AECM-90-0124, Forwards Rev 1 to Relief Request I-00018 Correcting Valve Number & Description of One Component.Review & Approval Requested Prior to 901001

Forwards Rev 1 to Relief Request I-00018 Correcting Valve Number & Description of One Component.Review & Approval Requested Prior to 901001

ML20044A925
Person / Time
Site:	Grand Gulf
Issue date:	07/09/1990
From:	Cotter W ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AECM-90-0124, AECM-90-124, NUDOCS 9007170001
Download: ML20044A925 (11)

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==p W. T. Cottle w e %.n July 9, 1990 N a m hu+

1 U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.

20555 Attention: Document Control Desk Gentlemen:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 ASME Section XI Relief Request Number 1-00018, Revision 1 AECM-90/0124 This submittal requests relief from the requirements of ASME Section XI, in accordance with 10CFR50.55a(g)(5 (iii). A revision to a previously

. approved relief request is attached).

. Relief Request 1-00018 Revision 1 addresses additional components for which relief is requested.

Also, a valve number was corrected in the description of one component and another component was deleted since an associated valve was found to be locked open during plant startup.

A summary-of changes'to Table 1 of the relief request made by this revision is provided in Attachment 1.

TheGrandGulfNuclearStationInserviceInspection(ISI)programis required to be u) dated every ten years to the latest edition of ASME Section XI approved by tie NRC. The initial u'adate of the GGNS program will begin in 1994 and be implemented in 1995. At t1at time, the testing proposed by the

attached relief request revision is scheduled to become a part of the GGNS ISI program.- Use of a later edition of ASME Section XI at this time will allow our resources to be spent on other activities, as well as potentially reducing the downtime of Emergency Core Cooling Systems, during the refueling outages prior to 1995.

Your review and approval of this request is requested prior to October 1, 1990, in order to allow planning for the upcoming refueling outage.

If additional information is required to support your review, please advise.

Yours truly, 9007170001 90o7o9

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Attachments M(

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AECM-90/0124 I ',

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P Mr. D. C. Hintz (w/a) cc:

Mr. -T. H. Cloninger w/a)'

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Mr. R.1 B.~ McGehee ( a) i Mr. N.' S, Reynolds

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Mr. H. L. Thomas (w o)(w/a)

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o" Mr. H. O. Christensen i

Mr.StewartD.Ebneter(w/a)

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a, Regional Administrator U.S. Nuclear Regulatory Commission

["g Region II.

101 Marietta St., N.W., Suite 2900 Atlante, Georgia 30323 j

Mr. L. L. Kintner,' Project Manager (w/a)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 11021 Washington, D.C.

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Page 1 of 2 p.

L Summary of Revision 1 Changes - Relief Request 1-00018

- Pressure Testino of Category B-P Pressure Retaining Components"~

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Relief Request Revision 1 Change Item No.

Requested Reason for Chance / Comments NA Delete' Item item No. 1 in Revision 0.

The associated valve is locked open during restart, therefore relief is not appropriate.

s 11

. Correct Description Item No. 7 in Revision 0.

The valve number is corrected to Q1C41-F222.

33 Changed to two items item No. 17 in Revision 0.

&34 This was made into two

. separate items in Revision 1 n

l for clarity.

To preserve system order in Revision 1, the following items from Revision 0 were s

re-numbered:

1 Re-number item item No. 3 in Revision 0.

3 Re-number item item No. 5 in Revision 0.

5' Re-number item Item No. 6 in. Revision 0.

7 Re-number Item Item No; 9 in Revision 0.

,16 Re-number item Item No. 10 in Revision 0.

28 Re-number item Item No. 11 in Revision 0.

29 Re-number item item No. 15 in Revision 0.

30 Re-number Item Item No. 16 in Revision 0.

L 32-Re-number item Item No. 14 in Revision 0.

38 Re-number item Item No. 13 in Revision 0.

39 Re-number item Item No. 12 in Revision 0.

LA9006271/SNLICFLR - 6

. to AECM-90/0124 Page 2 of-2 l'

Relief Request Revision 1 Change item No.

~ Requested Reason for Chance / Comments m

6,9,10,12-

' Add items Relief is requested for

- 15,17-27,31,

. components in addition to and 35 those ap) roved by Revision 0, due to t1e hardship of testing and to attempt to decrease Emergency Core Cooling Systems downtime during refueling outages. Relief would allow-system leak testian in accordance wit" rw 1s33 L

Edition.ture ~ 193$ Adc ada.

