NRC-87-0078, Forwards Response to Three Items of Addl Info Re 870131 Rev 0 to Change 2 to Inservice Insp/Nde Program Plan for Plant, Per NRC 870327 Request

Forwards Response to Three Items of Addl Info Re 870131 Rev 0 to Change 2 to Inservice Insp/Nde Program Plan for Plant, Per NRC 870327 Request

ML20214Q754
Person / Time
Site:	Fermi
Issue date:	06/01/1987
From:	Agosti F DETROIT EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-87-0078, CON-NRC-87-78 GL-84-11, IEB-80-07, IEB-80-13, IEB-80-7, IEB-83-02, IEB-83-2, NUDOCS 8706050159
Download: ML20214Q754 (8)

Text

._

)

DOITOil Femil2 Edison HEiEN c:a June 1, 1987 NIC-87-0078 U. S. !bclear Regulatory Commission Attna Document Control Desk Washington, D. C.

20555

References:

1) Fermi 2 NIC Docket No. 50-341 NBC License No. IPF-43 2)

Inservice Inspection - Non Destructive Examination (ISI-EE) Program Plan for Fermi 2, Revision 0, Change 2, dated January 1987.

3)

NIC Letter to Detroit Elison Conpany, " Request for Mditional Information Relative to the Fermi 2 First Ten-Year Interval Inservice Inspection Program Plan,"

data 3 March 27,1987.

Subject:

Mditional Information on First Ten-Year Interval ISI Procram Plan In the Referencs 3 letter, the NIC requested Detroit Riison to provide additional information on the Fermi 2 ISI-f0E Program (Reference 2).

As stated in the request, the inforlaation is needed by the Nlt Staff j

to couplete its review and evaluation of the Fermi 2 ISI-mE Program for the first ten-year interval of inspection.

Detroit Eli z.I's response to the three itens of a3ditional information requested is enclosed. Also, as requested, a copy of this respotse is being sent to the attention of Mr. B. Brown at Idaho National Digineerirvj Laboratory (INEL).

1

\\

a 8706050159 870601 i

[

PDR ADOCK 05000341 G

PDR,

l L

s USNIC Anne 1, 1987 NIC-87-0078 -

Page 2 If you have any questions regarding this submittal, please contact Mr. Iewis Bregni at (313) 586-4072.

I Sincerely,

_ '4. T.

F. E. Agosti Vice President MJGlear Operations Enclosure oc:

B. Brown (INEL)

)

A. B. Davis W. G. Rogers J. J. Stefano

(

E. G. Greenman l

l l

l l

~

.- - - ~. -

w Ehclcsure ta NIC-87 -0078 Page 1 ADDITIONhL IIFOINATION REWESZlD

.A.

Plans fcy inservice er. amination of the Beacter pressure Veseel' welds shouM address the degree of compliance _with Regulatory aside 1.150, " Ultrasonic Testing Of Reactor Vessel Welds During a

Preservice ard Inservice Examinations". Discuss the near-surface e

examination and resolution with regards to finding service irduced flaws and the use of electronic gating as related to the volume 60 material near the surface that is not being examined.

Detroit B!Ison h p Item Ar Inservice examircations of the Beactor Pressure Vessel will be performed using both manual and mechanical examination tecimiques from the outside surface of the vessel. The CRP presentation, which is the primary data acquisition technique to be used.for recording and analysis, is not electronically gated to esclude any areas during either the manual or mechanized examinatioris.

i The eltetronic gate / strip chart is used as a supplemental data recording system during mechanized examinations to flag areas of.

major concern.

Mere is a sinall volume, typically less than 1/2 inch, on the outside entry surface of the vessel which ic, masked by the initial pulse of the trans2fucer in which irdications would not be detected. This initial pulse effect is minimized by the design -

of trensducer wedges, in ithe case of manual examinations; or the modales which hold rultiple' transducers when performing examinations using mechenized technigaes.. The effect of this initial pulse as well as any other limitations encountered which affect the examination vollune as prGacribed by ASEE Section' XI i

will be documented in an emination report as required by -

Regulatory G2ide 1.150, Revision 1, Appendix A.

