ML042440590

Response to Request for Additional Information Concerning Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel

ML042440590
Person / Time
Site:	Oyster Creek
Issue date:	08/23/2004
From:	Swenson C AmerGen Energy Co
To:	Office of Nuclear Material Safety and Safeguards
References
2130-04-20201
Download: ML042440590 (4)

Text

AmerGen SM An Exelon Company C. N. (Bud) Swenson Site Vice President Oyster Creek Generating Station US Route 9 South P.O. Box 388 Forked River, NJ o8731 Telephone 609.971.2300 www.exeloncorp.com bud swenson@amergenenergycom 10 CFR 50.55a 2130-04-20201 August 23, 2004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Oyster Creek Generating Station Facility License No. DPR-16 Docket No. 50-219

Subject:

Response to Request for Additional Information Concerning Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel

References:

1)

AmerGen letter 2130-00-20300 dated November 10, 2000, 'Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel"

2)

AmerGen letter 2130-00-20304 dated November 14, 2000, "Modification to Proposed Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel"

3)

USNRC letter dated November 16, 2000, "Request to Use an Alternative Repair of the Control Rod Drive Housing Interface with the Reactor Vessel at the Oyster Creek Nuclear Generating Station (TAC NO.

MB0461)"

4)

AmerGen letter 2130-01-20031 dated January 19, 2001, "Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel Clarification of Leakage Inspection"

5)

USNRC letter dated January 8, 2002, "Oyster Creek Nuclear Generating Station - Clarification of Leakage Inspection (TAC NO. MB1 065)"

6)

AmerGen letter 2130-02-20214 dated July 26, 2002, "Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel"

7)

AmerGen letter 2130-02-20291 dated October 4, 2002, "Additional Information - Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel (TAC No. MB5700)"

8)

USNRC letter dated October 18, 2002, "Oyster Creek Nuclear Generating Station - Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel (TAC NO. MB5700)"

9)

AmerGen letter 2130-03-20271 dated October 21, 2003, "Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel"

10)

AmerGen letter 2130-04-20157 dated July 20, 2004, "Response to Request for Additional Information Concerning Alternative Repair of Control Rod Drive Housing Interface with Reactor Vessel"

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US Nuclear Regulatory Commission August 23, 2004 Page 2 In the Reference 9 letter, in accordance with 10 CFR 50.55a(a)(3)(i), AmerGen Energy Company, LLC (AmerGen) requested continued approval of the proposed alternative to 10 CFR 50.55a(g) as contained in the Reference 6 letter above.

This issue was discussed with the NRC staff in conference calls dated May 26, 2004, August 6, 2004, August 17, 2004, and August 19, 2004, and resulted in additional information being provided in the Reference 10 letter. In response to these discussions, we are continuing to request approval of the proposed alternative to 10 CFR 50.55a(g) as provided in the Reference 9 letter, with the addition of the revised allowable leakage rates and conditions as provided in the attached Tables 1 and 2.

If you should have any questions, please contact Mr. Tom Loomis at 610-765-5510.

Veers, C. N. Swensor Vice President ster Creek Generating Station AmerGen Energy Company, LLC

Attachment:

CRD Penetration - Allowable Leakage Rates cc:

S. J. Collins, USNRC, Administrator, Region I P. S. Tam, USNRC, Senior Project Manager, Oyster Creek R. J. Summers, USNRC, Senior Resident Inspector, Oyster Creek File No. 00086

Allowable Leakage Rate Tables Attachment Page 1 TABLE I CRD Penetration - Allowable Leakage Rates for Inspections During Plant Outages with a Scheduled Duration of Less than or Equal to 7 Days Condition Allowable Leak Rates3 Required Actions' 800-1100 Depressurized psig Previously 80 drops/min.

20 drops/min.

If leakage rate is zero, then acceptable for Unrolled startup.

If leakage is greater than zero, but less than or equal to allowable leakage rate, then acceptable for startup. However, roll expand to 4% or perform ASME code weld repair at next refueling outage. 2 If leakage is greater than allowable leakage rate, then roll expand to 4% or perform ASME code weld repair at this outage, Rolled 70 drops/min 15 drops/min.

If leakage rate is zero, then acceptable for Once startup.

If leakage is greater than zero, but less than or equal to allowable leakage rate, then acceptable for startup. However, roll expand to 6% or perform ASME code weld repair at next refueling outage. 2 If leakage is greater than allowable leakage rate, then roll expand to 6% or perform ASME code weld repair at this outage.

Rerolled 60 drops/min.

10 drops/min.

If leakage rate is zero, then acceptable for startup.

If leakage is greater than zero, but less than or equal to allowable leakage rate, then acceptable for startup. However, perform ASME code weld repair at next refueling outage.2 If leakage is greater than allowable leakage rate, then perform ASME code weld repair at this outage.

NOTE:

1.

Any roll repairs intended to be left in service after, or performed at, refueling outage R21 requires submittal of a relief request to the NRC 6 months prior to entering refueling outage R21 for approval.

2.

At the conclusion of the unit's refueling outage R21, all CRD penetrations, unrolled, rolled, rerolled, or weld repaired will meet a zero leakage requirement prior to returning the unit to power operation.

3.

Allowable leakage rates greater than zero leakage will no longer be acceptable as of the beginning of refueling outage R21.

1 Allowable Leakage Rate Tables Attachment Page 2 TABLE 2 CRD Penetration - Allowable Leakage Rates for Inspections During Plant Outages with a Scheduled Duration of Greater than 7 Days Condition Allowable Leak Rates 3 ReurdAtos 800-1100 Depressurized Required Actions1 psig__

Previously No leakage No leakage If leakage rate is zero, then acceptable for Unrolled startup.

If greater than zero leakage, then roll expand to 4% or perform ASME code weld repair at this outage.

Rolled 70 15 drops/min.

• If leakage rate is zero, then acceptable for Once drops/min.

startup.

If leakage is greater than zero, but less than or equal to allowable leakage rate, then acceptable for startup. However, roll expand to 6% or perform ASME code weld repair at next refueling outage.

If leakage is greater than allowable leakage rate, then roll expand to 6% or perform ASME code weld repair at this outage.

Rerolled 60 10 drops/min.

• If leakage rate is zero, then acceptable for drops/min.

startup.

If leakage is greater than zero, but less than or equal to allowable leakage rate, then acceptable for startup. However, perform ASME code weld repair at next refueling 2

outage.

If leakage is greater than allowable leakage rate, then perform ASME code weld repair at this outage.

NOTE:

1)

Any roll repairs intended to be left in service after, or performed at, refueling outage R21 requires submittal of a relief request to the NRC 6 months prior to entering refueling outage R21 for approval.

2)

At the conclusion of the unit's refueling outage R21, all CRD penetrations, unrolled, rolled, rerolled, or weld repaired will meet a zero leakage requirement prior to returning the unit to power operation.

3)

Allowable leakage rates greater than zero leakage will no longer be acceptable as of the beginning of refueling outage R21.