ML20151H747

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Forwards Relief Requests G to N Re Plant Inservice Insp Program Plan.Requests Being Submitted as Result of Observations Made During Refuel II & Addition to Previously Submitted Relief Requests
ML20151H747
Person / Time
Site: Callaway 
Issue date: 04/11/1988
From: Schnell D
UNION ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
ULNRC-1753, NUDOCS 8804200507
Download: ML20151H747 (17)
v • d • e


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This lottor is boing roissusd to clarify the date.

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1901 Grenot Stmt. St. Laws Donald F. Schnell April 11, 1988

-1 Vice m 3

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b U.S. Nuclear Regulatory Commissicn Atta:- Document Control Desk Washington, D.C. 20555 UI.Nac-175 3 Gentlemen:

b DOCKET 50-483 CAI.I.AWAY PI. ANT ADDITIONAL INFORMATION CCNCERNING THE CAI.LAWAY PI. ANT INSERVICE INSPECTION PROGMM PLAN N

References:

1) ULFRC-1457, dated March 3, 1957
2) ULNRC-1481, dated April 2,1967

' The referenced letters transmitted the latest informatien en i

the Callaway Inservice Inspection Program Plan.

Enciesed please find Relief Requests G through N to the subject plan.

These

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relief requests are being submitted as a result of observations made during Refuel II and are in addition to the previously submittsd relief requests.

1 Please contact us if there are any questiens concerning these relief requests.

(

very truly yours,

'. s I

V Donald F. Schnell j

WIX/ mat i

Enclosurs

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i STATE OF MISSOURI )

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SS CITY OF ST. LOUIS )

Donald F. Schnell, of lawful age, being first duly sworn

.i upon oath says that he is Vice President-Nuclear and an offices of

'i, Union Electric Company; that he has read the foregoing document and kncws the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the f acts therein stated are true and correct to t.v4 best of his knowledge, information and belief.

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By D6nald F. Schnell Vice President Nuclear SUBSCRIBED and sworn to before me this

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3AfttARA J. PFAT M0fMY PUIVO IIAII 0# *I*

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cc Gerald Charnof f, Esq.

Shaw, Pittman, Potts & Trowbridge

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2300 N. Street, N.W.

Washing ton, D.C.

20037 Dr. J. O. Cermak CFA, Inc.

4 Professional Drive (Suite 110)

Gaithersburg, MD 20879 W. L. Forney Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Conmission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RRf1 Steedman, Missouri 65077 Tom Alexion (2)

Od2 ice of Nuclear Reactor Regulation U.6. Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014 Manager, Electric Department Missouri Public Service Connission P.O. Box 360 Jefferson City, MO 65102 J

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/QA Record (CA-758)

E210.01 Nucisar Date DFS/ Chrono D. F. Schnell J. E. Birk J. F. McLaughlin A. P. Neuhalfen g,

R. J. Schukai M. A. Stiller G. L. Randolph R. J. Irwin E. Wuertenbaecher W. R. Campbell A. C. Passwater

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R. P. Wendling D. E. Shafer D. J. Walker O. Maynard (WCNOC)

R. C. Slovic (Bechtel)

G56.37 (CA-460)

T. P. Sharkey NSRB (Sandrs Auston)

W. E. Kahl D. M. Stepanovich e

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RELIEy REQUEST C Systemt teactor Coolant Category:

B-G-2 Q..

Component

Description:

Valve 88-83785, a 3" check valve from Chemical and Volume Control System (CVCS) to Reactor Coolant System cold les A.

Identified for

  • ~ ~,
  • inspection in the CVCS program plan.

Co te Requirement:

Visual inspection (VT-1) of bolting surfaces as required by item 17.70, category 3-G-2.

Areas for Relief:

100% of the bolting.

Basis,for Relief:

Due to the encapsulation of the body to bonnee joint the bolting is inaccessible without removal of the welded enc.spsulation. The encapsulation j

is a modification supplied by the vendor (West-inghouse) which was installed by Union Electric.

Alternate Test Method None; provided the valve is not disassembled.

The reactor coolant systen leakage detection system and ISI visual examinations for leakage will establish.che integrity of the pressure boundary. When the encapsulation is removed the required exam will be performed.

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ci.l CALLAVAT ISI RELIEF REQUEST U

l. ')

.4 Systems Reactor Coolant Category:

5-5

-1 Component

Description:

Steam Generator A.

Botton Head to Tubesheet Wald 2-E1801A-SIAM-lW.

'fI Code Requirements:

Volumetric examination of veld and 1/2 vessel thickness on each side of weld from two direc-

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.O tions.

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-[,

Areas for Relieft 35% of weld volume.

, f'j lasts for Relief:

Tubesheet obstructs full examination from one

..a side and Support lugs and a code data plate

' 'i obstruct examination at four circumf erential locations.

