ML20249C505

Forwards Rev 2 to 960726 License Amend Request for License DPR-22,which Proposed Changes to Ts,App A.Proposed Amend Changes TS Sections 3.6.C & 3/4.17.B & Associated Bases

ML20249C505
Person / Time
Site:	Monticello
Issue date:	06/19/1998
From:	Schibonski C NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20249C506	List: ML20249C505 ML20249C509 ML20249C512
References
NUDOCS 9806300194
Download: ML20249C505 (3)

Text

~. .< f i '

\[1- ' ' .

' ^ [: g " ;  :

. .p D j .' T. ;

L( ] [f[, [z'% '" h /'. h.1

. ,. i .

. - 1 _ (j I. .

N Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362 9637 June 19,1998 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Revision Two To License Amendment Request Dated July 26,1996 Reactor Coo! ant Equivalent Radiciodine Concentration And Control Room Habitability Ref.1 Letter from W. J. Hill, NSP, to NRC Document Control Desk, " Revision One to License Amendment Request Dated July 26,1996 Reactor Coolant Equivalent Radiciodine Concentration and Control Room Habitability (TAC M96256)," dated April 11,1997 Attached is Revision 2 to NSP's July 26,1996 license amendment request which proposed changes to the Technical Specifications, Appendix A of the Operating License, for the Monticello Nuclear Generating Plant (MNGP). This request is submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90. This revision supersedes in its entirety NSP's previous revision dated April 11,1997 (Ref.1).

This proposed amendment changes Technical Specification Sections 3.6.C, Coolant Chemistry, and 3/4.17.B, Control Room Emergency Filtration System and the associated bases for these sections. The changes are proposed to establish Technical Specification requirements that are consistent with the analysis inputs used for the evaluation of the radiological consequences of the Main Steam Line Break Accident (MSLBA).

The proposed changes include a request to revise the reactor coolant radiciodine concentration specified in Technical Specification section 3.6.C, Coolant Chemistry, to a value consistent with evaluations performed for a postulated High Energy Line Break (HELB) in the Reactor Water /

Cleanup (RWCU) system. By letter dated September 1996, NSP reported in Monticello Licensee Event Report (LER)96-008, Reactor Water Clean Up Line Break Reanalysis Due to an Error Discovered During Re-evaluation, that a discrepancy existed in the mass and energy release calculated for a RWCU HELB. The submittal of this license amendment request revision satisfies the action committed to in LER 90-008 to submit a change to the Technical

/ LgI

/

Specifications to establish the administrative !imit of 0.25 pCi/gm on reactor coolant dose equivalent radiciodine concentration as a Technical Specification Limiting Condition for Operation. , . . , - ,

..J v v b 1 6/19I98 oDJ J1UCENSE'.lOELEFTRER-DEFT LAR2 DOC

\

9006300f94 990619 PDR ADOCK 05000263 P PDRf

-e  !

I The analysis of the postulated RWCU HELB dose consequences, as summarized in Exhibit E, was performed using an input assumption for reactor coolant dose equivalent radiciodine of 0.25 j Ci/gm. The analysis of the postulated MSLBA summarized in Exhibit D was performed using a l dose equivalent radioiodine input of 2 Ci/gm. The MSLBA analysis was done in support of a l future license amendment request to raise the Technical Specification limit for reactor coolant I dose equivalent radioiodine concentration to 2 Ci/gm. This future amendment will also include a request for credit for the automatic RWCU isolation installed during the 1998 refueling outage. )

Exhibit A contains a description of the proposed changes, the reasons for requesting the I changes, a Safety Evaluation, a Determination of No Significant Hazards Consideration, and an Environmental Assessment. Exhibit B contains the current Tc::hnical Specification pages marked up with the proposed changes. Exhibit C contains revised Monticello Technical I Specification pages. Exhibit D, MNGP MSLBA Evaluation Summary, provides a summary of the modified Main Steam Line Break accident analysis and reports the results of the re-evaluation of this postulated accident scenario. Exhibit E, MNGP RWCU Evaluation Summary, provides a summary of the evaluation performed of the radiological consequences of a postulated line break in the RWCU system. I On May 12,1998 and May 21,1998, the NRC Staff and NSP discussed the control room l habitability sections of this license amendment request. NSP stated that certain items would involve a future commitment on Emergency Filtration Train (EFT) system testing . Although the l Monticello EFT System was designed to meet the requirements of ANSI /ASME N510-1980, l NSP stated that the requirements of ASTM D 3803-1989 and ASME N510-1989 would be incorporated into the EFT system testing to the extent possible. Because of the design vintage and configuration of Monticello's EFT system, certain exceptions from ASME N510-1989 are necessary. The subject commitment and the exceptions to ASME N510-1989 are documented in Exhibit F of this submittal. NSP has also identified a few minor differences between the ASME N510-1989 standard and NSP testing procedures. The affected NSP procedures will be amended to accurately reflect the standard prior to implementation of power rerate.

This submittal is also being used, in part, to supplement NSP's power rerate license amendment dated December 4,1997. The changes to this submittat do not affect the determination of no significant hazards that is included within the power rerate license amendment. Please contact Joel Beres at 612-295-1436 if additional information is required.

Craig A Schibonski Actin lant Manager Mo cello Nuclear Generating Plant i

[. _

9 c: Regional Administrator-Ill, NRC NRR Project Manager, NRC Resident inspector, NRC State of Minnesota Attn: Kris Sanda Attachments: Affidavit to the US Nuclear Regulatory Commission Exhibit A - Evaluation of Proposed Changes to the Technical Specifications Exhibit 8 - Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit C - Revised Technical Specification Pages Exhibit D - MNGP MSLBA Evaluation Summary Exhibit E - MNGP RWCU Evaluation Summary Exhibit F - EFT System Commitment and ASME N510-1989 Testing Exceptions l

________