ML20115H952

Forwards Info Addressing Remaining Draft SER Open Items Discussed at 850411-12 Meetings W/Nrc.Supplemental Info Requested Also Encl

ML20115H952
Person / Time
Site:	Vogtle
Issue date:	04/18/1985
From:	Bailey J GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
GN-584, NUDOCS 8504230325
Download: ML20115H952 (23)

Text

-

m Georgia Pow r Company Routa 2. Box 299A Wayn% boro, Georgia 30830 Telephone 404 554-9%1 404 724-8114 Southern Company Services, Inc.

Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Proj.ect April.18, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention:

Ms. Elinor G. Adensam, Chief Log: GN-584 Licensing Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 REQUEST FOR SUPPLEMENTAL INFORMATION STATUS MEETING - DSER OPEN ITEMS

Dear Mr. Denton:

On April 11-12, 1985, a meeting was held with members of your staff to discuss and resolve open items remaining on the VEGP draft SER. Attachment 1 is a listing of enclosures that address those open items discussed in the meeting, and in follow-up telephone conversations, and provide the information necessary for their resolution. Also included is supplemental information requested by your staff but not specifically called for in the draft SER.

If you staff requires any additional information, please do not hesitate to contact me.

Si erely, J. A. Bailey Project Licensing Manager JAB /caa Enclosure xc:

D. O. Foster l

R. A. Thomas G. F. Trowbridge, Esquire J. E. Joiner, Esquire C. A. Stangler L. Fowler M. A. Miller L. T. Gucwa G. Bockhold, Jr.

0173m 8504230325 850418 PDR ADOCK 05000424 E

PDR 1

L'

D

.4 ATTACHMENT VEGP OPEN ITEMS INDEX ITEM ENCLOSURE REMARKS 01-66 A

Additional information requested in the April 11-12 meeting on freeze protection. This information will appear in Amendment 16.01-105 B

This information on QA Regulatory Guides supercedes that submitted on this particular item in GN-570, 3/29/85 and will appear in Amendment 16.01-106 C

This information on the QA program and Q-List will appear in Amendment 16.

OI-126 D

Additional information on plant staffing requested by telephone on April 9.

This information will appear in Amendment 16.

430-41 E

This information on diesel intake and exhaust manufacturer's standards supercedes that pr.esented in GN-579, 4/15/85, and will appear in Amendment 16.

430-50 F

This information on overspeed protection was discussed at the April 11-12 meeting and will appear in Amendment 16.

METB G

Additional information on collection cartridges requested in the April 11-12 meeting.

MEB H

Additional information on IST pump and valve programs requested in telephone -

conversation on April 17, 1985. This information will be included in Amendment 16.

0173m

enc.losure. A oI-GG

' f VEGP-FSAR-Q Question 420.11 Describe features of the VEGP Units 1 and 2 environmental

'(-'

control system which ensure that instrumentation sensing and sampling lines for systems important to safety are protected from freezing during extremely cold weather.

Discuss the use of environmental monitoring and alarm systems to prevent loss of or damage to systems important to safety upon failure of the environmental control system.

Discuss electrical independence

(.

of the environmental control and monitoring system circuits.

Response

This question was discussed with the NRC at the ICSB meeting August 27-30, 1984.

Environmental control systems which protect systems including I

-instrument sensing lines from freezing during extremely cold l15 weather are heating and ventilation systems as discussed in section 9.4 and heat tracing systems are discussed in paragraph 8.3.1.1.9.

The two types of heat tracing systems are:

the' ambient sensed freeze protection for the nuclear service cooling water system and the process lines and instrument sensing' lines maintained at l15 preselected temperatures controlled by the resistance temperature detectors.

Freeze protection for the nuclear service cooling water system is discussed in paragraph 15 gglgg 9.2.1.2.3.

~

toith Dif ferent control'paheTs are~dsecl~ for each train, except for

,.yhuf auxiliary feedwater.

Because there are three process trains.of g

auxiliary feedwater, a single failure in one control panel will not cause loss of auxiliary feedwater.

(

Regulatory Guide 1.151, Revision 0, evaluation for VEGP is provided in table 420.11-1.

However, it is not applicable to VEGP as stated in the implementation paragraph of the regulatory guide.

