ML20093G110

Proposed Tech Specs,Reflecting Recent NRC Guidance Provided in Generic Ltr 83-36 Re NUREG-0737,Items II.F.1.1-6 & II.B.3

ML20093G110
Person / Time
Site:	Peach Bottom
Issue date:	10/05/1984
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20093F989	List: ML20093F987 ML20093G013 ML20093G110
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM GL-83-36, NUDOCS 8410150357
Download: ML20093G110 (16)

Text

'

PBAPS TABLE OF CONTENTS (Cont'd)

SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENT PAGE 3.12 RIVER LEVEL 4.12 237 A.

High River Water Level A

237 B.

Low River Water Level B

237 C.

Level Instrumentation C

238 3.13 MISCELLANEOUS RADIOACTIVE MATERIAL SOURCE 4.13 240a 3.14 FIRE PROTECTION 4.14 240c A.

Water Fire Protection System A

240c B.

CO2 Fire Protection System B

240g C.

Fire Detection C

2401 D.

Fire Barrier Penetrations D

240j E.

Water Supprcasion Systems E

240k F.

Battery Rm. Vent. Flow Detector F

2401 3.15 SEISMIC MONITORING INSTRUMENTATION 4.15 240t 5.0 MAJOR DESIGN FEATURES 241 6.0 ADMINISTRATIVE CONTROLS 243 6.1 Responsibility 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety Limit violation 253 6.8 Procedures 253 6.9 Reporting Requirements 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 6.14 Integrity of Systems Outside 263 Containment 6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 6.17 Offsite Dose Calculation Manual 265 6.18 Major Changes to Radioactive Waste 265 Treatment Systems 6.19 Post-Accident Sampling 268 iii h kDO O

P

TABLE 3.2.F SURVEILLANCE INSTRUMENTATION

~

l Minimum No.

of Operable Type i

Instrument Indication Channels Instrument and Range Action ***

i 2

Reactor Water Level Recorder 0-60" (1) (2) (3)

{

(narrow range)

Indicator 0-60"

~

2 Reactor Water Level

. Recorder -165"~to +50" (10) (11)

(wide range) 5 2

Reactor Water Level Recorder -325" to 0" (10) (11)

(fuel zone) 1

]

2 Reactor Pressure Recorder 0-1500 psig (1) (2) (3)

Indicator 0-1200 psig

}

2 Reactor Pressure Recorder 0-1500 psig (12) (13) j (SPDS)

• 1

%J l

l' 2

Drywell Pressure Recorder 0-70 psig (1) (2) (3) 2 Drywell Pressure Recorder 0-225 psig (8) (9)

(wide range) a l

2 Drywell Pressure Recorder 5-25 psia (8) (9)

(subatmospheric range) 2 Drywell Temperature Recorder 0-400 degrees F (1) (2) (3)

I Indicator 0-400 degrees F 1

2 Suppression Chamber Water Recorder 30-230 degrees F (1) (2) (3) (9) j Temperature

• Indicator ~30-230 degrees F 1

]

2 Suppression Chamber Water Recorder 0-600 degrees F (1) (2) (3)

Temperature **

Indicator 0-400 degrees F 1

l 2

Suppression Chamber Water Recorder 0-2 ft.

(1) (2) (3)

Level (narrow range)

Indicator 0-2 ft.

I 1

1 k

j

TABLE 3.2.F (Cen t ' d) - SURVEILLANCE INSTRUMENTATION Minimum No.

of Operable Tyjg Instrument Indication Channels Instrument and Range Action 1

?

2 Suppression Chamber Recorder 1-21 ft.-

(10) (11)

Water Level (wide range) 1 Control Rod Position 28 Volt Indicating

)

l Lights

)

(1) (2) (3) (4) r

)

l 1

Neutron Monitoring SRM, IRM, LPRM

)

0-100%

)

l i

1 Safety-Relief Valve Acoustic or (5) t

{f Position Indication Thermocouple

>iD a

2 Drywell High Recorder (7)

Range Radiation 1-lE (+ 8) R/hr Monitors i

1 Main Stack High Range Recorder

]

Radiation Monitor

1. 4E (-2) to 1. 4E (+4) uCi/cc (7)

{

l Reactor Building Roof Recorder j

Vent High Range Radiation

1. 4E (-2) to 1. 4E (+4) uCi/cc (7)

{

Monitor i

2 Drywell Hydrogen Analyzer and Recorder (1) (2) (3) 1 Concentration Analyzer 0-20% volumn j

and Monitor 9

i

• Effective when modification is complete.

l

• • Delete when modification is complete.

