ML20195G871

Proposed Tech Specs,Deleting Refs to Automatic Isolation of Main Control Room Environ Control Sys & to Main Control Room Chlorine Detectors

ML20195G871
Person / Time
Site:	Hatch
Issue date:	06/20/1988
From:	GEORGIA POWER CO.
To:
Shared Package
ML20195G868	List: ML20195G863 ML20195G871
References
TAC-68686, TAC-68687, NUDOCS 8806280167
Download: ML20195G871 (14)

Text

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,o BASES FOR LIMITING CONDITIONS FOR OPERATION occurs with each monitor indicating HI H! Hl, one monitor HI HI H! and the other downscale, or with both monitors downscale. The HI Hi H! setpoint cor-responds to the instantaneous release limit.

2. Refuelino Floor Exhaust Vent Radiation Monitors Four radiation monitors are provided which initiate isolation of the second-ary containment and operation of the standby gas treatment system. The in-strument channels monitor the radiation from the refueling area ventilation exhaust ducts.

Two instrument channels with two radiation monitors in each channel are ar-ranged in a two upscale (either channel) trip logic. Trip settings for the monitors in the refueling floor exhaust ventilation ducts are cased upon ini-tiating normal ventilation isolation and standby gas treatment system opera-tion so that none cf the activity released during the refueling accident leaves she reactor building via the normal ventilation path but rather all the ac-tivity is processed by the standby gas treatment system.

3. Reactor Buildina Exhaust Vent Radiation Monitors Fcur radiation monitors are provided which initiate secondary containment iso-lation, primary containment purge and vent valves isolation and standby gas treatment system actuation. The instrument channels monitor the radiation from the reactor building lower level ventilation exhaust duct.

Two instrument channels with two radiation detectors in each channel are ar-ranged in a two upscale (either channel) trip logic. The trip settings are based on limiting the release of radioactivity via the normal ventilation path and rerouting this activity to be processed through the standby gas treatment system.

4. Control Room Intake Radiation Monitors Two radiation monitors are provided to initiate pressurization of the main l control room and recirculation of control room air through filters. The instrument channels monitor radiation from the control room ventilation intake duct.

Two instrument channels are arranged in one upscale, two downscale trip log-ic. The trip settings are based on limiting the radioactivity f rom entering the control room from outside.

5. Main Steam Line Radiation Nonitors Although their primary function is to close the MSIVs, the four Main Steam Line radiation monitors also initiate isolation of the mechanical vacuum pump and the gland seal exhauster condenser. The instrument channels monitor the radiation in the main steam line tunnel. The purpose of automatically iso-lating the mechanical vacuum pump line is to provide timely protection against the release of radioactive materials from the main condenser. Upon receipt of main steam line high radiation signals, the primary containment and reac-tor vessel isolation control system initiates closure of the mechanical vac-uum pump line valve. This isolation precludes or limits the release of fis-sion product radioactivity which, upon fuel failure would be transported from HATCH - UNIT 1 3.2-66 Proposed TS/02290/221-0 8806200167 000620 1 PDR ADOCK O*>OO P

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• LIMITING CONDITIONS FOR OPER M ION SURVEILLANCE REQUIREMENTS 3.12.A.2. Performance Recuirements 4.12.A.2. Filter Testina

a. The results of the in-place a. The tests and analysis 00P and halogenat&d hydro- shall be performed at carbon tests at design flows least once per operating on HEPA filters and charcoal cycle, not to exceed 18 absorber banks shall show months, or af ter every 199-percent 00P removal and 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system opera-199-percent halogenated tion or following painting, hydrocarbon removal, respec- fire or chemical release in tively when tested in accordance any ventilation zone cco uni-with ANSI N510-1975. cating with the system,

b. The results of laboratory b. 00P testing shall be per-carbon sample analysis formed af ter each complete shall show 190-percent radio- or partial replacement of active methyl iodide the HEP.* filter bank or removal when tested in af ter any structural accordance with RDT-M16-li maintenance on the system (25'C, 95-percent R.H.). housing. ,

c. Fans shall be shown to c. Halogenated hydrocarbon operate within 110-percent testing shall be performed design flow when tested af ter each complete or in accordance with ANSI partial replacement of the N 510-197 5. charcoal adsorber bank of after any structural maintenance on the system housing.