(

(

Amend. 8 7/84 Amend. 11 11/84 Q420.11-1 Amend. 15 3/85 r

INSERT A TO Q 420.11 The heat tracing system is designed as a non-safety related system in accordance with the recommendations of IEEE-622.

Safety-related instrument sensory line temperatures are monitored by pipe mounted sensing devices (RTD's).

Freeze protection systems are monitored by independent ambient temperature sensing thermostats.

The primary monitoring thermostat is set at 40*F and the backup thermostat is set at 32*F.

Each system electrical panel contains provisions for monitoring undervoltage, loss of D.C.

power, ground faults, and heater malfunctions.

Both local and remote alarms are indicated upon loss of.any monitored function.

The remote alarms are annunciated in the main control room on the annunciator control board and the heat tracing annunciator cabinet back panel.

The heat tracing annunciator cabinet contains 50 alarm windows, each inscribed with information regarding the heat tracing equipment tag number, building, level, and room number where the monitoring panel is located.

The control room operator is directed to this panel by the common heat tracing trouble annunciator at the main annunciator control board.

Independent redundant heat tracing is provided for appropriate portions of the Safety Injection, CVCS, RWST, Waste Processing Liquid, Boron Recycle, and Radwaste systems.

Power for the Safety Injection, CVCS, RWST, Hydrogen Monitor sample lines and Radiation Monitoring System heat tracing panels is obtained from non-Class 1E diesel backed motor control centers.

The auxiliary feedwater system instruments are powered through separate circuits from different diesel backed panels.

Heat tracing for the RWST instrument tubing is powered from a diesel backed panel through a common circuit.

Power to the heat tracing on NSCW towers A and B is supplied from ambient sensing panels.

Power to the NSCW transfer pump and instrument tubing heat tracing is supplied from a separate heat tracing panel located in the auxiliary building.

The Unit 1 condensate storage tank area heat tracing is powered from a non-diesel backed panel.

The Unit 2 CST area heat tracing is powered from an ambient sensing panel.

2477t

bucko s u r e_ 6 o I - 105-VEGP-FSAR-1 1C 4.

Sections 4.3, 4.4, and 4.5 of ANSI N45.2.2-1972 titled, respectively, Precautions During Loading and Transit, Identification and Marking, and Shipment from Countries Outside the United States.

VEGP will conform with the requirements of these sections on a case by case basis.

l9 5.

Paragraph 5.2, Receiving Inspection Requirements.

[15 Preliminary visual inspection will be performed prior to unloading where practical; however, the receiving inspection of record will be performed in an area and in a manner which does not adversely affect the l7 quality of the item being inspected.

E 6.

Paragraph 5.3.1, Acceptable.

Item acceptance status

[15 will be indicated by application of tags, stickers, ribbons, or signs.

Storage areas are not designated as accept areas except for bulk items (e.g.,

rebar, structural steel, aggregate, etc.)

l9 7.

Paragraph 5.7, Documentation.

Receiving inspection E15 records will provide traceability to the item and its status.

Superfluous identification and tagging will not be recorded except when they are the subject of a nonconformance or specifically required by site inspection procedures.

l9 8.

Paragraph 6.2.1, Access to Storage Areas.

Items which l15 fall within the Level D classification of the standard will be stored in areas which may be posted to limit access, but other positive controls such as fencing or guards will not normally be provided.

9.

Parsg a h 6.3.3, Storage of Hazardous Material.

l15 sentence laced with the followin ardous chemicals, paints, ts,.

er materials of a like nature shall b e

roved cabinets or containers are not in close pro - -

to ed systems required for safe shutdown.

+ veGP shal\\ cowform +o +kis sen4ence_ b prodia for y

6 ca of ha24rJews chemicals, patwtsi s olv eats and o+ker-ruderlab of 4 hke. nahre 'm a or cowhIners dic.h are not e

in cjose prox imity ++ pproved cabine+5 installed s ireJ for 5 hub b

clown or-insh.llect Syste"s Mich ^#5""f ace '-[$ mend.

gg,_

FO "g[-( Poteh4(al o(-f-Sdeaf e_ 4he con.5 eguence5

/84 g(4(

o e.xposut es cd*P#akdr6nd.

