Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: 3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report, 3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re, 3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip, 3F0912-01, ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C, 3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip, 3F1112-02, 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250, ML11259A012, ML11300A226, ML11342A195, ML12031A032, ML12053A231, ML12107A068, ML12202A734, ML12205A357, ML12205A358, ML12240A119, ML12255A409, ML12262A385, ML12314A391, ML12314A392, ML12314A393, ML13032A540, ML13170A215
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MONTHYEARML11167A1072011-05-0606 May 2011 Request for Additional Information Required for the Development of Confirmatory LOCA and non-LOCA Models for the CR-3 Extended Power Uprate Project stage: Request 3F0611-02, Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request 309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards Considerations2011-06-15015 June 2011 Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request 309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards Considerations Project stage: Request 3F0711-07, Clarifications for Trace Confirmatory Model Development for Extended Power Uprate2011-07-0505 July 2011 Clarifications for Trace Confirmatory Model Development for Extended Power Uprate Project stage: Request 3F0811-04, Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-11011 August 2011 Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0811-02, Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-11011 August 2011 Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0811-01, Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-18018 August 2011 Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0811-03, Response to Request for Additional Information to Support NRC Mechanical and Civil Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-25025 August 2011 Response to Request for Additional Information to Support NRC Mechanical and Civil Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML11259A0122011-09-14014 September 2011 NRR E-mail Capture - Clarification for August 25 Emcb RAI Acceptance Review Letter Project stage: Other ML11286A0922011-10-11011 October 2011 Response to Request for Additional Information to Support NRC Reactor Systems Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML11300A2262011-10-25025 October 2011 Feedwater Line Break Overpressure Protection Analysis to Support NRC Reactor Systems Branch Acceptance Review of the CR-3 Extended Power Update LAR and LAR Approval Schedule Project stage: Other 3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip2011-10-25025 October 2011 ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip Project stage: Other ML11286A0842011-11-21021 November 2011 Acceptance for Review of License Amendment Request for Extended Power Uprate Project stage: Acceptance Review ML11326A2312011-12-0707 December 2011 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI 3F1211-05, Response to Request for Additional Information to Support NRC Health Physics and Human Performance Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-15015 December 2011 Response to Request for Additional Information to Support NRC Health Physics and Human Performance Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12205A3572011-12-15015 December 2011 Attachment a to 3F0712-03, CR-3 LOCA Summary Report - EPU/ROTSG/Mark-B-HTP, Revision 4 Project stage: Other 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 LAR2011-12-15015 December 2011 Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F1211-10, Response to Request for Additional Information to Support NRC Fire Protection Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-21021 December 2011 Response to Request for Additional Information to Support NRC Fire Protection Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12030A2092012-01-0505 January 2012 Response to Request for Additional Information to Support NRC Instrumentation and Control Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-0505 January 2012 Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML11342A1952012-01-0606 January 2012 Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non-safeguards Information Project stage: Other ML12024A3002012-01-19019 January 2012 Response to Request for Additional Information to Support NRC Component Performance and Testing Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0112-06, Response to Request for Additional Information to Support NRC Piping and NDE Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-19019 January 2012 Response to Request for Additional Information to Support NRC Piping and NDE Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report2012-01-31031 January 2012 Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report Project stage: Other ML12003A2172012-02-0808 February 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI 3F0212-01, Complex - Environmental Protection Plan Report 2011 Sea Turtle Rescue and Recovery Summary Report2012-02-0808 February 2012 Complex - Environmental Protection Plan Report 2011 Sea Turtle Rescue and Recovery Summary Report Project stage: Request ML1205505612012-03-0202 March 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12053A2312012-03-0202 March 2012 Request for Withholding Proprietary Information from Public Disclosure Related Extended Power Uprate Technical Report Project stage: Other ML12052A1302012-03-0202 March 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI 3F0312-02, Response to Second Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review of the CR-3 Extended Power Uprate LAR2012-03-19019 March 2012 Response to Second Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 3F0312-01, Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-03-22022 March 2012 Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12031A0322012-03-26026 March 2012 Request for Withholding Proprietary Information from Public Disclosure