ML20236E496

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Rev 0 to Instrumentation & Control Design:Lack of Valves in Sampling & Water Quality Sys, TVA Employee Concerns Special Program Element Rept
ML20236E496
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/30/1986
From: Damon D
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20236E191 List:
References
229.6(B), 229.6(B)-R, 229.6(B)-R00, NUDOCS 8710290247
Download: ML20236E496 (15)
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Text

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1 IVAEMPLOYEECONCERNS REPORT NUMBER: 229.6(B)

SPECIAL PROGRAM

] f REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 0 TITLE: INSTRUMENTATION AND CONTROL-DESIGN I Lack of Valves in Sampling and Water  !

Quality System PAGE 1 0F 14 )

REASON FOR REVISION:

PREPARATION

( b4 31GNATORE i7 / 2.4 / e.6 DATE-r REVIEWS REVIEW C IM ~.

m l lllh ifh4l86

'DATE y ~ SIGNATORE

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SIGNATURE DATE CONCURRENCES ,

af10290247Ohb27 ADOCK O PDR CEG-H: DU bk /2-10-EL

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SIGNATilRE DATE SIGNATURE DATE APPROVED BY:

k l DATE ~ MANAGER OF NUCLEAR POWER DATE f ECSP MANAGER CONCURRENCE (FINAL REPORT ONLY)

=-. - -

rm TVA-F.MPLOYEE CONCERNS REPORT NUMBER: 229.6(B)  ;

SPECIAL PROGRAM ~

REVISION NUMBER: 0

" (' PAGE 2 0F 14

1. CHARACTERIZATION OF ISSUES:

Concern: Issues:

IN-85-348-003 a.- Water Quality Monitoring' System (43)

" Unit #1, Elev. 713' pipe chase may contain radioactive materials  :

System 43 Water Quality under certain accident conditions. l l

Monitoring - has the potential to contain radioactively con- b. Lack of isolation and drain valves E taminated water under postula- does not permit controlled effluent ted accident conditions. _ ..

removal.

System does not.contain isolation / drain valves for controlled draining of effluent under routine /emer-gency maintenance conditions."

2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES NO X i

Identified by Not Applicable

(- Date Not Applicable Documentation Identifiers:

None

3. DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT:

1 System 43 Pipe Chase 1

4 INTERVIEW FILES REVIEWED- 1 IN-85-348 No additional _information in working file. Expurgated file references N5RS Report 1-85-151-WBN; however, this report has not been prepared to date, per M. Tuell of TVA (Reference 7.h).

S. DOCUMENTS REVIEWED RELATED TO THE ELEMENT: )

See Appendix A.

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[' TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.6(B) i SPECIAL PROGRAM ,

REVISION NUMBER: 0 l PAGE 3 0F 14

6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?

See Appendix A.

7. LIST REQUESTS'FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.

See Appendix A.

8. EVALUATION PROCESS:
a. Established contaminant potential in System 43 " Sampling and 1 Water Quality Monitoring." -i
b. Reviewed flow diagrams to verify extraction capability of potentially contaminated portions of System 43 in pipe chase.
c. Traced System 43 potentially contaminated effluents to proper decontamination facility prior to release.
d. Determined potential exposures to operators taking such actions.-
9. DISCUSSION, FINDINGS, AND CONCLUSIONS:

Chronology:

06/05: TVA receives employee concern on Watts Bar 05/86: WBN Element Report 229.6 finds no evidence to {

substantiate concern Discussion:

9.1 INTRODUCTION

The CI is concerned about "the potential [of System 43] to contain radioactively contaminated water under postulated accident conditions." This concern, in conjunction with a presumed absence of " isolation / drain valves for controlled draining of effluent," indicates a materials handling issue i that does not adequately consider the potential personnel exposure. The concern is quite specific that this condition

( prevails in "the [WBN] Elev. 713' pipe chase." l 06150 - (12/24/86)

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. i TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.6(B) )

SPECIAL PROGRAM REVISION NUMBER: 0  ;

PAGE 4 0F 14 9.2 GENERIC APPLICABILITY Although raised for Watts Bar Unit 1, Concern IN-85-348-003 is applicable to SQN because the primary and secondary j process systems, the sampling and water quality system ,

(System 43), and the physical layout at SQN are essentially I the same _as those at WBN. l l

9.3 SCOPE l Concern IN-85-348-003 is directed to System 43 piping in the 1 pipe chase at WBN Eles. 713'. Because the concern has t generic applicability, this report considers System 43 piping in the pipe chase at the equivalent elevation at SQN, Elev.