9 8/84 resu\\

1.9-38 Amend. 15 3,'85

.{ o Q,5 e, re fere-c e i n io e cri ico.it.

E nc.kostar e b or-106 VEGP-FSAR-17 Review of documentation required by the purchase order 8

sec.Fon. The dtc. ochrtm 1.the. procure ment reoieu3 is performed by x_' _ _it u>ill_p_e_r form s'aceipt-ins pedion o f B.

Inspections, tests, and other specified records 5"f*hI E*"S

• attesting to the acceptance of materials, equipment, and components are completed and available at VEGP prior to installation or use.

C.

Materials, equipment, and components _are inspected and judged acceptable in accordance with predetermined inspection instructions prior to installation or use.

Items accepted and released are identified as'to their inspection status prior to forwarding them to a controlled storage area or releasing them for installation or further 8

work.

Nonconforming items are clearly identified, controlled, and segregated where practical, until proper disposition is made.

For commercial (off the shelf) items where specific quality assurance controls appropriate for nuclear applications cannot be imposed in a practical manner, special quality verification requirements shall be established to provide the necessary r

assurance of the item.

The quality assurance department will audit the control of purchased materials, equipment, and services to ensure proper implementation of the requirements.

See subsection 17.2.18 for a description of the quality assurance audit system.

l l

l

\\

l 0385V 17.2.7-3 Amend. 8 7/84 l

l t

,A s

TABLE 3.2.2-1 (SilEET 90 OP 97)

(d)

(f)

(g)

(j)

{a)

(b)

(c)

VLGP (c)

Codes and Principal (i)

Environ-Principal System location Sour ce of Qua l i ty Sa fety Sei smic Sta nda rd s Construc- (h)

Safety mental (k)

_ a r.id_Componen t s Unit 1 Unit _2 Supply _,_ G roup Class Caggory Desigrjalol 1 ion Code Q-l ist RelaM Designator Comments

29. lurbine genor-S NA 6

2 C

AISC-69, N

N ator pedestal ACI 318-71, UBC-76 30 Storm dra in S

NA 6

2 C

AWWA C-200 N N

system (Note Y) 3 l15

31. River makeup S

NA 6

2 C

AWWA C-2OO N N

water piping

32. Radwaste 11 NA 6

2 C

AISC-69.

N N

solidification ACI 318-71, buiiding UBC-76

33. NSCW tower B

NA 0

1 C

AISC-69, Y

Y 8

valve house ACI 318-71 314 Radwaste B

NA 6

2 C

AISC-69 N

N t ra ns fe r ACI 318-71, buiiding UBC-76 t' H C

35. Category 1 B

NA O

1 C

AISC-69, Y

Y Note 2 electrical AISC-68 09 9 i cable t ray jO supports 3

ee

36. Category 1 il NA O

1 C

AISC-69 Y

Y Note 2 3

ilVAC duct p

1 supports

31. Pipe supports Note 2 L

38. Pipe whip W. Il NA O

1 C

AISC-69 Y

Y restraints

39. Wa ter t ight B

NA O

1 C

mfg Y

Y doors and seats

10. Wa te rp roo fi ng B

NA 6

2 C

mfg N

N 4

and water stops

11. Category 1 B

NA O

1 C

Y Y

4 hackfi!i 14 2. Category 1 O

O B

NA O

1 C

AISC-69 Y

Y tank iiner plate

13. Underground B

HA O

1 C

AISC-69, Y

Y 4

Category 1 ACI 318-71 3

piping alid conduits CONTAINMINT BUILDING POLAR BRIDGE CRANE 1.

Mechanical C

C 11 NA 6

1 6

mfg

/(f N

Note q M o.b P w (n w components U1 2.

Motors C

C 11 NA 6

2 E

NEMA MG1 fly N

h)ofe_ ab 3.

I ns t rumen t a t i on B

NA 6

2 J

mfg

)(y N

gg ab g

g and controls ggu N 00 CD CD co b u b U1 2

i

?~

,i

. TABLE 3.2.2-1 (SHEET 91'OF 97)

(d)

(f)

(g)

(J)

(a)

(b)

(c)

VECP (e)

Codes and Principal.

