ML20245K302

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Summary of 890615 Meeting W/Util in Rockville,Md Re Proposed Tech Spec Change 251 Dealing W/Table 3.7.A, Primary Containment Isolation Valves
ML20245K302
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/22/1989
From: Fields M
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-00080, TAC-00081, TAC-00082, TAC-80, TAC-81, TAC-82, NUDOCS 8907050086
Download: ML20245K302 (40)
v • d • e


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UNITED STATES 1

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,, .* i .E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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June 22, 1989 Docket Nos. 50-259, 50-260 dnd 50-296 1

l APPLICANT: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Plant, Units 1, 2 and 3

SUBJECT:

SUMMARY

OF MEETING WITH TVA ON JUNE 15, 1989 CONCERNING PROPOSED '

TECHNICAL SPECIFICATION CHANGE 251 DEALING WITH TABLE 3.7.A.,

" PRIMARY CONTAINMENT ISOLATION VALVES" (TAC 00080,00081,00082)

The meeting was held in Conference Room 6-B-11 at.One White Flint North in Rockville, Maryland. The attendance roster is Enclosure 1 and the handouts from TVA are Enclosure 2.

TVA explained their rationale for the changes to Table 3.7. A (refer to Enclosure 2). 1 The staff requested that TVA write a letter to the NRC in order to place the i hondout diagrams on the docket together with responses to requests for informa-tion listed below:

1. Complete the table, " Data Sheet for Isolation Valve Penetrations Of Con-tainment" Enclosure 3, by listing the data requested for each containment penetration.
2. For the reactor building closed cooling water system, provide documentation as to how the closed loop inside containment meets the intent of the applicable SRP criteria.
3. The staff needs a description of the means by which containment isoldtion is assured for isolation valves in non-essential systems that do not receive isolation signals.

The valves involved are:

43-28 A&B 43-29 A&B 84-19 84-8 A, B, C and D

4. Provide information supporting TVA's position that valves 71-39 and 73-44 are the preferred containment isolation valves to the motor operated valves that were located outside valves 71-39 and 73-44 q f

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5. Describe how the design and test features of the residual ' heat removal' .;

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suction flow system 'outside containment meet the ' containment isolation' requirements of Appendix.A and leak test requirements of.. Appendix J to- ~

10 CFR, Part 50. e h ,

Original signed'by 4

-" .Mel B. Fields,. Project Manager .

.0ffice of Nuclear Reactor Regulation

Enclosures:

1. Attendance List
2. Handouts: '

y 3. Table 3.7.A- ,

cc w/ enclosures:

See next page-o.

DISTRIBUTION

. Docket File NRC PDR' Local PDR. .

Those on Attached. List 0FC :NRR:TVA/LA :NRR:IVA/PM :HRR: VA/PM : ' fir:TVA/PM :TVA:AD/P  :  :

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PHear  :  :
6/W89 :6/h89 :6/@89  :  :

DATE:6/M89 :6/2?/89 0FFICIAL RECORD COPY

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  • Mr. Oliver Ol .Kingsley, Jr.  !

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General Counsel- Chairman, Limestone County Comission >

Tennessee Valley Aut.hority P. 0.. Box 188 400 West Summit Hill ~ Drive Athens, Alabama 35611 ET llB 33H Knoxville, Tennessee 37902 Claude Earl Fox, M.D. i State Health Officer- 4 Mr. F. L. Moreadith State Department of Public Health. j Vice President, Nuclear Engineering State Office Building j Tennessee Valley Authority Montgomery, Alabama 36130 j 400 West Sumit Hill Drive l WT 12A 12A Regional Administrator, Region 11  !

Knoxville, Tennessee 37902 U.S. Nuclear Regulatory Comission 101 Marietta Street, N.W. 1 Dr. Mark 0. Medford Atlanta, Georgia 30323 .

Vice President and Nuclear .

