Text

Forwards Design Basis Rept for New Monitors,Per G Kalman & C Hinson Request for Addl Info Re Proposed Amend 156
	ML20214T863
Person / Time
Site:	Rancho Seco
Issue date:	06/02/1987
From:	Andognini G; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Miraglia F; Office of Nuclear Reactor Regulation
References
	GCA-87-073, GCA-87-73, TAC-64879, NUDOCS 8706100454
	Download: ML20214T863 (49)
	v • d • e

%sMunSACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830 Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEAR f OF CALIFORNIA JUN 0 2 E7 GCA 87-073 Frank J. Miraglia, Jr.

Associate Director for Projects U. S. Nuclear Regulatory Commission Washington, DC 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit #1 REQUEST FOR ADDITIONAL INFORMATION - PROPOSED AMENDMENT NO. 156

Dear Mr. Miraglia:

In a telephone conversation, Masrs. George Kalman and Charles Hinson of the NRC staff requested additional information to complete the review of Proposed Amendment No. 156. Specifically discussed was the analyeis for the gaseous monitors in containment. Attached is the Design Basis Report for the new monitors. Based on our discussions, this should provide the information required to complete the review of the proposed amendment.

If you have any questions, please contact Robert Roehler of my staff.

Sincerely, 1 j- /b'wxc,

/ CarLAndogn)fli f

'G Chief Executive Officer, Nuclear cc w/atch:

G. Kalman, NRC, Bethesda (2)

A. D'Angelo, NRC, Rancho Seco J. B. Martin, NRC, Walnut Creek (2)

MIPC (2)

INP0

(

0706100454 G70602

~

PDR ADOCK 05000312 P PDR RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935

81kcnan S} '

~

'& SMUD- = = = =

DESIGN BASIS REPORT om .sv m 0 As 11/24/86 o -

aan

" I&C "s m a -e ca em a-.

547 808

~

wn = mm.

s. PURPOSE OF DESGN CHANGE:

See Attached E. DESGN CRrfERIA USED: * -

See Attached 11 CALCULATIONS & DESIGN INFORMATION:

See Attached IV. FAlWRE MODES.

O T>tS CHANGE DOES NOT AFFECT CONTROL ROOM INSTRUMENTATION 3 THIS CHANGE AFFECTS CONTROL ROOM INSTRUMENTATION. SEE ANALYSIS See Attached V. SPEQAL MAINTENANCE REQUIREMENTS-See Attached VL. SPECAL OPERATING REQUIREMENTS.

See Atta::hed VII. VERIRCATION CRl1ERIA:

See Attache.1 Vm. COMMENTS:

See Attached

/ f 1 0 . /./ A.

e, c& pes gjk, y 7 , -

3 2,El W n - . .

L,_ UA isla s l % M. W ylie i sa E*" rte 'L y% '

.$TW n->P"4 Ih aww,

9- .

' ~

. s DBR REY. NO. 0 -

ECN NO. R-0913, Rev. 1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 TABLE OF CONTENTS 4 - PAGE I. PURPOSE OF DESIGN CHANGE. . . . . . . . . . . . . . . . . . . . 2 .

J II. DESIGN CRITERIA . . . . . . . . . . . . . . . . . . . . . . . . 2 4

A. C od es . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 B. Reg ul a t o ry . . . . . . . . . . . . . . . . . . . . . . . . . 2

~

C. S ta nda rd s . . . . . . . . . . . . . . . . . . . . . . . . 3 D. NEP's . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 d

E. Design Guides . . . . . . . . . . . . . . . . . .. 3 F. Pla nt Specific Design Criteria. . . . . . . . . . . . . . . 4

1. R-15100 R.B. Leak- Detetection Monitoring Systs. .. . . 4-1 1

1

2. R-15044 R.B. Stack Moni tor . . . . . . . . . . . . . . 5

! 3. R-15045 Auxiliary Building Stack Monitor . . . . . . . 6

4. State Notification Systen. . . . . . . . . . . . . . . 6 S. Testi ng Requi renents . . . . . . . . . . . . . . . . . 7 l

i III. CALCULATIONS AND DESIGN INFORMATION . . . . . . . . . . . . . . 7

-A. D esi g n Info nna ti o n. . . . . . . . . . . . . . . . . . . . . 7-1

1. Stana ry and Scope of Desi gn. . . . . . . . . . . . . . 7

2. D esi g n D eta i l s . . . . . . . . . . . . . . . . . . . . 9 a)- R-15100 R.B. a leak det. Monitor. . . . . . . . . 9

1. Monitor Description . . . . . . . . . . . . 10 ~

2. Monitoring Systen Description . . . . . . . 11 1

z. - -

~

DBR REY.' NO. 0 ECN HO. R-0913, Rev. 1 MCR S-3960- WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 TABLE OF CONTENTS (Continued)

PAGE b) R-15044 R.B. Stack Monitor. . . . . . . . . . . 14-

1. ' Hi sto ry . . . . . . . . . . . . . . . . . . 14

2. Monitor Description . . . . . . . . . . . . 14

3. Monitoring Systen Description . . . . . . . 15 c) R-15045 Auxiliary Building Stack Monitor. . . . 17

1. Hi sto ry . . . . . . . . . . . . . . . . . . 17

2. Monitor Description . . . . . t . . . . . 17

? .- Monitoring Systen Description . . . . . . . 17 d) Sta te Noti fi ca ti o n. . . . . . . . . . . . . . . . 18 B.

SUMMARY

OF DESIGN BASES . . . . . . ... . . . . . . . . . 19

1. RCPB L ea k D etecti o n. . . . . . . . . . . . . . . . . 19

2. RB & A.B. Stack Monitors . . . . . . . . . . . . . . 20 C. CALCULATIONS AND CONCLUSIONS. . . . . . . . . . . . . . . 20

1. Description of Calculations. . . . . . . . . . . . . 20 a) Ge ne ral Meth od ol ogy . . . . . . . . . . . . . . 20 b) Speci fic Methodol ogy. . . . . . . . . . . . . . 20

1. R.B. Concentration . . . . . . . . . . . . 21

2. Sanpl e li ne Plateout. . . . . . . . . . . . 21

3. Response Times. . . . . . . . . . . . . . . 22

4. Sample F.ilter Lifetime. . . . . . . . . . . 22 l

i 11 ,

l l i

- ~ .

T l .

i _ _ _ 1. __ _ _

DBR'REV. NO.. O

~

ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 TABLE OF CONTENTS (Continued)-

PAGE c) Results of Calculatiors . . . . . . . . . . . . 23 .

1. R.B. Concentration (USAR Source Tenn) . . .

23

2. R.B. Concentration (Historical) . . . . . . 23

3. Sample Line Plateout. . . . . . . . . . . . 24

2. Revi ew of Enperical Data . . . . . . . . . . . . . . 24 a) Pa rti cul a tes. . . . . . . . . . . . . . . . . . 24 b) Iodi nes. . . .............. . . . 26' c) No bl e Ga's es .' . . . . . . . . . . . . . . . . . 26 d) % Fa i l ed Fu el . . . .' . . . . . . . . . . . . . 26

3. Deductions and Calculations Made Fran the Results of the Calculations and Review of Enperical Data . . 26 a) Pa rticulate Cha nnel . . . . . . . . . . . . . . 26

1. Response Time to Detect a 1 gpm Leakage at Normal Coolant Activities and at Typical R.B. Equili brium level s. . . . . . . . . . . 26

2. Response Time to Detect a 1 gpm Leakage at 1% Failed Fuel Coolant Concentration at Calculated Resultant R.B. Equilibriun L e v el . . . . . . . . . . . . . . . . . . . . 28-

3. Response Time to Detect a 1 gpm L'eakage at

.1% Failed Fuel Coolant Concentrations at calculated Resultant R.B. Equilibriun L e vel s . . . . . . . . . . . . . . . . . . . 28

4. Setp oi nts . . . . . . . . . . . . . . . . . 28

5. Sampl e Fil ter Lifetime. . . . . . . . . . . 28 111

. j DBR REY. NO.- -0 ECN NO. 'R-0913, Rev. 1 NCR S-3960' WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 TABLE' 0F CONTENTS (Continued)

PAGE b) Iodi nes Cha nnel . . . . . . . . . - . . . . . . . 29

1. Response Time . . - . . . . . . . . . . . . . 29

2. Setpoi nt. . . . . . . . . . . .-. . ... . . 29-

3. Sample Filter Li fetime. . . . . . . . . . . 29 c) No bl e Ga s Cha nnel . . . . . . . . . . . . . . . 30

1. Response Time . . . . . . . . . . . . . . . 30

2. Setpoints . ", . . . . . . . . . . . . 30 IV. FAILURE MODE . . . . . . . . . . . . .-. . . . . . . . . . . . 30 A. R-15100 R.B. at Leak- Detection Monitor. . . . . . . . . . 30

1. '4o ni to r Fa il u re. . . . . . . . . . - . . . . . . . . . 30

2. Heat Traci ng Fail u re . . . . . . . . . . . . . . . . 31

3. Fil ter Overl oadi ng . . . . . . . . . . . . . . . . . . 31 B. R-15044 R. B . Stac k Mo ni to r. . . . . . . . . . . . . . . . 31

1. Bl oc k Val ve & Fa n. . . . . . . . . . . . . . . . . . 31

2. M o ni to r. . . . . . . . . . . . . . - . . . . . . . . . 31

3. Hea t T ra c i ng . . . . . . . . . . . . . . . . . . . . . 32

4. Isoki neti c ' Fl ow Co ntrol . . . . - .- . . . . . . . . . . 32

5. RM11 Canputer/Consol e. . .. . - . . . . . . . . . . . . . 32.

k i iv f

-- w + - . , - - y rme- g - c-, --3 + - - - - - , + y -

r r--8 + --e-4 --~

. s . ,

DBR REV. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 TABLE OF CONTENTS (Continued)

PAGE C. R-15045 Auxilia ry Buildi ng. . . . . . . . . . . . . . . . 32'

l. Valve. . . . . . . . . . . . . . . . . . . . . . . . 32

2. Mo ni to r. . . . . . . . . . . . . . . . . . . . . . . 32

3. Hea t T ra c i ng . . . . . . . . . . . . . . . . . . . . 32

4. Isoki netic Fl ow Control . . . . . . . . . . . . . . . 32

5. RMll Canputer/Consol e. . . . . . . . . . . . . . . . 32 V. SPECIAL MAINTENANCE RtQCInCNE813 . . . . . . . . . . . . . . . 33 A. R-15100 ( R. B . ATM ) . . . . . . . . . . . . . . . . . . . . 33 B. R-15044, R-15045 (R.B. Stack, Auxiliary Building Stack. . 33 VI. SPECIAL OPERATING REQUIREMENTS . . . . . . . . . . . . . . . . 33 A. R-1 51 00 . . . . . . . . . . . . . . . . . . . . . . . . . 33 -

1. Filter Loadi ng Monitori ng. . . . . . . . . . . . . . 33 .

2. Filter Replacenent Frequency . . . . . . . . . . . . 34

3. Response to Al ert Ala rm. . . . . . . . . . . . . . . 34 B. G ra b Samp l i ng . . . . . . . . . . . . . . . . . . . . . . 34 C.. R-1 50 4 4 . . . . . . . . . . . . . . . . . . . . . . . . . 34' VII. VERIFICATION CRITERIA. . . . . . . . . . . . . . . . . . . . . 35 VIII. COMMENTS . . . . . . . . . . . . . . . ... . . . . ... . . . .-. 35 v

= - -

e m 4 - g

i DESIGN BASIS REPORT DBR REV. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE IaC MOD 547 DATE 11-24-86 I. PURPOSE'0F DESIGN CHANGE:

A. To replace obsolete Vict'oreen radiation monitors R-15001 and R-15002 which have had a long history of maintenance and operational problens.

B. To provide automatic tennination of Reactor Building Equalization Effluent in order to facilitate Technical Specification approval fran the NRC for the use of the R.B. Equalizing systen during power operations.