(i)

Environ-Principal System Location Sou rce of Qua l i ty Sa fety Se i sm i c Standa rds Construc- (h). Safety mental (k) cnd Components Unit 1 Unit 2 Supply Group Class Category Designator tion Code Q-List Related Designator Comments FUEL HANDLING SYSTEM 1.

New and spent FB F8 W

NA 0

1 5

mfg Y

Y Vil fuel storage racks Qe., ah 2.

SICMA refueling C C

W NA 6

2 6

mfg gy N

machino 3.

RCC storage C

C W

NA 6

2 6

mfg N

N station 4.

Thimble plug C

C W

NA 6

2 6

mfg N

N storage rack 5.

Integrated C

C W

NA 6

2 6

afg N

N 4

head cable ng assembly ob 6.

I nteg ra ted C

C W

NA 6

2 6

mfg N

N m

head cable i f.

tray ND

$ O'.

7.

I nteg ra ted C

C W

NA 6

2 6

afg N

N head lifting y

rig Iw 8.

I nteg ra ted C

C W

A 1

1.

1 til-NF Y

Y head lift rods 9.

I nteg ra ted C

C W

A 1

1 1

til-NF Y

Y head missile shield

10. Integ ra ted C

C W

NA 6

2 6

mfg N

N head operator support stand

11. I nteg ra ted C

C W

NA 6

2 6

mfg N

N head package stud support co l la rs

12. Radial arm C

C W

NA 6

2 6

mfg N

N hoist assembly

13. Radia l a rm C

C W

NA 6

2 6

mfg N

N stod tensioner hoist

14. Reactor C

C W

NA 6

2 6

mfg N

N internals lifting rig

15. f te t handling fB FB W

NA 0

1 5

mfg Y

Y Vil machine

16. Spent fuel FB fB W

NA 0

1 5

mfg Y

Y Vil handling tool

~

ej

r*%

s 6:

TABLE 3.2.2-1 (SHEET 92 OF 97)

(d)

(f)

(g)

(J)

(a)

(b)

(c)

VECP (e)

Codes and Principal (i)

Environ-Principal System Location Source of Quality Safety Seismic Standa rd s Construc- (h)

Safety mental (k) 3.id Components Unit 1 Unit 2 Supply Group Class Category Designator tion Code Q-1.ist Related Designator Comments

17. tew fuel fB fB W

NA 6

2 6

mfg N

N handling tool

18. fuel t ra ns fe r W

B 2

1 2

Ill-MC Y

Y tube

19. Fuel t ransfe r W

NA 6

2 6

mfg N

N system Nob Ab

20. New fuel FB FB W

NA 6

2 6

mfg gy N

elevator

21. Spent fuel fB FB B

NA 0

1 5

mfg Y

Y Note q cash bridge c ra ne O D mH I

• m "D (A>P

c 1w I

4 4

e t

O L -lO L.

VEGP-FSAR-3 TABLE 3.2.2-1 (SHEET 97 OF 97)

Position CMEB 9.5-1, Appendix A, attached to Nuclear l3 Regulatory Commission (NRC) Standard Review Plan 9.5.1.

w.

The quality assurance program to be applied to radioactive waste management systems is described in Regulatory Guide 1.143.

x.

The Seismic Category 1 fire protection standpipe system serves no safety function but is classified as project 3

class 313 to ensure the implementation of a seismic i

Category 1, ASME III-3 design and installation.

y.

Changes to the site grading will be done on an engineered basis so as to assure acceptability of the drainage analysis 15 for the probable maximum precipitation (?MP) event as described in paragraph 2.4.2.3.

GENERAL NOTES 1.

For systems under the Westinghouse scope of supply, all piping and all manual valves 2 in. and smaller are supplied by 3echtel, except for the reactor coolant loop piping, the pressurizer surge line, the pressurizer relief piping complex, reactor vessel bottom mounted instrument tubing, reactor vessel head vent piping to refueling disconnect flange, and reactor vessel seal leak detection leakoff appurtenance.

2.

Hangers and supports for Seismic Category 1 systems and components are designed as Seismic Category 1.

In general hangers and supports for Seismic Category 2 piping, cable tray, and ducting in Seismic Category 1 buildings are designed to maintain their structural integrity under the 12 postulated earthquake conditions; however, exceptions to this requirement are permitted when it is demonstrated that their failure will not adverselV affect adjacent seismic Category 1 equipment or systems.