690'. The report interprets " pipe chase" to include the adjacent hot sample room. This room contains the major items of System 43 equipment which handle materials with i radioactive inventory during normal plant operation and.is' - t the destination of the System 43 piping in the pipe chase which carries radioactive inventory. Because the concern is specifically directed to potentially radioactive System 43

, piping in the pipe chase and because this piping is normally l the most radioactive System 43 piping, this report does not consider System 43 piping in other areas or elevations in the l Auxiliary Building or in the Turbine Building. l t

9.4 SYSTEM 43 DESCRIPTION

. The System 43 design basis is established in Section 9.3.2.1 of the FSAR: ,

"The sampling system is designed to obtain j samples from tne various process systems in )'

each of the two units. The samples are obtained in the titration room, hot sample room, and locally (grab samples) for  ;

laboratory analysis. This system has no safety-related functions. During a Loss-of-Coolant Accident (LOCA), this system is isolated at the containment boundary.

Sampling system dischargers are designed to limit flows under normal operation and i anticipated malfunctions or failure to preclude any fission product release in excess of the limits as stated in 10CFR20" (App. A, 5.b, Section 9.3.2.1).

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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.6(B)

SPECIAL PROGRAM REVISION NUMBER: 0

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PAGE 5 0F 14 Samples are taken by extracting a small quantity of process fluid at the sample points. Samples are-then transported through the System 43 piping to the appropriate System 43 equipment. At this equipment, the samples are either analyzed or isolated in a container (grab samples) for-subsequent laboratory analysis.

According to Section 9.3.2.2 of the FSAR, samples from primary process systems, which are radioactive, are routed to the cubicles in the hot sample room:

" . . . for automatic analysi of such variables as pH and conductivity. These variables are indicated in the hot sample room and recorded in the titration room, except for evaporator condensate demineralized pH samples which are recorded in the hot sample room.

Any variable exceeding established limits is annunciated in the titration room.

Radioactive grab samples are taken to the radiocheinical laboratory for analysis.

( " Boron concentration monitors (one per unit) are also located in the hot sample room. The RCS letdown is sampled continuously by the boron concentration monitor, indicated in the hot sample room, and recnrded in the main control room. . . .

"The Gas Analyzer System [(one per plant) is also located in the hot sample room and]

sequentially monitors 20 points in the Waste Disposal System and CVCS for hydrogen and oxygen concentrations in a nitrogen atmosp here. The concentrations are indicated, recorded, and alarmed at the analyzer" (App. A, 5.b, Section 9.3.2.2).

9.5 PIPE CHASE The pipe chase is identified on SQU Drawing 47W600-204. The pipe chase is an irregularly shaped room which lies adjacent to the hot sample room, and abuts the outside wall of the Reactor Cuilding. Piping which carries samples with radioactive inventory from the primary process systems within the containment to the sampling

< system equipment in the not sample room passes through the pipe chase.

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TVA EMPLOYEE CONCERNS . REPORT NUMBER: 229.6(B)

SPECIAL PROGRAM REVISION NUMBER: 0

( PAGE 6 0F 14 Access to the pipe chase is from the hot sample room. Access to the hot sample room is through locked doors. Both rooms are under decontamination control and, therefore, personnel in these rooms will be subject to health physics procedures.

9.6 SAMPLING METHODS The FSAR explains the operation of the sampling system:

"The sampling system is operated manually throughout the full range of power operations. . . . Prior to collecting a sample, each sample line is purged according to sample line length and diameter to ensure a representative sample is obtained. The sample volume is dependent upon the chemical analysis to be run" (App. A, 5.b, Section 9.3.2.2).

