ML19329D608
| ML19329D608 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/14/1977 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003160232 | |
| Download: ML19329D608 (10) | |
Text
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-d h i Mr. John Stolz Branch Chief f
f Light Water Reactors Branch I Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUEJECT:
Florida Power Corporation Crystal River Unit 53 Docket No. 50-3C2
Dear Mr. Stolz:
On March 2,1977, Florida Power Corporation filed with the Commission additional information in support of our recuest for waiver from ASME Section XI Surveillance requirements for pumps and valves that we had determined to be impractical, in accordance with the Comission's le-*er of February 1, 1977 At that time, we indicated that an evaluation of our Inservice Insoection Program v;as underway to determine areas where the new code requirements cannot be met.
It was further stated that waiver requests for those code requirements cetermined by our evaluation to be impractical woulc be submitted to the Comission on or before April 15, 1977.
We hereby transmit for your review forty-three (43) copies of our request for waiver from ASME Section XI inservice inspection requirements that we have determined to be impractical.
The waiver requests are in the format requested in Appendix B of the Commission's February 1,1977 letter. Our Inservice Inspection Program is based on ASME Section XI, 1974 Edition through sumer 1975 Addenda, #or the period of 40 months following comercial operation.
As stated in our March 2 response, the overall develocment of the Inservice Inspection Program for CR #3 that is required to meet those portions of the new ASME Section XI code where compliance is possible, will not be complete until October 1977.
The development and implementatien of this new Inservice Inspection Program will include tne alternate examinations proposed in our waiver requests in lieu of the imoractical ASME code requirements.
The development of the Inservice Insoection Program by 4
October 1977 is well in advance of the first inservice insoection recuirec for CR #3, which is currently scheduled during the first refueling outage in the fall of 197S.
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.O Mr. John Stolz 2-April 14, 1977 i
.i It is hereby requested that Florida Power be granted waivers from those code requirements identified in the attached submittal and be given until October,1977 for development of the Inservice Inspection Program for CR #3.
Very.truly yours, Y
[V i
J.. Rodgers Asst. Vice President i
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IN WI'; NESS WHEREOF, the applicant has caused its name to be hereunto signed by J.T. Rodgers, Assistant Vice President, and its corporate seal to be hereunto affixed by Betty M. Clayton, Assistant Secretary, thereunto duly authorized the 14th day of April, 1977.
FLORIDA POWER CORPORATION By J
J.T.FRodgers
(/
Assistant Vice President ATTEST Y
A h
Betty & Clayton AssistEntSecret (CORPORATE SEAL)
Sworn to and subscribed before me this lath day of April 1977.
0W k. cf}M Notary Public 14y Comission Expires:
Notary Public State of Florida at Large My Comission Excires July 9,1978
......~........w.u..
. ivut n eigue u i.
t' age t Rev. 1 ASHE Section XI - 1974 with Addenda thru Suniner 1975 NAME: Reactor Vessel TAC NO.
RCRE-1 ASME CIASS:
1 LE8 IWIl-2600 IMPRACTICAL M HO./ CATEGORY DESCRIITION CODE REQUIREHENT REASON IT)R WAIVER ALTERNATE EXAMINATION 4
15-D Four Inlet Noz-Examine some nozzles Access would res[uire Examine both outlet nozzles plus zles HK-18 to during first and deiueling and removing acceshibic portion of vessel weld,.
86/87.
second thirds of the core barrel.
Shell-To-Flange, f rom flange sur-interval per IWB-2411 Nozzles face by end of first third of the MK-17 to 86.
interval. All nozzles will bes examined by the end of' the
)
Interval.
7 Il-G-1 Closure Studs, In Place th)t Applicable.
This examination will be done.with r The studs will be the studs removed.
removed with the head of the reac to r vessel.
I
'l l ll-G-2 CitDtl Bolts &
Examine 1007 of Bolts only accessible Examine bolts and nuts on 10E Nuts to head Tota l Quant ity.
when removed. Only of peripheral CRDtt's to c61ncide flange some peripheral nut wit.h category B-0 " Pressure Re-ri ngs are accessible,
taining Welds in Control Rod L2 B-il I nteg ra lly Not Applicable.
Drive I!ousings."
. Welded Vessel No i nt ergrally Suppo rt s welded vessel sup po r t s.
}
!!A!!E t Piping Pressure floundary TAC No.:
N/A FAllLE s _IWit-2600 ASHE CIASS:
t It!PitACTICAL ITEH tl0./CATECORY DESCRIITION Il4. 5 CODE REQtI1REhEITP ltEASON FOR WAIVER AI. TERNATE EXAMINATION Il I circumfe rential The area of exam-and longitudinal Ination shall in-Due to valve con-lies t effort scan shall pipe welds clude the weld and gu on, no he perfomed on an liy Valve No.
one wall thickness namination can be large a percentage of Core Flood Pipirip' beyond the edge of perfomed on valve the weld area as punsible, eg.y [ ([4uy the weld, side of weld.