Related to Extended Power Uprate Technical Report Project stage: Other ML1208300282012-04-0202 April 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI 3F0412-05, Response to Second Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-0404 April 2012 Response to Second Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 3F0412-04, Response to Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-0404 April 2012 Response to Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12107A0682012-04-0404 April 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Clarifications for Component Performance & Testing Branch (Eptb) Project stage: Other 3F0412-07, Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-12012 April 2012 Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0412-06, Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-16016 April 2012 Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0412-09, Response to Request for Additional Information to Support NRC Accident Dose Branch (Aadb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-26026 April 2012 Response to Request for Additional Information to Support NRC Accident Dose Branch (Aadb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML1208300382012-05-0404 May 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12102A0442012-05-0404 May 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12205A3582012-05-31031 May 2012 Attachment D to 3F0712-03, Technical Report, ANP-3114(NP), Rev. 0, CR-3 EPU - Feedwater Line Break Analysis Sensitivity Studies Project stage: Other ML12314A3912012-05-31031 May 2012 17877-0002-100, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment 2 Project stage: Other 3F0612-05, Response to Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (Snpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-06-18018 June 2012 Response to Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (Snpb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12206A3372012-06-29029 June 2012 Response to Second Request for Additional Information to Support NRC Accident Dose Branch (Aadb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip2012-06-30030 June 2012 Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip Project stage: Other ML12184A3442012-07-0202 July 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Discussion/Clarification of Emcb Draft RAIs Project stage: Draft Other ML12171A3472012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12174A2922012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12194A4172012-07-17017 July 2012 Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI 3F0712-06, Response to Second Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch (Esgb) Technical Review of the CR-3 Extended Power Uprate LAR2012-07-17017 July 2012 Response to Second Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch (Esgb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 2012-02-08
[Table View] |
Text
Duke Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Septemberl 7, 2012 3F0912-01 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - Extended Power Uprate LAR Supplement and Response to Second Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (SNPB) Technical Review (TAC No. ME6527)
References:
- 1. FPC to NRC letter dated June 15, 2011, "Crystal River Unit 3 - License Amendment Request #309, Revision 0, Extended Power Uprate" (ADAMS Accession No. MLI 12070659)
- 2. Email from S. Lingam (NRC) to D. Westcott (CR-3) dated May 8, 2012, "Crystal River, Unit 3 EPU LAR - Boric Acid RAls from SNPB (TAC NO.
ME6527)"
- 3. NRC to FPC letter dated August 2, 2012, "Crystal River Unit 3 Nuclear Generating Plant - Request For Additional Information For Extended Power Uprate License Amendment Request (TAC No. ME6527)" (ADAMS Accession No. ML12202A060)
- 4. FPC to NRC letter dated October 11, 2011, "Crystal River Unit 3 - Response to Request for Additional Information to Support NRC Reactor Systems Branch Acceptance Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527)" (ADAMS Accession No. ML11286A092)
Dear Sir:
By letter dated June 15, 2011, Florida Power Corporation (FPC) 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 (Reference 1). On May 8, 2012, via electronic mail, the NRC provided a draft request for additional information (RAI) needed to support the SNPB technical review of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR) (Reference 2).
During the June 2012 AREVA NP, Inc. safety analysis audit, CR-3 discussed the draft RAI with the NRC to confirm an understanding of the information being requested. On August 2, 2012, the NRC provided a formal RAI required to complete its evaluation of the CR-3 EPU LAR (Reference 3).
Attachment A, "AREVA Document ANP-3156(P) -
Crystal River 3 EPU Boric Acid Precipitation RAI Responses (Proprietary)," provides the formal response to the RAI.
Attachment A contains information that is considered proprietary. AREVA NP, Inc., as the owner of the proprietary information, has executed the affidavit provided in Attachment B, "AREVA Affidavit for Withholding Proprietary Information from Public Disclosure," and states that the identified information has been classified as proprietary, is customarily held in confidence, and not made available to the public.
AREVA requests that the identified proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390(a)(4).
Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428
U.S. Nuclear Regulatory Commission Page 2 of 4 3F0912-01 Attachment C, "AREVA Document ANP-3156(NP) -
Crystal River 3 EPU Boric Acid Precipitation RAI Responses (Non-Proprietary)," is a non-proprietary copy of the formal RAI responses with the proprietary information redacted.
Attachment D, "Supplement - Summary of the Reactor Coolant System Hot Leg Blowdown Line Design," provides a summary description of the Reactor Coolant System (RCS) blowdown line modification including a decision flowchart that illustrates how the two boron precipitation mitigation methods; RCS hot leg injection and RCS blowdown; are utilized during a loss of coolant accident (LOCA).
