ML100710430

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Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
ML100710430
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 03/10/2010
From: John Stanley
Calvert Cliffs, Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML100710430 (6)


Text

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG a joint venture of 0Constellation ey'eDF CALVERT CLIFFS NUCLEAR POWER PLANT March 10, 2010 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

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SUBJECT:

Document Control Desk Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-3 17 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Pursuant to Appendix H of 10 CFR Part 50, Calvert Cliffs Nuclear Power Plant, LLC hereby submits for approval a revision to its schedule for withdrawal of reactor vessel material surveillance capsule at the 1040 location for Calvert Cliffs Unit 1.

As is the case with the currently approved withdrawal schedule, the proposed withdrawal schedule satisfies the requirements of ASTM [American Society for Testing and Materials] E185-70, the version that was current at the time the reactor vessels were designed. The details of the proposed revision are contained in Attachment (1) to this letter.

SCHEDULE Based on the current reactor vessel surveillance capsule withdrawal schedule, the Calvert Cliffs Unit I capsule located at the 104°. location is required to be withdrawn during the 2010 refueling outage (March 2010). Therefore, we request that you complete the review of our application by March 16, 2010.

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Document Control Desk March 10, 2010 Page 2 Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.

Very truly yours, for James J. Stanley Manager - Engineering Services JJS/PSF/bjd

Attachment:

(1) Proposed Revision to the Schedule for Withdrawal of Reactor Vessel Material Surveillance Capsule for Calvert Cliffs Unit I cc:

D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC S. Gray, DNR

ATTACHMENT (1)

PROPOSED REVISION TO THE SCHEDULE FOR WITHDRAWAL OF REACTOR VESSEL MATERIAL SURVEILLANCE CAPSULE FOR CALVERT CLIFFS UNIT 1 Calvert Cliffs Nuclear Power Plant, LLC March 10, 2010

ATTACHMENT (1)

PROPOSED REVISION TO THE SCHEDULE FOR WITHDRAWAL OF REACTOR VESSEL MATERIAL SURVEILLANCE CAPSULE FOR CALVERT CLIFFS UNIT 1

i.

BACKGROUND Appendix H to 10 CFR Part 50 describes reactor vessel material surveillance program requirements.

Paragraph (III)(B)(3) of this Appendix states that a proposed material withdrawal schedule must be submitted with a technical justification per 10 CFR 50.4, and approved prior to implementation.

As is the case with the currently approved withdrawal schedule, the proposed Withdrawal schedule satisfies the requirements of American Society for Testing and Materials (ASTM) El 85-70, the version that was current at the time the reactor vessel surveillance program was designed.

Table (1) shows the currently approved withdrawal schedule for Calvert Cliffs Unit 1 reactor vessel surveillance capsules (Updated Final Safety Analysis Report Table 4413A).

II. PROPOSED REVISION TO THE WITHDRAWAL SCHEDULE Table (2) provides the proposed revision to the reactor vessel surveillance capsule withdrawal schedule for Unit 1. The revised schedule is based on ASTM El185-82 recommendations, and reflects updated fluence information from the surveillance capsule removed in 1992 with appropriate adjustment made for fuels loaded in subsequent cycles. As shown below in Section III, the proposed withdrawal schedule satisfies the requirements of ASTM El 85-70, the version that was current at the time the reactor vessels were designed. Therefore, the withdrawal schedule satisfies the requirements of Appendix H to 10 CFR Part 50.

III. JUSTIFICATION The Calvert Cliffs Unit 1 reactor vessel was designed to the 1965 through winter 1967 Addenda, edition of the American Society of Mechanical Engineers Code.

, American Society for Testing and Materials E185-70 Was the current standard when the surveillance program was designed. As stated in the Calvert Cliffs Updated Final Safety Analysis Report, the reactor vessel surveillance program meets the requirements of ASTM E 185-70.

The guidance provided in ASTME185-82 is consistent with, but more specific than, the guidance provided in earlier editions, including ASTM El 85-70 to which the Calvert Cliffs Nuclear Power Plant reactor, vessel surveillance program is required to conform, Therefore, compliance with the ASTME185-82 withdrawal schedule guidance ensures compliance with ASTME185-70 withdrawal schedule guidance., ASTM E185-82 provides a withdrawal schedule in terms of years of operation but also provides the option to develop a schedule tied to target fluences accumulated in the vessel. As in the case of the currently approved withdrawal schedule, the proposed withdrawal schedule follows the guidance that ties the withdrawal schedule to vessel fluence targets.