The sources of the samples which are sampled in the hot sample room are tabulated in Appendix B.

.(.

All samples are taken behind shatterproof glass windows. All cubicles are hooded and equipped with f ans which vent through HEPA filters. Consequently, any radioactive gases released from the sample stream will not be vented into the hot sample room when the hoods are opened to remove the samples.

Cubicles lA and 2A, which contain the most radioactive samples, have 2 inches of lead shielding and provisions to take samples in lead lined stainless steel cylinders.

Valving is included for bypass blowdown of sample lines in Cubicles lA and 2A. In other cubicles, sample lines are blown down directly into the sample sinks.

9.7 ISOLATION CAPABILITY Section 9.3.2.2 of the FSAR defines the requirements for isolation valves:

"All sample lines originating within containment have air-operated isolation valves near the sample point and inside and outside containment for containment isolation. All sample lines originating outside containment have manual isolation valves, except the volume control tank vent and RHR miniflow i'

lines which have air-operated isolation valves" (App. A, 5.b, Section 9.3.2.2).

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< SPECIAL' PROGRAM- a g,

REVISION NUMBER: LO ~

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kI PAGE.7 0F.14 K;

q; U g ' Isolation,valv'es in sample. lines originating

, outside the containment are also located near the . . .

sample point.

The design' drawings were re' viewed ;and the isolation valves;for each sample ~ line were. identified. ' These valves are listed.in Appendix B.; This review established that the design drawings reflect the FSAR . requirements'. In . addition, the. design drawings show isolation (block). valves at the inlet of L each sampic 1.ine.to the sample cubicles, boron monitors, and gas analyzer. > Additional isolation : ,

valves are provided in cubicles 1A and 2A and at

, the gas analyzer to permit removal .of sample cylinders. - The presence of the isolation valves shown on the design drawings has been confirmed by a walkdown (App. A, 7.j).

9.8 DRAINAGE CAPABILITY-System:43 piping in the pipe chase is. drained through the 1 sample . cubicles, boron monitors, and ~ gas analyzer in the hot sample room. Each module of cubicles 1A and 2A includes piping and valves which permit draining the sample _ line both arourd ~and through the . sample cylinder. The modules which handle primary system samples are drained-to.the CVCS volume control' tank which permits recycling material not removed from the system in a sample cylinder. These modules are identified in Appendix.B. The other modules of cubicles 1A and 2A are drained to the-building drainage system.- Eac h '

module of cubicles 1B, 28, and lC includes piping and valves which permit draining the sample line into the cubicle sink.

Each cubicle includes a sink which is inside the hooded and vented portion of the cubicle. Fluid which is discharged or spills into the sink flows by gravity to the building drainage system. The isolation capability of the building drainage system is described'in SQN Element Report 229.2, which concludes that "potentially radioactive inventory will not be released [from the buildin proper monitoring and treatment [g drainage and] the system] without potential exposure of operating personnel [to drainage with radioactive inventory] is consistent with . . . accepted health physics practices" (App. A, 5.g).

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'VA EMPLOYEE CONCERNS REPORT NUMBER: 229.6(B)

SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 8 0F 14 9.9 PERSONNEL EXPOSURE

-Since the sampling system handles samples of process fluids i~ with radioactive inventory and is required to conform to 10CFR20, the following precautions have been taken to protect personnel from exposure to radiation:

o "All sample lines . . . have . . . isolation valves near the sample point" (App. A, 5.b, Section 9.3.2.3) o " Sample lines from the RCS hotlegs contain a delay coil to provide 40-second sample transit time within containment . . . (allows for decay [of] N-16)" (App. A, 5.b, Section 9.3.2.3); Tl/2 = 7.1 seconds o "All sample lines originating within containment have air-operated isolation valves . . . inside and outside containment for containment isolation" (App. A, 5.b, Section 9.3.2.3) o " Sample lines from RCS hotlegs . . . [have] a 20-second l transit time from containment to hot sample cubicles