Technical Director. Mr. Danny Carpenter Tennessee Valley Authority Senior Resident Inspector 6N 38A Lookout Place Browns Ferry Nuclear Plant Chattanooga, Tennessee 37402-2801 U.S. Nuclear Regulatory Comission Poute 12, Box 637 Manager, Nuclear Licensing Athens. Alabama 35611 and Regulatory Affairs Ternessee Valley Authority Dr. Henry Myers, Science Advisor SN 1578 Loukout Place Comittee on Interior Chattanooga, Tennessee 37402-2801 and Insular Affairs U.S. House of Representatives Mr. O. c. Zeringue Washington, D.C. 20515 Site Director Browns Ferry Nuclear Plant Tennessee Yelley Authority fenressee h.lley Authority Rockville Office P. O. Box 2000 11921 Rockville Pike Decatur, Alabama -35602 Suite 402 Rockville, Maryland 20852 Mr. P. Corier Site Licensing Manager Mr. Oliver D. Kingsley, Jr.

Browns Ferry Nuclear Plant Senior Vice President, Nuclear Power j Tennessee Valley Authority Tennessee Valley Authority '

P. O. Box 2000 6N 38A Lookout Place Deutur, Alabama 35602 1101 Market Street Chattanooga, Tennessee 37402-2801 Mr. G. Campbell Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, Alabama 35602

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Meeting- Summary, Memoranda for Trip Reports or Site Visits **

bMEEN)0RJ~.

NRC PDR; Local PDR:

Projects Reading 0 .ADSP. Reading J.'Sniezek

'O.'Crutchfield.

B.'D.-Liaw l5. Black R. Pierson G. Gears D. Moran T. Daniels

'N.-Markisohn.

M. Fields P. Hearn M. Simms B. Wilson, Region II OGC ACRS (10)

GPA/CA(M.Callahan)(3)***

E. Jordan B. Grtmes P. Gwynn J. Scarborough

? G. Marcus-L. Norrholm C. Ader J. Gray .

R. Borchardt BFN Rdg. File

  • cc: Licensee / Applicant & Service List-Df%f f i I i I

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,j,.. ' ENCLOSURE 1 p MEETING PARTICIPANTS Name Affiliation Steve Frost TVA

-King.Turnbull TVA

-l Jimmy Pawlik TVA

' Steve Rowe' TVA L- David H 'Moran- ADSP Peter C Hearn ADSP Me11 Fields- ADSP Kevin Mulling TVA Creighton Miller TVA Fred Nilsen TVA

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L~*; t-ENCi.05URE 2 p,. ,

AGENDA j

' TVA/NRC MEETING - June 15, 1989 l:

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INTRODUCTION -FROST HISTORY- ,, . MULLING IMPLEMENTATION SCHEDULE MULLING 1

T.S. AMENDMENT ..

MULLING

' DESIGN BASES TURNBULL WORKING GROUP ,;

ALL 1,

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BROWNS FERRY APPENDIX J HISTORY

-JULY 7,1966 - BF UNIT 2 OL APPLICATION FILED FEBRUARY 14,1973 - 10 CFR 50 APPENDIX J PUBLISHED JUNE 28,1974 - BF UNIT 2 LICENSE ISSUED AUGUST 4,1975 - NRC REQUEST FOR TVA'S PLANNED ACTIONS AND SCHEDULE TO ATTAIN CONFORMZNCE WITH APPENDIX J SEPTEMBER 9,1975; OCTOBER 10, 1975; JANUARY 15, 1976; FEBRUARY 26,1976; JULY 8,1977 - TVA LETTERS TO NRC WITH EXEMPTION REQUESTS SEPTEMBER 20,1984 - TVA LETTER OF CLARIFICATION OCTOBER 24,1984 - NRC RULINp ON APPENDIX J EXEMPTION REQUESTS AND SAFETY EVALUATION - DENIES RBCCW EXEMPTION MARCH 15,1985 - TVA IDENTIFIES UNTESTED VALVE BONNETS MAY 10,1985 - TVA IDENTIFIES MODIFICATIONS FOR CONFORMANCE WITH APPENDIX J AND SCHEDULE.