C. To upgraue the Seat:a Notification System (SNS) by providing individual input cutout switches and SNS status indication to the Control Roam operators.

II. DESIGN CRITERIA:

A. Codes:

1. 10 CFR 50.34a - Design ohjectives for equipment to control releases of radioactive material in effluents.

2. 10 CFR 20 - Standards for Protection Against Radiation.

3. General Design Criteria 60 - Control of releases of radioactive materials to the environnent (10 CFR 50 Appendix "A").

4. General Design Criterion 64 - Monitoring radioactivity releases (10 !

CFR 50 Appendix "A").

5. General Design Criterion 30 -- Quality of reactor coolant pressure-boundary (10 CFR 50 Appendix "A").

B. Regulatory Requirenents

1. California Senate Bill 1184'- requires that the-plant's stack effluent radiation monitors be inputed to the State Notification System.

R0913R1 -2 -

l

_ '7

. v ..

DBR REY. NO. 0 ECN'NO. R-0913, Rev.1 - NCR S-3960 WORK-REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86

2. Regulatory Guide _1.97 - Instrunentation for light-water-cooled Nuclear Power Plants- to assess plant and environs' conditions during -

and following an accident. _

C.- Sta nda nis

1. ANSI N13.1 - 1969, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities.

2. ISA S67.03 - 1962, Standard for Light Water Power Reactor Coolant Pressure Boundary Leak Detection.

3. ANSI B31.1 - applies to QA class 1 piping used for R-15100's return M ne.

D. NEP's The following NEP's are used in the design and engineering work of this design change.

Design docunent= preparation and control.

a. 4109 - Configuration Control

b. 4110 - Inter Discipline Docunent Review

c. 4112 - Drawing Change Notice

d. 4118 - Environnental Qualification Program

e. 4119 - Fire Protection Program E. Design Guides

a. 5107.3 Stress

b. 5107.4 Pipe Supports-

c. 5204.1 Symbols for Single Line and Schenatic Diagrams-

d. 5204.2 Standani Device Function Nunbers

e. 5204.3 Cable and Tennination Nunbering

f. 5204.4- Standani Interconnecting Wire Nunbers and Color Code

g. 5204.5' Cable Codes -

h. 5204.6- Raceway Codes

1. 5205.7 Racetay Nunbering

j. 5204.8 Systen Single Line. Meter and Relay Diagrams

k. 5204.9 Systen Design

1. 5204.10 Circuit Design Implenentation

m. 5204.11 Layout Design

n. 5204.12 Preparation of Station Single Line Diagrams

o. 5204.13 Preparation of Schematic Diagrams

p. 5204.14 Preparation of Wiring Diagrams

l 3

l R0913R1 -3 -

DBR REV. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 F. Plant Specific Design Criteria

1. R-15100 - Reactor Building Abnosphere Leak Detection Monitoring System a) Shall be able to detect approximately 1 gpm of unidentif.ied Reactor Coolant Pressure Boundary leakage into the Reactor Building in approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and alert Control Roan operators of this fact, b) All equipnent associated with this system shall be QA Class II.

c) The electric power supply to the monitor's skid and RM-11 console shall be non-1E battery backed 120V AC.

d) The skid and sample lines shall be seismically installed to the 2/1 installation criteria.

e) The fixed filter paper used for the particulate channel shall be replaced on a weekly basis, f) Shall have autanatic sample blower protection against potential sample line blockages, such as that which would occur on SFAS contairment isolation.

g) The skid shall be supplied with regulated instrunent air at 4 psig for sample purge, h) The monitor shall be installed indoors in a tenperature controlled environnent of 39 - 122*F and less than 95%-relative humidity.

1) Heat tracing ard insulation of the supply sample line ~

is required to maintain the sample tenperature at 115*

+ 5 to prevent condensation.

j) Sanple pressure shall be-less than 15 psig.

k) Sample tenperature shall be maintained between 35 to 122*F (5*F/hr. maximum rate of change).

.y -

R0913R1 -

_ _4. . _ _._

DBR. REY..N0h 0 ECN'NO. R-0913, ~ Rev. 1 NCR S-3960- WORK REQUEST" DISCIPLINE I&C MOD 547 DATE 11-24-86

1) Shall have a range ca concentration of'10 gable

' to 10of monitoring noble gas 2 uCi/cc (Xe - 133) the purpose of providing data for pre-purge release- <

calculations.

~

m) Radiological grab sample points that were available ~

prior to this change must still be available.

n) The monitor. shall indicate and alann on the RM-11 console in the Control: Room, o) The sample line portions which are part of the Hydrogen Purge Systen shall be QA class 1, seismic 1, and all the previous criteria for this line still

~

apply. ANSI B31.1. shall apply, as well as the criteria stated in NEP 5107.3 " stresses" and NEP 5107.4 " pipe supports".

p) Setpoints shall be established which-are high enough to prevent spurious alanns and im enough to ensure the operators are alerted to a potential 1 gpm unidentified leak within approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2. R-15044 - Reactor Building Stack Monitor Note: The design basis for R-15044 as a post accident monitor per NUREG 0737 iten II.F.1 and as a R.B.

Equalization Vent Monitor is described in DBR 'A-5500, a) The monitor shall be c concentrations of 10 4pable

' uCi/ccof tomonitoring noble gas at least a decade above the maximum setpoint concentration calculated.

per the 0ffsite-Dose Calculation Manual'-(00CM).

b) The monitor's radiological setpoints shall be detennined in accordance with the 00CM.

c) The monitor'shall automatically. tenni nete R.B.

effluents upon exceeding a predetennined high radiation setpoint or upon monitor failure (i.e.

operate status sigral).

d) Shall be provided with continuous reconfing.

~

~ - 7 _

~

R0913R1 .

OBR REY.1K). 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE IaC ' MOD 547 DATE 11-24-86 e) Shall have a isokinetic particulate sampler and iodine sampler for grab sampling.

f) Shall have an iodine sampler flow measurenent device. -

g) Shall have a sample flow measurenent device.

h) Shall provide a high radiation signal to the State ~

Notification Systen.

f) Shall alert the Control Room operators upon abnormally high radiation levels and shall have indication, control, and alarms on the RM-11 console located in the Control Roan.

j) All equipment associated with R-15044 is QA Class II, non-seisnic.

k) The monitor, Renote Control Cabinet, RM-11 canputer and console shall be powered fran a non-1E battery backed 120V AC power source.

3. R-15045 - Auxiliary Building Stack Monitor Note: The design basis for R-15045 as a post accident-monitor per NUREG. 0737 iten II.F.1. is described in DBR A-3683.

a) R-15045 shall have the same criteria as R-15044 with the exception of R-15045's required control functior..

R-15045 shall be interlocked with RV-655i4 (Wastr Oas Header Isolation Valve) such that upon 1.11gh radiation or operate status signal the valve will autanatically close thereby tenninating effluents fran-the waste gas header pathway.

4. State Notification System-a) Shall be QA Class II, non-seisnic.

b) Poder supply for relays will be fran the H4MRG and power supply for the multiplexer transnitter will be fran connunication power panel S1PS inverter / battery backed (diesel backed power supply which will be available in case of loss of offsite power).

l

R0913R1 -6 -

DBR REY. NO. O _

ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST' DISCIPLINE I&C MOD 547 'DATE 11-24-86

5. Testing Requirenents.

a) Acceptance testing will be required : to ensure the -

systens perfom as designed. Control functions, indications, alams, software, and hardware .

operability will be tested..

The leak detection monitor (R15100) requires post b) start-up testing to detemine what the monitor's response is to known leakages and the response to actual R.B. concentration equilibriun levels. The setpoints shall be adjusted appropriately after gaining some operating experience.

III. CALCULATIONS AND DESIGN INFORMATION A. Design Infomation

1. Sunmary and scope of design Renove the entire systens for R15001 A and B, R15001 C, D and E and R15002. This includes the following:

a. Renoval of all three (3) skids

b. Renoval of sample lines to the RB, AUX Bldg. and RB Stacks

c. Renoval of electronics in the H4MR

1) Rateneters

2) Recorder Connections (including recorders on the H3TMI and H2 RWA)

3) Canputer Connections and Software-

4) Annunciator (H2PSA) Connections =

5) Monitors and Sample Pumps Controls-

6) other Monitor Interconnectors

d. H4MR panel modifications' forthe above:

, e. Renoval ard sparing of the monitors' power and instrument cabling and conduit.

Make the necessary engineering changes to allow conmissioning of R15045, the G.A. Wide Range Gas Aux.

Bldg. Stack Post Accident Radiation Monitor as a Tech Spec. Effluent and Post Accident Monitor. This involves the following:

R0913R1 -7 -

. ~

DBR REY. NO. O ECN.NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86

a. Provide high radiation and operate status (i.e.

radiation monitor failure) interlocks bebdeen R15045 and the Waste Gas Header Isolation Yalve RY-65514. .

' b. Provide a high radiation signal fran R15045 to the State Notification System to comply with Senate Bill 1184.

Make the necessary engineering changes to allow cannissioning of R-15044 (the existing G.A. Wide Range Gas Reactor Building atnosphere monitor) as a dual purpose R.B. Atmosphere and R.B. Stack monitor. In the stack mode the monitor could be used for normal R.B. purges, R.B. pressure equalization when Tech :

Specs are approved for this operation, and for post -

accident stack monitoring. This i nvolves the foll owi ng:

a. Provide high radiation and operate status (i.e. .

radiation monitor failure) interlocks between R-15044 and the R.B. Exhaust Fan ( A-536), the R.B. Supply Fan ;

( A-535), and the Equalization Block Valve (HV-53502). !

The above change will provide automatic tennination of l stack effluents upon high radiation or monitor l failure. The setpoints will be in accordance with the Offsite Dose Calculation Manual to ensure canpliance with 10 CFR 20. Software changes will be required.

b. Provide a high radiation signal fran R-15044 to the State Notification System to canply with California Senate Bill 1184.

Upgrade the State Notification System (SNS) by j providi ng: l

a. Individual input signal cutout switches with local status indicating lights in the HSSN.

b. provide signals fran the SNS into the Plant Canputer (IDADS) to alert the Control Room of the SNS status.

This includes software changes.

R0913R1 -8 -

~

DBR REY. NO. 0 ECH NO. R-0913, Rev.1 NCR- S-3960 WORK REQUEST DISCIPLINE IaC MOD 547 DATE 11-24-86 Replace the old Victoreen monitors R15001 AaB and R15001 C, D and E with a General Atomics Particulate, Iodine and Gas monitor (R15100). This includes the -

fo11 avi ng: -

a. Installation of the new skid in the sane roan as the old Victoreens.

b. Hookup the G. A. monitor into the RM-11 camputer, recorder on the H3TMI, and provide the monitor power.

c. provide the monitor instrument air for sample purging.

d. provide sample lines fran the same R.8. penetration that the old R15001 used. This may include heat traci ng.

-f

e. provide all the associated IDADS and G. A. conputer software changes.

This change will make the new G. A. monitor a R.B.

Abnosphere Leak Detection Monitor exclusively. This will leave R15044 and R15045 as the R.B. and Aux. Bldg Stack Monitors respectively.

2. Design Details a) R15100 - Reactor Building Atnosphere Leak Detection Monitor

1. Monitor Description Pa rticulate Fixed Filter Type ,

Algorithn - Capable of calculating-the )

particulate concentration in uCi/cc. The j monitor's microprocessor is programmed to develop a matrix of the detectors output at va ryi ng sample time i ntervals. The monitor collects enough sample data to assure a predetennined statistical accuracy. Once the monitor calculates that it has R0913R1 -9 - -

y I

DBR REY. NO. 0 ECN NO. R-0913, Rev.1 NCR- S-3960 WORK REQUEST ~

DISCIPLINE IaC MOD 547 DATE 11-24-86 enough statistical data the display will be '

upda ted. The monitor calculates. the concentration by dividing the rate of change of the detector's count rate by the sample .

flow rate, filter efficiency, and the detector's sensitivity. (See G. A. doctment E-155-1101, Review of Algorithms, October 1980 for further information).