3.

All "Q" listed coatings are assigned a project classification of 02C.

Q listed coatings are not seismically qualified but will not fail in a manner that would compromise the function of safety-related equipment in the event of an earthquake since they are applied to Seismic Category 1 structures.

~2.(se c. & M -561, 3/1ulGS) g (s<e G M-S70, 3lif / F8.)

ab, h perbe.d provisiws d Ne Q A PrograN5"b{,end. bgg.]

g w

\\

g dee_ iteus crs clescribed,m J'-

3 1/84 Amend. 12 12/84 Amend. 15 3/85

Legewel EXECUTIVE WICE PRESIDENT I

lk I

-h number of pers6..l pres.alf ass isaed 4c,

_"7,,,E,,,

4unchtow.\\ unit,

==a -R

%e numbe.r-of persawweI i

o 4o ke_ c ssi ned cd--fuel WJ.

g 4

E

,7

.mun oo,,AT,o 7dal numbe

.o f persc nael a,ssi ucci j

4 per %diend uni +.

i VICE PRESIDENT viCE pg4ESMNT

& GENERAL GBANAGER

& QENERAL GRANAGER 91UCLE AR OPERATIO885 wCGTLE Pfl0KCT I

I I

l l

l MANAGER IBANAGER gguCLEAR IE g

g g

. = 'A o

ANA-R % /-A Vi n""Z"'iA

/ "'"""'a /,

/OT='c=y i

i p-----__

f NUCLEAR NUCLEAR l

SdTE GEpsERE MANAGER MMATW ENERING vocTLg mijgtggR I

I l

'"E"l

. EV ALUATIOf8 l NALY$18 MANA OPERATIoss MANAGER MANAGER 4

l l

l l

NUCLE AR NUCLEAR LICE NSfMG LICE NSteeG

..U,, ORT

..U,,oR, 3

S '"" 4 ti2393tgosi> -

grag.p gjQ h dMe ivs'ML44 45ss f

o__

A Vqtle bJjed wi% m;'; 4 g

r e S ick e rsc.y c -f Ldo y egrs.

._A m e nd._15_3/85 k 8

$E$RIC GENERATING PLANT

-TECHNICAL SUPPORT ORGANIZATION.

g GeorgiaPower UNITJ AND UNIT 2 FIGURE _l')._1.1--2_(SHEET 2 OF 2) 433-9 i

1

my-h(Ac kos(de E

VEGP-FSAR-Q Question 430.41 In FSAR table 9.5.8-1, you list the cembustion air intake filter, silencer, and flexible connections as being designed to I

" manufacturer's standard."

In addition, the diesel engine exhaust silencer, exhaust piping, and flexible connections are listed as being designed to " manufacturer's standard" or an ASTM standard.

This is not acceptable without further justification.

The staff normally requires the entire diesel engine combustion air intake and exhaust system to be designed, fabricated, and

(

installed in accordance with ASME Section III, Class 3 requirements.

Provide justification for noncompliance.

Response

The combustion air intake piping is designed to Seismic Category 1, ASME Section III, Class 3 requirements, and the project class designation is 013.

However, due to the high operating temperature of the engine exhaust, there are no acceptable materials available that will meet both ASME Section III, Class 3 requirements and the operating temperature requirements.

Therefore, the exhaust piping is designed in

{

accordance with ANSI B31.1 with stress allowables in accordance with ASME Section III.

The material used is ASME II SA-155, KC 70, Class 1 carbon steel, rolled and welded pipe.

The pipe is 1

manufactured from SA-515 Grade 70 plate.

Material allowable stresses are based on SA-515, Grade 70 at 900 *F and are found in ASME Code Section 1, Table PG-23.1, 1974 Edition with Addenda through Summer 1975.

Except for the temperature limits, the exhaust piping meets ASME Section III, Class 3 requirements.

Also, the exhaust piping is designed to Seismic Category 1 13 pg requirements, and the project class designation is 015.