AUGUST 28,1985 - TVA/NRC MEETING IN BETHESDA PROVIDING NRC WITH PRESENTATION OF PLAN TO UPGRADE APPENDIX J PROGRAM 4

NOVEMBER 8,1985 - EXEMPTION REQUEST SUBMITTED FEBRUARY 21,1986 - TVA LETTER TRANSMITTING AEETING  ;

MINUTES AND A CHARACTERIZATION OF RHR AND CS SYSTEMS AUGUST 2,1988 - T.S. AMENDMENT SENT TO NRC UPDATING AND CONSOLIDATING THE PRIMARY CONTAINMENT ISOLATION VALVE TABLES -1 l

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ORIGINAL IMPLEMENTATION SCHEDULE I

COMPLETED ITEMS 71-17/18 RCIC PUMP SUCTION 71-34/547 RCIC PUMP MINIFLOW 73-26/27 HPCI PUMP SUCTION 73-30/559 HPCI PUMP MINIFLOW 71-14  ;

RCIC TURBINE EXHAUST (BONNET) 73-23 HPCI TURBINE EXHAUST (BONNET) 71-32 RCIC VACUUM PUMP DISCHARGE (BONNET), UNIT 3 ONLY 73-24 HPCI TURBINE EXHAUST DRAIN (BONNET), UNIT 3 ONLY ITEMS TO BE COMPLETED PRIOR TO STARTUP

)

U I AND U-3 ALL IDENTIFIED PROBLEMS U-2 U2 74-58 RHR CONTAINMENT SPRAY (BONNET)

U-2 74-792/804 I'SC HEAD TANK TIE IN TO RHR LOOP 1 U-2 74-802/803 PSC HEAD TANK TIE IN TO RHR LOOP 2 U-2 75-606/607 PSC HEAD TANK TIE IN TO CS LOOP 1 75-609/610 PSC HEAD TANK TIE IN TO CS LOOP 2 U-2 RHR AND CS SYSTEM WALKDOWNS U-2 U-2 71-32 RCIC VACUUM PUMP DISCHARGE (BONNET) 73-24 HPCI TURBINE EXHAUST DRAIN (BONNET)

ITEMS TO BE IMPLEMENTED BY U2 C7 STARTUP 70-47/506 RBCCW SUPPLY AND RETURN 84-8 A/B /C/D CAD VALVES (ARE CURRENTLY TYPE C TESTED, BUT

)

IN THE REVERSE DIRECTION)12-742 )

71-34 AUX BOILER TIE IN TO RCIC (BONNET ONLY) 1 RCIC PUMP MINIFLOW (BONNET ONLY AND ORIFACE) 73-30 HPCI PUMP MINIFLOW (BONNET ONLY) 74-103/103 RHR VENT RETURN 74-119/120 RHR VENTRETURN U2 WILL BE TYPE A TESTED THIS OUTAGE. ALL OF THE ABOVE WILL BE TYPE A TESTED PRIOR TO STARTUP, EXCEPT RBCCW VALVES 70-47/506.

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CURRENT STATUS Previously identified modifications are COMPLETE.

Appendix J program implemented.

i T.S. amendment being revie.wed by NRC.

FSAR update is in drafting. l s

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. LIST OFTABLES i

f 3.7. A PRIMARY. CONTAINMENT ISOLATION. VALVES 3.7.B .

TESTABLE PENETRATIONS WITH DOUBLE O-RINO SEALS i

3,7.C TESTABLE PENETRATIONS WITH TESTABLE BELLOWS j 3.7.D . AIR TESTED ISOLATION VALVES "

3.7.E PRIMARY. CONTAINMENT ISOLATION VALVES WHICH TERMINATE BELOW THE SUPPRESSION POOL WATER

. LEVEL j

3.7.F PRIMARY CONTAINMENT ISOLATION VALVES LOCATED IN WATER SEALED SEISMIC CLASS 1 LINES 3.7.H TESTABLE ELECTRICAL PENETRATIONS l I I

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l PRIMARY CONTAINMENT ISOLATION VALVES BEING MOVED FROM TABLE D, E, F TO TABLE A

-2 1192, 2 1383 kJ

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/ VR 2 1192 2 1383 33 785, 33 1070 kJ

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. 33 785 33 1070 32 336, 32 2163

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68 508, 68 523 / /L l' 68 550, 68 555 32 2163 32 336 68 508 68 550 68 523 68 555 l

l 84 8A,84-600 i g j 84 88, 84 601 d V3 ,

1 84 8C, 84 603 84 8A 84 600 l 84 88 84 601 l 84 8D,84-602 84 8C 84 603 l 84 8D 84 602 l l

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PRIMARY CONTAINMENT ISOLATION VALVES BEING MOVED FROM TABLE D, E F TO TABLE A l