B. Iselation Valve Operability and B. Isolation Valve Testino Closino Time (Deleted)

(Deleted)

HATCH - UNIT 1 3.12-2 Proposed TS/0231g/154-51

.., O, LIMITING CONDITIONS Fo1 OPERATION SURVEILLANCE REQUIREMENTS 3.12. C . Radiation Monitors 4.12.C. Radiation Monitors i The control room air intake The control room air intake  !

radiation monitors or suitable radiation monitors shall be  !

i respective temporary units shall tested in accordance with '

j be operable whenever the venti- Table 4.2-8.  !

4 1ation system is required to be l 1 operable by Specification 3.12. A.1.

. except that one radiation monitor i may be out of service 30 days.  !

D. Shutdown Reauirements '

In the event that Specifications  !

3.12.A. through 3.12.C. cannot be  !

met, the reacter shall be placed

• in the Cold Shutdown Condition with- t in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or, if refueling opera-1 tions are in progress, such opera-  ;

I tions will be terminated within l 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

E. Chlorine Monitors E. Chlorine Monitors l 1

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HATCH - UNIT 1 3.12-3 Proposed TS/0226q/221-22 1

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3.12, MAIN CONTROL ROOM ENVIRONMENTAL SYSTEM The control room air treatment system is designed to filter the control room atmosphere for intake air and/or for recirculation during pressurization conditions.

A. Ventilation System Operability Requirements The control room air treatment system operates on emergency power and is designed to filter the control rooin atmosphere for intake air and or recirculation air during control room pressurization conditions. l The control room air treatment s'. '-

s designed to automatically start upon receipt of an initiati signal ard to align the system dampers to provide for pressuri n tion of the control room.

Pressurization will be initiated upon receipt of any one of the follow-ing signals: High radiation at control room intake, LOCA signO from Unit 1 or 2, main steam line high radiation from Unit 1 or 2, main steam line high flow from Unit 1 or 2, or refueling floor high radiation from Unit 1 or 2. In this mode tht normal contrcl room exhaust fan is stopped and outside air is taken in through one of the charcoal filters to pressurize the control room with respect to the surrounding turbine building.

I High ef ficiency particulate air (HEPA) filters are installed Defore the charcoal adsorbers to prevent clogging of the iodine adsorbers.

The charcoal adsorbers are installed to reduce the potential intaFe of radioiodine to the control room. Bypass leakage for the charcoal adsorbers and particulate removal ef ficiency for HEPA filters are determined by halog:nated hydrocarbon and 00P, respectively. The laboratory carbon sample test results indicate a radioactive methyl iodide removal efficiency for expected accident conditions. Ope ra -

tion of the fans significantly different from the design flow will change the removal ef ficiency of the HEPA filters and charcoal adsor-bers. If the performances are as specified, the calculated doses would be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.

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HATCH - UNIT 1 3.12-4 Proposed TS/0226q/221-51

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8.  ! solation Valve Operability and Closino Time (Deleted)

C. Radiation Monitors At least one channel (detector) in the control room air intake radia-tion monitoring system must be operable at.all times for indication-alarm of radioactivity being drawn into the main control room. Main control room intake air filtration is required when a trip signal from the detectors is given via failure.or pressurization signals from both '

channels or a failure signal in'one channel and a pressurization signal in the other channel.

D. Shutdown Reauirements Shutdown requirements are based on the need to ensure habitability for operations personnel during normal plant operation and subse-quent to a postulated design basis accident.

F. Chlorine Monitors (Deleted) 4.12. MAIN CONTROL ROOM ENVIRONMENTAL SYSTEM l A. Ventilation System Tests Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 in. of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter. A test frequency of once per operating cycle established system verformance capability.

HATCH - UNIT 1 3.12-5 Proposed TS/0226q/221-51

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' The frequency of tests and sample armlysis are necessary to show that the HEPA filters and charcoal adsorbers .an perform as evaluated.