(- (allows for decay [of] N-16)" (App. A, 5.b, Section 4.3.2.3) o No System 43 equipment (other than piping) is located in the pipe chase o Isolation (block) valves which meet the ASME Section III Code are provided at the panel connections o " Cubicles lA and 2A have a 2-inch lead shield behind the front plate of the cubicles" (App. A, 5.b, Section 9.3.2.3) o "2-inch lead shielded [ stainless steel] sample cylinders are available for use" in cubicles lA and 2A (App. A, )

5.b, Section 9.3.2.3) o All cubicles are designed to permit collection of a sample behind a shatterproof glass window" (App. A, 5.b, Section 9.3.2.3) o "All cubicles have individual exhaust hoods and fans equipped with HEPA filters to ensure that any leakage other than noble gases will remain in the cubicle sink area" (App. A, 5.b, Section 9.3.2.3) l 0615D - (12/24/86)

TVA EMPLOYEE. CONCERNS REPORT NUMBER:- 229.6(B)

SPECIAL PROGRAM REVISION NUMBER: 0

. (" PAGE 9 0F 14 o Valves are provided to control discharge of sample fluid l from the panels o Panel drains are connected to the building drainage'  !

system (except for those modules which are drained to the CVCS volume control tank) o Access to the hot sample room and pipe chase is controlled by locked doors  !

o Access to the hot sample room and pipe chase is under administrative health physics control In addition, "all sample lines have the required [ pressure, temperature, and flow] indicators, pressure throttling valves, [and] heat exchangers . . . to ensure plant operator safety when collecting samples" -(App. A, 5.b, Section 9.3.2.3).

The FSAR states that " sampling system dischargers are designed to limit flows under normal operation and anticipated malfunctions or failure to preclude any fission I product' release in excess of the limits as stated in 10CFR20" and that " sample lines outside reactor containment [are] not considered hazardous because of their limited flow and nonessential nature." SQN Element Report 229.2 shows that l

" backflow of potentially radioactive drainage into floor drains is unlikely" and " venting of . . . dissolved gasee that would be radioactive . , presents an insignificant exposure issue."

4 Findings: I System 43 piping in the pipe chase was found to contain  !

o radioactive material not only during postulated accident conditions but, by design intent, durirg normal plant operating conditions.

o System 43 piping was found to contain isolation valves.

These valves are not located in the pipe chase.

o System 43 piping was found to contain valves that con' trol the draining of effluent under both operating and maintenance conditions. These valves are not located in the pipe chase.

o Additional precautions were found to be taken to reduce personnel expnsure to radioactivity to levels below the limits of 10CFR20.

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-kVAEMPLOYEECONCERNS: -REPORT NUMBER': ~ 229. 6('B ) '

SPECIAL PROGRAM "

REVISION NUMBER: 0.

'PAGE.10 0F 14. <

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Conclusions:

' Although the presence of radioactive material in System'43 piping' l fin the~ pipe chase'is confirmed. such presence is by design intent. j

-Sufficient valves are present'for isolation of; System'43 equipment i and piping and for controlled draining.of System'43~ effluent.under routine'and'emergencyLconditions. Precautions:have been.taken in the design and location of System.43. equipment and piping to -

maintain personnel exposure levels to radioactivity,within 10CFR20 limits. . The concerncis not valid.

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. E10. CORRECTIVE' ACTION:

'No corrective action is required.

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'TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.6(B)

SPECIAL PROGRAM REVISION NUMBER: 0 i PAGE 11 0F 14 APPENDIX A

5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
a. TVA Employee Concern Assignment Requests:

i Concern IN-85-348-003

b. TVA, Sequoyah Nuclear Plant, Final Safety Analysis Report, j i.hrough Amendment 3 l
c. TVA Specification 1713 for Water Quality Sampling, Analysis, Instrumentation, and Control Systems for SQN 1 and 2 and WBN 1 and 2, No. 38-83574
d. TVA Drawings

i 478601-43-0 through -42 Instrument Tabulation 1 47W343-1 through -5 Sampling & Water Quality System 47W620-1 through -7 Water Quality and Sampling System 47W625-1 through -22 Radiation Sampling System 47W610-43-1 through -7 Control Diagram, Sampling & Water

