ML13018A307

Request for Additional Information for Extended Power Uprate License Amendment Request

ML13018A307
Person / Time
Site:	Crystal River
Issue date:	02/01/2013
From:	Siva Lingam Plant Licensing Branch II
To:	Franke J Florida Power Corp
Lingam, Siva
References
TAC ME6527
Download: ML13018A307 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 1, 2013 Mr. Jon A. Franke Vice President Crystal River Nuclear Plant (NA2C)

ArrN: Supervisor, Licensing and Regulatory Programs (NA 1 B) 15760 W. Power Line Street Crystal River, FL 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527)

Dear Mr. Franke:

By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011, August 11, 2011 (two letters), August 18, 2011, August 25,2011, October 11,2011, October 25,2011, December 15,2011 (two letters), December 21,2011, January 5, 2012 (two letters),

January 19, 2012 (two letters), January 31,2012, March 19, 2012, March 22,2012, April 4, 2012 (two letters), April 12, 2012, April 16, 2012, April 26, 2012, June 18,2012, June 29, 2012, July 17, 2012 (two letters), July 31,2012 (two letters), August 21,2012 (two letters), August 30,2012, September 6,2012, September 17,2012, September 27,2012, October 4, 2012, October 11, 2012, November 7, 2012, and December 18, 2012 (two letters),

Florida Power Corporation, doing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant.

The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on January 31, 2013, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter.

If you have any questions regarding this matter, I can be reached at 301-415-1564.

Sincerely,

~(j'.~

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRA TE TO INCREASE THERMAL POWER LEVEL FROM 2609 MEGAWATTS THERMAL TO 3014 MEGAWATTS THERMAL CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 By letter dated June 15, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112070659), as supplemented by letters dated July 5, 2011, August 11, 2011 (two letters), August 18, 2011, August 25, 2011, October 11, 2011, October 25, 2011, December 15, 2011 (two letters), December 21, 2011, January 5, 2012 (two letters), January 19, 2012 (two letters), January 31,2012, March 19, 2012, March 22, 2012, April 4, 2012 (two letters), April 12, 2012, April 16, 2012, April 26, 2012, June 18,2012, June 29,2012, July 17,2012 (two letters), July 31,2012 (two letters), August 21,2012 (two letters), August 30,2012, September 6,2012, September 17, 2012, September 27,2012, October 4, 2012, October 11,2012, November 7, 2012, and December 18,2012 (two letters)

(ADAMS Accession Nos. ML11201A310, ML11228A032, ML11234A051, ML11234A427, ML11242A140, ML112860156, ML113040176, ML11354A232, ML11354A233, ML11361A460, ML12011A035, ML12030A209, ML12024A300, ML12024A301, ML12032A280, ML12081A293, ML12086A107, ML120970114, ML12097A246, ML12107A216, ML12114A002, ML12118A498, ML12173A391, ML122060421, ML122050452, ML12205A268, ML12216A354, ML12216A355, ML12240A009, ML12240A010, ML12254A241, ML12251A250, ML12264A087, ML12272A344, ML12279A383, ML12286A329, ML123140487, ML12361A009, and ML12361A010, respectively), Florida Power Corporation (the licensee) submitted a license amendment request for an extended power uprate (EPU) to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant (CR-3). Portions of the letters dated June 15, 2011, August 11, 2011 (ADAMS Accession No. ML11228A032),

January 31,2012, June 18, 2012, July 17, 2012 (ADAMS Accession No. ML122050452),

August 30,2012, and September 17, 2012, contain sensitive unclassified non-safeguards information and, accordingly, those portions have been withheld from public disclosure. In order to complete its review of the above documents, the U.S. Nuclear Regulatory Commission (NRC) staff requests additional information originating from its Reactor Systems Branch (SRXB). The following input includes the topics of Section 2.8 of Attachment 5 or 7 of your original application dated June 15, 2011.

Main-steamline break Inadvertent opening of a pressurizer pressure relief valve Steam generator tube rupture Emergency core cooling system and loss-of-coolant accidents Enclosure

- 2 SRXB REQUEST FOR ADDITIONAL INFORMATION 2.8.5.1.2 Steam System Piping Failures Inside and Outside Containment 2.8.5.1.2.1 The technical report (TR) describes predicted plant performance following a double-ended rupture of a main steamline. Please address reactor system performance following a smaller break, which would require a longer time to reactor trip and potentially delay the actuation of mitigating safety features.

2.8.5.1.2.2 Consistent with CR-3 current licensing basis and NRC-approved methodology, the steamline break analyses assume that some initial conditions are at nominal values. The assumed primary system pressure and steam generator initial inventories have some degree of uncertainty and operating variability associated with them. Please characterize the effect that this uncertainty and variability will have on the results of the analyzed events.