Attachment E, "Markup Pages of the CR-3 EPU No Significant Hazards Considerations Evaluation," provides the affected pages noting the licensing basis change request provided herein.
These changes are in addition to the changes provided in FPC to NRC letter dated October 11, 2011 (Reference 4).
Attachment F, "Revised Pages of the CR-3 EPU No Significant Hazards Considerations Evaluation," provides a clean typed revision of the affected pages noting the licensing basis change request provided herein. These changes are in addition to the changes provided in FPC to NRC letter dated October 11, 2011 (Reference 4).
Additionally, this correspondence revises one of the licensing basis changes proposed for the requested EPU license amendment (Reference 1):
"Credit the new LPI System HLI line as the primary method of boron precipitation mitigation during a LOCA, thereby eliminating the need for the two active methods currently credited and allowing deletion of CR-3 OL License Condition 2.C. 11."
The licensing basis change request is revised as follows (change in italics):
"Credit the new LPI System HLI line and the new RCS hot leg blowdown line as the primary methods of boron precipitation mitigation during a LOCA, thereby eliminating the need for the two active methods currently credited and allowing deletion of CR-3 OL License Condition 2.C. 11."
The information provided herein does not change the intent or the justification for the requested EPU license amendment (Reference 1). FPC has evaluated the new RCS hot leg blowdown line modification and determined that this supplement does not alter the conclusion that the proposed license amendment does not involve a Significant Hazards Consideration. Revised wording of the 10 CFR 50.92(c) evaluation provided in the June 15, 2011 submittal (Reference 1) is included in Attachments E and F.
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.
Si River Nuclear Plant JAF/krw
U.S. Nuclear Regulatory Commission Page 3 of 4 3F0912-01 Attachments:
A. AREVA Document ANP-3156(P) -
Crystal River 3 EPU Boric Acid Precipitation RAI Responses (Proprietary)
B. AREVA Affidavit for Withholding Proprietary Information from Public Disclosure C. AREVA Document ANP-3156(NP) - Crystal River 3 EPU Boric Acid Precipitation RAI Responses (Non-Proprietary)
D. Supplement - Summary of the Reactor Coolant System Hot Leg Blowdown Line Design E. Markup Pages of the CR-3 EPU No Significant Hazards Considerations Evaluation F. Revised Pages of the CR-3 EPU No Significant Hazards Considerations Evaluation xc:
NRR Project Manager Regional Administrator, Region II Senior Resident Inspector State Contact
U.S. Nuclear Regulatory Commission 3F0912-01 Page 4 of 4 STATE OF FLORIDA COUNTY OF CITRUS Jon A. Franke states that he is the Vice President, Crystal River Nuclear Plant for Florida Power Corporation; 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.
Crystal River Nuclear Plant The foregoing document was acknowledged before me this ti day of
_____"_-__-____,2012, by Jon A. Franke.
Signature of Notary Public State d ~
i iLIC-STATE OF FLORIDA
eryl M. McCullough
'- Commission # EE011293
--4
, Expires: JULY 25, 2014 BONDED THRU ATLANTIC BONDING CO., INC.
(Print, type, or stamp Commissioned 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 B AREVA AFFIDAVIT FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
AFFIDAVIT COMMONWEALTH OF VIRGINIA
)
) ss.
COUNTY OF CAMPBELL
- 1.
My name is Gayle F. Elliott. I am Manager, Product Licensing, for AREVA NP Inc. (AREVA NP) and as such I am authorized to execute this Affidavit.
- 2.
I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.
- 3.
I am familiar with the AREVA NP information contained in the report ANP-3156(P), entitled "Crystal River 3 EPU Boric Acid Precipitation RAI Responses," dated September 2012, and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.
- 4.
This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5.
This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is
requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information".
- 6.
The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary:
(a)
The information reveals details of AREVA NP's research and development plans and programs or their results.
(b)
Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c)
The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.
(d)
The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.
(e)
The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.
The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b) and 6(c) above.
- 7.
In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8.
AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9.
The foregoing statements are true and correct to the best of my knowledge, information, and belief.
SUBSCRIBED before me this /._
day o0vl 40012.
Kathleen A. Bennett NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 8/31/2015 Reg. #110864 KATHLEEN ANN BENNETT Notary Public Commonwealth of Virginia 110864 My Commission Expires Aug 31, 20156