12 738, 12 741 71 14, 71 580 -

71-32, 71 592 12 741 12-738 7* 14 71 580 73 23, 73 603 71-32 71-592 73 23 73 603 73 24,73-609 73 24 73 609 74 60, 74 61 74 71, 74 72 A A FM VR 74 74,74-75 j 74 61 74 60 74 75 74-74 74 57, 74 58 74 58 74 57 74 72 74 71 74-722 BUND FLANGE 74 722 70, 25, 75 26 75 26' 75 25 75-54* 75 53 75 53, 75 54' f LM f V3

  • Already in table A, no change

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PRIMARY CONTAINMENT ISOLATION VALVES BEING MOVED FROM TABLE D, E, F TO TABLE A l

3 558*, 3 554*

73 45, 73-44 "

3 558* 3-554' l

  • Already in table A, no change

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" Being deleted from T.S. 73-45 73 44 " i

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85 576*

69 579 85 576*

69 579

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3 572*, 3-568*

3 572* 3 568*

71 40, 71 39"  ;

Already in table A, no change Being deleted from T.S. 71-40 71-39 '

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PRIMARY CONTAINMENT VALVES BEING ADDED TO TABLE A THAT WERE NOT I PREVIOUSLY IN T.S. OR IN APPENDIX J i

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J 71 17, 71-18 73 26, 73 27 kJ k2 VR V3 71 17 71 18 73 26 73-27 71-34, 71 547 13-30, 73 559 - k l 71-34 71 547  ;

73-30 73 559  !74-792, 74 804 '

74 802,74-803 75 606, 75 607 74 804 74-792 75 609, 75 610 74 803 74-802 75 606 75-607 75 609 75-610 70 47 70-47 LA 70 506 f FR 70 506

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PRIMARY COh'TA!NMENT ISOLATION VALVES BEING DELETED FROM T.S.

1 PART I - DELETIONS FROM TABLE A l i

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71 6 A,' 71-6B l

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  • Currently in T.S. JL I~

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- i 71-7A, 71 78 )

  • Already in Table A
    • To be deleted 71-40' 71-39'*

DRYWELL kJ F7 3 572* 3-568* FFOMCONDENSER .

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l PRIMARY CONTAINMENT ISOLATION VALVES BEING DELETED FROM T.S.

PART I DELETIONS FROM TABLE A

. 1 l 1 73-17A, 73 178 f

i 73-26 73 27 VJ TM ~ LJ '

y3 73 ( 7 3-17 A 73-17 8 LA LA FROMSEALCONDENSER r, r, 3-558 3 554

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FW LINE A I

DRYWE11 73 45 1

FCV 73 6A, 73 6B i I

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73 2 73 3 kJ kJ V3 V3 TURBINP 9y

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73 81 J

's ,r 77 73-6B ag 1

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e PRIMARY CONTAINMENT ISOLATION VALVES BEING DELETED FROM T.S.

PART I DELETIONS FROM TABLE A BEFORE MOOlFOATON 74 102 74-102 74-119 74-103 TORUS kJ k2 VR )

V3 74 119 74-103 74-120 kJ kJ 74 120 V7 F7 AFTER MODIFICATION 74-102 74-119 TORUS kJ . k2 VR V3 74-103 74-120 kJ kJ CAPPED F F f

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J BEFORE MOOlFICATON 85 573 85-573 85 576 O WM [, [

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1 AFTER MODIFICATION j 1

3 572 3 568 ,

FW LINE B 85 576 l

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PRIMARY CONTAINMENT ISOLATION VALVES' BEING DELETED FROM T.S.

PART 11 - DELETIONS FROM TABLE D 3-572 3-568 71 39 FW LINE B 71 40 71-39 kJ

/ VM 69 579 85 576 1

i 73 44 3 558 3-554 l

73-45 73-44 kJ

/ VM

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PRIMARY CONTAINMENT ISOLATION VALVES BEING ADDED TO TABLE A BECAUSE OF ADDITION OF CONTAINMENT PENETRATION PATHWAY (TIE IN)-

32 2163*, 32 336' 32 2163* 32 336*

84 617

  • Already in T.S. being moved 84-617 to Tabte A. _

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CONTAINMENT ISOLATION DESIGN  !