• • • Notes for Table 3.2.F appear on pages 78 and 78a.

4, i

4 3

1

s PBAPS NgT!!_{Q3_T3!!!_3 2 [

2 3 1)

From and after the date that one of these parameters is reduced to one indication, continued operation is permissible during the succeeding thirty days unless sach instrumentation is sooner made operable.

t 2)

From and after the date that one of these parameters is not indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

3)

If the requirements of notes (1) and (2) cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4)

These surveillance inst uments are considered to be redundant to each other, 5)

If this parameter is not indicated in the control room, either restore at least one channel to operable status within thirty 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 />.

6)

A suppression chamber water temperature instrument channel 3

will be considered operable if there are at least ten (10) resistance temper 3ture detector inputs operable and no two i

(2) adjacent resistance temperature detector inputs are inoperable.

7)

With the number of operable channels less than the minimum number of instrument channels shown in Table 3.2.F, initiate the preplanned alternate method of monitoring the appropriate parameter within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and:

a) either restore the inoperable channel (s) to operable status within 7 days of the event, or b) prepare and submit a Special Report to the Commission within 10 working days following the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to l

operable status.

8)

With the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F,

-continued operation is permissible during the succeeding thirty days, provided both Drywell Pressure instruments (0-l 70 psig) are operable; otherwise, restore the inoperable channelt 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 />.

p m _,

I 1

• e PBAPS NOTES FOR TABLE 3.2.F (Cont'd) 9)

If no channels are operable, continued operation is permissible during the succeeding 7 days, provided both Drywell Pressure instruments (0-70 psig) are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.

10)

With the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F, continued operation is permissible during the succeeding 30 days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the i

' inoperable channel 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 />.

11)

If'no channels are operable, continued operation is permissible during the succeeding seven days, provided both narrow range instruments monitoring the same variable are operable; otherwise, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.

12)

With the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F, continued operation is permissible during the succeeding 30 days provided both of the other reactor pressure instruments (0-1500 recorder, 0-1200 indicator) are operable; otherwise, restore the inoperable channel 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 />.

13)

If no channels are operable, continued operation is permissible during the succeeding 7 days, provided both of the reactor pressure instruments (0-1500 recorder, 0-1200 indicator) are operable; otherwise restore the inoperable i.

channel (s) to operable status with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.

-78a-

. ~.

~

s TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY.POR SURVEILLANCE INSTRUMENTATION i

Instrument Channel Calibration Freguency Instrument Check 4-

--- lEEEEE555GDIET-~~~

---

=

-- ---==

~~- - -

18)

Drywell High Range Radiation Monitors Once/ operating cycle **

Once/ month j

'19). Main Stack High Range Once/ operating cycle Once/ month Radiation Monitor l

20)

Reactor Bldg. Roof Vent Once/ operating cycle Once/ month High Range Radiation Monitor j

21)

Drywell Hydrogen Concentration Quarterly ***

Once/ month Analyzer and Monitor i

Perform instrument functional check once per operating cycle.

4 Channel calibration shall consist of an electronic calibration of the 1

i channel, not including the detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr with an installed or portable gamma source.

1 At least a two-point calibration using sample gas.

t I

l l

PBAPS 3.2 BAjES (Con t ' d )

trip and the other a downscale trip.

There is a fifteen minute delay before the air ejector off-gas isolation valve is closed.

This delay is accounted for by the 30-minute holdup time of the off-gas before it is released to the stack during reactor power operation when the recombiner system is not operating.

Both instruments are required for trip but the instruments are so designed that any instrument failure gives a downscale trip.

The trip settings of the instruments are set so that the instantaneous stack release rate limit given in Sepcification 3.8 is not exceeded.

Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.

Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.

Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.

Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.

Flow integrators are used to record the integrated flow of liquid from the drywell sumps.

The alarm unit in each integrator is set to annuciate before the values specified in Specification 3.6.c are exceeded.

An air sampling system l

is also provided to detect leakage inside the primary l

containment.

I Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements.

The instrumentation and the applicable NUREG-0737 requirements are:

1.

Wide range drywell pressure (II. F.1. 4 )

2.

