Text

Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment
	ML090820031
Person / Time
Site:	Monticello
Issue date:	03/20/2009
From:	Tam P; Plant Licensing Branch III
To:	Pointer K, Salamon G; Northern States Power Co
	Tam P
References
	TAC MD9990
	Download: ML090820031 (3)
	v • d • e

Accession No. ML090820031 From: Peter Tam Sent: Friday, March 20, 2009 4:21 PM To: 'Pointer, Kenneth'; 'Salamon, Gabor' Cc: Roger Pedersen; Karl Feintuch

Subject:

Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990)

Ken:

Our review of your 11/5/09 application for an extended power uprate (EPU) amendment is ongoing. Our Reactor Inspection Branch has provided the following draft RAI questions in the health physics area. Please contact me to set up a conference call to discuss these questions.

If you desire to have the proposed conference call during 3/24/09 - 4/10/09 when I am on leave, please contact my back up Karl Feintuch (301-415-3079).

1. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, indicates that an analysis predicts only a 3 percent increase in dose rates at the high pressure (HP) turbine due to increased N-16 in the steam entering the turbine. This is somewhat lower than analysis provided for similar uprates at other BWRs in the U.S.

a. Provide a detailed description of this analysis and input parameters. Include the main steam transient time, from the reactor head to the HP-LP turbine crossover line under full power CLTP conditions; and the corresponding transient time under full power EPU conditions.

b. It is the staffs understanding that the steam crossover line from the HP to LP turbines is the major source of N-16 gamma radiation shine from BWR turbine buildings. Verify that this is the case for Monticello or provide the transient time information in 1.a. above from the reactor head to the turbine building component determined to be the major gamma source.

2. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-344, indicates that EPU may result in a maximum sky shine source dose rate increase of up to 34.4 percent and that this results in a maximum increase in offsite dose due to sky shine at EPU conditions of less than 6 mrem/yr.

a. Resolve the apparent discrepancy between the 3 percent increase stated on page 2-343 and the 34.4 percent increase stated on page 2-344.

b. Describe how Monticello currently demonstrates that the annual dose to the maximum exposed member of the public meets the 25 mrem/yr requirement of 40 CFR 190.

c. What is the nominal annual dose (allowing for variations from year to year) to the maximum exposed member of the public from Monticello operations under CLTP conditions? What are the contributions to this dose from N-16 shine, Nobel Gas, and other plant effluents?

3. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, Table 2.10-2, indicates a possible increase in localized dose rates in the balance-of plant (BOP) of up to 1130% under EPU conditions.

Verify that these increases do not change the radiation zoning of the BOP spaces.

4. The Safety Analysis Report for the Monticello Constant Power Uprate , dated October 2008, page 2-340, Table 2.9-1, indicates the dose consequences in the Control Room and Technical Support Center, from a design-basis loss-of-coolant accident under EPU conditions, as 3.80 rem and 0.83 rem, respectively. Verify that these results include direct radiation exposure from plant systems containing the accident source term, consistent with the assumptions in NUREG-0737, item II.B.2.

If not, demonstrate that the direct radiation dose rates for these two vital areas meet the GDC-19 dose criteria, as specified in NUREG-0737, item II.B.2.

This e-mail aims solely to prepare you and others for the requested conference call. This e-mail does not convey a formal NRC staff position, and does not formally request for additional information.

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451 E-mail Properties Mail Envelope Properties (3D6B1F4F51D25E4E9B6C93FF92DAE5171443BF3C27)

Subject:

Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990)

Sent Date: 3/20/2009 4:21:23 PM Received Date: 3/20/2009 4:21:00 PM From: Peter Tam Created By: Peter.Tam@nrc.gov Recipients:

Kenneth.Pointer@xenuclear.com ('Pointer, Kenneth')

Tracking Status: None Gabor.Salamon@xenuclear.com ('Salamon, Gabor')

Tracking Status: None Roger.Pedersen@nrc.gov (Roger Pedersen)

Tracking Status: None Karl.Feintuch@nrc.gov (Karl Feintuch)

Tracking Status: None

Post Office:

HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 17372 3/20/2009 Options Expiration Date:

Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:

v t e Letter Sequence Draft RAI
TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 16 December 2008 11 February 2009 11 March 2009 12 March 2009 18 March 2009 18 March 2009 19 March 2009 20 March 2009 23 March 2009 29 March 2009 28 March 2009 28 March 2009 6 April 2009 6 April 2009 29 April 2009 26 June 2009 2 July 2009 2 July 2009 14 July 2009 14 July 2009 5 November 2009 16 March 2011 12 September 2011 4 October 2012 8 November 2012 28 March 2013 17 May 2013 9 July 2013 26 November 2013 18 December 2008 18 December 2008 19 March 2009 25 October 2009 15 February 2013 12 March 2013 10 May 2013 24 April 2013 Answers 25 January 2010 28 September 2010 13 January 2012 21 December 2012 7 March 2013 18 March 2013 21 March 2013 10 April 2013 18 July 2013 18 July 2013 2 August 2013 18 May 2016 19 July 2012 31 January 2013 29 March 2013 10 April 2013 Results Approval, Approval, Approval, Approval, Approval, Approval Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
MONTHYEAR2009-02-24 [Table View]

ML090820031

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