ClV-2 (14")
CIN-3 (14")
ClY-4 (14")
s llake-tip Piping N
tulv-36 (2 !,")
huV-37 (25")
inn-38 (2h")
tilN-39 (25")
titN-40 (25")
litN-41 (2b")
HtN-42 (25")
tilN-43 (2k")
MIIV-160 (25")
Ittiv-161 (23;")
1:tiv-162 (4")
MtN-163 (25")
titIV-164 (25")
ItCV-46 (15")
ItCV-47 (1s")
Decay llcat Piping t)
DilV-1 (10")
DliV-2 (10")
DilV-3 (12")
bilv-4 (12")
RCV-12 (2")
RCV-53 (2")
Pressurizer Spray PJping RCV-13 (2h")
RCV-14 (2h")
RCV-36 (25")
Reactor Coolant Dra f n Piping itCV-22 (It")
RCV-40(ll[")
RCV-23 (15")
RCV-49 (1(n)
RCV-27 (1\\".)3
~,, e n ni.
... ~. oac a v n.e suspecuon waiver ucquest Page 3 Rev. I ASME Section XI - 1974 with Addenda thru Sunener 1975 NAME:
Piping Pressure Boundary TAC NO.
ti/A ASME CIASS: 1 ILEs 1Wis-2600 DESCPTPTIOli IHPRACTICAL
- M NO./ CATEGORY WEI.D tlUMBER CODE REQlIIREMEITT REASON FOR WAIVER ALTERNATE EXAMINATION.
.5 B-J Core Flood The area of examin-Limited examinations Best effort scan shall be. I,,L.
Piping ation shall include due to geometry ot performed on as large a 8'
CF-10 (14")
the weld area one nozzles.
percentage of the weld area as CF-23 (14")
waai thickness ha-possible.
Pressurizer yond the edge of Spray PipinM the weld.
,]
E 89 (4")
,5 B-J Pressurizer The area of examin-1.imited examinations Best effort scan shall be Spray Piping ation shall include due to tee coinfigura-performed on as large a 11K 105 (2k")
the weld area one Lion.
percentage of the ucid area as tiK 101 (2!a")
wall thickness beyond possible.
the edge of the weld.
Core Flood Piping i
CD-16D (10")
CF-10B (10")
tia k e-Ilp Piping Drawing flumber JAJ-8067-1
' ( l '2" )
,)'
4 (1k")
6 (lk")
i 7 ( l '2" )
II ( l '." )
f till 259 C (25")
till 259 11 (2'2")
till 259 J (25")
till 259 K (2k")
till 261 D (2'.")
110 ?61 E (2k")
1111261 F ( 2 L" )
till 259 D (2k")
till 259 E ( 2 '2" )
!!!! 259 F (25")
till 260 E (2 k")
flll ?60 D ( *> *," )
-_=
_..,._-.--........,.ooi.
P ge 4 Rev. 1 ASHE Section XI - 1974 with Addenda thru Summer 1975 NAMES Piping Pressure Boundary TAC 110.3 II/A ASME CIASS: 1 ILE8 IWH-2600 IHpRACTICAL I
.H NO./CATECOMY DESCRIPI' ION CODE R EQU f REMEtTI' HEAS0tl FOR WAIVER ALTERtlATE EXAMINATION,
WELD HUMBER 4.5 B-J (Con't.)
HU 262 B (2k")
The area of c: cam-Limited examination Best effort scan shall be Hil 262 C (2k")
ination shall in-due to tee config-perfonned on as large a till 262 D (2k")
clude the ueld area uration.
percentage of the weld area as HU 264 B (2k")
one wall t hickness possible.
HU 264 C (25")
beyond the edge of HU 264 D (2k")
the weld.
s V
fill 298 K (4")
11U 298 F (4")
!!U 278 D (4")
H.acthr Coolant Drain Piping RC 9 (lk")
- i. 5 B-J Pressurizer The area of exam-Limited examination Best effort scan shall be Spray Piping Ination shall in-dne to reducing taper.
perfonned on as large a t1R l'06 to 104 clude the weld area percentage of t'he weld area as (15")
one wall thickness possible.
beyond the edge of this weld.
.5 B-J Reactor Cool-The area of exam-flo exaininat ion due Examinations will be performed ant Piping ination shall in-to geometry of plunp.