Alternate Testing:

Noce. Reactor Coolant leakage detection system and ISI visual inspections for leakage vill establish the integrity of this vele 5

i 4.

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Appendix H j

Page 1 of 1

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CALLAWAY ISI l

ret,IEF REQtTEST I 1

Reactor Coolant Systes:

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Category:

C-A Component

Description:

Steam 8enerator 3. Tubesheet to Stub Barrel veld

- l 2-11805-5EAM-2-W.

Volumetric examination of weld and

.'5 inch on 1

Code Requirements:

each side veld from two directions.

Areas for Reliefs 30% of weld volume.

Basis for Relief:

Tubesheet obstructs full examination from one side. Three aanways, a pipe attachment and a i

code data place, obstruce examination at various eircualereatial locations.

Alternate Testing:

None. Extent of volumetric estamination and I5I visual inspection for leakage vill establish the integrity of this veld.

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Appendix I

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Page 1 of 1 I

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RELIEF REQUEST J System Reactor Coolant Category:

3-5

  • /

Component

Description:

Pressuriser, Botton Head to Shell Wald 2-T3503-CIRCUM-5-W.

Code Requirements:

Volumetric examination of weld and 1/2 vessel head thickness on each side of weld from two directions.

Areas for Relief:

2% of weld volume.

Basis for Relief:

Five 1 inch sample lines and 8 welded lugs obstruct examination at various circumferencia.

locatters.

Alternate Testing:

None. Reactor Coolant leakage detection' system.

ISI visual inspections for leakage, and the extent of the completed examination establish the integrity of this veld, t

Appendix J Page L of 1 I

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cat.!.XJAY ISI Rit.IET REQUEST K 3

Reactor Coolant Systeer 5-A Category:

Reactor Vessel. Reactor Vessel Closure Head Component

Description:

Meridional welds:

2-CH-101-104-3 2-CE-101-104-C Volusecite examination of weld and 1/2 vessel Code Requirements:

head chickness on each side of weld from two directions.

Vessel lif ting lugs obstruct a full examination Areas for Relief:

from one side.

None. Ex:ent of examination, Reactor Coolant Alternate *esting:

leakage detection system. and ISI vtaual exami-4 nations for leakage vill establish the integrity of these velds.

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Category:

3-A Component

Description:

Reactor Vessel, Reactor Vessel Closure Head to flange veld:

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2-CH-101-101 h.

Code Esquirements:

Volumetric examination of veld and 1/2 closure head thickness en each side of weld from two directions.

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Areas for Relief:

52% of weld volume.

3 asis for Relief:

Closure flange obstructs full examination from one side and Closure Head lif ting lugs obstruct examination at three circumferential locations.

Alternate Testing:

None. Extent of examination. Reactor Coolant leakage detection system, and ISI visual exami-nations for leakage vill establish the integrity of the veld.

t i

Appendix L t

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.4 CALI.A' JAY I$I RELIIT RIQtJEST M System:

See attached pages Category:

Piping, See attached pages Component

Description:

See attached pages i

Code Requirenant:

See attached pages Areas for Relief:

See attached pages Basis for Relief:

See attached pages Alternate Test Method: See attached pages 9.

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SYSTFn Chemical and Volume Control f.

j Caserory Description Conguinent I.D.

On=8e Beaguirements Area for Belief Basle for Relief Alternate Testing f.

N/A 1" pipe to walve 2-RC-01-F002 Augment ed volumet ric case-IM of weld volume Valve to pipe geometry a'a"a s Estemt of esam-obstreacts circassferee-Saat tam completed and

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j livel52 weld tenation reapsised for EreA E8al esaminatten ISI visual for leakage i

Esclustese assedmen 0800) will estabitain the integrity of this esold.

l' SI/A Valve ifVelS2 to 2-DC-01-F001 Aessmented wolemmet ric eman-I n of weld walasse Valve to pipe geometry alone s Esteet el esen-olestrescas circassferen-inattom completed and

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laat taa resysteed for Break 3" pipe weld Encluefan tNIARFC 0800) tlat esaminatlea ISI vlamat for leakage

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Im agrity of this weld.

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N/A Orifice flange 2-SC-09-FW189 Au pented volumetric enam-

  • 20% of weld volume Flange preventa complete sinne s Essent of eman-esaminet taan.

Samatoes and ISI viemal

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EI-145 to 2" pipe for leakage will estab-g buessedary (IsumEC oc00) l Blain the integrity of g5 this weld.

N/A Ortilce flange 2-SC-09-FU419 AupenteA walismetric eman-50% of weld volume Flange prevents emplete asune s Esteet of esam-i:

esamination.

Saation and ISI wisenal inattom for bseak esclusion for leakage esill estab-f l

FI'-14) to 2" pipe bounstery (IsumEC Os00) lists the Integrity of p

this weld.