Idh Te ustion ir filters and sil neers and the exhaust

}

~

I serf I si neer or cee the manufac rer's standard is means that ome mater.

e heavier than r comme

,ap lications To h l

(

and th the units rengthene i

aw ing, etc.

service, the t

qualify ese co onen i-ory/ made of hea ier l

manufactur s

ve provi de whic i

material tha standard r 'ial pro nd reinforced o

withstand e

eis as w as the oper 1

orces invcived.

Model an ys -

used t dete ine tha stress not

(-

exceed allowa e for the mat la sed.

The projec ss d

ation for the components i 015.

ue to the low cperating pressures for the combustion air intake and exhaust systems, the requirements to design these systems to completely meet ASME Section III, Class 3 requirements do not

(

add to the reliability of these systems.

n Amend. 7 5/84 Q430.41-1 Amend. 13 1/85

Insed A Question 430.41 Intake and exhaust system components (silencers, filters, and expansion joints) are manufactured in accordance with the guidelines as stated by the DEMA standards.

They are designed in accordance with seismic Category I requirements.

To qualify these non-ASME Code components for seismic Category 1 service, the manufacturers have provided equipment which is made of heavier material than standard commercial products, and reinforced to withstand the seismic as well as the operating i

forces involved.

ASME materials (SA-36 material for the intake filter and silencer, and SA-283-C material for the exhaust silencer) were used to fabricate these components.

Model analysis performed by the diesel generator manufacturer, Transamerica Delaval. Inc. (TDI) shows the maximum predicted stresses for these components are less than 70 percent of the minimum yield strength for each of the materials as allowed by ASME,Section III.

The project class designation for those components is 015.

These components are not available as ASME Section III, Class 3.

These components are identical to, or similar to those components used at other recently licensed plants.

In addition, J

2468t Q430.41-1

Eirclosu re. F VEGP-FSAR-Q Question 430.50 Describe your program for periodic testing and inservice inspection of the main steam stop and governor control valves, the combined reheat stop and intercept valves, and the steam extraction nonreturn valves.

Response

Georgia Power Company (GPC) will develop a turbine overspeed protection reliability program which will consist of a comprehensive program for turbine inspection and the maintenance, calibration, and testing of the turbine overspeed protection system.

This program will be designed to provide assurance that flaws or component failures in the overspeed sensing and tripping subsystems, main stop valves, control valves, combined intercept valves, and steam extraction check valves that might lead to an overspeed condition above the design overspeed rating will be detected and thus provide assurance of turbine integrity.

The requirements of SRP 10.2, as addressed in ESAR section 10.2.3.6 will be incorporated into 13 the turbine overspeed protection program.

This program will be

,(

similar to programs which have been implemented at the Callaway and Earley plants.

The program will be based on calculations by General Electric Company for missile generation probabilities and recommendations by General Electric Company regarding turbine inspection, valve maintenance, testing, inspection and calibration, operating e::perience at nuclear plants with similar 15 units, operating experience at other GPC plants, and regulatory guidance.

This program will be implemented via the VEGP Technical Specifications and will be submitted for review when the VEGP Technical Specifications are submitted.

A AA *aser+

to R3 c). 56

's s

Amend. 7 5/84 Amend. 13 1/85 Q430.50-1 Amend. 15 3/85

V

\\

' Insert to 430.50 The requirements for Valve Testing in the TOPRP will be:

Main Stop Valves Weekly (1)

Combined Intercept Valves Weekly (1)

Control Valves Manthly (2)

Extraction Nonreturn Valves Prior to each start-up (2)

The basis for the Main Stop, Combined Intercept and Control Valves' test frequency is General Electric Company's Technical information letter TIL-969. The test frequency for the Extraction Nonreturn Valves is based on the assumptions used in the General Electric Company's missile generation probability calculations.

To assure that the VEGP Program is comprehensive as well as practicable, an extensive review and evaluation of the General-Electric recommendations, the General Electric calculations for missile generation, pertinent sections of the FSAR, SRP (10.2) and VEGP DSER Sect. 3.5.1.3 was performed.

(1) Verification of operation by direct observation of valve movement will be performed monthly.

(2) Verification of operation by direct observation of valve movement will be performed at each test.

