ML20098F070

Responds to 840917 Request for Addl Info Re 1984 Refueling Outage Insp Program for Stainless Steel Piping.Topics Addressed Include Sampling Plan,Qualification of Exam Personnel,Leak Detection & Leakage Limits

ML20098F070
Person / Time
Site:	Hatch, Robinson
Issue date:	09/26/1984
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
GL-84-11, NED-84-506, TAC-55236, TAC-55488, TAC-55489, NUDOCS 8410020285
Download: ML20098F070 (4)

Text

j Georgia br Company 333 Piedmont Avenue Atlanta. Georg:a 30308

. Telephone 404 5266526 Mailing Mrfress:

Post off:ce Box 4545 A:tanta, Georgia 30302 Georgia Power

' L T. Gucwa t*v3 southem etectic sys:em Manager Nuclear Engineering and Chief Nuclear Engineer Septa ber 26, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4

. Division of Licensing U. S. Nuclear Regulatory Ccanission Washington, D. C.

20555 NRC DOCKLT 50-321 OPERATING LICENSE DPR-57 EDWIN I. FRIGI NUCLEAR PIAVf UNIT 1 RESIONSE 'IO NRC REQUEST FOR ADDITIONAL INFOFMATION ON 1984 REFUELING OUTAGE INSPECTION PROGRAM C4ritl een:

Georgia Power Ccapany (GIC) hereby provides the following infennation in response to the Septenber 17, 1984 telecupy fra the Plant Hatch NRC Licensing Project Manager, Mr.

G.

Rivenbark, raluesting additional information concerning our May 31, 1984 subnittal on the 1984 Plant Hatch Unit 1 refueling outage inspection plans for stainless steel piping.

We four topics addressed in the telecopy were smpling plan, qualification of exmination personnel, leak detection and leakage limits, and plans for other inspections in selected ccaponents as a result of IGSCC observed at other utilities.

SAMPLING

%e ntaber of welds scheduled to be exmined by size and category as identified in NRC Generic Letter 84-11 are:

Welds Not Exmined Previously 4" Recirc - None to be ex mined, 100% exmined during previous outage 12" Recirc - 6 welds to be ex mined 22" Recirc - None to be exmined, 100% exmined during previous outage 28" Recirc - 6 welds to be exmined None to be ex m ined, 100% exsiined during previous outage 20" RHR None to be exmined,100% exmined during previous outage 24" RHR 3 welds to be exmined 6" IECU Subtotal - 15 welds to be exmined 8410020285 840926 l 0 PDR ADOCK 05000261 G

PDR

r-GeorgiaPower d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief

-Operating Reactors Branch No. 4 Septaber 26, 1984 Page Two Welds Exmined Previously 4" Recirc - 1 weld to be exmined (bypass reoved during 1977 refueling outage) 12" Recire - 5 welds to be exmined 22" Recirc - 3 welds to be exmined (in addition, 5 more. welds are to be exmined due to weld overlay repairs or being left unrepaired - see below) 28" Recirc - 2 welds to be exmined 1 weld to be exmined (in addition, 1 more weld to be 20" RHR exmined due to weld overlay repair - see below) 1 weld to be exmined (in addition, 1 more weld to be 24" RHR ex mined due to weld overlay repairs - see below) 2 welds to be exmined 6" FWCU Subtotal - 15 welds to be ex mined overlay Repaired Welds (Notes affected piping size only shown) 22" Recirc - 4 welds to be exmined 1 weld to be examined 20" RHR 1 weld to be exmined 24" RHR Subtotal - 6 welds to be exmined Cracked, Unrepaired Welds (Note affected piping size only shown 22" Recirc - 1 weld to be exmined i

Subtotal - I weld to be exmined ibtal - 37 welds to be exmined fra above fcur categories GC has reviewed the requirments of NRC Generic Ietter 84-11 and has determined that the scope of exmination muct be expanded to meet minimum requirments for 6" BWCU not exmined previously and 4" Recirc exminal previously.

Consequently, four welds (vice three noted above) will be exmined for 6" mcu not exmined previously and two welds (vice one noted l

above) will be exmined for 4" Recirc exmined previously in lieu of that shown above.

7herefore, the grand total of exminations has increased to thirty-nine (39) welds requiring exmination for the four categories specified in NRC Generic letter 84-11.