( Quality System 1 47W809-1 through -2 Flow Diagram i

e. 10CFR20, Standard for Protection Against Radiation i
f. Watts Bar Nuclear Plant, Engineering Related Employee l- Concerns Subcategory / Element Review Sheets, Subcategory 229, Element 229.6, (05/23/86)
g. TVA Employee Concerns S ecial Program, Sequoyah Element Report 229.2,(12/02/86
6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
a. 10CFR20
b. SQN FSAR Section 9.3.2 l

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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.6(B)

SPECIAL PROGRAM REVISION NUMBER: 0 Y

PAGE 12 0F 14

7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
a. Telecon Langtry, Bechtel, to Ibanez, Bechtel, Request for Drawings (12/03/86); reply TTB-164-5
b. Telecon Langtry, Bechtel, to Ibanez, Bechtel, Request for FSAR Sections and Drawings (12/04/86); reply TTB-166-5, TTB-167-4 :J
c. Telecon Langtry, Bechtel, to Ibanez, Bechtel, Request for DC, DG (not issued), and Drawings (12/08/86); reply TTB-168-3,12, TTB-169-8
d. Telecon Langtry, Bechtel, to Ibanez, Bechtel, Request for Drawings (12/12/86); reply TTB-171-2
e. Telecon Langtry, Bechtel, to Ibanez, Bechtel, Request for System Description (not available) and NSRS Report (12/15/86)

(See item 7.h)

f. Telecon Langtry, Bect.tel, to H. A. Mahlman, TVA, Discussion

(- of Concern, Proposed Report, Drainage to Volume Control Tank (12/15/86)

g. Telecon Langtry, Bechtel, to Ibanez, Bechtel, Request for Drawings (12/16/86); reply TTB-174-4
h. Telecon, Langtry, Bechtel, to M. Tuell, TVA, Request for NSRS Report I-85-151-WBN; report not yet prepared (12/17/86)
1. Telecon, Langtry, Bechtel, to H. A. Mahlman, TVA, Discussion {

of Limits of Proposed Report (12/17/86)

j. Bechtel memo, E. Croft to 0. L. Damon, Report of SQN Walkdown,(12/18/86) l t

1 l 06150 - (12/24/86) l L__ _ _ __ _ _ .__ _ _ _ _ _ _

TVA EMPLOYEE CONCERNS j (ENDIX B SPECIAL PROGRAM OLING PANELS

'f SAMPLE ROOM-Cy16

" Hot" Outlet Samp1<.r Bg6 Description Drawing Inlet inel ~ Elev - Col Hot Leg Loop 1 Yes) Vol Control Tank Cylinder YQ 690 wAS Cubicle 1A (Panel 1-L-231) SQN 47W343-21.

Hot. Leg Loop 3 Yes)

2. ' Pressurizer Liquid Yes Vol Control Tank Cylinder b
3. Pressurizer Gas Yes Vol Control Tank Cylinder YG
4. Vol Control Vent Yes Vent Header Cylinder Q
5. Inlet Mix Bed Demin Yes) Vol Control Tank Cylinder Y'
6. Outlet Mix Bed Demin Yes)
7. Inlet Ion Exchange Yes Drain kylinder Yc
8. Outlet Ion Exchange Yes Drain tylinder Y:
9. CVCS Holdup Tank Recirc Yes Drain Cylinder Yc
10. Tritiated Dr Tank Recirc Yes Drain Cy1'pder Yc Vol control Tank 690 wall Cubicle 2A (Panel 2-L-231)

Outlet Boric Acid Blend No Drain via sink Valve C3 690 wAS Cubicle IB (Panel 1-L-232) SON 47W343-4 1. Drain via sink Valve Q

2. Accum Tank Hdr Outlet No
3. Contmt Drain Sump 1 Yes) Drain via sink Valve R

) Contmt Drain Sump 2 Yes)