Subatmospheric drywell pressure (II.F.1. 4 )

i 3.

Wide range suppression chamber water level (II. F.1. 5 )

4.

Main stack high range radiation monitor (II.F.1.1) 5.

Reactor building roof vent high range radiation monitor (II.F.1.1) i 6.

Drywell hydrogen concentration analyzer and monitor (II. F.1. 6 ) -.

PBAPS 3.2 BASES (Cont'd.)

7.

Drywell high range radiation monitors (II.F.1.3) 8.

Reactor Water Level - wide and fuel range (II.F. 2) 9._

Reactor pressure (I.D.2) 10.

Safety-Relief Valve position indication (II.D.3) 1 The recirculation pump trip has been added at the suggestion of i

ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.

The response of the plant to this postulated event fall within the envelope of study events given in General Electric Company Topical Report, NEDO-10349, dated March, 1971.

In the event of a loss of the reactor building ventilation system, radiant heating in the vicinity of the main steam lines raises the ambient temperature above 200 degrees F.

Restoration of the main steam line tunnel ventilation flow momentarily exposes the temperature sensors to high gas temperatures.

The momentary temperature increase can cause an unnecessary main steam line isolation and reactor scram.

Permission is provided to increase the temperature trip setpoint to 250 degrees F for 30 minutes during restoration of ventilation system to avoid an unnecessary plant transient.

The Emergency Aux. Power Source Legraded Voltage trip function prevents damage to safety-related equipment in the event of a sustained period of low voltage.

The voltage supply to each of the 4kV buses will be monitored by undervoltage relaying.

With'a degraded voltage condition on the off-site source, the undervoltage sensing relays operate.to initiate a timing sequence.

The timing sequence provides constant and inverse time voltage characteristics.

Degraded voltage protection includes:

i (1) An instantaneous relay (ITE) initiated at 90% voltage which initiates a 60-second time delay relay and a 6 second time delay relay.

The 6-second time delay relay requires the presence of a safety injection signal to initiate transfer; (2) An inverse time voltage relay (CV-6) initiated at 87% voltage with a maximum 60 l

second delay and operates at 70% voltage in 30 seconds; and (3)

- An inverse time voltage relay (IAV) initiated at approximately 60% voltage and operates at 1.8 seconds at zero volts.

When the timing sequence is completed, the corresponding 4kV emergency circuit breakers are tripped and the emergency buses are transferred to the alternate source.

The 60-second timing sequences were selected to prevent unnecessary transfers during motor starts and to allow the automatic tapchanger on the startup_ transformer to respond to the voltage condition.

The 6-i second timing sequence is necessary to prevent separation of the l

emergency buses from the off-site source during motor starting l

transients, yet still be contained within the time envelope in FSAR Table 8.5.1.

l

-93a-i

. -.__-,-..._.__.--,..,,_. _ -,,_m

PBAPS LIMITING CONDITIONS FOR OPERATION ________ SURVEILLANCE REQUIREMENTS _______

3.5.D Reactor Core Isolation 4.5.D Reactor Core Isolation Cooling _jRCIC_Sub-Systeml Cooling _jRCIC_Sub-System [

1. The RCIC Sub-System shall be

1. RCIC Sub-System testing shall operable whenever there is be performed as follows:

irradiated fuel in the reactor vessel, the reactor pressure Item Freguency is greater than 105 psig, and prior-to reactor startup from (a) Simulated Once/ Operating a Cold Condition, except as Automatic Cycle specified in 3.5.D.2 below.

Actuation Test *

(b) Pump Once/ Month Operability (c) Motor Operated Once/ Month Valve Operability (d) Flow Rate at Once/3 Months approximately 1000 psig Steam Pressure **

(e) Flow Rate at Once/ Operating approximately Cycle 150 psig Steam Pressure **

(f) Verify auto-Once/ Operating matic transfer Cycle from CST to suppression pool j

on low CST water l

level

2. From and after the date that

2. When it is determined that t

the RCICS is made or found the RCIC sub-system is inop-to be inoperable for any reason, erable, the HPCIS shall be L

continued reactor power opera-demonstrated to be operable l

tion is permissible only during immediately and weekly there-l the succeeding seven days after.

I provided that during such seven days the HPCIS is I

operable.

l

3. If the requirements of 3.5.D

• Shall include automatic restart

[

cannot be met, an orderly shut-on low water level signal.

