ML18026B029
| ML18026B029 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/07/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GL-84-07, GL-84-11, GL-84-7, TAC-55590, TAC-55591, TAC-55592, NUDOCS 8406120185 | |
| Download: ML18026B029 (10) | |
Text
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REGULATORY NFORMATION DISTRIBUTION S 1'EM (RIDS)
ACCESSION NBR:8406120185 DOC,DATE,- 84/06/07 NOTARIZED: YES FAOILSQ 259 Browns Ferry Nuclear Power Stationg Uni,t 1E Tennessee 50-260 Browns Ferry Nuclear Power Stat)one Uni,t 2~
Tennessee 50 296 Browns Ferry Nuclear. Power Stations Unit 3<
Tennessee AUTH~ NAME AUTHOR AFF ILIATION MILLStL ~ M ~
'Tennessee Valley Authority
~RECIP ~ NAhlE'ECIPIENT AFFILIATION DENTONiH,RB Office of Nuclear Reactor Regulationg Director DOCKET 05000259 05000260 05000296 SUBJECT; Respond -to,Generic Ltr 84 1]g "Insps of BAR Stainless Steel Piping," Response addresses scope 8 schedule of future pipe insps~oxaminer qualification 8, availabilitygprimary sys leak'etection surveillance measures L compensatory
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II June 7, 1974 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.-20555
Dear Mr. Denton:
In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 Enclosed is the response to Generic Letter No. 84-11 dated April 19, 1984, subject, Inspections of BWR Stainless Steel Piping, for the Browns Ferry Nuclear Plant.
As requested in the generic letter, our response addresses scope and schedule of futur e pipe inspections, examiner qualification and availability, primary system leak detection surveillance
- measures, compensatory actions if cracks are discovered, and results of IE Bulletin inspections not previously submitted.
The deadline for submitting a response to the generic letter was June 4, 1984. For some reason, we did not receive the generic letter until May 1, 1984, thus, 11 days had elapsed before we received the letters The possibility of needing additional time to respond was discussed with the NRC Browns Ferry Project Manager on May 2, 1984.
If you have any questions concerning this information, please get in touch with us through the Browns Ferry Project Manager.
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, <Subsciibe ~d sworn to before me ths
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Very truly yours, TENNESSEE VALLEY AUTHORITY Q.'N~
Nuclear Licensing 1984.
Notary Public My Commission Expires cc:
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Mr. Harold R. Denton June 7, 1984 cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II ATTN:
James P. O'Reilly, Regional Administrator 101 Marietta Street, NH, Suite 2900 Atlanta, Georgia 30303 Mr. R. J. Clark Browns Ferry Prospect Manager U.S. Nuclear Regulatory Commission 7920.Norfolk Avenue
- Bethesda, Maryland 20814
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ENCLOSURE ONSE TO GENERIC LETTER 84-11 DATED APRIL 19, 1984 BROWNS "'ERRY NUCLEAR PLANT 1.
Scope and schedule of planned inspections.
Unit 1 Cycle 6 (Currently Scheduled for March 1985)
Piping replacement is scheduled.
. Stainless steel welds greater than 4 inchesa which are not being replaced will be selected for examination in accordance with the guidance given in Generic Letter 84-11.
Unit 2 Cycle 5 (Currently Scheduled for August 1984)
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One hundred-percent examination of the accessible stainless steel welds greater than 4 inche&before Induction Heat Stress Improvement (IHSI).
. Twenty-five percent sample of the stainless steel welds (greater than 4 inches) following IHSI.
The sample will be selected from those welds which require recording/evaluation of indications.
Any additional welds needed to complete the 25-percent sample will be from weld locations shown to have the highest propensity for cracking.
Unit 3 Cycle 5 (Currently in an Outage)
One hundred-percent examination of the accessible stainless steel welds greater than 4 inches*before IHSI.
~ Twenty-five percent sample of the stainless steel welds (greater than 4 inches% following IHSI.
The sample was selected from those welds which require recording/evaluation of indications (34 welds) and additional welds from locations shown to have the highest propensity for cracking (9 welds).
Unit 3 Cycle 6 (Currently Scheduled for December 1985)
. The sample will be in accordance with Generic Letter 84-11 with the exception of 100-percent examination following IHSI.
The post IHSI sample will be the 25-percent sample performed during unit 3 cycle 5.
2.
Availability and qualification of examiner.
TVA presently has available 4 Level III examiners and 20 Level II examiners who are certified by either the IE Bulletin 83-02, Demonstrated Capability Process or the EPRI-NDE Center Training and Testing Process.
In addition, numerous Level I examiners have been trained and certified by TVA, but they are predominantly contractor-supplied and their availability is unknown.
~greater than or equal to 4 inches.
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3.
Description of any special surveillance measures for primary system leak detection beyond those required by current technical specifications.
Leak detection and leakage limits that will be used at Browns Ferry Nuclear -Plant are those described in the technical specifications for units 1, 2, and 3.
Leakage detection and limits follow the requirements of attachment 1 to Generic Letter 84-11 with the following exceptions.
a.
The containment air-monitor system has not been upgraded or calibrated to correspond,to a particular leak rate.
This is the system which promptly indicates an increase in leak rate.
b.
Leakage rate is monitored at 8-hour intervals.
c.
At least one sump leakage monitor must be operable or power operation is permissible only for the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Results of bulletin inspections not previously submitted to NRC.
There are no bulletin examination reports outstanding.
5.
Remedial measures, if any, to be taken when cracks are discovered.
TVA intends to follow the recommended actions in attachment 2 with the following exceptions.
a.
Item 2(b)(i)
We believe that the first weld layer that clears dye-penetrate testing inspection should be counted as effective overlay thickness if it can be demonstrated that cracks will not grow during the proposed operating per iod to within one weld layer thickness of the pipe outside diameter surface.
b.
Item 2(b)(ii)
We believe that the above comment is applicable to Item 2(b)(ii).
We also believe that less than two weld layer s should be permitted if it can be demonstrated that the cracks are arrested by one weld layer and that the requirements of IWB-3640 are met.
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