ML20079F917

Interrogatories Re Steam Generator Repair (Set 1). Certificate of Svc Encl

ML20079F917
Person / Time
Site:	Three Mile Island
Issue date:	01/16/1984
From:	Aamodt N, Jun Lee AAMODTS
To:	METROPOLITAN EDISON CO.
Shared Package
ML20079F903	List: ML20079F899 ML20079F908 ML20079F911 ML20079F917
References
NUDOCS 8401190344
Download: ML20079F917 (6)

Text

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- UNITED STATES OF AMERICA -

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'I NUCLEAR REGULATORY COMMISSION -

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(

BEFORE THE ATOMIC SAFEIT AND LICENSING BOARD l

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00CKETED

-In the Hatter of ) CSNPC

)

METROPOLITAN EDISON COMPANY,'ET AL. ) Docket 50-289 .

) (Steam Generator bpsN)18 A10 :42 ,

.(Three Mile Island Nuclear ) -

Generating Station, Unit 1) ) LFFICE OF SECRETAP -

' 00CHEi!!G & SERvit SRANCH LEE ET AL. INTERROCATORIES OF LICENSEE (SET 1) ,

' l. Wat is the composition of the tubes. in the steam generators at THI (1)

(hereafter referred to as " tubes")?

a) Give range of content of each element, b) Give range of content of each sulphur compound.

2. What contaminants were present in tube material "as received"?

3. Wat is the range of the content of the contaminants described in answer to 1(2)27

4. Wat precipitates were found within or on the flanks of tube cracks generated in the plant?

5. Wat precipid rce re found within or on the flanks of cracks

, generated in laboratory tests?

6. Give composition of tubes of 1(2)4.

7. Regarding samples of 1(2)5

--provide composition of samples

--provide sample preparation method (s), including heat treatment

--provide test description, including test environment

--provide method whereby crack composition was evaluated ~ '

--provide all test procedures

--provide all test data .

8. Describe in full'the mechanism (s) licensee relies upon to describe ICSCC generation in the tubes of the CISG.

9. Describe all programs conducted by or for licensee to determine whether agents other than sulfur contributed to IGSCC. ,

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10. Provide all results obtained from the programs described in answer to 9.

c. 11. Describe all programs conducted by or for licensee to deter =ine whethe r

' 0 agents other than sulfur caused IGSCC.

to 0 12. Provide all results obtained from the programs described in answer to 11.

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13. What significance does liccusee place on IGA islands remote from

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< expansion area?

l b8 14. What progression of morphological change does licensee rely upon to describe IGA islands over the projected life of the CISG's?

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15. Provids list "of all alsments, compsunds, and other esntaminants cnd chair censsntraticos which ceuld be expectad to be fcund in thz watar passing through the tubes of the CISG's ever their expected lifetime.

In the following qtscions, reference is made to Rep' ort of the Third Party

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Review of Three Mile Island,11 nit 1, Steam Generator Repair,. Supplement 1 May 16, 1983 16 a. Has Licencee obtained a Total Organic Carbon (TOC) analyzer?

b. If not, when does Licensee expect to obtain one?

c. Has Licensee in its employ personnel who are trained to use and/or interpret the data obtained from a TOC 7

d. Identify these personnel.

e. Describe the technical specifications of Licensee's TOC, if existent, relative to PPM. (See page 3, "Further Comment 3".)

17. Has Licensee determined the nominal or " background" sodium'as recommended at page 4, "Purther Comment 6".

18. a. As discussed at page 4, "C. Materiala Application, Comment 1",

have any sus 11 cracks, not detected at the time of the repair of the tubes been detected since that time?

b. Have any further inspecti~ons beer. conducted since the repairs until the present time?

c. If so, provide the results of these inspections (and dates),-

names of GPU or contractor personnel who made the inspections.

19. Co.2cerning the recommendation at page 5 "Cosanents 2 and 3", what plans has Licensee made and/or implemented to make corrosion tests?

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20. , Provide Licensee's assessment of the effectiveness of removal of l sulfur from steam generators.

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21. Has Licensee observed any harm to the plant, in- any way, shape or l

form, as a result of the flushing of the plant? If s'o, describe

- observations with specificity including dates and personnel involved.