I down shall be initiated and I

the reactor pressure shall

• • The RCIC pump shall deliver be reduced to 105 psig within at least 600 gpm for a system 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

head corresponding to a reactor pressure of 1000 to 150 psig.

-130-

LI ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment 4.7.A Primary Containment 6.

Containment Atmosphere

6. Containment Atmosphere Dilution Dilution

a. Whenever either reactor

a. The post-LOCA contain-is in power operation, ment atmosphere dilu-the Post-LOCA Containment tion system shall be Atmosphere Dilution Sys-functionally tested tem must be operable and once per operating capable of supplying

cycle, nitorgen to either Unit 2 or Unit 3 containment for atmosphere dilution if required by post-LOCA conditions.

If this specification cannot be met, the system must be restored to an operable condition within 30 days or both reactors must be taken out of power opera-tion.

b. Whenever either reactor

b. The level in the is in power operation, liquid nitrogen storage the post-LOCA Containment tank shall be Atmosphere Dilution Sys-recorded weekly.

tem shall contain a mini-mum of 2000 gallons of liquid nitrogen.

If this specification cannot be met, the minimum volume will be restored within 30 days or both reactors must be taken out of power operation.

c. Whenever either of the reactors is in power operation, there shall be at least one CAD system oxygen analyzer serv-ing the drywell and one CAD system oxygen analyzer serving the sup-pression chamber on that reactor.

If this speci-fication cannot be met,

-172-

LIMITING CONDITIONS'FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A.6.c (Cont'd)-

4.7.A.6 (Cont ' d )

the unit shall be in Hot

c. The CAD system oxygen Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, analyzers shall be tested for operability using standard bottled oxygen once per month and shall be calibrated once per 6 months.

The atmospheric analyzing system shall be functionally tested once per oprating cycle in con-junction with the speci-fication 4.7.A.6.a.

Should one of the two oxygen analyzers serving the drywell or suppressica pool be found inoperable, the remaining analyzer serving the same compartment shall be tested for operability once per week until the defective analyzer is made operable.

d. A 30 psig limit is the maximum containment repressurization allowable-using the CAD system.

Venting via the SBGT system to this stack must be initiated at 30 psig following the initial peak pressure at 49.1 psig.

-173-

PBAPS 3.7.A & 4.7.A BApEg (Cont'd) periodic testing of the system is required.

Twice weekly operation of the containment oxygen analyzer that-is associated with the containment inerting makeup system is sufficient to insure its readiness.

Reliance on that oxygen analyzer for this purpose of post-LOCA oxygen measurement will terminate when the CAD system is operable.

The Post-LOCA Containment Atmosphere Dilution system design basis and description are presented in Question 14.6 of the FSAR.

In summary, the limiting criteria, based on the assumptions of Safety Guide 7, are:

1.

Maintain oxygen concentration in the containment during post-LOCA conditions to less than 5 %

Volume.

2.

Limit the buildup in the containment pressure due to nitrogen addition to less than 30 psig.

3.

To limit the offsite dose due to containment venting (for pressure control) to less than 30 Rem to the thyroid.

By maintaining at least a 7-day supply of nitrogen on site, there will be sufficient time after the occurrence of a LOCA for obtaining additional nitrogen supply from local commercial sources which have been discussed in Question 14.6 of the FSAR.

The system design contains sufficient redundancy to ensure its reliability.

Thus, it is sufficient to test the operability of the whole system once per operating cycle.

Redundant oxygen analyzers are provided for both the'drywell and suppression chamber, i.e.,

there are four oxygen analyzers on each Unit.

By permitting continued reactor operation at rated power with two of the four I

analyzers inoperable, redundancy of analyzing capability will be maintained while not imposing an unnecessary interruption l

in plant operation.

If one of the two analyzers serving one of the compartments of the containment (drywell or suppression chamber) fails, the frequency of testing of the I

other analyzer of the same type serving the same compartment will be increased from monthly to weekly to assure its continued availability.

Monthly testing of the analyzers using bottled oxygen will ensure the system's readiness j

because of the multiplicity of design.

Since the analyzers are normally not in operation, there will be little i

deterioration due to use.

