ML20076D756
| ML20076D756 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/26/1991 |
| From: | Woodard J ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-89-001, IEB-89-1, NUDOCS 9107300204 | |
| Download: ML20076D756 (4) | |
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Docket Nos.
50-348 10 CFR 50.54 (f) 50-364 h
U. S. Nuclear Regulatory Commission Attnt Document Control Desk Vashington, D. C.
20555 Joseph M. Farley Nuclear Plant Response To NRC Compliance Bulletin No. 89-01, Supplement 2
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Gentlement 1
In response to NRC Conipliance Bulletin 89-01, Supplement 2, " Failure Of Vestinghouse Steam Generator Tube Mechanical Plugs", the following information is provided for the actions requested:
NRC Item 1 Addressees are requested to verify that information contained in Table 2 of Reference 4 for their plants is correct for plugs fabricated from group 2 heats.
(Addressees have previously verified similar information for group 1 plugs in response to the original bulletin.) The specific information to be verified is the number of Vestinghouse mechanical plugs installed in the hot-leg and cold-leg side of each steam generator, categorized by heat number and date of installation. The plug operating temperatures for each plant given in *,is Table should also be verified.
If information from this Table is incorrect. addressees should provide correct information.
Addressees are requested to so state if their plants have not installed Vestinghouse mechanical plugs from group 2 heats.
APCo Response The information contained in Table 2 of Reference 4 from the group 2 heats relating specifically to Farley Nuclear Plant (FNP) Units 1 (ALA) and 2 (APR) is correct except for the following:
- One of the heat no. 6135 plugs in APR SG B has been removed from both the HL and the CL.
Table 2 of Reference 4 does not note that any plugs have been removed for this heat in this generator.
The installation date for the heat no. 6135 plugs in APR SG C vas 03/89 and not 08/89 as shown in Table 2.
NRC Item 2 Addressees are requested to take the following--actions, to be implemented Initially during any refueling outage or extended outage (greater than four weeks) which ends 60 days or more following receipt of this bulletin and during all future refueling outages.
For the period of time between receipt of the
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U. S Nuclear Regulatory Commission Page 2 bulletin and 60 days, the actions requested in the original version of this bulletin continue to be applicable for plugs fabricated from group 1 heats.
NRC Item 2a Addressees should implement appropriate remedial actions (i.e., repair and/or replacement) for all plugs whose estimated lifetime in item 2b, below does not extend to the next refueling outage, APCo Response Based on Table 2 of Reference 4 none of the FNP Units 1 & 2 plugs have estimated lifetimes which do not extend to the next refueling outage, therefore, no remedial actions are required.
NRC Item 2b Remaining lifetime estimates (in effective full power days (EFPD)) are given in Table 2 of Reference 4 in the column entitled " Remain EFPD to HIN."
These remaining lifetime estimates are relative to reference-dates given in the column entitled " Reference CALC Dates." These remaining lifetime estimates-may be used directly. These estimates should be adjusted to refle-t any corrections noted in Actions Requested, item 1.
APCo Response None of the corrections noted in item I have an effect on these calculations.
According to these calculations the earliest required repair and/or replacement for any of the group 2 heats for the FNP Units are as follows:
Unit Heat No.
Year 1
2387 (HL) 1998 2
6135 (HL) 1994 NRC Item 2c For refueling outages or extended outages ending prior to November 30, 1991, remedial actions for plugs fabricated from NX-5222 may be deferred until the next scheduled refueling outage.
APCo Response None of the FNP Unit I and Unit 2 plugs are fabricated from heat no. NX-5222 therefore, no-remedial actions are required.
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' U. S. Nuclear Regulatory Commission Page 3 NRC Item 2d Installation of-Vestinghouse mechanical plugs fabricated from Inconel 600 should be discontinued.
APCo Response Installation of plugs fabricated from Inconel 600 has been discontinued.
NRC Item 2e If for any refueling outage, the addressee does not plan to satisfy items 2a to 2d above, an alternative plan for insuring plug integrity, with appropriate technical justification, should be submitted to the NRC at least 30 days before the end of the refueling outage.
APCo Response-FNP plans to satisfy the requirements of Items 2a and 2d as noted above therefore, no further action is required for this item.
NRC Item 2f Prior to any plug repairs or replacement, addressees are reminded that their responsibilities under ALARA require analysis of the various plug repair or-replacement methods.
In choosing a plug repair or replacement method, the l
licensee should consider the accessibility of the plugs and the dose reduction benefit of using robotic manipulators.
Prior to plug repair or replacement, the licensee should consider steam generator decontamination and/or local-
. shielding.to reduce working area dose rates.
APCo Response Radiation exposure, robotic manipulators, accessibility, shielding, decontamination and schedule vill be considered in th implementation of the
-plug repair and replacement program.
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U. S. Nuclear Regulatory Commission Page 4 1
If there are any questions, please advise, j
Respestfully submitted, ALABAHA POVER COMPANY a
crt (J. D. Voodard JDV/ CDP:pgr DK4-23 cci Hr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell SVORN TO AND SUBSCRIBED BEFORE HE r.M[
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