Detector range 5 to 101 uCf (10 -107 cpm). Note: the monitor's range for ,

particulate concentrations is dependent 'on a nimber of variables such as the background (due to acctnulation on the filter and external field) and the desired response timpI 10-' o t 10-3 uCi/cc, however it varies asTypicgily the range explained above.

Sensitivity - 1.15 x 106 cpm /uci (Cs -137) ,

Accuracy - approximately 207, overall Detector type - Beta scintillation Response times - See Calculations Has built in check source Iodine Channel Fixed charcoal cartridge type Detector type - gamma scintillation which views the charcoal filter for any I-131 a bsorbed. ,

Algoritta - uses the same differentiating algorithm as the particulate channel, range 4 to 102 uCi (10 to 107 cpm).

Note: the range in uti/cc is variable like the particulate channel.

Sensitivity - 1.01 x 105 cpm /uct (I-131)

Has built in check source R0913R1 o

DBR REY. NO. -

0 ECN N0. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11 86 Response times - see calculations Overall accuracy - approximately 2(E ,

Noble Gas (low range) Channel Detector - Beta scintillation Range - 10 7 to 10-1 uCf /cc (Xe-133)

Has built in check source Sensitivity - 5.38 x 10-8 uCi/cc per CPM (Xe-133) .

Noble Gas (high range) Channel Detector -Beta scintillation Range 4 to 10 2 uCi/cc (Xe-133)

Has built in check source

~

Overall accuracy - approximately 33%

Sensitivity - 5.38 x 10-5 uC1 cc

/ per CPM (Xe-133)

Sample Blower Protection - If sample flow rate drops below I scfm (monitor item 6) for greater than one minute, the sample blower will autmatically secure without damage.

This will protect the blower fra sample if ne blockages due to SFAS containnent isolation.

Monitor type - Offline .

2. Monitoring Systen Description for R15100 Recording - each channel will- be continuously recorded on a Texas Instrtanent strip chart reconfer in the H3TMI cabinet located in the Caputer Rom. A log output of the detector's count rate in cpm will be recorded on 6_ decade R0913R1 11 - .

__ ~ _ _ _

-08R REY. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960~ WORK REQUEST OISCIPL.INE I&C MOD 547 DATE 11-24-86 log chart paper. The particulate and iodine channels will sgm a continuous increase of '

cpm, fra 10-10 cpm, as the filters accoulate sample activity. These channels -:

will give operators indication of when the filters becue overloaded (i.e., have activity on reachthetheir filters that range upper causes the dete9 value tors to-of 10 cpm. ) -

The gas channels will also be reconfed in CPM and can be converted to uCi/cc by multiplying by the respective sensitivities stated above.

Caputer Outputs - Each of the monitor's channels will be inputed to IDADS via the GA to IDADS caputer li nk. ,,

Indication, Control, a'nd Ala nn - Will be available on the RM-11 console (H1DRMS) located in the Control Rom. Monitor control consists of manual sample purge or sample pap control . Upon a high, alert, or operate status alarm, a console horn will annunciate and a CRT status light will blink indicating the alanning channel, i Sampling Systen - ,

R-15100 takes an air sample fra the Reactor Building through penetration 52 and returns the sample to the Reactor Building through penetration 53. The sample lines tap off the Hydrogen Purge Systen's Class 11' stainless steel 1" and 2" piping.

The sample supply 11no was designed to minimize ,

plateout. 3/4" diameter stainless steel tubing with the ;

maxima slope obtainable and minimum bends was called '

for. The line was seismically installed in acconiance with the I-1155 series installation instructions. The-If ne is-approximately 30' long, t The sample will be the Reactor Buf1 ding Atmosphere. By Tech Spec, the R8 pressure will be controlled to + 1.5 --

psig. The maxima tenperature will be limited to 120*F.

The hunidity is naina11y less than 857, relative hunidity. The R8 Normal HVAC recircs the building air through HEPA filters at fim rates of 400,000 cfm (USAR j Section 9.7).

l 1

l R0913R1 '

i

~

. DBR REY. NO. 0

. ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST ~

DISCIPLINE I&C MOD 547 DATE 11-24-86 In post LOCA conditions, R8 pressure can rise to approximately 50 psig. An SFAS contairment isolation signal will, occur at a R8 pressure of 4 psig or RCS pressure of 1,600 psig. Thus, the monitor will be 6

isolated fra the R8 at 4 psig which is below the 15 psig monitor's rating.

In post leak conditions where building pressures are less than 4 psig, the relative hunidity should still be controlled to less than the monitor's 95% relative humidity sample rating. RB temperatures will still be controlled to less than 120*F by the R8 coolers which is less than the monitor's sample temperature rating. (See calculation sectior 'r adsscription of radiological characteristics of 1.M 5 pie.)

Heat tracing and insulation will be provided on the sample supply line fra the R8 penetration to the monitor. The heat tracing systen will maintain sample tenperature at 115 + 5*F to ensure that condensation doesn't occur and tliat the sample-temp is still less than the monitor's rating. The heat tracing systen has inputs in IDADS to alert operator of sample line low temperature or heat tracing power failure. The controller will be -

located in the same rom as the monitor.

Sample flow rate will be nominally 3 scfhi. The monitor has autanatic flow control which will maintain flow within 10% of the setpoint.

Locations - R-15100 skid will be located in the Auxiliary Building +20 elevation in the same' rom as the Victoreen monitors. it replaces.

Power Supplies - The monitor will be powered fra the SIN 1 inverter through panel S1N1-1. This iwerter is battery backed and.will run on the battery alone for two (2) hours. The battery and t werter are normally kept charged and powered fran charger (H48N1). Supply for this charger comes fran load center S382 which is diesel backed. This power supply (SIN 1-1) is QA' Class II; however, it is very reliable.

R0913R1 -

DBR REY. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST l DISCIPLINE IaC MOD 547 DATE 11-24-86 The RM-11 canputer/ console and reconfers in H3TMI are podered fran the 1G inverter which is also a QA Class II; however, it is a reliable power supply. -

Basis for Leak Detection (response times, setpoints, sensitivity) - See calculations section.

b) R-15044 - Reactor Building Stack Monitor

1. History R-15044 was originally installed as a RB abnosphere monitor for the purpose of pre-hydrogen purge release assessnent and to assist in 35'-iri.a a PASS sample under ECN A-3683.

Additionally, t?le monitor has been intended to serve as a backup means of core damage assessnent.

Under ECN A-5500, the monitor was modified by making it a dual purpose RB Stack and RB Abnosphere monitor. Isoki netic probes and process flow instrunentation were installed in

! the RB Stacks. This was for the purpose of Post Accident and RB Equalization Effluent monitoring in accordance with NUREG-0737 II.F.1.

2. Monitor Description (see ECNs A-3683, A-5500)

Range 7 to 10 5 uCt/cc of noble gas (Xe-133)

Sample Flav Rate Nonnal train - 2.0 scfm Accident train .06 scfm Monitor has automatic flow control to maintain isokinetic sample fim conditions.

Sampler Skid Contains particulate filter and iodine filter cartridges for pa rticulate ant iodi ne grab sampling.

Accident train filters have lead shielding.

i

a R0913R1 DBR REY. NO. 0 ECH NO. R-0913. Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE IaC MOD 547 DATE 11-24-86 Sample Flow Rate - Monitor has flow indication at the skid and the RM-11 console.

Stack Process Flow Indication is available at the RM-11 console RM-23 (monitor iten 29) and IDADS. The rage is 0-81,000 scfm. Naninal stack flow rate is 74,000 scfm.

3. Monitoring System Description Canponent Locations Sanpling and Detection Skids - Spent Fuel Building Isckinetiv Probes ard Flow Elenents - RB Stacks,124 foot ei ev-ti on-Microprocessors (RM-80) - TSC Corridor, Auxiliary Building +40 elevation Renote Control Panel (H2DRMC) - TSC RM-11 Conputer and Printer - NSEB +40 elevation RM-ll Console (H1DRMS) - Control Roan Heat Trace Controller - Spent Fuel Building Corridor Modes of Operation RB Equalization Mode - Tech Spec approval to equalize RB pressure at power is currently being sought fran the NRC. Reactor Building pressure equalization is done by opening the 12" SFV-53603 and SFV-53610 equalization containnent isolation valves and venting the RB pressure out the RB stacks via the 12" equalization system. The RB exhaust fan will be on and the dilution damper (HV-53602) will be open hence diluting the effluent.

RB Purge Mode - This mode is only allowed while the plant is shutdown. The 66" The RB Exhaust Fan (A-536) will purge valves will the be on exhausting be RB opened.

Atnosphere and the RB Stacks. At the same time, RB Supply Fans will be on purging the RB with outside air.

O R0913R1 s --

i

. DBR REV. NO.. 0 ECN NO. R-0913, Rev. 1 NCR S-3960 WORK RE0 VEST DISCIPLINE IAC MOD 547 DATE 11-24-86 Post Accident Mode - Currently, this mode is required only during and following an accident when in the RB Equalization mode. (See NRC to SMUD letter dated March 16, 1984.) -It is required to monitor the R8 Stack Effluents for a wide range of noble gas concentrations. -

Also, isokinetic grab sampling capability must be avenilable for particulates and iodines. The monitor would check for contaiment isolation valve leakage and could assess any resulting post accident R8 Stack release.

Control Functions RB Equalization Mode - R-15044 will autmatically temirate R8 Equalization effluent by tripping the R8

%aust Fan ( A-536) and closing the Equalization Block h1ve (HV-53502)'upon a high radiation or operation status signal. Operator action will not be required to assure release limits are not being. exceeded.

Setpoints shall be in acconiance with the Offsite Dose Calculation Manual.

R8 Purge Mode - R8 effluent will be autanatically temirated by tripping the R8 supply and exhaust fans upon a high radiation or operate status sigral fran R-15044. However, a small release may still continue due to any R8 pressure above the outside pressure since the purge valves still will be open. The USAR Chapter 14.3 describes this. ,

Indication, Control, Recording, and Alams - Indications, monitor control, reconfing, arti visual alam is provided in the TSC on H2DPJ4C (Ranote Control Cabinet). Recordi ng of all three (3) gas channels-is provided on a strip.

chart recorder. A single pen reconfer reconis the total

. effluent release rate for both stacks in uC1/sec from channel 4. A timer is also available which can be.used to autanatically control the time a grab sample is taken. An RM-23 provides roote indication, monitor control and visual alam.

Also in the Control Room indication, monitor control, audible and visual alams, and trending is provided on the RM-11 console (H1DRMS). Hard copy printing of monitor status is available on a printer in the NSEB.

~

R0913R1 ._. .- _- . - . - _ . - . . . . - - . .

. = . -. -- .-. - .- - - - - -. .-

DBR REV. NO.' 0' I

ECN NO. R-0913, Rev. 1 .NCR S-3960 WORK REQUEST i

DISCIPLINE. I&C MOD 547 DATE 11 85 ~

1 i

~

At the skids, controls are also available for the sample

peps and filter selection. .

4 i

Caputer Displays and Software j RM-11 Console Display - since R-15044 is a dual purpose monitor (i.e., R8 Stack /RB Atmosphere) the:RM-11 console l

will show two separate monitor displays. Each mode will be assigned a different set of channel designations. The

selected mode will be apparent to the operato.r by the

color of the monitor display.

)

l The RM-11 Caputer will store the associated monitor data 1 base for each mode. Each mode will be assigned a

! separate RM-80 address. The modes can be changed by changing the address selector switch at the RM-80 and

down loading the associated data base fra the RM-11 to the RM-80. (See the special operating requirments ^ ' " -

section. )

i IDADS Display - Two sets of computer points will be-i assigned for each mode. Again, the operator will be able to recognize the active mode by the color of the display. ;

R-15044 will display channel 4 (release rate) on SPDS i (see ECN R-1041). Not in the scope of this ECN.

t i Power Supply - R-15044's RM-80, Ruote Control Cabinet, and skids are powered fra the $1N1 inverter.