- of ASME LarW 9

• mur than the 1977 E. t!wa Semt b.'9 Addenda. Th, h e us1 by Revision I w,-

u amwd Jy review of the. urrend configuration of i..; untire reactor coolant pressure boundary, including some systems not addressed for Revision 0. The components added by Revision 1 include some-high/ low pressure interface piping.

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Relief Request Number 1-00018 Revision 1 i:

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" Pressure Testina of Category B-P n-Pressure Retaining Components" l0 I

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6 Pages=

Relief Request - Revision 1 2

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L ' GRAND'GuLr NUCLEAR STATION.

INSERVICE INSPECTION REQUIREMENTS

" V' s INSERVICE INSPECTION:

SECTION 4 1

TEN YEAR PROGRAM RELIEF REQUESTS i

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GRAND GULF NUCLEAR STATION i

UNIT 1 r

RELIEF REQUEST I 00018 REVISION I j

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PRESSURE TESTINA DE CATEGORY B P 9:

PRES $URE RETAINING COMPONENTS i

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Component:

Class I pressure retaining components,

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Examination Category-B P (see table 1).

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Code:

The pressure retaining components within this catelcry are designed and fabricated to ASME

i Sect < on III, class I requirements.

Applicable inservice inspections are performcd in accordanco 1

with ASME Section XI,1977 Edition through and including-the' Sunener 1979 Addenda. -

III.

_ Code Requirements:

Class' l pressure retaining-components, category B P,.are required to receive a= system leakage:

test (IWB 5221). each refueling outage, and a system hydrostatic test- (IWB-5222) each

. inspection interval.

IV:

Information.to

'ASME Section XI, 1977-Edition, Summer 1979 support the Addenda, Table IWB-2500-1, category B-P, note 1,

-f determination that requires the test boundary for both the system l

-the code leakage and the hydrostatic test to include-the-requirements are entire reactor coolant system.

This boundary, ~ as impractical:

defined, requires portions of piping to be.

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pressure tested that are: isolated by normally closed valves.

To accomplish testing of the.

isolated piping, extensive efforts are required-1 that may include the installation of mechanical p

jumpers, initiation of -false signals to ' open L' '

valves or the erection of independent water and pressure sources.

Later editions of ASME Section:

XI have. redefined the test boundary for the system leakage test.

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y9 Note 1 1' of IWB 2500-1, Category B-P' has b'een revised to address only the system leakageitest 6.y and to redefine the test boundary as:-

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system leakage test shall correspond to the-reactor coolant system, with' alle valves: in'the h

normal position,1 which -is required Ar normal'

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reactor operation startup.

The VT-2' examination ~

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-Soecific Relief-Permission is: requested to'. perform system 11e'akag'e closed valve,atithe boundary extremity."

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.f.equested:

. testing of the. class 1 boundary as' described by-V ASME Section~.XI,.1983; Edition, Summer 1983~

W Addenda.. Table ~ IWB-2500-1, Category ' B-P; - This:

t request appliesc only toithe system leakaget testi k,

and : not to the : hydrostatic - test required -'each.

interval. fTable-1 listsithe portions Lof the-systemstthat are examined by the VT-2 method but.

m" excluded from pressurization.

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Reasons why-relief

' Request..for altering the class' 1 system le'akage -

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.should be granted:

test boundaries as : discussed herein shouldi be

'i granted for the following reasons:

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All components excluded from the system

~w leakage test are designed,. fabricated, installed and tested to-the requirements of J

'ASME Section III, Subsection'NB (class 1).

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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 y,,

TEN YEAR Paoo m RELIEF REQUESTS f

GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00018 REVISION 1 PAGE 3 0F 6 PRESSURE TEST'ING D.E CATEGORY B P PRESSURE RETAINING COMP 0NENTji u

2.

The componentr..xcluded frt.n the system loakage test are subjected to the system hydrostatic test once each interval.

3.

DELETED 4.

This request for relief, if approved, would be consistent with the current NRC approved edition of ASME Section XI (1933 Edition, Summer 1983 Addenda).

VII.

Alternate Testing:

None VIII.

