ML20148J128
| ML20148J128 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/23/1988 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| IEB-88-002, IEB-88-2, NUDOCS 8803300177 | |
| Download: ML20148J128 (6) | |
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Alabama Power Company 600 North 18th Street Post office Dox 2641 Birmingham, Alabama 35291-0400 Telephone 205 250-1835 L
"0N/e";,',ioeni-MWmNw NMS-88-0195 the swthan ewrcswom Docket Nos. 50-348 50-364 March 23, 1988 U. S. Nuclear Regulatory Comission ATIN: Document Control Desk Washington, DC 20555 Gentlemen:
J. M. Farley Nuclear Plant - Units 1 and 2 Rapidly Propagating Fatigue Cracks in Steam Generator Tubes - NRC Bulletin No. 68-02 NRC Bulletii No. 88-02 requested that Alabama Power Company implement actions to ninimize the potential for a steam generator tube rupture event caused by a rapidly propagating fatigue crack such as occurred at North Anna Unit 1 on July 15, 1987. Specifically, within 45 days of receipt of this bulletin, dabama Power Company is to sul:mit a written report detailing the status of its compliance with the bulletin provisions.
If denting is found, the 45-day report is to include a schedule for completion of an analysis to assess the potential for a failure such as experienced by North Anna. The 45-day report is also to include the results of a review for evidence of denting at the uppermost tube support plate.
If denting is found, an enhanced primary-to-secondary leak rate monitoring program is to be implemented and documented as part of the 45-day report. his interim program is to remain in effect until NRC review and approval of a long-term program to minimize the probability of a rapidly propagating fatigue failure is received. W e long-term program is to be submitted to the NRC in sufficient time to allow NRC staff review and approval prior to the next scheduled restart from a refueling outage. Where the next such restart is scheduled to take place within 90 days, staff review and approval for restart from that outage will not be necessary. The analysis, noted above, to assess the potential for a steam generator tube failure is to be submitted as part of the long-term program.
In the event that no denting is found, comitments to review future steam generator tube inspection results and to implement appropriate actions are to be made.
fgh 8803300177 800323 PDR ADOCK 0S000340 Q
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s U. S. Nuclear Regulatory Commission March 23, 1988 Page 2 Upon receipt of NRC Bulletin No. 88-02, Alabama Power Company immediately initiated actions to review its most recent steam generator inspection data for evidence of denting.
It soon became apparent that, due to the proximity of the Unit 1 outage, it would be more practical to conduct the analysis for susceptible tubes prior to reviewing inspection data for evidence of denting.
Due to the nature of this review and the availability of skilled manpower resources, it was not practical to simultaneously conduct an analysis to identify susceptible tubes and to review inspection data for evidence of denting. This analysis of susceptible tubes includes a review of inspection data for an assessment of the depth of penetration of each antivibration bar (AVB).
The timely completion of the analysis will potentially allow sufficient time to implement interim corrective actions on Unit 1 during the forthcoming outage, if only a minimal number of t.ubes were involved.
The results of the reviews for denting for both Units 1 and 2 are not available at this tiae. Alabama Power Company has therefore initiated the interim compensatory measure of an enhanced primary-to-secondary leak rate monitoring program on both Units 1 and 2.
This interim program is described in the enclosure to this letter and will remain in effect until the denting determination is made.
If no denting is determined, Alabana Power Company will advise the NRC of its plans to address the provisions of paragraph B of the bulletin.
If denting is determined, the interim program will remain in effect until the NRC staff approves the long-term program eM.acussed in the bulletin.
Farley Nuclear Plant Unit 1 is scheduled to restart from the next refueling outage within 90 days of receipt of this bulletin. NRC Bulletin No. 88-02 was received on February 8, 1988. Unit 1 is currently scheduled to leave Moce 5 on May 5, 1988 and enter Mode 2 on May 8, 1988. NRC approval of the long-term program is therefore not required for either Unit 1 or Unit 2 at this time; nowever, Alabama Power Company will coordinate with the NRC Pro ject Manager to ensure that the analysis submittal schedule for both Farley Nuclear Plant units will be acceptable to allow timely NRC approval for the restart from the next refueling outages for each unit (Unit 1 l
ninth, Unit 2 sixth).
on March 8, 1988 Alabama Power Company initiated a telephone conversation witit the NRC staff to discuss the requirements of NRC Bulletin No. 88-02.
Since the denting review could not be completed within the 45-day regntrament and an interim enhanced leak rate monitoring program was altsad scheduled to be implemented, Alabama Power Company discussed its plais '.o address the denting review and flow analysis issues in an alternative manner. This alternative involves Westinghouse, the steam generator designer, utilizing a flow peaking analysis which factors in the depth of penetration of each AVB to locate potentially susceptible tubes in both units. Westinghouse is scheduled to specify which tubes are potentially susceptible by April 6, 1988 for Unit 1 and by April 22, 1988 for Unit 2.