4. Accum Tanks 1 No)

Accum Tanks 2 90) Drain via sink Valve 9 Accum Tanks 3 No) tecum Tanks 4 No)

5. Steam Gen Blowdown 1 Yes)
6. Steam Gen Blowdown 2 Yes) Drain via sink Valve C
7. Steam Gas Blowdown 3 Yes)~
8. Steam Gas Blowdown 4 Yes) l 690 wall Cubicle 2B (Panel 2-L-232)

Upstr Boron In.1 Tank 1 Yes Drain via sink Valve f

690 wA5 Cubicle 1C (Panel 0-L-233) SON 47W343-3 1. Drain via sink Valve f
2. Dnstr Boron inj Tank 1 Yes Drain via sink Valve (
3. Lystr Boron Inj Tank 2 Yes Cnstr Boron inj Tank 2 Yes Drain via sink valve i 4.

Yes Drain via sink Valve i

5. Upstr RHR Exch 1A Yes Drain via sink Valve
6. Upstr RHR Exch IB Drain via sink Valve

- 7. Upstr RHR Exch 2A Yes Drain via sink Valve

8. Upstr RHR Exch 2B Yes Drain via siak Valve
9. Wte Evap Cnds Fitr Inlet Yes Drain via sink Valve
10. kte Evap Demin Outlet Yes
11. Before Evap Cnds Demin 1 Yes) Drain via sink Valve
12. Af ter Evap Cnds Domin 1 Yes)
13. Before Evap Cnds Demin 2 Yes) Drain via sink Valve
14. After Evap Cnds Demin 2 Yes)
15. SIS Pump Refueling Wtr 2 Yes Drain via sink- Valve
16. SIS Pump Refueling Wtr 1 Yes Drain via sink Valve
17. RER Pp Min F1 Line 1A Yes) Drain via sink. Valve RFR Pp Min F1 Line 2B Yes) 0
18. RIR Pp Min F1 Line 2A Yes) Drainviasink'QJalve l

RtR Pp Min F1 Line 2B Yes)

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['l REPORT NUMBER: 229.6(B)

REVISION NUMBER: O PAGE l' 0F 14 i l I'

'! Cylinder Root Valve Containment Valves isolation

. Sampler Bypass Drawing Valve No Inside Outside valve Coments k Cylinder Yes 47W465-5 Oct A7 W 1-8056 FCV-43-22 FCV-43-23 FCV-43-20 l 47W465-6 Det B7 W 1-8077 FCV-43-22 FCV-43-23 FCV-43-21 k Cylindxr Yes 47W465-2 Sec C2 W 1-8080 FCV-43-11 FCV-43-12 FCV-43-10

k Cylindir Yes AtW465-2 Sec A2 W 1-8078 FCV-43-02 FCV-43-03 FCV-43-01 Cylinder No 47W406-2 See C2 'W 1-8373 FCV-43-05 k'[ylinder Yes 47W406-2 uA5. All W 1-8372 j- 47W406-2 W 1-8372 Cylinder Yes 47W555-5 Mk 258 i Cylinder Yes 47W555-14 A14 Mk 307 Cylinder Yes 47W555-5 Mk 258 ylinder Yes 47W560-7 C7 1-9219

.k 47W406-2 W 1-8372 Same as 1A

, Valve N/A' 47W555-18 1-84 31 Valve N/A 47W625-2 W 1-8962  ;

Valve N/A 47W625-13 Mk 44  :

47W625-13 Mk 44 l 47W435-6 W 1-8933A FCV-43-34 FCV-43-35 FCV-43-30

_47W435-7 W 1-8933B FCV-43-34 FCV-43-35 FCV-43-31 Valve N/A 47W435-8 W 1-8933C FCV-43-34 FCV-43-35 FCV-43-32 47W435-9 W 1-89330 FCV-43-34 FCV-43-35 FCV-43-33 47W400-7 Mk 329 FCV-43-55 47W400-7 Mk 329 FCV-43-58