NRC discussion 10CFR50.55a(g)(3)(v) permits updating to the statement for the requirements of later approved editions and approval of addenda of the ASME Code, or portions thereof, revision 0:

which are incorporated by reference in paragraph 50.55a(b), subject to Ine limitations and modifications listed therein.

Based on the staffs evaluation, it is concluded that the i.icensee is permitteti to update to later editions and addenda of the Code and that compliance with the specific requirements of Section XI (77579) would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.

Therefore, relief is granted as requested.

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,JIEM SYSTEM' LINE CLASS DESCRIPTION-

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,z LINE DOWNSTREAM OF Q1821-F1368-

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2 B21 1" DBA-87 LINE 30WNSTREAM 0F Q1B21-F136A 4

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L31 B33' 2" DCA;24 LINE DOWNSTREM OF Q1B33-F051Al a

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2" DBA-42 LINE DOWNSTREAM 0F Q1833-F029' n

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'B33 2" DCA-24

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JC41 1 1/2" DCA-3 itINE DOWNSTREAM 0F QlC41-F219 lC41-3/4" DCA-33 LINE 00WNSTREAM.0F!Q1C41-F2'9 I

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.C41 1" DCA-31 LINE.00WNSTREAM 0F-Q1C41-F210-

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'C41 1" DCA-34 LINE UPSTHEAM OF QlC41-F222L

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~C41 1" DCA-34 LINE~. DOWNSTREAM OF QlC41-F218

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_i PRESSURE TESTING QE CATEGORY B-P PRESSURE RETAINING COMPONENTS TABLE 1 11EM SYSTEM LINE CLASS __

DESCRIPTION 14 E12 6" DBA-32 LINE UPSTREAM 0F Q1E51-F066 l

15 E12 1" DBA-80 LINE UPSTREAM 0F QlE51-F066 l

16 E12 1" DBA-80 LINE DOWNSTREAM 0F QlE12-F344 17 E12 14" DBA-28 LINE UPSTREAM 0F QlE12-F041B l

18 E12 1" DBA-81 LINE UPSTREAM 0F Q1E12-F0418 l

19 E12

,1 " DBA-81 LINE DOWNSTREAM 0F Q1E12-F236 l

20 E12 20" DBA-64 LINE DOWNSTREAM 0F QlE12-F009 l

21 E12 14" DBA-29 LINE UPSTREAM 0F QlE12-F041A l

22 E12 1" DBA-4 LINE DOWNSTREAM 0F Q1E12-F223 l

23 E12 12" DBA-38 LINE UPSTREAM 0F Q1E12-F041C l

1 24 E12 1" DBA-79 LINE UPSTREAM 0F Q1E12-F041C l

25 E12 1" DBA-79 LINE DOWNSTREAM 0F Q1E12-F234 l

26 E21 14" DBA-1 LINE UDSTREAM 0F QlE21-F006 l

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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAa PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00018 REVISION 1 PAGE 6 0F 6 PRESSURE TESTING o

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[.AIE@RY B-P PRESSURE RETAINING COMPONENTS TABLE 1 11 @

SYSTEM LINE CLASS DESCRIPTION 27 E21 1" DBA-31 l.INE UPSTREAM OF Q1E21-F006 l

28 E21 1" DBA-31 LINE DOWNSTREAM 0F Q1E21-F207 29 E22 12" DBA-5 LINE DOWPSTREAM 0F Q1E22-F005 30 E22 14" DBA-5 LINE UPSTREAM 0F Q1E22-F005 31 E22 1" DBA-78 LINE UPSTREAM 0F Q1E22-F005 l

32 E22 1" DBA-78 LINE DOWNSTREAM OF Q1E22-F218 33 E38 1 1/2" DBA-87 LINE UPSTREAM 0F Q1E38-F002A 34 E38 1 1/2" DBA-87 LINE UPSTREAM 0F Q1E38-F002B 35 E51 10" DBA-24 LINE DOWNSTREAM 0F Q1E51-F063 l

36 E51 1" DBA-34 LINE D0WNSTREAM 0F Q1E51-F076 l

37 G33 6" DBA-86 LINE DOWNSTREAM 0F Q1G33-F250 l

38 G33 1" DBA-86 LINE DOWNSTREAM OF Q1G33-F241 39 G33 3/4" DBA-82 L?NE DOWNSTREAM OF Q1G33 F002 M:\\lE:CH\\ pip 1NC\\ LEWIS \\M489 1\\RRI 18R1

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