-194-l

[

PBAPS hldlIIEE 99dEITIONS_FgR_QPERATIgN________ SURVEILLANCE, REQUIREMENTS _____

3.11 Additional Safety ~Related Plant 4.11 Additional Safety Related s555E}[I5! ~ !5kb5$s5555I55Ie ' ~' ~~~~~~~ A. Main Control Room Emerg~ency A. Main Control Room Emergency $!5 I15Y1552!5 56~~~~ ~~ $555d 55Ik5$!555kb

1. Both control room emergency

1. At least once per operating ventilation systems shall be cycle, the pressure drop operable at all times when across the combined HEPA secondary containment integ-filters and charcoal adsorber rity is required except banks shall be demonstrated that one system may be to be less than 8 inches out-of-service for of water at system design 7 days, flow rate.

2. If Specification 3.11. A.1

2. a. The tests and sample cannot be met, be in analysis of Specification hot shutdown within 3.11. A 4 shall be perform-12 hours and cold ed initially and at least shutdown within the once per year for following 24 hours.

standby service; or after every 720 hours

3. With both control room of system operation; emergency ventilation systems or following significant inoperable, suspend core painting, fire or chemical alternations, handling of release in any ventila-irradiated fuel in the tion zone communicating secondary containment, and with the system while operations with a potential it is in operation, for draining the reactor vessel.

4. a. The results of the

b. Cold DOP testing inplace cold DOP and shall be performed halogenated hydrocarbon after each complete j

refrigerant tests at or partial replace-l approximately 3,000 CFM ment of the HEPA [ on HEPA filters and char-filter train or after coal adsorber filter any structural maintenance trains shall show >99% on the system housing. DOP removal and >99% halo-genated hydrocarbon removal or that filter train shall not be

c. Halogenated hydrocarbon considered operable.

refrigerant testing shall be performed af;er each complete or partial replacement of the charcoal adsorber filters or after any L structural maintenance on the system housing. -233-

PBAPS ElglTING CgNDITIgNS_FgR_gPgRATIgN________SgRVgILLANCg_RgQgIRgMgNTS_____

b. The results of laboratory

d. A dry gas purge shall carbon sample analysis be provided to the filters shall show 90% radioactive to insure that the methy1' iodide removal at relative humidity in the a velocity within 20%

filter systems does not of system design, 0.05 exceed 70% during idle to 0.15 mg/m3 inlet

periods, methyl iodide concentra-tion, >95% relative

3. At least once per operating humidity and >125 degrees F, cycle automatic initiation or that filtei train shall of the control room air not be considered operable.

treatment system shall be demonstrated,

c. Fans shall be shown to operate at approximately

4. Operability of the main 3,000 CFM +/- 300 CFM control room air intake (design flow for the radiation monitor shall filter train).

be tested every 3 months, f

5. At least 1 of the 2 main control room intake air radiation monitors shall be oper-able with the inoperable channel failed safe whenever the control room emergency ventilation air supply fans and filter trains are required to be operable by 3.11.A.1 or filtration of the control room ventilation intake air must be initiated.

-233a-

PBAPS o 6.19 Postaccident Sampling Administrative controls shall be implemented to ensure the capability to obtain and analyze: (1) reactor coolant and containment atmosphere samples under accident conditions, and (2) radioactive iodines and particulates in plant gaseous effluents under accident conditions. The administrative controls shall include the following: 1. Training of personnel, 2. Procedures for sampling and analysis, 3. Provisions for maintenance of sampling and analytical equipment. -268- . - ~

i eo.o PBAPS 6.19 BASES These administrative controls apply to the systems installed to ensure the capabilities required by NUREG-0737, Item II.B.3 (Post-Accident Sampling Capability) and Item II.F.1.2 (Iodine and Particulate Sampling). The first capability is accomplished through the use of the Post-Accident Sampling System (PASS) located in the M-G set rooms and by the equipment available to handle, transport and analyze the samples. Analytical capability is provided at both the Unit 1 laboratory and an off-site laboratory, provided by contractual arrangements, for selected analyses. The of f-site laboratory is relied upon to perform the chloride analysis required by NUREG-0737, Item II.B.3. The data obtained from the post-accident sampling system would be utilized to calculate the extent of fuel damage during accident conditons. The second capability (II. F.1. 2) is accomplished by the use of shielded sample collection devices, special handling tools, a shielded transport container, and high radiation measuring techniques. The collection devices (particulate filters and iodine cartridges) are located on the main stack and reactor building vent sampling systems. -269-}}