State Notification - A high radiation signal fra R-15044 i

will be inputed into the State Notification Systa (see i State Notification Systen Description).

i i c) R-15045 - Auxiliary Building Stack Monitor

1. History - This monitor was originelly installed by ECN. '

A-3683 to meet NUREG-0737 II.F.1, Post Accident Requi reents.

2. Monitor Description - Same type of monitor as R-15044.

I- 3. Monitoring Systa Description I.

}

R0913R1 - -

~

i DBR REY. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST l

DISCIPLINE I&C MOD 547 DATE 11-24-86 l

Canponent Location - Same as R-15044 l

Control Functions - R-15045 will duplicate the control

~

functions of R-15002. Upon a high radiation or operate -

L status signal from R-15045, the Waste Gas Header Isolation Valve (RY-65514) will autanatically close.

Effluents fran other Auxiliary Building Stack release pathways will continue to be released as previously d esig ned. The basis for this is that it is better to renove airborne contamination fran the Auxiliary Building so that it can be habitable to operators who will be required to mitigate the cause of the release than to l terminate the stack effluent. If the radiation levels I exceeds allowable limits, the operators can manually trip l the Auxiliary Building Exhaust Fan thereby reducing the release rate. l State Notification - A high radiation signal fran R-15045 l will be inputed to the State Notification Systen. (See ,

State Notification System Upgrading.) i d) State Notification System Upgrade Individual input signal cutout switches with local status

, indicating lights will be provided in the HSSNSA (SNS l cabinet) located in the Canmunications Roan. This will l allow technicians or operators the ability to cutout l notification sigmis to the Office of Emergency Services (OES) when a channel is put in test for maintenance pu rposes. Also, the cutout switch can be used to cutout R-15044's signal when the monitor is in the RB Atmosphere mode and notification is not desired.. Local status lights will alert the technician when ary switch is in the cutout position.

Signals will also be provided fran the SNS to the IDADS I camputer to alert the Control Room of the SNS Status.

One conputer point will be used to alert operators that ary individual cutout switch or test switch (SW2) is in

. the cutout position, thereby disabling the SNS. Al so, l individual conputer points for each channel will be established to tell the operators that the state received

! a notification signal and which channels caused the alert. The H4CDAR2 MUX, located in Comnunication Roan, will be fed digital signals fran adjacent HSSNS.

1

~

7 ,

+

R0913R1 l

DBR REY. NO. 0

. ECN N0. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE IaC MOD 547' DATE 11-24-86 B. Stanary of Design Bases

1. Design Basis for reactor coolan,t pressure boundary leak detection by means of radiation monitoring. --

The Reactor Building Atmosphere Leak Detection Radiation Monitor's (R15100) function is to alert the Control Room operators of a possible small unidentified RCPB leak that would evaporate into the R.B. atmosphere. Upon receiving an alann the operators should verify leakage by the other two means of leak detection (i.e. sump level and coolant inventory). The leak detection monitor does not provide an accurate means to quantify the leak rate.

The replacement leak detection monitor's particulate channel has the ability to detect a small unidentified leak, on the order of 1 gpm, in approximately one hour for the expected operating condition of less tha n .057, failed fuel . The monitor is not expected to function with greater than about .lf, failed fuel. This should not pose a problen since the plant has not experienced high failed fuel nor does it expect to.

The noble gas channels are no longer an effective means of leak detection. This is due to the masking effects of. high equilibrium levels of gaseous concentration in the R.B. that build up during the course of plant operation fran small identified leakage. This masking effect was not accounted for in the original plant safety analysis since it was assuned that the R.B. would be purged during power operation. The plant, however, is no longer licensed to purge while at power.

The iodine channel of R15100 is also limited and ineffective for leak detection purposes. Likewise, this is due to the masking affect of high equilibriun levels of iodine.

- These results are based upon calculation and by review of enperical da ta . Reactor Building air sample data, coolant concentrations, and strip chart recordings of R-15001 were reviewed for the period of 1979 through 1985. This data was used in establishing radiological source tenns which are representative of the actual RB Atmosphere concentrations that the monitor would sample fran identified and unidentified leakage. Also, the data denonstrates the actual response of R-15001 to known leak rates that have been experienced in the past. This data was used in assessing the validity of the calculation, the particulate channel, fixed filter lifetime, and in R0913R1 DBR REY. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 detemining monitor setpoints. A calculation was perfomed to detemine R-15100's response time, sensitivity, sample line plateout, setpoints, and filter lifetime using both calculated RB air concentrates that would result fran reactor coolant concentrations stated in the USAR Appendix 14D as well as fran enperical data. <

2. Design Basis for the R.B. and Auxiliary Building Stack Effluerit Radiation Monitors (R15044 and R15045, resp. )

Both R15044 and R15045 will meet the existing Technical Specification requirenents stated in Appendix A, Section 3.16, " Radioactive Gaseous Effluent Monitoring Instrumentation." The monitors will monitor and control, as appifcable, the release of radioactive materials in gaseous effluent during actual or potential releases. The alam/ trip setpoints for these monitors shall be calculated in acconiance with the methods in the ODCM to ensure that the alam/ trip will occur prior to exceeding the limits of 10 CFR 20.

C. Calculations and Conclusions Calculation of the RB Leak Detection Monitor's (R-15100) Response Times, Sensitivity, Setpoints, Sample Line Plateout, and Sample Filter Lifetime.

(SMUD Calc No. Z-RDM-10126, Bechtel Calc No.1001)

1. Description of the Calculation a) General Methodology First the RB equilibriun activity concentrations were calculated which would result fran a base case 1 gpm identified RCPB leak.

Then the consequential sample that the monitor would see was detemined by accounting for calculated sample line plateout.

The accunulation of this sample activity deposited on the particulate fixed filter was calculated to detennine when the particulate detector would exceed its upper range limit. This sample accunulation effect was also calculated for the fixed charcoal cartridge on the iodine detector. The response time of the monitor to an additional one (1) gpm unidentified leak for one (1) hour, after one week of filter accumulation (worst case) was then calculated as well as for a couple of leak rates corresponding to sane chosen setpoints. Finally, the response times were calculated for a range of various RB equilibriun concentrations.

b) Specific Methodology ;

' ~

R0913R1 1

e I

DBR REY. NO. 0 ECN NO. R-0913, Rev. 1 NCR S-3960 WORK REQUEST DISCIPLINE IaC M00 547 DATE 11-24-86 e

RB Concentrations RB atmosphere concentrations were calculated fran coolant concentrations stated in USAR Table 14D-6 as well as from _

measured coolant grab samples stated in SMUD's chenistrf reconis (" historical concentrations"). A 40% flashing

! fraction was applied to the isotopes except for the noble gases where a 100% fraction was assumed. The R.B. HVAC system was assumed to recirculate the R.B. atmosphere including the flashed leakage at a nate of 400,000 cfm l

(USAR Chapter 9.7). The resulting particulates were l

. assumed to be renoved by 99% efficient HVAC recirculation I fil ters. A honogenous mixture of the R.B. abnosphere was assumed.

Bechtel Standani Canputer Program LOCADOSE, NE 319 Release 2 was used to calculate the decay of isotopes released to the atmosphere, the resulting daughter products, and the renoval effect of particulates by the i HVAC filters.

USAR Table 140-6 lists the canputed coolant isotopic concentrations for 1% failed fuel. The coolant l concentrations for 0.1% failed fuel (USAR Table 140-8) is i exactly a factor of 10 lower than that fran USAR Table 140-6. Hence the calculated R.B. concentrations fran 0.1% failed fuel were derived fran USAR Table 140-6 resul ts.

Sample Line Platecut The methodology to estimate the fraction of the particulates plating out in the sample line was taken fran NRC accepted plateout calculation studies. Usi ng this method, referenced in the calculation, the plateout was calculated for a range of 0 to 6 micron particulate diameters with 49/cc particulate de~sity. The case of 0%

plateout was also assumed in the calculation as suggested by the studies for 1 g/cc particulate densities.

The calculated plateout for iodines was used for the 1

elemental and particulate iodine only. Organic f odine were assuned not to plateout.

l l

1 .

R0913R1 DBR REV. NO. 0

. ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE IaC MOD 547 OATE 11-24-86 Response Times The monitor's response times were calculated for the particulate and iodine channels. Noble gas channels response time calculations were not necessary because it can be shcwn that these channels are ineffective for leak detection.

Response times were calculated by assuning a step increase of R.B. concentrations that would be due to a 1 gpn leak for one hour (the design criteria). USAR and historical source tenns were used to calculate the consequential R.B. concentrations that would result fran this leakage. The response times were calculated from the methodology stated in General Atomic Docunent No.

E-115-1101 ; Review of Algorithms used in General Atanic Radiation Monitoring Equipment. This method only calculates responses to step increases. No other methods were available to calculate the response to the expected exponential increase therefore this method had to be used. Deductions of the results have been made to account for the differences.

Response times .were also calculated for chosen setpoints of 1 X 10-8 uCf/ cc and 1 X 10-7 uct/ cc particulate R.B.

concentrations.

-The above response times were calculated for various initial R.B. equilibriun levels and sample filter loadings, (background). These are significant factors in the response time of the monitor.

The response times were calculated for filter ages of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , then daily for 7 days since the filter will be replaced on a weekly basis.

Sample Filter Lifetime The valueparticu} ate and of 10 cpm andiodine detectors have corresponding an upper range filter deposited activities of 10 uCi and 100 uC' respectively. It was necessary to detennine when this limit would be reached because the monitor would be disabled at approximately this point.

O R0913R1 .

~~

OBR REY. NO. 0

. ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C M00 547 OATE 11-24-86 The activity level deposited on the filters-was calculated via LOCADOSE at various R.B. concentre on using the previously described source tenns. The ample flow rate was assuned to be 3 cfm and filter efdiciencies -

if 99%. The detectors sepsitivities, in epm /uct , were used to detennine when 10' cpm was exceeded.

It was assuned the filter would be replaced weekly.

Calculations of filter age were done for the first hour, then daily for 7 days. .

c) Results of the Calculation i 1. R.B. Concentrations USAR Table 140-6 Source Tenn (short and long lived isotopes)

Pa rticulates Equilibriun level - 5.644E-6 uCf /cc Contribution due to 1 gpm leak for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - 5.638E-6 l uCi/cc i

Iodines Equilibriun level - 1.182E-3 uCi/cc 4 Contribution due to 1 gpm leak for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - 1.258E-5 uCf/cc Noble Gases Equilibriun level - 1.9E-1 uCi /cc Contribution due to 1 gpm leak for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - 8.0E.4 uCf /cc

2. R.B. Concentration (Historical Coolant Concentrations, long lived isotopes) i Particulates Equilibriun level - 1.8E-6 uCf /cc I

~

,5 4 R0913R1 .- . _ - __- _ _ _ -

..- - _ . . . . _ ~ -.

D8R REY. NO. 0 .

, . ECN~NO. R-0913, Rev. 1~ NCR -S-3960 WORK REQUEST DISCIPLINE IaC MOD 547 DATE 11-24-86 T

Contribution due to 1 gpn for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - 1.48E-6 uCi/cc 4

Iodines _ -

~

4 Equilibrium level 5.3E-5 uC1/cc i

Contribution due to 1 gpa leak- for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - 6.2E-7 uCi/cc Noble Gases i Equilibriun level - 3.0E-1 uCi /cc Contribution due to 1 gpm leak for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months - 4.3E.4 uCi /cc I

, 3. Sanple Line Plateout Pa rticulates Size Fraction J

i 0-2 .10 1 2-4 .29 4-6 .23-

_J5 - .38 i

NOTE: Response time and filter age calculations were done l' using 42% plateout for a corresponding mixture of

- particulate sizes and 0% assuning 1 g/cc particulate

, densities.