Replacement adsorbent should be qualified according to the guidelines of Regulatory Guide 1.52. The charcoal adsorber ef ficiency test procedures shall allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtain-ing at least two samples. Each sample should be at least 2 in, in diameter and a length equal to the thickness of the bed. If the iodine removal ef ficiency test results are unacceptable, all adsorbent in the system should be replaced. Any HEPA filters found defective should be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.

Operation of the system every month will demonstrate operability of the filters and adsorber system. Operation for 15 minutes demon-strates operability and removes the moisture build-up during testing.

If painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemi-cals or foreign reterials, the same tests and sample analysis should be performed as required for operational use.

Demonstration of the automatic initiation capability is necessary to assure system performance capability.

B. Isolation Valve Testina (Deleted)

C. Radiation Bases for the control room air intake radiation monitors are specifi-cally discussed in Bases for Limiting Conditions for Operation, Speci-fication 3.2.H.4., and are generally discussed in Bases for Surveillance Requirements, Specification 4.2.

D. . References

1. (Deleted)

2. (Deleted)

3. ANSI Stardard N101.1,1972, "Ef ficiency Testing of Air-Cleaning Systems Containing Devices for Removal of Particulat:s".

HATCH - UNIT 1 3.12-6 Proposed TS/0226q/221-51

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37 TABLE 3.3.6.7-1 fSHEET 1 OF 21 - . '.o 3>

-4 n MCRECS ACTUATION INSTRUMENTATION-x c: MINIMUM NUMBER APPLICABLE TRIP FUNCTION OPERABLE CHANNELS OPERATIONAL 4

{c PER TRIP SYSTEMialfb) CONDITION

~ . ACTION'

1. Reactor Vessel Water Level -

PO 2 1, 2,- 3 52 Low Low Low (Level 1) (c)

. 2B21-N691 A, B, C, D .

2. D rywe l l Pressure - High (c) .,

2E11-N694 A, B, C, D 2 1, 2, 3 52

3. Main Steam Line Radiation - High (c) 2 1, 2, 3,'**

2011-K603 A, B, C, D. $3

4. Main Steam Line Flow - High (c) 2/line 1, 2, 3 2821-N686 A, B, C, D 53 2B21-N687 A, B, C, D 2821-N688 A, B, C, D

- 2821-N689 A, B,C,D

5. Rerueling Floor Area Radiation - High (c) 1 2021-K002 A, D 1, 2, 3,5,* $4 N

es 6. Control Room Air Inle'. Radiation - High (c) 1 1,2,3,5.*

1Z41-R615 A, B 54 co o,

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MCRECS ACTUATION INSTRUMENTATION ACTION ACTION-52 -

Take the ACTION required by Specification 3.3.3.

ACTION 53 -

Take the ACTION required by Specification ~3.3.2.

' ACTION 54 -

a.

With one of the required radiation monitors inoperable, restore the monitor to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiateofand mode maintain operation of the MCRECS in-the pressurization operation, b.

With no radiation monitors OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation.

operation of the MCRECS in the pressurization mode of c.

The provisions of Specification 3.0.4 are not applicable.

NOTES When handling irradiated fuel in secondary containment, a.

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveiliance without placing the trip system in the tripped condition, provided atthat system is monitoring leastparameter, one other OPERABLE channel in the same trip b.

With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to 0PERABLE status witnin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.6.7-1 for that Trip Function shall be taken, c.

Actuates the MCRECS in the control room pressurization mode.

d. (Deleted) e.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20 percent rated power, the normal full power radiation background level and associated trip setpoints may be changed the test. based on a calcula ud value of the radiation level expected during The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen inj tion. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20 percent rated power.