~ Valve N/A 47W400-7 Mk 329 FCV-43-61 47W400-7 Mk 329 FCV-43-64 Same as 18 l

Valve N/A 47W435-4 Sec 04 W 1-8910 Valve N/A 47W435-4 Sec A4 W 1-8908 Valve N/A 47W435-4 Sec D4 W 2-8910 i

Valve N/A 4 W435-4 Sec B4 W 2-8908 Valve S/A 47W432-1 W 1-8725A Valve N/A 4N432-1 W 1-8725B Valve N/A 47W432-1 W 1-8725C Valve N/A 4N432-1 W 1-87258 Valve N/A 47W560-9 Sec A9 9277A Valve N/A 47W560-14 Sec Cl4 92778 47W555-15 W 1-8201 Valve N/A 47W555-15 W 1-8214 47W555-15 W 2-8201 Valve N/A 47W555-15 W 2-0214 Valve N/A 47W435-1 W 2 8932 Valve N/A 47W435-1 W 1-8932 47W432-1 P1690 Mk 308 ~ FCV-43-70

' Valve N/A 47W432-1 P1690 Mk 308 FCV-43-71 47W432-1 PI 690 Mk 308 FCV-43-67 Velve N/A FCV-43-69 47W432-1 P1690 Mk 308 I

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REPORT NUMBER: 229.6(B)

REVISION NUMBER: O PAGE 14 0F 14

,- Cylinder Root Valve Containment Valves isolation Sampler Bypass Drawing Valve No inside Outside' Valve Comments l

47W406-4 Mk 307 -- --

FCV-43-76 l 47W406-9 3/4 T 68 FCV-43-75 FCV-43-77  !

47W406-2 W 1-8372

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1 Same as 1-C7

'I 47W406-2 Sec C2 W 1-8414

,y gj' 47W560-13 Sec A13 9302 h 47W465-2 Sec A2 W 1-8092 IFCV68308 1FCV68307

?"5 1k . 47W560-16 7 g fE 47W5f5-6 Sec A6  ?

L. .. ..

.I Iinder Yes 47W555-6 Sec A6  ? 1 l .o 47W560-16  ? from Trap j'y M fN; 47W406-2 Sec C2 W 2-8414 4Q 47W465-2 Sec A2 W 2-8092 2FCV68308 2FCV68307 h

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' TVA EMPLOYEE CONCERNS

  • : APPENDIX B; h SPECIAL PROGRAM -

c SAMPLING PANELS 1

. HOT SAMPLE ROOM :

Drawing ' Inlet " Hot" Outlet Panel Elev' Col -Description )

Dnstr Ltdn Heat Exchgr Yes) -(Sampie Return : l' SON 47W610

' 1-C7. . 690 - wA5 Boron Monitor. 1 'Dnstr Excess Ltdn HE. Yes) .(Drain .

Sample Return (2-C7'.690. wall Boron' Monitor A8 . 690 . . wA9 Gas Analyzer Pane);. Customline 1. Spare (Capped) -)

Control. 2. CVCS Vol. Control Tk 3 Yes)

(Panel 0-L-206) Spent Resin Stg Tk. .Yes) 4918-1, 3.

4. RCS Press' Relief Tk 1- Yes)

'5.: WDS Gas Decay Tk Auto Yes)

- 6.- CVCS Holdup Tk 1 Yes)

7. Spare (Capped)' -).

CVCS Holdup Tk 2 Yes)J(SampleVent" 8.

9. WDS Gas Decay ik Man Yes) (Drain
10. Spare'(Capped) .)

-11. Spare (Capped) -):

12. CVCS Vol Control Tk 2 Yes) -

.13. RCS Press Relief Tk 2 Yes)

14. Spare (Capped) )

15.' . Spare (Capped)- -)

16. ' Spare (Capped) -).

Nol,

17. Purge Air

.18. Zero Gas No ) Calib Gas vent

19. Span Gas No )

N/A = Not Applicable i

i l:[

I

.J

_ 2:_.1.__ . .. __ _ _ . _ _ . _ . _ . . _ . _ . _ . . _ _ _ . . _ _ . . . _ _ . . _ _ _ _ . _ _ _ - . _ . . . _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ .

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