I Iodi nes

! Plateout. - 8.01%

1

2. Review of Baperical Data l .

l a) Particulates i l Strip chart recording (RJR13-01,02) of R15001 A and B (particulate i and gas channels, resp.) were reviewed -for the full power cycle I fran June /79 through Jan 80. Also the charts were reviewed fran 12/13/85 through 01/02/86. RCPB leakage to the RB annosphere of about 1 to 2 gpm was reported around 01-07-80 (ref: Mattimoe to R0913R1 l

l DBR REV. NO. 0 ECN NO. R-0913, Rev.1 NCR' S-3960 WORK REQUEST i f

DISCIPLINE IAC MOD 547 OATE 11-24-86 engelken (NRC) meno dated 02-11-80). A 15 to 20 gpm leak was also reported around 12/22/85 (ref: SMUD to NRC, Operating '

Status Report for Deceber 1985 and LER, Pressurizer Liquid Senple Isolation Valve Leak dated 12/22/85). l It can be concluded fra a review of the charts that the R.B.

easilibrim particulate concentration are approximately 3 X 10-9 e uC1/cc from both long and short lived isotopes. Fram review of !

R.B. air samples for several of years of plant operations it~ is concluded that nomal long lived particulate activities are on

/

the The order of 10-10 difference uCf between cc with chart a max reconf of about 3 X 10-9 ed concentrations of 3 XuCi/cc.

10- 9 and grab air samples is accountable to short lived activities believed to be mainly fran the short lived particulate daughter products of noble gases.

Graphs of the monitor's response to the leaks identified above were made (see attachments 6 and 7). :It can be seen fram the.

first graph (attachment 6) that causes an increase of 1.2 x 10 g 15-20

' uCi/cc gpma (17.5 above typicalgpm ave.) leak equilibrim level. Likewise, attachment 7 shws that a 1-2 gpm (1.5 gym ave.) leak causes an increase of 7.7 x 10 -u uCi/cc above a typical equilibrim level.- This information can be used to approximate the increase in RB concentration that would be due to a 1 gpm leak as follows:

1.2 x 10-7 uCf /cc = 7 x 10-9 uCi/cc per gpm

+ 17.5 gym ave.

and 7.7 x 10-8 uti/cc' = 5 x 10-8 uCi/cc per gpm l n

1.5 gpm ave.

ii The results ara, consistent with each othee within'an order of i' magnitude.

A monitor-setpof nt which-to based upon alerting the operators of a 1 gpm increase in RCPB leakage can be determined fran the above results. The setpoint will be the se of the typical equilibrim i

value and the increase in R.B. concentration due to a g gpm 4 + leakage increase as6follows: 3 x 10-9 uCi/cc + 7 x 10- uCf/cc =

1 x 10-8 uCi/cc. The lesser value of 7 x 10-9 uCi/cc per g,1m was chosen since it is the more conservative value.

i E -

~ ~

.R0913R1 ,

~

DBR REV. NO. O

ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 b) Iodines

Iodine concentrations have typically been reported in the chenistry records as follows: -

Isotope (uCf /cc) Half life 11 31 - 10-9 8.04 day I133- 5 X 10-9 20.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months I135- 10-8 6.58 hour6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months c) Noble Gases (Typical Equilibriun Values)

Isotope fuCi/cc) Hal f li fe, Xe 133- 1 X 10-2 5.25 day Kr 85m 1 X 10-6 4.48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Kr 88 1 X 10-6 2.84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months Xe 133m 1 X 10-6 2.19 day Xe 135 1 X 10-4 9.09 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months d) % Failed Fuel Typical % failed fuel have been less than .05% as confinned by the plant chenist.

3. Deductions and conclusions made fran the results of the calculation and review of Empirical Data.

a) Particulate Channel

1) Response time- to detect a.1 gpm . leakage.at Nonnal Coolant activities and at typical RB equilibrium levels, a) Using the results fran the review of R15001 Chart' Recording Data (see paragraph III.C.2.a above) a typical R.B.

From the review particulate of the chart equilibriun valuerecordings,9 of 3 x 10- uC1/cc and a monitor setpoint of 1 x 10-8 uCi/cc was detemined. The response a 1 x 10 b'ime of the was uCi/cc setpoint monitor to cause calculated using an alert alan historical coolant concentrations (i.e. nonnal coolant concentrations) at a typical R.B. equilibriun level of 1.8 x 10-9 uti/cc. The 1.8 x 10-9 uCi/cc value was selected since it is the closed calculated value to the enpirically detennined value of 3 x 10-9 uCi/cc.

~ ~

R0913R1

. . =- - .

J

. 'DBR~ REY. NO. 0

. ECN NO. R-0913, Rev. 1 NCR- S-396O WORK REQUEST DISCIPLINE I!C MOD 547 OATE 11-24-86 i

Fra Table 3C (attachent 31 it can be seen that the calculated response time for a 1 x 10-5 uCi/cc setpoint is about 62.5 minutes for " Historical Coola - Concentrations" at a typical R.B.

equilibrim value of 1.8 x 10- uCi/cc. -

b) Using the results of the calculated R.B.' concentrations due to a 1 gym leak of USAR coolant adjusted to .05% failed fuel (see '

para. III.C.1.c).

The calculated contribution to the R.B. atmospheric concentration fra a 1 gpm leak is 5.6 x 10-6 uCf/cc using 1% failed fuel USAR 4 coolant concentration data. For .05% failed fuel, this would result in a 2.8 x 10-7 uCf /cq increase of the R.B. concentration in one hour (.05 x 5.6 x 10-0 = 2.8 x 10-7 uCi/cc).

The response time of the monibr'to cause an alert alam with a 2.8 x 10-' uCf /cc setpoint and a 3 x 10-9 uCi/cc typical equilibrim level can be approximated by using t available cll culated response time for a 1 x 10uCi/cc ge closest-setpoint and a 1.8E-3 uCi/cc equilibrium level.

From Table 38 (attachment 21 it can he-seen that the calquiated response time for a 1 x 10-/ uCi/cc setpoint ami a 1.8E-V uCi/cc

' equilibrim level is about 62.5 minutes for " Historical' Coolant Concentrations. " Historical Coolant approximates USAR Coolant adjusted to .05%.

c) Using the calculated R.B. concentration increase due to a 1 gpm leak of Historical Coolant (see paragraph III.C.1.c).

The calculated contribution go uCi/cc the R.B. atmospheric using historicalconcentration coolant fra a 1 gpm leak is 1.48 E-concentrati ons.

4 The response time of the monitor to cause an alam with .a 1.48E-6 uCf /cc setpoint and 3 x 10-9 uCi/cc typical equilibrim value can be appro3i mated by using the closest calculated response time for a 1.48E-0 uCf /cc setpoint and-a 1.8 x 10-W uCi/cc equilibrim-level.

Fra responseTable time 3A (attachent ga)uCi/cc for a 1.48E- it canincrease be seen(i.e.1 that the gpmcalculated increase)-

and a 1.8 x 10-8 uCf /cc equilibrim level is about 62.5 minutes i for " Historical Coolant Concentrations".

i

= ,

R0913R1 !

._- __. _ _ ~ -1r ._ _. _= .

, J)BR REV. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C M00 547 DATE 1'1-24-86 O

2) Response time to detect 1 gpm leakage at 1% failed fuel coolant concentration at calculated resultant R.B.

equilibriun level (see para. III.C.1.c)

The calculated contribution to the R.B. atnospheric concentragion fran aThe 1 gpm leak of R.B.

calculated 1% failed fuel coolant equilibrium level is 5.6 x 10- uCf/cc.

that would result fran a 1 gpm identified leak (1 max. tech. spec. allowed identified leakage) is 5.gpm x 10-is ghe uCi/cc. Fran Table 3A' ( Attachnent 1), "USAR Coolant Concentrations for 1% Failed Fuel," it can be seen that the particulate channel is unable to detect leakage due to the fact that the filters become overloaded within 21 minutes.

3) Response time to detect 1 gpm leakage at .1% failed fuel coolant concentrations it calculated resultant R.B.

equilibriun le: is.

The calculated R.B. equilibriun leyel that would result fran 1 gpm identified leakage is 5.6 E-' uC1/cc. The calculated R.B. atmospheric concentration igresse due to an additional 1 gpm unidentified leak is 5.6 E-' uct/cc. Fram Table 3A, "USAR Coolant Concentrations for .1% Failed Fuel," it can. be seen that the particulate channel is unable to detect leakage due to the fact that the filters becane overloaded withi n 3.68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months .

4) Setpoi nts The initial setpoints, based on the above, will be 1 X 10-8 uCf/ cc (see para III.C.2.a) for the alert and 4 X 10-8 uCi/ cc for the high. The 1 X 10-8 uCf / cc alert setpoint is about 3 times the expected equilibriun value and should be leak without able causing to alert thealarms.

spurious operators

. Theof4aXpotentiaj/cc 10-8 uC high setpoint will confirm the potential leak.

These setpoints shall be adjusted appropriately, after sane actual operating experience is obtained for the monitor to.

see what the actual equilibriun levels will be, ard the response to a -knavn leakage increase.

5) Sample Filter Lifetime As discussed earlier the particulate filter lifetime depends on the amount of deposited activity. The maximum accunulated activity allowed is 10 uC1, R0913R1 -

e a

~

. -DBR REV. NO. O

. ECN N0.. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I!C MOD 547 OATE 11-24-86 Fran Table 3A the filter will expire at an equilibriun level of about 5.6 X 10-8 uC1/cc in less than the 1 week design filter change period.

It is reasonable to conclude that 1% or .1% failed fuel coolant concentrations could cause the filter to be replaced more frequently or declare the monitor inoperable. . However, the plant- has never' experienced high failed. fuel and probably never will and therefore the monitor should not' pose a limited condition of operation as designed.

The filter age will be detennined by observation of the strip chart reconting which reads the detector's count rate. The allowed limit will be detectors uppc; range value ofcpm). 10j X.10-0 cpm (80% of the For maximun historical equilibriun levels and coolant ;

concentrations the filter lifetime will exceed 7 days and should pose no problens.

b) Iodine Channel Conclusions

1. Response time to a 1 gpm leak increase typical iod"ne R.B.

equilibrius levels are on the- order of 5 X 10-8 uc' /cc. From Table 4 (Attachment 5) it can be deduced that the response time of the monitor, as calibrated, to a 1 gpm leak increase from~ a typical coolant activity as represented by historical concentrations in about 5.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Due to this long response time this channel will be used as a secondary means of leak detection to the particulate channel.

2. Setpoi nt The initial setpoints will be 1 X 10-7 uCi/ cc for the alert and 5 X 10-7 uC1 / cc for the high. The-alert is set at about'2 times l the expected background and therefore is set at the most conservative value which should not cause spurious trips. These setpoints will be: adjusted appropriately. after gaining operating experience.

3. Sample Filter Lifetime With high failed fuel coolant concentrations, this filter could becane overloaded and would require increased changeout or render the channel inoperable. However, at expected maximun coolant concentration the filter will pose no limitations.

R0913R1 _

~

~ 77' DBR REY. NO. O

", ECN NO. R-0913, Rev. 1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-86 c) Noble Gas Channels

1. Response Time: -

lated muilibrium concentrations were approximately 0.03 The to 0.c 1cd1/cc u aM the measured equilibriun concentration was 1.6 X 10- uCf/cc. The activity concentration contributW by 1 gpm 5 uC1 /cc using of unidentified historical coolant leakage in one hourand concentrations were 8 5X X10-4 10 Ci u /cc using the USAR coolant concentrations. It can be seen that the additioral leaka'ge is about three orders of magnitude lower than the background activity and will be difficult to detect. Unless the difference between the background and the contribution fran the leakage is about a factor of 10 the monitor will not be able to dett:t any cortribution fran unidentified leakages. This channel is not a viable means of detecting small leakage increases.