I Regulatory Q2ide 1.150, Revision 1, Appendix A, Section 3.1(a) addresses, as a primary concern, the vessel inner surface area and_ recocuends tie use of the 2 percent notch which panetrates the internal (clad) surface of calibration blocks' for detoction of flaws in the region. This is the calibration.and examic9 tion method that will be used. Therefore, service induced flaws which may originate in the inner surface clad material and propagate i

into the base material in the order of magnitude of the 2%

calibration notch specified in Section V, Article 4, Figure T-44.1 would have a.h!.gh probability of detection depending upon their orientation with respect to the search units.

Indications, regardless of applitude, will be recorded on tape during' the mechanized examissations for analysis. Similarly, signal responses will be scrutinized durire the manual examination process and indications will be recorded for further malysis and_ resolution.

i

.-+

i

+

Ehclosure to 15C-87-0078 Page 2 B.

The Licensee has discussed the augmented examinations that will be performed in accordance with NURBG-0313 and -0619, IE Bullet.in l

Nos. 80-07 and 83-02, and NIC Generic Letter 84-11. In addition to the requested infoimation in item A above, discuss any other augmented examinations that will be performed during the first 10-year inspection interval (e.g. compliance with NURBG-0800, Section 3.6.1; NURBG-0803; IE Bulletin 80-13; etc.).

Detroit Elson Response to Item Br IURBG-0803, Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping.

With regard to piping, Detroit Eison has' performed or.has incorporated into its program the following itens which satisfy the staff recomendations contained in NORBG-0803.

1.

To ensure the integrity of the Sctam Discharge Volume (SDV) piping and supports a walkdown of the SDV piping system was performed to verify the as-built condition. A seismic i

analysis and stress report was performed on the piping system in accordance with A!ME Section III, Class 2.

2.

EDV piping welds have been selected in aocordance with requirements of AfME Section XI, and have been included in the ISI-PDE Program (Reference 2, page A-6-81).

3.

A preservice weld inspection using Ur and MP has been performed for the selected SDV piping welds.

In addition, although not reconsnended in NURBG-0803, a visual walkdown of the SDV piping is performed os part of the leakage reduction program.

IE Bulletin No. 80-13, Cracking in Core Spray Sp&rgers This bulletin was forwarded to Detroit Eison for information and required no writtEra response. However, although IE Eulletin No.

80-13 is not specifically addressed in the ISI-BOE Program, a visual examination (VT-3) of the core spray spargers and core-spray vessel interior piping is performed. This inspection is -

described on page A-6-59 of Reference 2.

Consistent with the examination frequercy and type given for vessel internals in A!ME Section XI, the core sprt.y sparger and interior piping are scheduled for inspection at the first refueling outage and every.

3 years thereafter. Please note there is an error in the nethod 1

of examination to be used as given in Reference 2.

A remote visual examination will most likely be used as opposed to direct.

i 1

i-

_ _ _.--,, _. _ - _ = =.. _... _, _. _, _-. _... _.s -

Enclosur@ to NIC-87-0C18 Page 3 Petroit Etlison Response to Item Bt (Cont.)

NUREG-080!), Standard Review Plan - Section 3.6.1., Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment.

There are no augmented inspections identified in the Fermi 2 ISI-?DE Progrge for piping between containment isolation valves.

We selection of Class 1 and 2 pressure retaining piping welds for inservice inspection was made using the requirements of ASME Section XI. These weld selection criteria are discussed in Part E, Appendices A and B of Reference 2.

Weld selection criteria include consideration for terminal ends, high stress, coderate stress, and random selection. These criteria were used to select welds for inservice inspection in piping between containment isolation valves as well. Therefore, es a result of the established method for selecting pipe welds, sume welds in piping between containment isolation valves are included in the ISI-10E Program.

Some welds that are located in piping between containment isolction valves are inaccessible (i.e. those within penetration assenblies). Cn the basis of tre established weld selection criteria, one moderate stress weld would have required examination. For this case a specific relief request has been made and is contained in Section 4.0 of Reference 2.

It should be noted that the Fermi 2 Construction permit

@ plication was tendered in 1969, which precedes the date of issuance of NUREG-0800.

L

Belosura to i

NIC-87-0078 -

Page 4 i.

C.

Provide the staff withia reference list of calibration blocks including identificationsi material specifications, and sizes:

Detroit E$ison Response to Item Cr REFERE!CE ID No.

DESCRIPTION MATERIAL TYPE HEAT ND.