This request proposes to revise the reactor vessel surveillance capsule withdrawal schedule to allow the removal of the capsule located at the 284' location in place of the scheduled 1040 capsule. During the 2010 refueling outage several attempts were made to remove the 1040 capsule using enhanced tooling.

These attempts were unsuccessful even with the enhanced tooling, which included an increased load capacity of the tooling.

We reviewed the other capsules that were available for withdrawal and determined that the 2840 capsule was an appropriate substitute for the 1040 capsule. The 2840 capsule is isofluent to the 1040 capsule and meets the requirements of ASTM E185-82 to withdraw the third capsule at a time when the accumulated neutron fluence on the capsule corresponds to the approximate end of life fluence at the reactor vessel 1

ATTACHMENT (1)

PROPOSED REVISION TO THE SCHEDULE FOR WITHDRAWAL OF REACTOR VESSEL MATERIAL SURVEILLANCE CAPSULE FOR CALVERT CLIFFS UNIT 1 1/4 T location. As noted on Table (2), we would withdraw the 2840 capsule during the 2010 refueling outage and designate the 1040 capsule as the standby capsule.

This proposed change meets the requirements of Appendix H to 10 CFR Part 50.

Table (1)

Current Unit 1 Reactor Vessel Surveillance Program Capsule Removal Schedule Capsule Target Fast Neutron Projected FluencePrecd Azimuthal Position (x 1019 n/cm2)

End-of-Cycle Date 2630 0.62 a Withdrawn, 1979 970 2.64 b Withdrawn, 1992 1040 3.06 c 2010 830 5.26 d 2020 2770 6.59 2032 2840 STANDBY Notes:

a Actual capsule fluence [Perrin, J S, et al., "Calvert Cliffs Unit No. I Nuclear Plant Reactor Pressure Vessel Surveillance Program: Capsule 263," Battelle Columbus Laboratories, December 1980].

b Actual capsule fluence; [Lowe,.A L, Jr., et al., "Analysis of Capsule 970 Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant Unit No. 1," B&W Nuclear Service Company, BAW-2160, June 1993].

C Withdrawal criteria - Capsule fluence that corresponds to the projected fluence at the vessel 1/4 T location at end of extended life.

d Withdrawal criteria - Capsule fluence that corresponds to the projected fluence at the vessel inner wall location at end of extended life.

Withdrawal criteria - Not less than once or greater than twice the peak end of extended life vessel fluence at the vessel inner wall (5.09x10' 9< fluence in n/cm2 <10.18xl01 9). Note: This capsule also satisfies the requirement in the Nuclear Regulatory Commission safety evaluation report for Calvert Cliffs license renewal, that one capsule containing dosimetry is to be removed during the final 5 years of the extended license.

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ATTACHMENT (1)

PROPOSED REVISION TO THE SCHEDULE FOR WITHDRAWAL OF REACTOR VESSEL MATERIAL SURVEILLANCE CAPSULE FOR CALVERT CLIFFS UNIT 1 Table (2)

Proposed Unit 1 Reactor Vessel Surveillance Program Capsule Removal Schedule Capsule Target Fast Neutron Projected FluencePrjce Azimuthal Position (x 1019 n/cm 2)

End-of-Cycle Date 2630 0.62 a Withdrawn, 1979 970 2.64 b Withdrawn, 1992 2840 3.06 C 2010 830 5.26 d 2020 2770 6.59 e 2032 1040 STANDBY Notes:

a Actual capsule fluence [Perrin, J S, et al., "Calvert Cliffs Unit No. I Nuclear Plant Reactor Pressure Vessel Surveillance Program: Capsule 263," Battelle Columbus Laboratories, December 1980].

Actual capsule fluence; [Lowe, A L, Jr., et al., "Analysis of Capsule 970 Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant Unit No. 1," B&W Nuclear Service Company, BAW-2160, June 1993].

C Withdrawal criteria - Capsule fluence that corresponds to the projected fluence at the vessel 1/4 T location at end of extended life.

d Withdrawal criteria - Capsule fluence that corresponds to the projected fluence at the vessel inner wall location at end of extended life.

Withdrawal criteria - Not less than once or greater than -twice the peak end of extended life vessel fluence at the vessel inner wall (5.09x10 9< fluence in n/cm2 <10.18x10`9 ). Note: This capsule also satisfies the requirement in the Nuclear Regulatory Commission safety evaluation report for Calvert Cliffs license renewal, that one capsule containing dosimetry is to be removed during the final 5 years of the extended license.

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