ML18031A985
| ML18031A985 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/10/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| GL-84-11, NUDOCS 8611140203 | |
| Download: ML18031A985 (9) | |
Text
ACCEBBI8N NBR:
FACIL:50-259 50-260 50-296 AUTH. NAI'IE QRXDLEYiR.
REGULATOR NFORI'IATION DISTRIBUTION S'TEI'I (R IDS) 86 1 1 140203 DOC. DATE: 86/1 1/10 NOTARIZED:
NO DOCKET Browns Ferrrl Nuclear Power Stations Unit ii Tennessee 05000259 Browns Ferrrj Nuclear Power Station>
Unit 2>
Tennessee 05000260 Browns FerrrI Nuclear Power Stationi Unit 3i Tennessee 05000296 AUTHOR AFFILIATION Tennessee Vallerl AuthoritrI RECIPIENT AFFXLIATIQN BWR ProJect Directorate 2
SUBJECT:
Forwards response to II Qrotenhuis 860326 request For addi info re stainless steel piping reinspr per Generic Ltr 84-11.
Response
to NRC 861003 questions re results of recent insps will be submitted when corrective action plan completed.
DISTRIBUTION CODE:
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RECIPIENT ID CODE/NAI'IE BWR EICSB BWR PD2 LA GEARS> Q BWR RSB COP IES LTTR ENCL 2
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TENNESSEE VALLEYAVTHORITY CHATTANOOGA, TENNESSEE 3740 l 5N 157B Lookout Place IOV l 0 1986 Director of Nuclear Reactor Regulation Attention:
Mr. D. R. Muller, Project. Director BWR Project Directorate No.
2 Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Muller:
In the Matter of the Tennessee Valley Authority Docket Nos.
50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT STAINLESS STEEL PIPING REINSPECTION (GENERIC LETTER 84-11)
By letter from Marshall Grotenhuis to S. A. White dated March 26,
- 1986, we received a request for additional information regarding, stainless steel piping reinspection at the Browns Ferry Nuclear Plant (BFN).
Enclosed is our response to that request.
The technical specifications requested will be submitted separately.
TVA acknowledges receipt of the October 3, 1986 questions concerning the results of recent inspections of the recirculation inlet nozzle and core spray nozzle safe-ends.
We are currently finalizing the corrective action plan for these safe-ends and will respond to these questions when this plan is completed.
If you have any questions, please get in touch with M. J.
May at 205/720-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY Enclosure cc:
See page 2
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R.
ridley, Di ector Nuclear Safety and Licensing 8611140203 861110 PDR ADOCK 05000259 8
PDR p,,l l
1 An Equal Opportunity Employer
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Director of Nuclear Reactor Regulation NOV 10 $86 cc (Enclosure):
Mr. G. E. Gears U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue
- Bethesda, Maryland 20814 U.S. Nuclear Regulatory Commission Region II ATTN:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. G.
G. Zech
- Director, TVA Projects U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
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ENCLOSURE
RESPONSE
TO MARSHALL GROTENHUIS'S MARCH 26, 1986 LETTER TO S. A. WHITE REGARDING PIPING REINSPECTION BROWNS FERRY NUCLEAR PLANT 1.
NRC RE VEST Post Induction Heatin Stress Im rovement IHSI Ins ection Provide assurance that if 100% of the IHSI welds are not inspected the examination of the remaining, welds will be completed at the next refueling outage.
Of course, the sampling will be expanded if crack indications are reported in the IHSI treated welds.
TVA RESPONSE Unit 1 No IHSI treatment has been performed on unit 1. If TVA elects to replace pipe on this unit, IHSI treatment of field welds may be performed.
Since this would constitute IHSI treatment of new, resistant material, post-IHSI inspections will be performed based on prevailing regulatory guidance for this category material.
If TVA does not replace pipe on this unit and elects to pursue alternatives, IHSI treatment will be a part of this strategy.
In this case, post-IHSI inspections will be performed consistent with prevailing regulatory guidance for this category of material.
Additionally, this unit will not return to service without a 100 percent inspection of susceptible welds or a 100 percent inspection of newly installed resistant welds.
Unit 2 A 100 percent examination of the accessible, susceptible welds was performed before the IHSI treatment of unit 2.
This examination and IHSI treatment were performed during the current cycle 5 outage.
A post-IHSI examination of a 25 percent sample of these welds was also performed during the current cycle 5 outage.
The 25 percent sample was selected from those welds which required recording and evaluation of indications, and any additional welds needed to complete the 25 percent sample were taken from weld locations shown to have the highest propensity for cracking.
The results of the pre-and post-IHSI inspections have been provided by R. L. Gridley's letter dated March 10, 1986 to D. R. Muller.
Additional post-IHSI examinations in excess of the 25 percent sample size are being performed on unit 2 during the current outage.
The post-IHSI examination of any remaining, welds will be completed during the next (cycle 6) refueling outage.
Unit 3 A 100 percent examination of the accessible, susceptible welds was performed before the ZHSZ treatment of unit 3.
This examination and ZHSZ treatment were performed during the cycle 5 outage.
A post-IHSI examination of a 25 percent sample of these welds was also performed during the cycle 5 outage.
The 25 percent sample was selected from those welds which required recording and evaluation of indications, and any additional welds needed to complete the 25 percent sample were taken from weld locations shown to 'have the highest propensity for cracking.
The results of the pre-and post-IHSI inspections were provided by J.
A. Domer's letter dated August 9, 1984 to H. R. Denton.
The post-IHSI examination of the remaining welds will be completed during the next (cycle 6) refueling outage.
2.
NRC RE VEST Reactor Coolant Leaka e Monitorin Provide assurance that the Technical Specifications will be changed to monitor the leakage rate every four hours and to limit the inoperable period of the sump monitoring system to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or, provide an acceptable basis for any variations from those limits.
TVA RESPONSE Technical specificatiens requiring leakage rate monitoring every four hours and limiting the inoperable period of the sump monitoring system to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be submitted under separate cover.
3.
NRC RE UEST Weld Overla Desi n Provide assurance of adequate margin in IGSCC resistance by making each overlay repair consist of a minimum of two layers or, provide an acceptable basis for any variations from the minimum two layers.
TVA RESPONSE Unit 1 All of the weld overlays on unit 1 were designed and applied before Generic Letter 84-11.
- However, each overlay does consist of at least two weld layers.
The design details for these overlays were provided in TVA letters from L. M. Mills to H. R. Denton dated October 19, 1983 and November 17, 1983.
Unit 2 The sole weld overlay repair, GR-2-15, performed to date on unit 2 was performed during the current cycle 5 outage.
This weld overlay repair was designed and applied in accordance with the recommendations of Generic Letter 84-11.
The details have been provided in TVA's letter from R. L. Gridley to D. R. Muller dated March 10, 1986.
This letter will be supplemented later based on additional inspections performed.
Unit 3 The two weld overlay repair's, Jp-3-1A and Jp-3-15, on unit 3 were performed during the cycle 5 outage.
These overlays conform to the recommendations of Generic Letter 84-11.
The details were provided in TVA's letter from J.
A. Domer to H. R. Denton dated August 9, 1984.
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