2. Setpoi nts The initial alert setpoint will be set at 5 X 10-2 uCi/cc. The alert setpoint is set at about 2 times the maximum expected equilibrium level and therefore is the most~ conservative setting that should preclude spurious trips. Again these setpoints will be adjusted appropriately when actual operating experience data is obtained.

IV. FAILURE MODE A. R-15100 - R.B. Atmosphere Leak Detection Monitor

1. Monitor Failure - audibis and visual "Instrunent Failure" alarm will be received on the Control Room RM-11 console if the monitor self diagnoses the applicable failure conditions listed in channel item 2 or monitor item 44 of its data base (Ref. N16.13-IM06 - Model RM-80 Software Design Document). Some of these conditions are as follows:

a. Loss of Power

b. Tow Counts from- Detectors

c. Loss of Sample Flow

d. Checksource Test Failed

e. Filter Clogged

f. Excess Negative Readings.

_y - -

R0913R1 .

DBR REY. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST

". DISCIPLINE I&C MOD 547 DATE 11-24-86 i

In addition an audible and visual alam will be reviewed locally at j R15100's skid for the " operate status" conditions (i.e. a-e above).

The " excess negative readings" alarm may may result fran the effects of short lived activity decaying on the filter. This will cause a decrease in filter activity over time and the monitor's alogorithm -

will calculate a negative reading, i Currently, Tech. Soec., Appendix A, Section 3.1.6.7 states, "The i systens sensitive to radioactivity may be out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided two other means are available to detect leakage." This is the consequence if R15100 fails. .This is not a new failure mode.

The consequences can be mitigated by corrective maintenance.

2. Failure of Heat Tracing Systen - an alam will be received locally at t*,e banc,jrace panel and on IDADs if heat trace tenperature is aJr,w; tnt ce upon loss of power. Excess sample condensation may occur and would likely ruin the filter paper. This is not a new failure mode. Consequences can be mitigated by corrective maintenance.

3. Sample filter overloading as discussed in the previous section could

- render the monitor inoperable. The monitor indication in uCi/cc would decrease-to zero since no change in the count rate would be:

seen by the monitor. The consequences may be mitigated by replacing -

the filter paper more frequently. It may-be necessary to declare the monitor as inoperable and the Tech. Spec. L.C.O. (3.1.6.7) will apply. This is not a -new failure mode.

B. R-15044 - R.B. Stack Monitor

1. Failure of the monitor to trip the R.B. Fans and/or close the equalization block valve (HV-53502) on high radiation could result in the need to marually teminate the release before exceeding 10CFR 20 limits. This-.is an unlikely event since-a monitor failure (operate

- status) interlock is provided. Operators would know of this failure

~ bf observing that the stack process flow rate or radiation levels were abnomally high after receiving a high mdiation alam on the

> - RM-11 console. This is not a new failure mode.

?

2. - Monitor Failure - The operator will receive the-same alams upon the same monitor failure conditions as described for R15100. This is not a new failure mode.

l l

l

- R0913R1 .

. - - .L .- . = - .- . ~ . = - - .-

~

DBR REY. NO. 0 ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST ,

DISCIPLINE I&C MOD 547 DAT_' 11 86 I

Upon declaring R15044 inoperable the limiting conditions of operation stated in Tech. Spec., Appendix A, Tables 3.16-1 and 3.5.5-1 will

> apply. These consequences can be mitigated by' dot.ng corrective j maintenance on the monitor. ,

i Receiving an " operate status" condition (see the monitor failure

? section for R15100) will cause automatic tennination of the effluents. Sane as R-15100 except there are no filter failure alarms.

i l 3. Failure of Heat Tracing Systen-same as R-15100, i

4. Failure of isokinetic flow control. .

This would result in an erroneously high or low grab sample of na rticulates. A monitor failure alarm would be received at the RM-11 coesole upon this condition. The monitor would automatically establish a fixed 2 cAn sample flow rate which would minimize grab

. :- sampling errors.

5. Failure of RM-11 Canputer or Console - Indication control, and alarms I

would still be available on HZDRMC located ~ in the TSC. The monitor

would still provide it's control functions.

C. R-15045 - Auxiliary Building Stack Monitor i 1. Failure of the monitor to close Waste Gas Header Isolation Valve .

J (RV-65514) on high radiation could result in the need to manually j

tenninate the release before exceeding 10 CFR 20 limits. This is an

unlikely event since a monitor failure (operate status) interlock is ,

j also provided. Operators would know of this failure by observing ;

that R15045's radiation levels were still abnormally high after i receiving a high radiation alann. This is not a new failure mode.

! 2. Monitor Failure-- same as R-15044;-

~

l

3. '

Failure of Heat Tracing System - same as R-15044.

i

4. Failure of isokinetic flow control - same as R-15044.

)

j 5. Failure of RM-11 Computer or Console - same as R15044.

! 1 4

= -

R0913R1 . _

l i

_ _ _ . . [ _ _ _ . _ , . . _ _ , , _ _ ,

~

DBR REY. NO. 0

~

ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST i

'. DISCIPLINE' I&C MOD 547 DATE 11 86 V. SPECIAL MAINTENANCE REQUIREMENTS A. R15100

- 1. G.A. Field Service Manager infonns.me that the Thomas Sanple blower requires frequent seal replacement. .

2. Caution should be exercised due to potential ~ radiological contanination. of the monitor. Coordination with the H.P. should be done before working on the-monitor:

B. R15044 ard R15045

. 1. Caution should be exercised.due to potential radiological contanination of the monitor. Coordination with the H.P. should be done before working on the monitor.

2. Isokinetic nozzles should be inspected on a refueling outage basis.

Backflushing should be done as required.

3. Prior to putting the monitor into- test during maintenance, be sure to cutout the monitor fran the State Notification System to preclude false alarms to the 0.E.S. Cutout switches are available at the H5SNS panel . Besure to return swit;h to normal after the monitor is returned to service.

4. These monitors require to be calibrated quarterly per Tech. Spec.,

Table 4.20-1 VI. SPECIAL OPERATING REQUIREMENTS A. R-15100

1. Sanole Filter Loading Monitoring. - read the, strip-chart recorder R-15000D located on the H3TMI cabinet and f odine channels do not exceed 8x10 cpm,gaily. to ensure indicating thatthe theparticulate filters are overloaded.

Investigate the cause. Possible causes are-as.follows:

a) extraordirarily high failed fuel causing high RB equilibrium l evel .

b) extraordinarily high known RCPB leakage causing high RB equilibrium levels.

R0913R1 -

33 - _

wh P'PE L -

J hi- 4, W uS $ W r -y $ r eq -- -

Tesa +- - m -'7 4 T

y v.

DBR REY. N0. 0

. ECH NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11 86 c) Failure of R.B. HVAC recirculation fans or filters. (See the Section III for more infonnation.)

2. Particulate and Iodine sample filters must be replaced on a weekly "

basis. Chen-Rad can use these for weekTy grab samples for lab a nalysis.

3. Upon receiving the alert alann on the RM-11 console, the operators should verify that a RCPB leak exists by the other two means of leak detection (i.e. sump level and coolant inventory).

B. Gra b Sampli ng

1. A 14 SCFM sample flow rate must be maintained to obtain a representative particulate grab sample from R15001 and- R15002's isokinetic nozzles in the R.B. and Auxiliary Building stacks.

2. If R15044 or R15045's grab sampling systen fails (most likely a sample pump failure) an alternate means of grab sampling can be perfonned by connecting a portable 2 CFM sample pump, particulate and iodine filters, and a noble gas bottle into the monitor's sampling conditioning skid. This can be done by removing one of the monitor's nonnal train filter cartridges and. inserting the portable sampling systen into the now available quick disconnect that is connected to the sampling line. The monitors' sampling conditioning skids have the necessary isolation valves. (See P&ID M512)

3. For R15100, the monitor's particulate and iodine filters can be used for a weekly grab sample.

C. R-15044 Procedure to change fran R.B. Stack Mode to R.B. Atmosphere Mode. (Note:

R-15044 will nonna11y be lined up to the R.B. STACK. R.B. Atmosphere mode will be a highly abnonnal line-up for a post-accident condition.)

1. Make necessary valve line to sample fran the the R.B.

2. Make necessary software changes as follows:

a. Change RM-80 address from 208 to 238 by changing the two rotary switches in the RM-80 (RY-15044).

b. Down load the R.B. Atmosphere mode database fram the RM-11 canputer to the RM-80 by pushing the reset button on the RM-80 mother board.

i = -

~

f R0913R1 , . _ __

i DBR REY. NO. 0

ECN NO. R-0913, Rev.1 NCR S-3960 WORK REQUEST DISCIPLINE I&C MOD 547 DATE 11-24-66

c. Channel Iten 16 must be charged to 001 for all 4 channels. This can be done at the RM-ll console.

d. Cutout R-15044 fran the State Notification system. _

e. The reverse of this procedure can be done to change it back to the R.B. Stack Mode.

VII. VERIFICATION CRITERIA None VII. COMMENTS

1. The following documents need to be revised a) USAR chapter 4.2.3.7-Leak- Detection b) USAR chapter 11.3 - Radiation Monitoring System, c) Tech. Spec. ; Appendix "A", 3.1.6 - Leakage

1) Bases section needs to be revised

2) Other sections needs to be revised which reference R-15001, R-15002, R-15044, or R-15045 accordingly.

d) R.G.1.97 position papers need to be revised accordingly.

4 R0913R1 -

. , G I e == .

tanens ..c3 Unit 1 - _

[ j!

Lees Oetection *cnitor stucy L-raote a

' Particulate Monitor (As calibratec) tescorise Time in Minutes to 1 ;;:'n LesKage as e Function of Filter Paper Age teactor l l Maximas l ~

Butidits l USAK Cootant- Concentretions (no ptateout) 11 Fai ted- Fuel l 7iLter l Equilibchap l l Capacity l Concentration l Port!culate Filter Peger Age l Time l ,

T dsve L davs T days 6 days T days I (days) !

(ucf/cei ' t hour- t daw 2 davs 5.60E-6 l NONE MONE NCHE MONE m m McNE NONE l 21 airr l 5.60E 7 l 62.5 NCNE NCNE NCNE NONE NONE NCNE NONE l S.4.Mrs l 5.60E 8 12.5 62.5 NCNE' NCNE NCNE ' NCNE NCNE NCNE' l 1.6 cays l l

5.60E 9 12.5 62.5 62.5 62.5 62.5 62.5 62.5 62.5 l > 7 days l l

5.60E-10 12.5 12.5 12.5 12.5 62.5 62.5 62.5 62.5 l > T days l l

5.60E-11 2.5 12.5 12.5 1Z.5 12.5 12.5. 12.5 12.5 1 > T says l l

r.60E-tr Z.5 r.5 2.5 1Z.s 1r.5 t r.5 1r.5 tr.5 [ - r days.l l

7. 5 21 f 2.5 l

T days f T.60E 1T I .i T. T 2.T ?. ? 2.i l

teactor j l Maximuur l Building- l USAR' Coolane Concentrations (no plateout) 0.1% Failed Fuel l Filter l Equilibrium- l -

l Capacity l Concentretierr l Particulate F1tter Peoar Ager l Timur l I 1 hour- 1 env 2 days T deve: 4 dava i days 6 deve 7 dave I fdawn) I~

fuct/ce) 5.60E-T l^

$r.I NONE MONE MONS. MONE . MONE MONE MONE [ I.6E hrs l T.60E C l 6r.5- 31r.2 NcNE NONE: McNE NCNE NOME NCNE [t.56. days.]