SS-2 28-XXX-1.5-SS-2-FER A!ME Sh-358 (Sh 240 GR. 304) 24720 SS-3 2&XXX-1.076-SS-3-FER A!ME SA-358 (Sh 240 GR. 304) 24720 CS-5 26-XXX-1.125-CS-5-FER A!ME SA-155-GR NCF 70 9919 (Sh-516 GR. 70)

CS-6 26-XXX-1.500-CS-6-FER A!ME Sh-155 KC70 (Sh-516 2G2575 GR. 70)

CS-7 24-100-1.531 CS-7-FER AfME SA-106 GR. B.

453543 SS8 24-100-1.531-SS-8-FER A!ME Sh-358 (Sh 240 GR. 304) 724043 I

CS-9 24-80-1.218-CS-9-FER AfME SA-106 GR. B

~ L25222 l

SS-10 22-XXX-1.125-SS-10-FER A!ME Sh-240 GR. 304 855315 CS-ll 20-100-1.281-CS-ll-FER AfME SA-106 GR. B 253732 (Sh 333 GR. 6)

CS-12 20-80-1.031-CS-12-FER A!ME Sh-106 GR. B L25047 SS-13 20-80-1.031-SS-13-FER AfME Sh-358 GR. 304 855315 (SR 240 GR. 304) l CS-14 14-XXX-1.0-CS-14-FER A!ME SA-106 GR. B L20993 CS-15 12-100-0.844-CS-15-FER A!ME Sh-106 GR. B 234537 SS-17 12-80-0.688-SS-17-FER A!ME Sh-358 (SR 240 GR. 304) 646518-2D CS-18 10-120-0.844-CS-18-FER A!ME Sh-106 GR. B L61275 SS-19 10-80-0.594-SS-19-FER A!ME Sh-376 GR. 304 535641 CS-20 8-160-0.906-CS-20-FER A!ME SA-106 GR. B 252086 CS-il 6-160-0.719 CS-21-FER A!ME Sh-106 GR. D N54044 CS-22 6-120-0.562-CS-22-FER A!ME SA-106 GR. B N54029 SS-23 4-160-0.531-SS-23-FER A!ME Sh-376 GR. 304-M0118 CS-24 4-120-0.434-CS-24-FER A!ME Sh-106 GR. B G97821-l SS-25 4-80-0.337-SS-25-FER A!NE Sh-376 GR.' 304 M2152 CS-26 3-160-0.438-CS-26-FER AfME SA-106 GR. B

- L24259 i

CS-27 2.50-160-0.375-CS-27-FER A!ME SA-106 GR. B X773794 SS-28 2-160-0.344-SS-28-FER A!NE SA-182 GR. F304 75678 SS-29 1.5-160-0.281-SS-2 M ER AfME SA-132 GR. 304 SZ460 l

SS-30 28-XXX-2.5-SS-30-FER A!NE 358- (Sh-240 GR. 304)

IK5853 CS-31 20-XXX-1.5-CS-31-FER A!ME Sh 516 GR. 70 2C1676 CS-32 12-140-1.125-CS-32-FER A!ME SA-106 GR. B 45860 I

SS-33 PL.750-SS-33-FER A!ME SA-240 GR. 304 F81443 l

l SS-34 PL-1.5-SS-33-FER AfME SA-240 GR. 304 F74272

{

CS-35 2-XXX.4-CS-35-FER A!ME SA-106 GR. B N57214 CS-36 10-80.594-CS-36-FER A!ME SA-106 GR. B LO4243 CS-37 10-160-1.125-CS-37-FER A!ME Sh-106 GR. P, 252486 CS-38 12-80.688-CS-38-FER AME SA-106 GR. 3

' N13535 CS-39 14-80.750-CS-39-FER A!ME SA-106 GR. B N12947 CS-40 18-40.562-CS-40-FER A!ME SA-106 GR. B LO2322

{

CS-41 18-80.938-CS-41-FER A!ME Sh-106 GR. B

-N95312 CS-42 20-40.594< S-42-FER A!ME Sh-106 GR. B 33210 1

i CS-43 24-40.688-CS-43-FER A!ME SA-106 GR. B LO3155 i

74...-,,.,.

.o_......_..-

-..~..,m

.y

,y.._,-._,

..,y

..y_

.y,_...

y__.__._y..