2.8.5.1.2.3 Other analytic methods tend to require the evaluation of hot zero power and hot full power events; however, the TR describes the evaluation of pre-and post-trip events. Please explain how a post-trip main steamline break analysis differs from a hot zero power events, and address whether the post-trip analysis is limiting if compared to another hot-zero power condition.

2.8.5.1.2.4 Explain how the availability of offsite power maximizes heat removal via the once through steam generators.

2.8.5.1.2.5 Please explain the assumption of the lower core power for post-trip reactivity response and explain the significance of reduced post-trip decay levels.

2.8.5.1.2.6 The TR states that boron is not credited until after an appropriate delay. Please quantify the delay and provide information to justify its appropriateness.

2.8.5.6.1 Inadvertent Opening of Pressurizer Pressure Relief Valve 2.8.5.6.1.3 The supplemental analysis of the reactor coolant system depressurization (ADAMS Accession No. ML11286A094) indicates that zero percent steam generator tube plugging is assumed. Justify this assumption.

2.8.5.6.1.4 The supplemental analysis also discusses the assumption of a positive moderator temperature coefficient, which causes a power increase associated with the reactor coolant system depressurization. From a thermal-hydraulic perspective, this discussion is counter-intuitive because a cooling effect is usually associated with a system depressurization. Please explain how the moderator temperature coefficient is determined and expressed, in order to clarify the effect of the moderator density reduction in the presence of the positive moderator temperature coefficient.

- 3 2.8.5.6.2 Steam Generator Tube Rupture 2.8.5.6.2.1 The supplemental information concerning the steam generator tube rupture indicates that a moderator temperature coefficient of 0.0 x 10-4 6k1krF (ADAMS Accession No. ML11286A093). The TR characterizes this value as a bounding value. In the reactor coolant depressurization analysis, a positive value is used, which results in an increase in power. In light of this information, please explain how the zero value is bounding for the tube rupture analyses.

2.8.5.6.2.2 Please clarify the atmospheric release pathway for the radiological analysis. The thermal-hydraulic analysis discussed in the TR assumes that the steam is dumped using the turbine bypass valves. Is this the case for the radiological analysis?

2.8.5.6.3 Emergency Core Cooling System and Loss-ot-Coolant Accidents 2.8.5.6.3.1.

It appears that the chosen linear heat generation rate (LHGR) limit is quite high and not reflective of expected plant operating conditions. Please justify the chosen LHGR limit. The maneuvering analysis which includes the non-Ioss-of-coolant (non-LOCA) imposed limitations and/or the calculation addressing each of the 4 criteria listed on page 214 of "CR-3 LOCA Summary Report - EPU/ROTSG [replacement once-through steam generator]/Mark-B-HTP

[high thermal performance]" would be helpful in understanding.

2.8.5.6.3.2 Please provide more specific results for oxidation.

February 1, 2013 Mr. Jon A. Franke Vice President Crystal River Nuclear Plant (NA2C)

AnN: Supervisor, Licensing and Regulatory Programs (NA 1 B) 15760 W. Power Line Street Crystal River, FL 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527)

Dear Mr. Franke:

By letter dated June 15,2011, as supplemented by letters dated July 5, 2011, August 11, 2011 (two letters), August 18, 2011, August 25, 2011, October 11, 2011, October 25, 2011, December 15,2011 (two letters), December 21,2011, January 5,2012 (two letters),

January 19, 2012 (two letters), January 31, 2012, March 19, 2012, March 22, 2012, April 4, 2012 (two letters), April 12, 2012, April 16, 2012, April 26, 2012, June 18,2012, June 29,2012, July 17, 2012 (two letters), July 31,2012 (two letters), August 21,2012 (two letters), August 30,2012, September 6,2012, September 17, 2012, September 27,2012, October 4,2012, October 11, 2012, November 7,2012, and December 18, 2012 (two letters),

Florida Power Corporation, doing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant.

The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on January 31, 2013, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter.

If you have any questions regarding this matter, I can be reached at 301-415-1564.

Sincerely, IRA!

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL2-2 RlF RidsNrrDorlLpl2-2 RidsNrrPMCrystalRiver RidsNrrLABClayton RidsOgcMailCenter RidsNrrDorlDpr RidsAcrsAcnw_MailCTR S. Lingam. NRR RidsRgn2MailCenter RidsNrrDssSrxb B. Parks, NRR ADAMS Accession No: ML13018A307

• B-:symemo OFFICE LPL2-2/PM NAME SLingam DATE 1/31/13 LPL2-2/LA(IT)

FKeith 1/25/13 LPL2-2/LA BClayton 1/31/13 DSS/SRXB/BC*

CJackson 1/16/13 LPL2-2/BC JQuichocho 2/1113 OFFICIAL RECORD COpy