22 Relative to page 5 " Comment 4 and Recommendation 1", last para. ,

provide the opinions of other experts, including the identity of ,

these experts, known to Licensee, concerning the desirability or necessity for sulfur removal to be completed.

23. Provide the analysis of the cause of the anomalous data from the beaker test which would allow data to be set aside. (Ref. page 6, first para.)

2! . How does Licensee explain the uncertainty concerning percentage of residual sulfur, estimated between 20 and 50. at page 67

25. a. How will Licensee manage the "co= plicated precess" of control of sulfur residues?

b. What Licensee personnel,have been assigned to this function?

c. Provide identity and qualifications of these personnel,

d. Provide job assignment of these personnel if prihary assignment is other 'than sulfur control and percent of job time estircted to be assicned to sulfur control.

. paga 3, est 'l Licantsa .

26. What " upsets" in the chemical control of sulfur residue have been identified as possible and defined by the third party review committee, its members individually, or other experts? -

27. Provide the procedure which will address the sampling of the process control of peroxide flush based on the skeletal proposal of Table B-1, TR-010.

(See .page 6, Further Comment 1, Report , Phy 16, 1983)

27. Has Licensee evaluated the potential for chloride throw from the sulfate removal resin? If so, provide evaluations. If not, why not? -(See page. 7, para, one)

! 28. Provide any documentation and/or information, verbal or written, that addresses the issue of agents other than sulfur as being the cause or a potential contributing factor towards corrosion in the steam generator l tubes.

29. Provide any documentation and/or information, verbal or written, t

.concerning the action of synergists in the chemical and/or metallurgical processes leading to IGA of nickel base austentic and/or other alloys. -

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30. Describe all studies conducted fo.rfLicensee to evaluate the effect of the following parameters on intergranular crack initiation and/or growth:

1. Carbon content of alloy i

2. Titanium content of alloy

3. Sulfur content of alloy

4. Water temperature

5. PH of water

6. Boron content of water

7. Radionuclide content of water

8. Sodium content of water

9. Chlorine content of water

31. Describe all studies conducted by or for Licensee to ' evaluate the inter-relationships of the effects of the parameters listed in (18) on intergranular crack initiation and growth.

32. Provide all documents generated by or for Licensee or relied upon- by Licensee in the studies (both laboratory and literature-based) described in response to questions (30) and (31).

33. Describe all cases of intergranular attack observed in plant piping and the tubes of the steam generators prior to 1962

34. For each case described in your answer to Question 33, provide the L fo: lowing data:

a. Descriptice of morphological changes noted, including depth end circucierential arc of sny cracks

b. Analysis of pipe or tube alloy

c. Analysis of water (esticated if measurements were not made) which contacted these pipes and tubes over their

• lifetine prior to observed morphological changes

35. For each case described in your answer to Question 33, describ'e the mechanism upon which Licensee relied to describe the cause of

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morphologicci chang 2 ,

36. Provide all information concerning the repair process used in repair of the steam generator tubes. Include all proprietary information, chemicals used.and their intended function, the flushing process, and all other processes.

37. Provide all information concerning problems encountered with the repair process, including all verbal and written com=unications between any or all of the following: Licensee personnel, contractor personnel, L1:ensee experts / consultants, NRC Staff, Third Party Review Group or any of its members, NRC Staff experts / consultants, Babcock and Wilcox personnel or consultants.

38. Describe, in full, Licensce's administrative program for the detection of breaks in the steam generator tubes.

39. Describe any past relationship (s) between Licensee and any member of the Third Party Review Group.

40. Did Licensee proaride or promise any renumeration of' any king to any member of the Third Party Review Group?

41. Did Licensee participate in the NRC Staff's selection of the members of the Third Party Review Group?

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50-289/83-26 The following question pertain to NRC Inspection Report

42. Concerning the release of Krupton gas on August 29, 1983, was the tracer gas

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' being used to test the intergrity of the steam generator tubss?

43. Has Licensee determined whether any gas was released because of a failure, or multiple failures, in the tube (s)?

44.. Describe the identified paths of leakage. .

45. At any time during the review of this event by Licensee management or plant personnel was it believed that there was any release of Krypton through the stes= generator tube (s)?

(a) If so, by whom?

(PIR) No.1-83-14, there was uncertainty 46.