,.m.,,,_yy..

n.,c,.

w..,,,,

..~w

..,.,n.y

'Ehclosura to NRC-87-0078 Page 5 REFERE2CE ID No.

DESCRIPTION MATERIAL 'IYPE HEAT NO.

CSCL44 12.750-CSCL-X-1.0262-AEME SA-508 CL2 218993 44-FER IN-45 12.9-IN-X-1.165-45-FER AfME SB 166 AVX CS-46 14.125-CS-X.95-46-FER AfME SA-508 CL2 218993 CSCL47 5.438-CSCL-X.813-47-FER AfME S1508 CL2 218993 CSCL48 6.438-CSCL-X.782-48-FER A!NE SA-508 OL2 218993 IN-49 6.5-IN-X.802-49-FER AEME SB-166 2155-0-3443 CS-50 10-100.719-CS-50-FER AEME SA-106 GR. B N52963 CSCL51 IR-CfCL-51-FER AfME SA-508 CL2 02Q99NQP CSCL52 FS/L-CSCL-52-FER A!NE SA-508 CL.2 Q20100NQRP CS-53 8.75-6.25-8-CS-53-FER AfME SA-540-GR B24 6051044 CECL54 14.5-CSCL-X-1.200-54-FER ASIM A-508 CL2 020110NQP CSCL55 29.375-CSCL-X-1.760-55-FER ASIM A-508 CL2 020110NQP SS-56 14.5-SS-X-1.200-56-FER ASIM A-182 F304 82741 SS-57 29.375-SS-X-1.500-57-FER ASIM A-182 F304 82741 f

SB-58 SB-2667-58 AfME SA-533 GR. B CL.1 C5445-1 SB-59 SB-2667-59 AfME SA-533 GR. B CIASS 1 C4504-3 SB-60 SB-2667-60 ASME SA-533 GR. B CIASS 1 C4505-3 SB-62 SB-2667-62 AfME SA-533 GR. B CIASS 1 -

C-4578 SIAB 1 ED-63 SD-2667-63 ASME SA-508 CIASS 1 AEME SA-508 CIASS 2 ED-64 ED-2667-64 AEME SA-508 CIASS 1 216617 ASME SA-508 CIASS 2 AV 3504-909446 ED-65 SD-2667-65 AfME SA-508 CIASS 1 OlOlN-772B-4 AfME SA-508 CIASS 2 IV-3459 SER 194 ED-66 SD-2667-66 AfME SA-508 CIASS 1 OlOlN-773B-7 AEME SA-508 CIASS 2 IV3459 SER 194 ED-67 SD-2667-67 AEME SA-182 F304 Cl335 ASME SA-508 CIASS 2 AV3926 SD-68 ED-2667-68 SA-182 F304 61581-CV A!NE SA-508 CIASS 2 2L-1318 ED-69 ED-2667-69 AEME SA-182 F304 AfME SA-508 CIASS 2 ED-70 SD-2667-70 ASME SB-166 9492 AEME SB-182 F304 3082570 SC-74 SC-2667-74 AEME SA-540 GR. B24 ED-76 ED-2667-76 AEME SA-508 CIASS 2 AV3929-9E9210 ED-77 SD-2667-77 AEME SA-508 CIASS 2 AV3929 9E9210 SD-78 ED-2667-78 AEME SA-508 CIASS 2 E -4A CB&I MK-4A SB-166 SA-508 CIASS 1 MK-5A CB&I N -5A SB-166 SA-508 CIASS 2 B31 CAP GE 66B9241 SA-403 GR. 304 743668

Enclosur@ to IGC-87-0078 Page 6 RITERi@CE ID No.

DESCRIPTION MATERIAL TYPE HEAT NO.

B31S'IU B-3047025 AS40 GRADE B-23 95865 CS-79 IR-CSCL-79-FER SA-508 CIASS 2 Q20lllNQP CS-80 PL-1. 5-CS-80-FER SA-516 GRADE 70 2G7527 CS-81 IR-CS-81-FER SA-105 5458619 KCE

- 1. 53 - CS FER Reference ID No.

Wall Thickness Pipe ~ Schedule Pipe Diameter CS-Stainless Steel CSCL-Carbon Steel Clad PL-Plate CS-Carbon Steel IN-Inconnel XXX-Special Thickness or Schedule ED-2667-70 This series of calibration blocks supplied by Conbustion Ehgineering i

d i

i

-