0185m s

-m-.7.-

v

---"-- - = ' * - - -

' ~ ~

Eulosa G

• ()t&ssh hem he'.

a,k E e e y I C e,hS$2SSmen

@PO(t R u 9, m a y m a p'ter:

l*s 4

s e 2 - M e-

'4-^

(PE

$"., 0, 0 c.r.d M..

o.co w ua i.eu amgenefra e rupture accident, and to monitor potential effl P felease paths. These monitor strapped on the m steam 11 s.

are classified as T A/ Category 1 and are s smically and environment yqualified). ey are designed to opera for a two (2) week duration lowin 4 Design Basis Accident.

a back-up

/

indication of a t rupture, the condenser a ejector and steam pa:kingexhaut[rradi s monitor (PE-15), ill continuously measure p

gaseous activity in the di arge. The

-15 monitor is classified as Ty tegory 2 and is not s s.

ally or environmentally qualified design basis accidents.

s, however, qualified for a mild environment.

3.2.1 Detennin t n of Ranges n ally, NRC Regulatory Guide 1.97, Rev - n 2, is the l

uling criterion on detennination he ranges f the PAMS airborne monitors. Typically (5) decade monit are preferred. When the rejqui e range is too wide for one

(

detector, there shaWbe = minimum one (1) decade overlap ktg. r=;n Of =1 t'f e :;te:t:r:.

(Sg3 [g Q{M 1

3.2.1.1 Plant Vent Monitors Table 2 of NRC Regulatory Guide 1.97, Revision 2 lists the range for a PWR plant vent monitor, with containment purge included, as 10-6 to 10 uti/cc. This range is acceptable for 4

the Vogtle plant, and accordingly, the PAMS plant vent l

radiogas monitor (PE-44C) has a range of 10-6 to 10 uCi/cc.

4 l

Since PE-44A & B are passive filter / cartridges, no range is assigned to them.

It is important from an ALARA aspect to assess the quantity of radioactivity that can build up on the collection cart-ridge as a function of time for various postulated plant t

1338e:ld/062584 3-18

radiological conditions.

Therefore, activity build-up versus time was calculated for the following conditions:

1) Nomal operation (assuming 0.12% failed fuel),

2) Release of the entire reactor coolant inventory (assuming 0.12% failed fuel) to the containment,

3) A postulated " TID-14844" release into the containment (i.e., assuming 50% of the core inventory of halogens, and 1% of the other fission products), and,

4) A postulated degraded core accident release into the containment (i.e., assuming 100% of the core inventory of the halogens, and 100% of cesium).

The calculational model assumed continuous containment purge l

at 5,000 cfm; the plant vent flow rate was assumed to be 150,000 cfm.

l The results of the buildup calculations for the above four postulated conditions are presented graphically in Figures 3-2 through 3-5, respectively, for I-131, Cs-137, Co-60, and Sr-90.

~

l The table below shows the calculated dose rate associated with these collection cartridges (assuming no shielding) at one foot from the cartridge for the four conditions cited above. These dose rates indicate the need for special l

shielding and/or handling techniques required to change the cartridge in the event of an accident condition.

l 1338e:1d/062584 3-19

r

.s DOSE RATE (mR/hr)

PE-44 A PE-44 B PARTICULATE COLLECTOR IODINE COLLECTOR COLLECTION TIE COLLECTION TIME CONDITION 30 MINUTES 1.0 EEK 30 MINUTES 1.0 WEEK Normal Operation 10-7 10-5 10-6 10-4 Reactor Coolant 10-4 10-3 10-1 100 Release TID-14844 Release 102 103 105 106 Degraded Core 104 105 105 106 Release Regulatory Guide 1.97, Revision 2, requires that the design envelope for the plant vent monitors for shielding, handling, and analytical purposes should assume 30 minutes of in-tegrated sampling time at sampler design flow, an average 5

concentration of 100 uCi/cc, and an average gamma photon energy of 0.5 MeV per disintegration. Based on these design parameters, the dose rate at one foot from an unshielded cartridge is about 800 R/hr, indicating that special shield-ing/ handling is required under such conditions. The collec-tion assembly includes 2 inches of lead shelding to minimize personnel dose if handling is required. However, if high activity has been observed through sampling, then a surface -

radiation survey should be made before handling is attempted.

,_. ~...... _

r= i n m....