In. Plant Incident Reportconcerning the path of leakage which was resolved in a r to this report. Explain the uncertainty, how it was resolved, and provide the identity of all the persons involved.

'7.

- Were any inspections , repeirs, or adjustments made to the stesu generator If there tubes between 3:30 p.m. on August 29,15f.,3, and 1.ugust 30,19237 were any such inspections, repairs, or adjustments, describe them.

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Rafcrring to ACRS Mesting cf Jcnuary 28, 1983, provida answers t'o tha j

, i fallowing quentiens-i

48. Explain Licensee's identified inad'equacy of present emerscncy action

• levels re condition of steam tubes as discussed at page 211.

49. Explain how the emergency use of the condensate storage tank at TMI-2 in the event of steam tube rupture at THI-1 (as discussed at page 199) is consistent with the separation of waste handling of Units 1 and 2.-

50. De::cribe staffing that Licensee has committed to monitoring of leak rates from steam generator tubes (see page 214). ,

51'.. Provide the procedures which administer the monitoring of leak rates from steam generator tubes (See page 214).

52 Provide the ATOG procedures that have been modified or created to deal with the steam generator tube problem.

53. Provide documentation concerning proposed change of .20 degrees in subcooling i tempetature as discussed at page 222 .

54 Provide GPU Nuclear presentations made at April 12 and 13,1983 meetings with Third Party Review Group.

Pursuant to 10 C.F.R. 2.740b and 2.741, the joint intervenors, Lee et al. ,

hereby request that Licensee answer separately and fully in writing, and under v

oath, each of the above interrogatories. These interrogatories are intended to be continuing in nature, and the answers should b.e promptly supplemented or amended as appropriate, pursuant to 10 C.F.R. 2.740_(e), should Licensee or any ,

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one acting on their behalf obtain any new or differing informat' ion responsive,to ,

these interrogatories. Licensee is to respond according to the same standards 1 t

described in Licensee's First Set of Interrogatories and Request for Production i of Documents to Joint Intervenors, December 15, 1983 at pages 2'through 4. and i 15 through 16 Respectfully submitted,

. giac klQ-.i'.4'~

• Jane Lee / -

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6 b h.,o Norman O. Aamodt 3 rucry 16, 1934

. UNITED STATES OF AMERICA -

. NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD-D M r'E UWC In the Matter of. )

)

METROPOLITAN EDISON CUMPANY,*ET AL. ) Docket 50-28984 JM 18 Al0:42'

) (Steam Generator Repair) ,

(Three Mile Island Nuclear )

' Generating Station, Unit 1) ) 0FFtLE OF& SE(ith'i' 00CKEliNG SEM i.'

BRANCH CERTIFICATE OF SERVICE I hereby certify that copies of LEE ET AL. RESPONSES TO STAFF IhTERROGATORIES (12/23/83)

LEE ET AL. RESPONSES TO LICENSEE'S FIRST SET OF IhTERROGATORIES LEE ET AL. IhTERROGATORIES OF NRC STAFF (Set 1)

LEE ET AL, INTERROGATORIES OF LICENSEE (Set 1) in the above-captioned proceeding have been served on the following by' -

deposit in the United States mail, first class, this 16th day of January 1984.

Sheldon J. Wolfe, Chairman Docketing & Service Section Atomic Safety & Licensing Board Office of the Secretary U. S. Nuclear Regulatory Consnission U. S. Nuclear Regulatory Commission Washington, DC 20555 Washi ' ton, 20 55 Dr.' James C. Lamb, III 313 Wood haven Road /vh*b 8 Chapel Hill, No-th Carolina 27514 Dr. David Hetrick Professor of Nuclear Energy University of Arizona Tuscon, Arizona 85721 ,

'Three Mile Island' Alert i 315 Peffer Street .. .' ,

Harrisburg, l'A -

1 l Atomic Safety & Licensing Appeal Board ,

l Board Panel ,

l U. S. Nuclear Regulatory Cocxnission  :

Washington, D. C. 20555 l George F. Trowbridge, Esq.

Shaw, Pittman, Potts & Trowbridge '

1800 M Street, NW Washington, DC.20036 [

Richard J. Rawson, Esq.

NRC Legal Offices Nucicar Regulatory Co=:sission Washington, D. C. 20555

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