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2 N/A OrificeItanke 2-SC-09-FW4 )4 Aespented velasmet r ic eman-Set of umid valemme Floose Prevents complete hs Essent of enam-r emaalast less.

Instlan and ISI wisesal p

DE-144 to 2" pipe snatton for break enctesten for leakage will estatr-p amoundary (sedpFC 0800) lists sine integrity os g

this weld.

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1 N/A Osefice flange 2-bC m404 Augmented wolesmet ric eman-Set of wild wolesme Flange prevents complete IInes Esteet of esse-1 emantmation.

Santism and ISI wisesal

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FI-142 to 2" pipe inat fan for break esclassion for leakage will estab-bous dary (esMBEC 0000) lista the lategrity of i

this weld.

14 N/A Oriffre flange 2-hC-09-FW)90 Anspented wolesmet ric esam-50% of eseld volesse Flange prevents complete alone s Estent of enam-enamtmation.

Imatten and ISI wisenal n'

Inaa lues for beeA esclusico for leakage will estab-l IE-145 to 2" pipe L==Jary (sessitEC 0000) llaan the integrity of 1

this veld, 1

s/A 2" pipe to 2-BC-09-FWlg)

Ansemarr.ted votammett Ic esam-20% of eseld wolesse Tee geommary prevents no : Estesnt of enam-2" x 2" a 1/4" taat ton for break encloseton eseplete enamtmagles saattaa and ISI wisual s

for leakage natll estah-I.oessalary (fluSEC anise) limb the Integrity of j

Tee this weld.

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Unemical and Volume Cesstrol (Ceasetinued)

SYSTIM:

Area for Relief Baals for Belief Alternate Teet tag rav ageisy Scac ripe t osi raroasent I.D.

Cude Respelrements Itene s Esteet of emes-20% of weld volume Tee seemetry preweeta inattan and 111 wtaunt c/A 2" m 2" m 2/4" 2-DC W392 Amynented volumet ric enam-complete emassmettaa for leakage will estab-inesian for hveak encleaston Tee to ripe tauundary (leMetEC 424MA) tiete eine lategrity of this weld.

10% of weld volume.

Tee geometry preweets llama t Esteet of esam-laatten and ISI viennet M/A 2" Ftpa t o 2-BC-09-D8f.39 Augmented valismet ric enam-csaplete esasematten for leakage will estats-inattesi for bseak enctissian 2" a 2" a 3/4" L=adary (seultFC 0800) lisen the integrity of Tee this weld.

s-llame t Esteet of esam-10% of weld volumen Tee gesmetry preweet's lastles and 151 wieneal 5/A 2" a 2" a 1/4" 2-ac-09-FIA 38 Aeagmented volismet tic enam-complete esaminatlen for leakage will esteh-inatten for break escluelen Tee to 2" Ftpa L-dery (flustEC 0800) lisen the lategrity of this weld.

S SYSTIM: Main Feedwater Area for Retter Beets for Relief Alternate Teettaa s

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t I.D.

Code Reasuirements Creegory inesc ript ica nL=as Estest of esam-25% of weld weline Vatwo to pipe seemetsy 2-AE-05-F031 Aasynented valismetric esam-abstriscts complete laattan completed and C/A 4* Elben. to laatisan seapelsed for Sreak esaminatica 151 visenal for leakage VmIve Vl?&

Esclassian (10HREC 0000) will estabitsh time lategrity of this w=ld.

2% of weld wolesse Fitting geneetry does alone Esteet of esam-C/A 14" Fire to 2-AE-OS-S004A Anagmented walianet ric esam-aas allana esmplete ination campleted and 151 wisual f or leakage lnattusi re p.tred for treak camminattaa 14" a 4" lesidelet Eaclasstem (sm88tt.C 0800) will establisen alie f ategrity of this weld.

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i RELIET REQUEST H

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l Systsa:

All ASM1 class 1, 2 and 3 systems

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l Category / Ices:

T. C l

Component

Description:

Supports with Mechanical or Hydraulic Snubbers Code Requirement:

Operability testing of snubbers and visual inspectica (VT-3 and VT-4) of snubbers and supports with snubbers.

y Areas of Relief:

100%

3 asis for Relief Callaway impleeents a testing and visual inspection program in accordance with the Program Plan identified in the Plant Techni-cal Specifications. This program Plan asets the testing and inspection requirements of the Operation and Maintenance (CM)-4 docu-sent. This document was written by the AEME Section II Working Group on Mechanical Equipment Rectraints. This document has also been invoked in its entirety within ASM! Section K! 1986 Edition. Winter 1987 Addenda.

4 Alternate Test Method:

None I

I

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l Appendix N Psge t of I l

.

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