NRC REGULATIONS RND TilR CIS DESIGN DATES I ~

Development of GE CIS design began 1960 (1950's + oarly 1960's) 1961 1962 BFN Design + Analysis Report 1963 i

1964 1965 1966 GE Design Spec for Reactor Containment AEC Interim GDC 53 1967 22A1169 1968 L construction C permit issued for BFN 1969 1970 NRC GDC 54,55,56, + 57 1971 GE CIS Design Specification 22A1132AE 1972, 10CFR50, Appendix J 1973 BFN FSAR submitted to NRC g974 BFN unit 1 operating license Standard Review Plan 6.2.4 1975 BFN received SER from NRC 1976 (CIS design accepted) 1977 -

1978 '

1979 1980 1981 1982 1983 I 1984 1985 1986 1 1987 1988 1

1989 I...

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CONTAINMENT ISOLATION REGULATORY REQUIREMENTS CRITERION 51 - REACTOR COOLANT PRESSURE BOUNDARY OUTSIDE CONTAINMENT (Category A)

If part of the reactor coolant pressure boundary is outside the containment, '

appropriate features as necessary shall be provided to protect the health and safety of the public in case of an accidental rupture in that part. Determination of-the appropriateness of features such as isolation valves and additional l' containment shall include consideration of the environmental and population conditions surrounding the site.

CRITERION 53 - CONTAINMENT ISOLATION VALVES (Category A)

Penetrations that require closure for the containment function shall be protected by redundant valving and associated apparatus.

CRITERION 54 - CONTAINMENT LEAKAGE RATE TESTING (Category A)

Containment sha13 Le designed so that an integrated leakage rate testing can be conducted at design pressure after completion and installation of all penetrations and the leakage rate measured over a suf'ficient period of time to verify its conformance with required performance.

CRITERION 55 - CONTAINMENT PERIODIC LEAKAGE RATE TESTING (Catezory A)

Ne containment shall be designed so that integrated leakage rate testing can be done periodically at design pressure during plant lifetime.

CRITERION 56 - PROVISIONS FOR TESTING OF PENETRATIONS (Category A)

Provisions shall be made for testing penetrations which have resilient seals or expansion bellows to permit leaktightness to be demonstrated at design pressure at any time, l

CRITERION 57 - PROVISIONS FOR TESTING OF ISOLATION VALVES (Category A) )

Capability shall be provided for testing functional operability of valves and associated apparatus essential to the containment function for establishing that no failure has occurred and for determining that valve leakage does not exceed a:ceptable limits.

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Vent to Standby Gas - Treatment l-i X-26 '

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.L 2 K7 F C V 19 i

l' X-231
1) Redundant Valves
2) Normally Closed
3) Administratively controlled .

a) SOS controlled key b) OI and EOI restricted use per FSAR.

4) Appendix J tested References 2-47E2865-12 4 2-47E862-1

, -4 RHR Torus Spray X-211 A X-211 B

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Torus Spray {j VM V F C V -7 4 -5 8 FCV-74-57 Test FC V-74-72 FC V-74-71 Return _ f

\ X-210A

_ X-210B

1) Redundant Valves (Water seal and FCV-74-57(71) for the Test Return Line)
2) .Normally Closed '

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3) Interlocked with system LPCI initiation.
4) Standard BWR Design i
5) Required post accident (Essential System).
6) Water sealed l
7) Appendix J tested References 1

2-47E811-1 I

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Drywell Control Air ' Supply J

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l Drywell 2-32-336 X-22 2-32-2163 2-84-617*

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1) Redundant Valves
2) Equivalent isolation capability as original design basis.
3) Appendix J tested
  • New Valve References 2-47E862-1 4 2-47E2847-5 2-47E2847-9

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i Reactor- Building Closed Cooling Water -

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Drywell X-23 7.D - 5 0 6 -

1) Group C velve
2) Specifically described in the FSAR
3) Appendix J tested i

References 2-47E822-1

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TIP Purge 76-653 X-35f

1) Normally Closed 7 2) Original design
3) Justified per 'GE NEDC 22253 ~and accepted -by NRC on other dockets.

a) Function as' instrument lines or support the operation -

of instruments.

b) Small diamete'r lines c) Safety Grade valve d) Off-site dose is a small fraction of 10CFR100 limits.

