3F1211-06, Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR

Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR

ML11354A232
Person / Time
Site:	Crystal River
Issue date:	12/15/2011
From:	Franke J Progress Energy Florida
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F1211-06, TAC ME6527
Download: ML11354A232 (4)

Text

Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 December 15, 2011 3F1211-06 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527)

References:

1. CR-3 to NRC letter dated June 15, 2011, "Crystal River Unit 3 - License Amendment Request #309, Revision 0, Extended Power Uprate" (Accession No. ML112070659)

2. NRC to CR-3 letter dated December 7, 2011, "Crystal River Unit 3 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request (TAC No. ME6527)" (Accession No. ML11326A231)

Dear Sir:

By letter dated June 15, 2011, Florida Power Corporation, doing business as Progress Energy Florida, Inc., requested a license amendment to increase the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts (MWt) to 3014 MWt. On December 7, 2011, the NRC provided a request for additional information (RAI) required to complete its evaluation of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR).

The attachment, "Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 EPU LAR," provides the CR-3 formal response to the RAI needed to support the Vessels and Internals Integrity Branch technical review of the CR-3 EPU LAR.

This correspondence contains no new regulatory commitments.

If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Superintendent, Licensing and Regulatory Programs at (352) 563-4796.

incere on A. Franke Vice President Crystal River Nuclear Plant JAF/pdk

Attachment:

Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 EPU LAR xc:

NRR Project Manager Regional Administrator, Region II Senior Resident Inspector State Contact Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428

U.S. Nuclear Regulatory Commission 3F1211-06 Page 2 of 2 STATE OF FLORIDA COUNTY OF CITRUS Jon A. Franke states that he is the Vice President, Crystal River Nuclear Plant for Florida Power Corporation, doing business as Progress Energy Florida, Inc.; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

,Kon A. Franke Vice President Crystal River Nuclear Plant The foregoing document was acknowledged before me this 6 ik..,,_, 2011, by Jon A. Franke.

day of (Print, type, or stamp Co Name of Notary Public)

Personally Known Produced

-OR-Identification

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 /LICENSE NUMBER DPR-72 ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT NRC VESSELS AND INTERNALS INTEGRITY BRANCH TECHNICAL REVIEW OF THE CR-3 EPU LAR

U. S. Nuclear Regulatory Commission Attachment 3F1211-06 Page 1 of I RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT NRC VESSELS AND INTERNALS INTEGRITY BRANCH TECHNICAL REVIEW OF THE CR-3 EPU LAR By letter dated June 15, 2011, Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., requested a license amendment to increase the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts (MWt) to 3014 MWt. On December 7, 2011, the NRC provided a request for additional information (RAI) required to complete its evaluation of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR). The following provides the CR-3 formal response to the RAI needed to support the Vessels and Internals Integrity Branch (EVIB) technical review of the CR-3 EPU LAR. For tracking purposes, each item related to this RAI is uniquely identified as EVIB X-Y, with X indicating the RAI set and Y indicating the sequential item number.

Vessels and Internals Integrity Branch (EVIB)

30.

(EVIB 1-1)

The EPU Technical Report, Table 2.1.1-3 indicates that Babcock & Wilcox Owners Group (B&WOG) Capsule A5 fulfills the requirement of American Society for Testing and Materials

[ASTM] E185-82 for the last capsule to receive not less than once nor greater than twice the peak EOL vessel fluence. Table 2.1.1-1 of the EPU Technical Report shows the pea vesssl inner surface fluence at EOL (50.3 EFP

[e fective uyear ower]) as 1.57 x 10 n/cm However, BAW-1543, Revision 4, Suppler ent 6, Tabe VIs ows the fluence received by B&WOG Capsule A5 as 0.637-1.042 x 10 n/cm.

Explain how B&WOG Capsule A5 is meeting the requirement for the last capsule since the fluence received is less than one times the projected EOL vessel fluence.

Response

As documented in BAW-2360P, "Analysis of A5 Capsule B&W Owners Group -- Master Integrated Reactor Vessel Surveillance Program," 4ýeferelce 1), the B&WOG Capsule A5 weld specimens received a neutron fluence of 1.56 x 10 n/cm at Ion Ul~it 1 prior to insertion into the capsule and received an additional fluence of 1.042 x 10, n/cm at Davis-Besse while in Capsule I T1~erefore, the total neutron fluence of the specimens in Capsule A5 is 2.602x 10 n/cm.

As noted in Table 2.1.1-1 of the CR-3 EPU Technical Report (Reference 2, Attachments 5 and 7), the projected CR-3 end-of-life (EOL) reactor pressure vessel (RPV) fluence at EPU conditions is 1.57 x 1019 n/cm.

B&WOG Capsule A5 meets the applicable criteria of ASTM E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," (Reference 3) and Chapter XI, Section M31 of NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," (Reference 4) for the last surveillance capsule: C psule ý5 neutron fluence is greater than the peak projected CR-3 EOL RPV fluence (1.57 x 101 n/cm2) and less than twice the peak projected CR-3 EOL RPV fluence (3.14 x 10 1 n/cm2).

References

1.

BAW-2360P, "Analysis of A5 Capsule B&W Owners Group -- Master Integrated Reactor Vessel Surveillance Program," June 1999.

2.

CR-3 to NRC letter dated June 15, 2011, "Crystal River Unit 3 - License Amendment Request #309, Revision 0, Extended Power Uprate," (Accession No. ML112070659).

3.

ASTM E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," July 1982.

4.

NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," Revision 2, December 2010.