HK 55 to A-1 clude the weld area on one side of the gump weld. 3 with 0, 45 and 60.
WJ-2-2 one wall thickness
!!KA-1 to 49 eyond the edge of WJ-31-2 this wen.
i IIK 55 to A-2 WJ-2-1 HK A-2 to A-49 W.;-31-1 flK 55 to B 'll W.1-2 3 tlK 11-1 to 49 WJ 'll-3 tlK 55 to B-2 tlK H-2 to 49 L ' l- ?- 4,
W.1-11-4
._,-___-............~-
Page 5 Rev. 1 ASME Section XI - 1974 with Addenda thru Sunner 1975 NAME:
Piping Pressure Boundary TAG NO.
II/A ASME CLASS: 1
.E 8 _ 1Wii-7(,00 IMPRACTICAL 1 NO /CATECORY DESCRIPTION CODE REQUIREME!TE REASON FDR WAIVER ALTERNATE EXAMIt4ATION.
I B-K-1 Integrally Welds to the. press-Geometric configuration Dye Penetrant Examination welded supports ure-retaining bound-problem for ultrasonic ary and the base examination. Weld not metal beneath the designed for ultra-weld zone and along sonic volumetric exam-
-s the support attach-ination
,d ment member for a distance of t wo support thicknesses.
i I
HDE Inservice Inspection Waiver Request PCge 6 i Rev. 1 ASME Section XI - 1974 with Adderda thru Sununer 1975 NAME Pressure Vessels TAC NO.:
DilllE-1 A, IB ASHE CIASS: 2 ABLES IWC-2600 IMPRACTICAL TEM NO./CATECORY DESCRIPTION CODE REQillHEMENT REASON IVR WAIVER A!!rERNATE EXAMINATION
- 1.2 C-D A&B Decay lleat Examine 1007. of Limited examination Best effort scan shall be Cooler Nozzle total quantity.
due to weld config-performed on as large a percent (
to Shell Welds.
uration.
of total weld area as possible..
1.1 C-A A&B Decay lleat Examine 207. of No examination due lies t effort examinationshal*].
Cooler Nozzle total quantity.
to Flange configuration.
be perfonned from opposite stue to Flange Welds, of joint.
I 1.1 C-A AAll Decay lleat Examine 207. of 1.fmited examination due flest effort scan shall be Cooler Shell to Lote.1 quantity.
to bevel and head performed on as large a percenta llead Welds.
curvature.
of total weld area as possible.
- 1,1 C-A A&B Decay licat Examine 207. of Limited examination llest effort examination shall j
Cooler Shell to r'tal quantity.
due te flange, be performed on as large a perc~
studs and nuts.
age of total weld area as possia i
NDE Inservice Inspection Waiver Request Pegn 7 *.
Rey, 1 ASME Section XI - 1974 with Addenda thru Summer 1975 NAME:
Piping Pressure Boundary TAC NO.:
N/A ASME CI. ASS:
2 ABI.E:
IWC-2600 IMPRACTICAL y ~lO./CATECORY
'l DESCRIPTION CODE REQUIRE!!ENT REASON FOR WAIVER ALTERNATE EXAMINATION 2.1 C-F, C-G Ci rcumfe ren-Examination shall No examinations poss-Best effort scan shall be performed tici Butt include 100% of the Ible on the valve or on as large a percentage of the weld Welds.
weld.
flange sides of joints area as possible.
due to geometric con-fi gu ra t i on.
2.2 C-F, C-C 1.ongitudinal Examinatione shal)
Only ilmited scan Best effort scan shall be performed Weld Joints include 100% of possible on fittings on as large a percentage of weld in Fittings weld.
where branch lines area as possible, occur.
2.3 C-F, C-G liranch pipe Examinations 9 hall Only limited examina-Best effort scan shall be performed to pipe include 100% of t ton of the weld area on as large a percentage of weld weld joints.
weld.
is possible due to area as possible.
configuratlon.
IMMENTS:
1.
100% of the welds in the Decay lleat and Make-Up Systems were volumetrically examined on as large a percentage of the weld areas as possible during baseline examinations.
2.
Specific welds, for which a " Reason for Waiver" applies, are contained and recorded on the volumetric
)
examination sheets in the Preopera**"nal lospectional Manual for Crystal River Unit #3 which are on file at the plant-site.
3.
Although Appendix I, " Ultrasonic Examination" of the ASMS Code Section XI does not apply to piping, examinatton results are recorded on the data in accordance with 1-5120, " Extent of Scanning."
4.
Ilest effort and maximum practical extent of weld areas w il be examined in in-service inspections of alI required welds of Section XI and applicable addendas.
-.