4) Appendix J tested Reference 2-47E600-14 t

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$ I s i L J k J k J kA D V 3 l--% W l FS V-43-28 A FS V-43-28 B l FS V-43-29 A FSV-43-29B X-225A 4 X-225B i

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1) Redundant Valves
2) Normally Closed
3) Conservative inclusion of valves - normally isolated by manual valve. '
4) Administratively controlled - Chemistry Instruction

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5) Water sealed
6) Appendix J tested l

References i

1 2-47 E610 1 2-47 E 811 - 1 l

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X-25 X-205 S

FSV-84-S A

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FSV-84-8 B FSV-84-8C.

FSV-84-8D

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1) Redundant Valves I
2) Normally Closed .

3)- Administratively controlled - OI and EOI.

4) Required post-accident (Essential System).
5) Appendix J tested References 2-47E862-1 l

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HPCI Min Flow -

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1 X-210B Torus L~~]

w A V 3 FC V-73-3 0 73-559

1) Redundant Valves
2) Normally Closed ,
3) System isolation signal - interlocked with turbine operation.
4) Water sealed
5) Appendix J tested i

References 2-47E812-1

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I RHR Drywell Spray i

X-39 A X-39B k J L J '

Y3 Y R F C V 61 FCV-74-60 FCV-74-75 FC V-74-74 l

1) Redundant Valves
2) Normally Closed
3) Interlocked with system LPCI initiation.
4) Standard BWR Design
5) Required post accident (Essential System).
6) Water sealed
7) Appendix J tested References i 2-47 E 811 - 1

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1 Core - Spray Injection X- 16 A X-16B j

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FCV-75-25 FCV-75-53 9

1) Redundant Valves
2) Normally Closed
3) Administratively controlled (OI and EOI)
4) Standard BWR design.
5) Required post accident (Essential System).
6) Water sealed .
7) Appendix J tested References 2-47E814-1

_ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ __ _ _ . _ _ _1

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HPCI Pump Suction X-226 k' C I I L J s Torus L Y R V m FCV-73-26 FCV-73 27

1) Redundant Valves i
2) Normally Closed l
3) Group 4 Isolation
4) Water sealed aj Required post accident (Essential System)
6) Appendix J tested References 2-47 E812- 1

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RCIC Min Flow .

X-210 A Torus L_J.

L J V ~ R F C V-71 -34 71-547-

1) Redundant Valves
2) Normally Closed
3) System isolation signal - interlocked with turbine operation.
4) Water sealed
5) Appendix J tested References 2-47E813-1 e

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RCIC Suction i X-227A '

l O O L 2 L J Torus r m V m FC V 17 FCV 71-18

1) Redundant Valves
2) Normally Closed
3) Administrative Control (Operating Instructions)
4) Water sealed
5) Required post accident (Essential System)
6) Appendix J tested References 2-47E813-1

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l. M 1-RHR & Core Spray System Fill Connections-i 74-802 74-803 74-792 74-804 75-609 75-610 75-606 75-607

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1) Redundant Valves
2) Water sealed
3) Appendix J tested Reference 2-47E811-1 2-47 E 814-1 i

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FCV-73-26 FCV 73-27 l I

Torus L M L l

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Containment Boundary

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  • FC V-73 17 A *

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{ From s Condensate X-9A Pump Drywe!! s 3-558 3 554 k To Reactor s

k FCV 73 44*

73-45

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X-210B s s

I FCV-73-30 k i I 73 559 A_ J s&%

Torus F'7 [ g Min Flow Line 6

1) System Isolation Valves
2) Outside Primary Containment Isolation Boundary Valves Deleted from Table Reference 2-47E812-1 8

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Containment aoundary %

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/

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/

h

, { FCV 73 6B* FCV-73 6A*

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HCV-73 24  %

73-609 M

/

lW X 222 g l

t

1) System Isolation Valves i

f

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l

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k FCV-71 -39' 71-40

& L M

/;  %

r ,

X-210A k FCV-71 34 g 71-547 %

Torus k

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1) System Isolation Valves
2) Outside Primary Containment Isolation Boundary Valves Deleted from Table Reference 2-4 7E813 1

_ _ _ _ _ _ _ _ _ - - - . - - _ _ _ _ _ n'

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Reference 2-47E813-1

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