RADIOACTIVITY h The indicators of the containment airborne radioactivity can t be'of two types

the direct measurement, and an indication of its potential via the reactor coolant radioactivity con-centration.

4 . l' Airborne Radioactivity Measurement In order to be.able to measure airborne levels of the order of 1/4 MPC with confidence, continuous air monitors (CAM) with measurement capability below this value will be needed. CPS employs state-of-the-art CAM's.which are capable of measuring 1/10 MPC in one hour'of its occurrence.

_4_

.- + .

The: greatest potential for airborne activity exists i

.within and in.the vicinity of the radiation cubicles,

, .regardless of whether the purge is operating or not.

If'the purge is operating and the pressure boundaries -!

are maintained,: the potential for airborne activity to enter the general' areas.exis.ts only through the leakage of' air from those-area-coolers which~are located outside '

of the rooms that they serve. A list of CPS containment

-cubicles, their locations and the location of their '

area coolers'isoprovided in Table 1. 'The cubicle g locations are also-shown in Figures 2, 3 and 4.

Based upon this information it is determined that the smonitoring for airborne activity will be very effective '

at.the following locations.

a. Containment Building elevation 778'-0", Az. 300* '

b. Containment. Building elevation 803'-3", Az. 45'

c. Containment Building elevation 737'-0", any azimuth.

4.2 Reactor Coolant Radioactivity Concentration Reactor coolant concentration and its leakage outside

'the drywell largely determine the airborne activity in the containment. - Figure 1 provides the airborne levels cased upon the : design basis coolant activity concentration, which is 1.5x10-2 pCi/cc for I-131i and --

a leak rate of 1 gpm at a partition factor of 0.01.

If.the coolant concentration and/or its leak rate are smaller, the equilibrium airborne level in the con-tainment will accordingly'be smaller.

Based upon maintaining the containment airborne level at or.below 1/4 MPC, a threshold coolant concentration can be defined as one-that will. lead to 1/4 MPC in the containment with the purge isolated. Once the threshold value is exceeded, the use of the. containment purge becomes necessary for maintaining' containment. airborne level at or below 1/4 MPC. (This threshold value is not to be confused with the technical specification value of the coolant concentration, which is based upon the offsite dose considerations, and is intended to accommodate transient conditions.) Since the design basis coolant concentration leads to 93 MPC in containment, the thres-hold goncentration corresponding to 1/4 MPC would be 4x10- pCi/cc of I-131. It is possible to measure.such

'a concentration from a coolant sample.taken either at the reactor building sampling phnel or the postaccident sampling -

panel.

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.t Similarly, the threshold value of coolant leak rate can be~ defined as one that will~ lead to airborne level of 1/4 MPC at design basis coolant concentration and with purge. isolated. The threshold leak rate is determined to be ((1/4)/93xl;0) or 0.003 gpm at 0.01 partition

' factor. This is an immeasurably.small leak rate, and

, hence cannot serve as a guideline for purge operation.

It. indicates, however, that even small leak rates can

' lead to higher than acceptable airborne activity.

5.0 ? INTERIM GUIDELINES FOR PURGE OPERATION 5.1 Bases and Discussion Containment purging.is needed for personnel accessi-bility which is required in the Mark III containment.

During plant operations prior to the first refueling, IPC.will determine the accessibility requirements more precisely through a Data Gathering Program and Con-tainment Access Management Program (References 3 and 4) .

The present guidelines are proposed for interim use.

From Section 3.2 above, it is seen that the airborne

~

activity level is heavily dependent upon whether the purge is operating or is isolated. Initiation of the purge operation can be based upon the measured airbo,rne radioactivity level or'the reactor coolant I-131 concentration level,as' discussed in' Sections 4 1' and 4.2 above. The CCPS is designed to maintain 1/4 MPC in containment general areas with,the coolant concentrations at the design basis levels, and its leakage at 1,gpm at

.0.01' partition factor. Once the purge is initiated, the airborne level in the containment is expected to decrease generally to a level below 1/4 MPC, unless design basis conditions exist. .