T.60E-95 l 17.5- 6r.2 6r.1 6r.2 62.7 31tI 31 7.5 Ifr.T l > Tdoye> [

r.60e-te l 1r.s 6r.5 6r.s 6r.s 6r.5 62.r 6r.5 6r.5 l - r days,j 5.60E-1T l 1r.T 12'.I tr.T 1r.f 6r.5 6r.F 6r.T 6r.T l - T days. l 5.60E-tr I r.r 1r.I 12.5 t r.s. tz.s tr.s tr.s ir.5 l > r days.l 5.60E-17 l 2' i

. 2.5 Z.5 Z.5- 17.T 17.5 12.5' 1Z.5l>Tde l 5.sCE ' A I .? 2.5 ?.i ?.? ?.S ?.i ?.5 ?.5 i > c eavs '

I I

l l

l

~

-?

f wav.= ewe 17 toAA - 19 08:00:04 - - - - , . ._ .,

L..'. ,

. f tanc.a.o seco Uni! 1 _

f . hvW

' Less Detection *cnt ter Stucy

,

M

a icte IA (Contirsec)

Reactor l Maximun l l

Buildins ] if storical Coolant Concentrations (no plateout) l Filter l lCacacityl Eaullibriue l Tfme [

Particulate Fittee Pacer Age l Concentratiert l 7 days I (days) I ruci/ce) I 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i day 2 days T dave & days i davs 6 daws '

1.SOE & 62.5 NONE NONE NONE# NONE NOME MONE

NONE l17.2 hrs l l

62.5 6Z.5 6Z.5 6Z.5 62.5 62.5 62.5 6r.5 l > T days ,l 1.30E-T l 62.5 62.5 62.5 62.5 62.5 62.5 62.5 l > T cays l 1.30E 8 l 62.5 12.5 12.5 12.5 12.5 62.5 62.5 1 > T cays-!

1.30E 9' l 12.5 12.5 12.5 12.5 12.5 12.5 12.5 12.5 l > T cays l 1.3CE-10 ! 2.5 12.5 2.5 2.5 2.5 2.5 12.5 12.5 l > T cays l 1.3CE 11 1 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 l >- rcays [

1.3CE-11 l Z.5 2.$ 2. 5 2.5 i

7 days i 1.30E-1T i 5 5 .5 .? ?. T teactor l l waxinase- l Building j Historical Coolanc Concentrations- (421 platecut) l Filter l Equilibritar l lCacocityl Concentration- l Particulate Fittes- Peoer Age

l Time l I davs A days i days 6 days 7 davr I (days) f CuCf/ce) 8 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 cav 2 days 1.30E-& 62.I 112.1 NONE MONE NONE MONE NOME NONE l1.6Fdayrl l

1.a0E-r j 6r.s 6z.s 6z r 6r.s 6Z.I 6r.r 6r.s 6z.s I > r day -l 1.30E-a- l 6r.r 6r.r 6r.s 6r.s 6r.s 6r.s 6r.s 6r.r [ > rdev I 1.a0E-* 1 tr.s 12.5 tr.r f f.5r - tr.s tr.s 6z.s 6r.r l - r day. l 1.30E- TO' T.7 12.T 12.s 12.7 17.5 17.5 12.5 1Z.I l > T days l l

1.3CE-1T j Z.5 Z.I r.7 Z.r I.5 Z.5 12.Y 12'.f l > r days l 1.30E- tr l z.s z.5 z.i z.s z.I Z.5 z.s 2.5 1 - r day. I

' 3CE-'T 1 .5 T .? 3 2.5 T. T 2.5 2.5 1 > 7 ca n t Note: NCNE

teens tnat amount of activity cecosited On the filter is aoove the range of the cetector; filter is overicaced.

e-l .

^

RancM3 Secs Unit 1

, .- /

t.eas Getecticn Monitor Stucy-b.

1 1

Table 35 Particulate Monitor (As calibratec) Response flme in Minutes for a 1 x 10*I d.1/cc Setpoint as a Function of Filter Peper Age Reestor l , lMeafnar l But Ldins l USAE Cootanc Concentratione.(no plateout) ~11 FeiLed Fuel }l Fitter l

' _ ~ .~ ~[Casesityl Ceaf tibriuer l ,

Concentretiert l Particulate Fitter Paper Age l Tlme l -

ruct/ce) ! t hour i day 7 ms Tm f. davr T devs 6 deve 7 dava 1 (dave) !

5.60E-6 l wcNE McNE woNE of McNE ONE 40NE NcNE l ZT sitt l S.60E 7 l 62.5 MONE OE NCNE NCNE WE MONE 4QNE l S.4 hrs [

5.60E 8 62.5 312.5 NONE 4CNE M MONE MONE MONE l'1.6 days l l

5.60E 9 12.5 312.5 312.5 312.5 312.5 312.5 312.5 312.5.l > 7 days l l

5.60E 10 12.5 62.5. 62.5 62.5 62.5 62.5 62.5 62.5 l' > T cays- l l

5.60E-1T 2.5 62.5 62.5 62.5 62.5 62.5 62.5 6Z.5 l > T days. l l

5.40E-1Z 2.5 12.5 1Z.5 1r.5 12.5 1Z.T 62.5 6Z.5 l

Tdays. l l

f.60F-1T I tr its 17.5 17.5 12.T it f tri 12.5 8 - rdave '

l Reactor l [ l Building. l Historical Coolanc Concentrations. (no plateout) l,Meximar Filter- l Eaui Librius. l l Capacity 1.

Concentration l Porticulate Filter Peper Age l Time- l (tf f /ce) I i hour- T' day

2 days I davs 4 davs i dave 6 davs 7' dave I (deve) !

1.30E-6 l 6Z.E ' NOME NONE. MONS- NOME MONE MONE NOME . l17.2. hrs l 1.a0E-T l 6Z.1 11 7.5- 31Z.5 313 5 31ti. 31Z.I 312.I 312.5 l > Tdays l T.30E-e l 6r.E 6Z.5 62.1 635 6r.Y 62.5 6Z.5 62.5 l > Tdays l j r.a0E-* l 6ts 6r.s 6Z.I 6tr ans 6r.s 6Z.s 6r.I l > rday.1 f .30E l 17.5 1Z.5 17.5 12.5 ftE 17.5 6Z.5 6Z.I l > T days l l'.30E-17 l 17.5 12.1 1Z.I tai tr.1 tr.I 17.1 12.1 l > T doye. l f.30E-tr l r.5 2.5 2.7 T.E Z.1 2'.5 1Z.1 1Z.5 l > T days- [

t . 20F 1T I 2.5 2.5 ?.5 T. T 2. f 2.5 2.T ?. T I > *'M i

Reector" l l *eximum i Building l Historical Coolant Concentrations-(427. stateout) l Filter l EauiLibeiue l l Capacity l Concentration l Particulate- Filter Peoer Age l fine l .

ftri/ce) I i hour i day 2 days 3 dava 4 dawn 5 davs 6 davs 7 davs ! (dave) !

1.a0E 6- l 62.5 312.5 40NE NONE - NOME NONE - NONE NOME l1.65 deve l 1.aOE-T l 62.T 62.5 317.5 312.5- 31Z.5 ' 312.5 312.5 312.5 l > T days l l

i t.aot a- l 62.1 62.5 62.5 6Z.5 ,62.5 62.5 62.5 . 62.5 l > T doye I t'.a0E-9 l 6r.5 ' 6Z.5 62.5 6r.5 6Z.1 6r.i 6Z.5 62.5 l > T deve l ,

T.30E-12 l 12.5 12.5 1Z.5 1Z.1 12.5 62.5 6Z.5 62.5 l > T days- l 12.5 l > 7 days l 1.30E-1t l Z.5 2.5 12.5 12.5 17.5 12.5 12.5 1.30E 12 l 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 l > 7 days l l

t.80E-13 f 2.5 2.5 ?.5 2.5 7. 5 2.5 2.5 2.5 I > 7 days t Mete: MONE scene that amount of activity cecosited on the filter is acove the range of tne detector; filter is overloaded.

e

tenens secs Unit 1 g/M// 47 A"

^ #

- Leandetection donitor Stt.;cy Ta'b te 3C Particulate Monitor (As calibratec) tespanse Time in Minutes for a 1 x 10'8 41/cc setooint as. a Functiott of Filter Paper Age toestor- l l Maximme l Buildirig l USAR Cootant Concentrations (ne plateout) 1% Failed Fuel l Filter [

Equilibrids l lCaposityl

~

Concentreti,orr l Porticulate Filter Peper Age- [ Tfae- l o f t wour- 1 day 1tw T== L devs i deve 6 deve Tdeve 3 edavai 1 ftri/ce) 5.60E 6 l MONE MONE MONE M NONE MONE MONE- M l 21 sin l 5.60E T l 62.5 m M N OE a m W l 3.4 hrs l 62.5 312.5 MCNE MONE MONE NONE MONE l 1.6 days ~l 5.60E-5 j 4CNE 312.5 312.5 312.5 312.5 312.5 312.5~1 > 7 cays l 5.6CE A l 62.5 312.5 5.60E-10 62.5 312.5 312.5 312.5 312.5 312.5 312.5 312.7 l > T osys [

l 5.60E-17 1Z.5 62.5 62.5 6Z.5 . 62.5 6Z.5 62.5 62.5 l > T days l

[

5.60E- 1z tz.5 6r.s 6z.s 6r.r 6r.5 62.s 62.5 62.5 l >- T doves i l

5.6er- tT i 17.5 1r. 5 $ 2. 5 tr. 5 tr.5 17.5 tr.5 17.5 i - r eavs i

- Reactor- l l Maximar l

< But t

rs l MistoricaL CaoLanc Concentratians (no ptatsout) l F f Iter- l Equit w. .ar [ l Caoecity l Particulate Filter-Pecer- Age- l Time- l.

Concentratiorr l t t hour i day 2 deve T deve - 4 dave 5 dava 6 dave T davn I (days) I fuci/ce) 1.30E l 6LI NONE NOME MONE NONE ' NONE NOME NOME l17.2.hrtl t.80E r l 6LI 11 7. 5 31ti 11Z:5~ 11Es' 31r.I 11 2.5 31Z.5 l > r dove l t.aoE-e 1 6r.y str.s star 3tz.s str.1 31z.5- sta r 11ts;l > rosy I r.aoE w l 6cs 6r.s 6z s 6ar 6r.s a.s 62.5 6r.r J > roovei l

r. ace.10- [ 6r.s 6r.r 6r.r 6r.s 6r.r 6r.r 6r.5 6r.s l >-r dove; l 1.30E-tt I tZ.r- tes 1r s 1r.s 6r.1 u.s 6r.5 a.r 1 - rday. I t .s0E-Ir l r.r its , tri Iz.y tr.I ins 1r.s 1r.5 [ >- r d y l t.!CE-TT I ?. T T. T ?. T ?. T ?. T 2.5 17.T 17. T I > T days I teactor- l l waxins l Building Mistorical Coolant Concentrations-(42*. plateout) l Filter l l '

Ecuilibrium l l Capacity l Concentration l Particulate- Fitter- Pacer

Age- l Time l 2 dave I dave 4 days 5 dave 6 days 7 dava f ' days) I (uCf/ce) i 1 hour- 1 day 1.30E 6 l 62.5 312.5 NONE MONE MONE NOME MONE- NONE [1.65 days.l 1.aot-T l 62.5 312.5 312.5 312.5 312.5 312.5 312.5 312.5 l > r daya l 1.aoE l 6z.5 62.5 312.5 31z.5 312.5 312.5 31Z.5 312.5 l > T days l .

1. ace 4 l 62.1 62.5 62.5 6z.s 6z.5 6z.5 6z.r 6z.5 l > r devs l-

t.aoE.tcr I a.5 62.5 a.5 6z.s 62.5 6z.5 6z.5 6z.5 l - r d y. I 1.80E-11 l 12.5 12.5 12.s 12.5 1Z.5 62.5 62.5 62.5 l > T days l 4

1.30E-?2 l 12.5 12.5 12.5 12.5 12.5 12.5 12.5 12.5 [ > 7 days l i 12.5 12.5 12.5 12.5 12.5 12.5 t > 7 days !

1.9CE 13 12.5 12.5 Ntte: 40NE - means,that amount of activity deoosited on the filter-

! is above the range of tMe-detector; ffiter is overloaded.

.- a

=

4

, _ .- - - - - . . _ . , . , , , . _ _ _ - _ _ . _ - . .._y , -e

6

. . .e

. Rancn3 secs Unit 1 1.ees Detection wonitor Stucy h WW !