[

Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Septaber 26, 1984 Page Gree PIANS IOR OTHER INSPECTIONS In addition to the above proposed smple, the following exminations will be peciomed as a result of recent cracking experienced at other NTi utilities:

a)

At least one recirculation outlet nozzle-to-safe end weld and two recirculation inlet nozzle-to-safe end welds will be exmined during the upcming Plant Hatch 1 outage.

These inspections were comitted previously by GPC to NRC through the GE BWR Owners Group response to NRC regarding cracking in Inconel-clad safe ends and nozzles; b)

Fifty percent (50%) of the recirculation inlet nozzle themal sleeve attachr.ent welds will be exmined during the upcming outage. Should unacceptable indications be observed, the reaining 50% would then be exmined, radiation levels pemitting.

%e configuration of these welds at the Plant Hatch units differ significantly frm those units observing cracking in this typo weld in that the themal sleeve does not weld to the nozzle safe end at either Plant Hatch unit. n is was discussed in considerable detail with NRC Region II personnel during a telephone conversation on August 16, 1984; and c)

Both "A" and "B" recirculation loop jet pmp instrmentation nozzle safe end-to-penetration seal welds will be ex mined during the upcming outage. %o safe end-to-nozzle welds for these particular nozzles will not be exmined since they were exmined during the previous outage.

QUALIFICATION OF UT PERSONNEL We infomation provided in our May 31, 1984 sutaittal was spec.fic regarding qualification of UT personnel in that a)

It did indicate that procedures similar to those previously qualified at Battelle-Colmbus (BCL) for IGSCC detection would be used.

ne latest approved revision of the procedure technically meets or exceeds the originally BCL-qualified procedure, e.g.,

calibration requirt ments, recording requirments, etc.

Further, similar procedures, techniques, etc. have been reviewed and found acceptable for use through NRC Region II I&E inspections at Plant Hatch during inservice inspection activities; and

z. -

' GeorgiaPbweiA yDirector of Nuclear Reactor Regulation

- Attention: ~ Mr. John F.. Stolz, Chief.

Operating Reactors Branch No. 4

Septaber 26, 1984.

Page Four F

b)

~ It did indicote that various Invels II and III inspection personnel who will perform data evaluation have been qualified in the

' detection of IGSOC through the process currently in effect at the EPRI. NDE ' Center. -

EE. personnel under contract to our : primary

' inservice; inspection group, Southern Ocznpany Services, who have qtalified at the EPRI EE Center in the detection and

. interpretation of IGSOC' may also perform. exminations. and evaluations, as appropriate. ~ As is_ the case of the procedures, inspector qualification is subject to audit by NRC regional

- personnel and have met the necessary requirments to date.

e With regard ~ to qualification of personnel in sizing of IGSCC, NRC has not

formally notified GPC through implementation letter, bulletin, etc. per the' NRC's' review and. approval process that' this is a requirment.

In-anticipation.of any such future sizing qualification requirment, the t

primary inservice inspection group to be used at Plant Hatch has -several Iwals II; and III personnel on its staff qualified through the EPRI NDE Cent.er ' for the sizing of cracks.

hose personnel and any subcontractor personnel similarly qualified can be used for sizing of IGSCC indication depth should reyrtable indications be observed.

LEAK DEIECTIN AE IEAKAGE LIMITS Our May-31,1984 _sutaittal indicated that proposed Technical Specification changes to aucynent these existing reactor coolant leakage ~ detection requiranants were subnitted ~ to you by letters dated February 10 and 11, 1983.

He proposed changes were subsequently reviewed and approved as discussed :in the NRC's Plant Hatch Unit 1 Safety Evaluation Report ~ dated

~

February 11, 1983.

% e proposed changes meet the intent of the leak detection and leakage limits discussed in Attachnent 1 of NRC Generic IAtter 84-11. No changes other than those discussed in Section 2.5 of AttachNnt 1 to ocr May 31 subnittal are planned.

o Should you have any questions in his regard, please contact this office.

Sincerely yours,.

' q f.bes-h

'^

L. T. Gucwa

-JAEAnb xc:

J, T. Beckhm, Jr.

=H. C. Nix, Jr.

J.: P. O'Reilly (NRC-Region II)

Senior' Resident Inspector