Activi he secondar side main steam i ' monitored by PE-5[,B,Cand e purpose of th e monitors is 6 detect a steam nerator tu e (SGTR) acci t,

7

/ identifyJt affected generat

,and r

potential effluest' release path vi team side atm heric f

i

.-.. ___-... w.__..___

2 2.

1338e:ld/062584 3-20

.10-I I-131 10-2

~

CS-137 10-3 CO-60 8

uw 104 3

Y s

lg g

10-s D

0 SR-90 c

10-s 10-7

~

I 10-e 1

e i

i i

i i

i i

e i

i i e

i e

i 10-1 100 101 102 103

~

TIME (HOURS)

FIGURE 3-2 ACTIVITY ON PLANT VENT MONITOR ~ COLLECTION CARTRIDGE VS TIME FOR NORMAL OPERATION CONTAINMENT CONCENTRATION (BASED ON 0.12% FAILED FUEL)

o 8

10 I-131 102 1

10 8

t w

h 10 0

-CS-137 o

E to-c0-s0 5'

p E

10-2 10-3 SR-90 l

l 10

'I I

4 l

10-1 100 101 102 103 TIME (HOURS)

FIGURE 3-3 ACTIVITY ON PLANT VENT MONITOR COLLECTION CARTRIDGE VS TIME FOR RELEASE OF ENTIRE REACTOR COOLANT INVENTORY INTO CONTAINMENT (BASED ON 0.12% FAILED FUEL)

~*

0 10 I-131 s

10 i

7 10 S

j u

CS-137 y go, SR-80 o

'# r p

J E

i 10 CO-60 go-1 4

3 1

)

10 3

10-2 i

1

.I i

i i

i I 2

i i

. I 10-3 10 i

10-1 100 101 102 g03 i

TIME (HOURS)

"A FIGURE 3-4 ACTIVITY ON PLANT VENT MONITOR COLLECTION CARTRIDGE VS TIME FOR A POSTULATED RELEASE INTO CONTAINMENT (BASED ON TID-14844 SOURCE ASSUMPTIONS)

3 18 J

10

.e i

I-131 l

10s i

i i

j CS-137

)

los i

e t;

SR-90 w

d 107 0

3 10s s

~

i p

e 5

CO-60 10 10-1 104 10-2 1

103

'I I

' I 10-3 i

10-1 100 101 102 103

\\

TIME (HOURS) i FIGURE 3-5 ACTIVITY ON PLANT VENT MONITOR COLLECTION CARTRIDGE VS TIME FOR l

A POSTULATED RELEASE INTO CONTAINMENT i

(BASED ON A DEGRADED CORE ACCIDENT SOURCE TERM) i

~-

.~

d Eulosure N O

U VEGP-FSAR-Q t

Question 210.49 Provide a schedule for the completion of the program for O.

inservice testing of pumps and valves.

The program should contain any relief requests from ASME Section XI requirements together with the justification,for requesting relief.

Response

C.>

Due to the requirements of 10CFR 50.55 a (g), the code in effect for inservice testing of pumps and valves is indeterminable at this time cince 10 CFR 50.55 a (g) requires the use of approved ASME Section XI Code in effect 12 months prior to operating license date.

It i 2nti;ient d th t The IST programs will be4

mpleted for cuhmitt:1 to th: Nuclear R ;ul:tery C:: iccien

ppreni= tely 2 monthe prier te th: anticipated Operating lic;n : d:t: Of :: h unit.

He.2fer, there menual: 'till be suha.itted to the Nuclear R:gulatery Cermierien ne later than

-C deaths foll,;ing th; dat: Of rc:cipt of the oper2 ting licen %

for

h VZCr unit.

S: th: VECF rcepence to 2250.5 'bchind the 01, 1000 tah in Volum

24) for discussion cf the requent 13 1

O

'==== *='-

sub mihJ two months Prior to th e an+ ic.i p<ted J

operating hc.e.nsing afe_. The. Isr p rog ra ms u>ill clescri be b.

Pumps anc! valve.s to be tested, tes6 frequencie.s,and reNef O

re.guesesay mL ams+4r wo cc ceus repe sts.

O O

Amend. 12 12/84 Q210.49-1 Amend. 1.3 1/85