These potentially susceptible tubes will then be reviewed for evidence of denting utilizing inspection data from prior refueling outages
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(Unit 1 seventh, Unit 2 fifth) of each unit with a report from Westinghouse j
expected by May 15, 1988.
In addition, at a future date, a review of both 1
t
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. S. Nuclear Regulatory Comission March 23, 1988
-rage 3 Farley units inspection data will be conducted, on a sampling basis, for all regions of the upper support plates to determine the extent of any evidence of denting which may be present. Subnittal of the bulletin required long-term program to include the results of the analyses stated above will then be submitted for NRC review and approval well in advance of the next scheduled refueling outage of each unit.
Alabama Power Company considers that the alternative approach with supporting justification described above satisfies the intent of NRC Bulletin No. 88-02.
If there are any questions, please advise.
Respectfully suhnitted, ALABAMA COMPANY 7/
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R. P. Mcdonald RPM MSF:csl-V5 Enclosure cc:
Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford SWORN 'IO AND SUBSCRIBED BEFORE ME
'INIS h C?3 OF.. $\\atek
, 1988 LGMA NOTARWPUBLIC
~W My Commission Expires:
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ENCIDSURE LEVEL 1 - Given that no primary to secondary leakage exists, sampling is conducted as shown in the attachment.
If one of the following radiation monitors alarms, a steam generator blowdown or air ejector sample is immediately collected to determine leak rate.
Out of Monitor **
Service Alarm Service RE-15A Condenser Air Ejector 150 cpm (Unit 1)* Note 1 400 cpm (Unit 2)*
RE-15B Condenser Air Ejector 4.5 mR/h Note 2 (intermediate tange)
RE-15C condenser Air Ejector 50 mR/h Note 2 (high range)
RE-23A&B Steam Generator Blowdown 500 cpn (Unit 1)* Note 3 300 cpm (Unit 2)*
RE-60A,B,C&D Main Steam Relief and 71 mR/h Note 4 Atmospheric Steam Dump and AfW Turbine Exhaust Note 1: Obtain air ejector grab sample every eight hours.
Note 2: Verify 15A is in service once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or obtain air ejector grab sample every eight hours, Note 3: No action for 23A.
Sample every eight hours if DEI) 0.01 or once i
every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if DEIf 0.01 for 238.
Note 4: Verify 23A or 23B is in service once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or obtain steam generator blowdown grab sample once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- Adjusted based on background levels and current plant operational status.
- Calibration performed in accordance with Technical Specifications except RE-23A which is performed once every 18 months.
If primary to secondary leakage is determined to exist while in Level 1, the leak rate will determine the appropriate level of action to be entered. Leak rate data will be trended on a daily basis.
LEVEL 2 - Leak rate determined to be less than 25 gallons per day (gpd).
LEVEL 3 - Leak rate determined to be greater than or equal to 25 gpd but less than 50 gpd.
LEVEL 4 - Leak rate greater than or equal to 50 gpd.
Details of each monitoring level are provided in the attachment.
ADMINISTRATIVE LIMITS At a determined leak rate in excess of 150 gpd in any steam generator, pcrer will be reduced to less than 50 percent within six hours.
At a determined leak rate in excess of 300 gpd in any steam generator, the plant will be in Mode 3 within three hours and will continue to cold shutdown.
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ATTACHMENT PARAMETER LEVEL 1 LEVEL 2
_ LEVEL 3 IEVEL 4 Gross Beta /Camma every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Tritium every 7 days every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Note 2)
]
H3 Leak Rate N/A every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Note 1)
Xe Leak Rate N/A every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Note 1) i Na24 Leak Rate N/A every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Note 3)
(Note 3)
(Note 3) i I
Gamma Isotopic every 7 days every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
SJAE Gas every 31 days every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Note 2)
SJAE Particulate every 7 days Same Same Same SJAE Iodine every 7 days Same Same Same l
DEI every 6 mo. if < 0.01 Same Same Same
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every 31 d. if 3 0.01 Same Same Same Dissolved Gas every 31 days same Same Same Tritium SGBD Composite every 31 days same Same same Alpha every 31 days Same same Same Sr89,90 every quarter Same Same Same Fe55 every quarter Same Same Same Note 1: H3 leak rate and Xe leak rate are performed once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> on a staggered basis.
Note 2: H3 analysis and SJAE gas analysis are performed once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> on a staggered basis.
Note 3: Na24 leak rate is performed if Na24 is detected in the samples.
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