Termination of the containment purge will be based upon the elimination of the origins of airborne radioactivity.

Table 2 provides a listing of the origins of airborne activity,and the ways that they can be eliminated. It is further.noted that the purge cannot be terminated based upon a low airborne level,.because without any change in the sources contributing to the' airborne level it will build up again quite' rapidly to unacceptable levels.

Thus, basing the purge termination on low airborne level will result in cyclic use.of the purge system and cyclic opening and closing of the containment isolation valves.

. 'Such.an operation could be.very harmful to the life and dependability of'the isolation valves, and is to be avoided.

0 i .

l 5.2 Description The following guidelines for the containment purge operation are proposed based on the above information and discussion. These guidelines apply to the use of the low volume CCPS only.

a. Initiate CCPS operation after an airborne level of 1/4 MPC or greater is. measured at any of the three 3 locations given in Section 4.1 above. IPC proposes to use a portable CAM at each of these locations, which will feed information to,the main control room.

b. Initiate CCPS operat' ion after the coolant I-131 con-centration is measured in a sample to be higher than the threshold value of 4x10-5 pCi/cc.

c. Put the CCPS in use for the duration of any welding operations or cleaning tasks using chemicals within '

the containment.

d. Once initiated, leave the CCPS on until one of the -

ways of removal of the origins of airborne activity,

,as listed in Table 2, has been implemented.

It is anticipated that the CCPS may be in continuous use for extended perio'ds of time. The guidelines, however, provide the operator with criteria based upon which he may keep the system isolated until the airborne radiation in the containment becomes a potential problem.

9 4

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e 6.0 REFERENGS

.l. Final Safety Analysis Report, Clinton Power Station, Septicn 9.4.6.

2. NUREG-0853, Supplement No. 2, " Safety Evaluation Report Related to the. Operation.of Clinton Power Station lbit No.1," U.S. Nuclear Regulatory Comission, May 1983.

3. IltG-II Positicn Paper 4-CSB, " Containment Purge Operational Data Gathering and Evaluation Progra," June 1984.

4. LRG-II Position Paper 5-GB, " Containment Access Kenyt Program,"

Jtme 1984.

MMe 9

?

TABLE 1 RADIATION' CUBICLES WITHIN THE CGNTAINMENT Cubicle Cooler No. Description Location Within or Outside

1. Reactor Water Cleanup System El. 816'-7" Within

'(RWCU) Valve Room

2. . Filter /Demineralizer (F/D) El. 803'-3" None Holding Pump Cubicle

3. Pipe Cubicle El. 789'-1" Within

4. RWCU Backwash El. 778'-0" Within Receiving Pump Cubicle

5. RWCU Backwash El. 778'-0" Within Receiving Tank Cubicle

6. RWCU Valve Room A El. 789'-1" Within

7. -RWCU Valve Room B El. 789'-1" Within

8. Fuel Transfer Valve Room El. 755'-0" None

9. Main Steam Pipe Tunnel El. 755'-0" . Within

10. Regenerative & Non-Regenera- El. 789'-1" Outside tive Heat Exchanger Cubicle A llc Regenerative & Non-Regenera- El 789'-1" Outside tive-Heat Exchanger Cubicle B

12. F/D Vessel A El. 803'-3" Outside

13. F/D Vessel B El. 803'-3" Outside I

TABLE 2  ;

1 ORIGINS OF CONTAINMENT AIRBORNE RADIOACTIVITY Origin Way'to Remove / Improve

1. Leaky Fuel Refueling

2. Power Level Change Transient condition (Leads to iodine spiking) self-rectified

3. Reactor Water Cleanup Maintenance

• System Malfunction

4. Leaky Equipment Maintenance

• Inside Containment

5. Condensate Polisher Maintenance

• Malfunction

6. SRV Discharges Transient condition self-rectified

• MaintenancEscheduleandfrequencyisdeterminedbythe technical specification requirements and the existing approved plant maintenance program.

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