HATCH - UNIT 2 3/4 3-58b Proposed TS/0230q/221-88

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> TABLE48.3.6.7-1 y MCRECS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2

8 CHANNEL CilANNEL FUNCTIONAL OPERATIONAL C TRIP FUNCTION CHANNEL CONDITIONS IN WHICH:

CHECK TEST 2 _

CAllBRATION SURVEILLANCE REQUIRED Q -1. Reactor Vessel Water Level -

Low Low Low (LeveI 1)

S M R 1, , 2, 3 N

2. Drywe l l Pressure - High S M R 1, 2, 3

3. Main Steam Line Radiation - High D W E *8 R 1, 2, 3 24 Main _ Steam Line Flow - High S M R 1, 2, . 3

5. Refueling Floor Area Radiation - D M t **'

liigh Q . 1,2,3,5

6. Control Room Air inlet NA ME** R Radiation - liigh 1* 2* 3 *' 5**-

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tn co CL When handling i rradiated fuel ibthesecondarycontainment.

s. Instrument alignment using a standa rd current source. ,

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PLANT SYSTEMS 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM (MCRECS)

LIMITING CONDITION FOR OPERATION 3.7.2 Two independent MCRECS shall be OPERABLE.

APOLICABILITY: CONDITIONS 1, 2, 3, 5, and **.

, l ACTION:

a. With one MCRECS inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the foliowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With both MCRECS inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.2 Each MCRECS shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is s 105 F.

b. 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.

c. At least once per 18 months or (1) after any structural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:

1. Performing a visual inspection of the system and all associated components before each leak test in accordance with Section 5 of ANSI N510-1975.

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• • Whsn handling irradiated fuel in secondary containment.

HATCH - UNIT 2 3/4 7-6 Proposed TS/0227q/221-71 1

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Verifying that the cleanup sy' stem satisfies the.in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S a, C.S.c and C.S.d of Regulatory Guide 1.52, Revision 1, July 1976, ano the system flow rate is 2500 cfm i 10 percent.

3. Verifying within 31-days a,t.'r removal that a laboratory analysis of a representative "bon sample obtained in accordance with Regulatory Po.4tica C.6.b.of Regulatory 1

Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52, Revision 1, July 1976.

4. Verifying a system flow rate of 2500 cfm 110 percent during system operation when tested in accordance.with ANSI N510-1975.

d. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by 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 1, July 1976, meets the _ laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 1, July 1976.

e. At least once per 18 months by:

1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 in.

W. G. while operating the system at a flow rate of 2500 cfm i 10 percent.

2. (Deleted) -

HATCH - UNIT 2 3/4 7-7 Proposed TS/0232q/154-0

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l PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

3. Verifying that on each of the below pressurization mode actuation test signals, the system automatically switches to the pressurization mode of operation and maintains the main control room at a positive pressure of 2 0.1-in.

W.G. relative to the adjacent turbine building during s

system operation at a flow rate 5 400 cfm.

a) Reactor vessel water level - low low low b) Drywell pressure - high c) Refueling floor area radiation - high d) Main steam line radiation - high e) Main steam line flow - high f) Control room intake monitors radiation - high f.

After each complete or partial replacement of a HEPA filter  !

bank by verifying that the HEPA filter banks remove 2 99 percent of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm 1 10 percent.

g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 2 99 percent of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm i 10 percent.

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INSTRUMENTATION J

BASES' C

' MONITORING INSTRUMENTATION (Continued)'

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3/4.3.6.4 POST-ACCIDENT MONITORING INSTRUMENTATION

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The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant'param-eters to monitor and assess important variable following an accident.

3/4.3.6.5 SOURCE' RANGE MONITORS

~The source range monitors provide the operator with information on the status of the neutron level in the core at very low rower levels during startup. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.

3/4.3.6.6 TRAVERSING INCORE PROBE SYSTEM The OPERABILITY of the traversing incore probe system with'the specified minimum complement of equipment ensures that the measurements obtained from use of this equipmer.t accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector to be used and

.v. normalizing their respective outputs.

n 3/4.3.6.7 MCRECS ACTUATION INSTRUMENTATION The OPERABILITY of the-MCRECS ensures the necessary protective actions will_be automatically initiated to provide protection for control room personnel.

3/4.3.6.8 (Deleted)

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l. HATCH - UNIT 2 8 3/4 3-4 Proposed TS/0233q/154-70 1