- Table 3D l

particulate Monitor (Oesensitized) Resoonse Time in ifnutes to 1 g;za Lessage as a Function of Filter Paper Age Reector- i l Maxiest l Building l USAR Coolanc concentrations (no plateout) l Filter

l ,

!<alilibritar j l Capacity l l Concentration l Porticulate Filter Peoer- Age. l Time l _

l ftcf/ce) I 1 Maur- 1 day Z davs T dave & dava i dave 6 davs 7 dava i edawn) I 5.60E-6 l 62.5 312.5 MONE 40NE 40NE MONE NOME m l 1.65E+0 l ,

5.600 7 62.5 312.5 312.5 312.5 312.5 312.5 312.5 312.5 l > T days [

l 5.60E 8 62.5 62.5 62.5 62.5 62.5 312.5 312.5 312.5 l > T cays l ,

1 5.60E 9 12.5 62.5 62.5 62.5 62.5 62.5 62.5 62.5 l > 7 days l I l

5.60610 l 12.5 1r.5 12.5 6z.5 62.5 62.5 62.5 62.5 l > T cays l 5.60E-1T l 2.5 1Z.5 12.T ini 1r.5 12.5 12.5 12.5 l > 7 cays.l 5.60E-tr l 2.s z.5 2.s 2.I 2.r; tZ.s tr.5 12.5 l > r cov. l 2.5 7. T ?. T ?. 5 ?. T 7. T 7.T 8 > P days I l T.60ET I ?. T

)

l Reactor- [ ]Maximur l.

Suilding- l Historical Coolane concentrations (no platoout) l Fi t ter- l Eaui Libeitar l l Caoectty l T'me l Concentration l Particulate Filter- Pecer" Age l fuci/e=) I 1 hour- 1 dav 2 days T deve a days 5 dave 6 davs 7 days - 1 (da d j 1.aot 6 l 6r.s 62.5 31r.5 11r.s 31Z.r 312.s 312.s 31z.5: [ - r d.y l 1.30E 7' l 6Z.5 62.I 62.5 62.E 6n5 6Z.T 67.7 62.I l > T days. [

f.30E 8' l 6ns 62.5 $r.T 6ET 6ES 6Z.5 62.T 62.7 l > Tdevs l T.30E 9 l 1Z.3 17.5 17.5 tii 17.2 17.I 12.7 1Z 5 l > T d.yo l T.30E-1tI l 17.E tr.E 17.2 Ins 12.5 1Z.5 1Z.1 12.5 l > T days l r.s0E-tr l r.5- 2.5 2.s r.s ne r.s 2.s z.s l w rdev. I 1.a0E-tr l z.s r.r z.s 2.s nr nr Z.5 2.5 l > r d.y. l t . 30s. t y I 2,y 7,5 7,5 7,5 7,5 7, y 7. T 2.T f > P days I teactor l [ *aximus [ ,

3uilding l distoricat Coolaer Concentrations (42% otateout) { ritter j f

Ecuilibriun l [ Capacity l j Concentration l Particulate Filter paper Age [ Time l l (uci/ce) I 1 hour- 1 day 2 days 3 davs & days 5 davs 6 davs 7 davn I (days) I 1.30E 6 [ 62.5 62.5 312.5 312.5 312.5 312.5 312.5 312.5 l > T days-l t.a0E-T l 62.5 62.5 62.5 6r.s 62.5 62.5 62.5 62.5 l > T d y l t.80E E l 12.7 62.5 6Z.5 62.5 62.5 62.5 62.5 62.5 l > T days l l

t.30E-9 l 12.5 12.5 12.T 12.1 12.5 12.5 12.5 12.5 l >- T dove l 1.s0E-1cr l 2.5 12.5 tz.5 in5 12.5 12.5 12.5 12.5 l > r day. l 1.80E-1t l 2.5 2.5 2.5 2.5 2.5 2.5 12.5 2.5 l > T days l 1.30E 12 l 2.5 2.5 2.5 2.5 2.5 2.5 2.5 ' 2.5 l > T days l 1.30E-13 8 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 i > 7 days i Mote MCNE means tMac amotsit of activity cecosited on the filter-is above t?!e range of the detector; filter is overtcased.

. - l

% .no a~d so m m.ca.m

Ranen3 .ec3 unie 1 0

Leac Detection Monitor Stu:y

. e Tacle 4-Iocine Monitor (Desensitizec) Resconse Time in Minutes to 1 ;pm Leakage as a Function of Filter Pacer Age Riector l Maximun l l

Sullding l USAR Coolane Concentrations l Filter l l Caoecity l Emaillbrius l Concentratforr l Iodinea Charcoal Filter Paper Age l Time l ,

I days 4 days i days 6 days T eavs t (days) I fuCf/ce) I t %2r- t day 7 dave 1.17E T l 4CNE NONE OE 4CNE MCNE 4CNE MONE NONE l 54-min l 1.17E 4 l 312.5 OE NCNE 4CNE 4CNE 4CNE 4CNE 4CNE l 3.9 hrs l 1.17E 5 62.5 312.5 312.5 312.5 312.5 NCNE MONE NONE l /. 996 cays l l

1.17E 6 l 62.5 312.5 312.5 312.5 312.5 312.5 312.5 312.5 l > 7 days l 1.17E-7" l 62.5 62.5 62.5 62.5 62.5 62.5 312.5 312.5 l > T days l 1.17E l 1Z.1 62.5 62.5 62.5 62.5 62.5 62.5 62.5 l > T cays i 1.17E l 1Z.I 12.2 12.5 12.5 62.5 6Z.5 62.5 62.T l > T days l 1~.1 M- 10 8 ?. T T T. T 17.T 17.9 17. T 12".5 17.5 17.7 I

T eaYs I

~~

Reactor l l Neximus- l Sullding. l liistorical Coolant Concentrations. l Filter l Cquilibriur l ,,

l Capacity l C-a. .starr l Iodine Charcoal Fitter- Paper Age [ 7imer l (uct/cey I t hour- f day 7 davw T days & deve T- davr 6 deve T deve I (days) 1 -

F.11E-f l 31Z.f WCNE NCNtf NOME NONE NCME NOME NOhE l 20:Mrs j f.3TE-6. l 37 7.5 31 7.1 11 7. 7 11 7.5 317.5 312.5 Itz.T 31LY l

T days- l T.31E-T l 62.1 112.T ITI.5- 312.I 312.5 312.5 312.5 317.Y l >- T days i f.31E-T l 62.5 31 7. I 37Z.5 312.7 312.5 31Z.5 31Z.5 325.Z l > T days l T.31E-4 l 62.T 62.5 62.5 67.T 62.5 62.5 31 2.5 31 2.5" l > T days l 5.3

E- 10 1 12.5 62.5 62.5 62.5 62.5 62.5 62.5 e2.5 l >- 7 cays t 5.31E-11 l 12.5 12.5 12.5 62.5 62.5 62.5 62.5 62.5-

> T cays l 5.3'E '2 !

12.5 12.5 12.5 12.5 12.5 12.7 '2.5 *2.5 i >7 1sys Note: NONE means enac amount of activity cecosited on the filter is aoove tne range of tne detector; filter is overloaded.

j

-er <ees .v . nn.nn.nL

o o_,

O- O x, ,,,;s s ='~ __

v '.re ~. ' ' ::-- w,v,rr..

O w - e s'7 s2:2 ,7~ n - - - - m-i f.svie '

j

~ ~

? yrh p_ ll_ '.~ y-- -

-,1----- [ ~-----_9

.% L wi e- __

og l _ . _

'-~

~~7

f. - -

- - ~ ~ -

7g_ 7/7 I' ,

I : __.-1_. .

_ _ _ . - " bi T_l'l- - _ ~ . - ~ ~

T i -= -

= . - -- -

- . --=

- - ==- :=. --- - -

l I

-\

Jj .- [.

1 -x ~

%it!

D 3 3-g I

l,

'}

.- _ _ .J.-_- - _

i saa um1.w z. , ,

. sra /

' - ~

a ( AgffW

? ' 'jt D E . g

. G"Mu4sr- na a -- - % -

4, 4 w - . -

Q N, _s

_ .r ._ F ,

. A

adu saEF[J , _f e_ pa e uneem l 9 ic

[ 'l i

i . .

-Q

-~ ('a ,

=

l

,. y w ._m w. .

e 7.

.O p :m < 7 ; g y, :

g _;. ,'

l ,

i E

f 'N

[ - % ---,k g to s, \

rg g ha ,-

/

, n 2, - v - ,

s-__- _E 3

~ ~~

_--_---[~-- ---

[r- 4N s

s-w_

- - m

.r

-s 1-6 a

{ -} l

. G}l a,

li 1

b

j. .{

. = 1 a -

~ ,

M mh -

7,

c. --

x -. -

,g .

- 1 M . . .

+ 2; h . _ L.'.. ~__

~'-

?f.i@g_.

..-_____..__...m

.=_g ..

-m d

a I

e saw%s maic e se cHwssears M..- C et a u ev.cL.a.s . y gI t ~ ve ,

imag e

ku lO

.as_- i ..,o e

. au

,n - - . . . . ,;' %.-, .'- , ,

_g r .

. .? * .t1 * }* =~

'4} %

s

% mi_ ~

w. -

4.-

2

- __..-___-_.. ______. w. _ _ ..--

g1 .-

a

_g .

su.2 . . e.g p * . .

~

-.h . _ . __ . . . _ __ ._ .

. _ _ _ _ _ _ _ _ n. .-~~~- -_-o- . -..

.- -m

=.

Wh.emew. -e

. +-**=-%

_-e-- _ - _ .

- - - - e-.=~.-

w, ._ _

i1.-

.--.,,m.,e-

, j .

H 4

..",- p M

%~

% f p'

1'

}

a

m. I 7 M

.-.e-e - -

h -

ww em mmm.e +e, esim ee is me 6 x '

3. _ -. ,'- e -

_ , p v 1 _J

, - %d

'l 's.

. d g; ' . ~

1 w

..3 7 =3

} ===

2 .t i u_ .

_ ,e i

. r w w.

.. 6WlAfl9 FKS31"b . w -

w- _ . _/- p" N( % r PO v

L h - #

b E

1

==

sentnentsmw.'m . t

' u$

Al 2 WYS.%- - y\

? --#

. . r s I. 'I - #

.f

~. "_-' "" 'a 1 I

n. n s

.a ff I

f ^

. f.

[_

r-

x. . --

1 >

1 n N: 'l 1 1

)

E' P P L A 6. 1; G*

a m .

_'i_

x.

m. C ""

= :un . g

-a .

Ji

.. = r v .

ar=- y:

g ,

< W=$ *

.we e.,s y 1

4-

] ;)-

Q p.

l-S _- _ --_ _

I R / I I

-.. -. ._,.A -

.-l-

==*w'**-= ^

-e s. e- .

..f.. .

$ -- e.-

eM ..M .,

4 w

.-+-e. *< -

, r-- - L-;.-_ -

N==

, i f. , . a; en-t

6. -

,)

O- 1 3

_, - :-c ,

%' i

a. ' we ;

k4.. am

(

' A t N -

_ _ _ - 's

- ag % -'

Me=-_.

6N -'-*

M g

m. ' ' ' %.

]

- 2I 2 M {

- q ww 1

. %'%i . 4 m : ~ ,,,,,,.

^

_n"~f^~ ^ #

-WD* ,

--M : . - = , = =eW -

~?- - , . . . , , . . - . . . , .

~

M^N. $ a h-.u-H -

-pp

' I%

s

. &Rify ,

.,

v t e Letter Sequence Request
TAC:64879, (Approved, Closed)
Initiation Request, Request, Request Acceptance... Administration Questions Answers Results Approval Other: ML20212E407
MONTHYEAR1987-02-20 [Table View]

ML20214T863

Text

Dear Mr. Miraglia:

SUMMARY

Navigation menu

Search