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{{Adams
#REDIRECT [[NG-98-0493, Application for Amend to License DPR-49,revising TS Re Reactor Vessel Pressure-Temp Curve Update]]
| number = ML20217B799
| issue date = 04/15/1998
| title = Application for Amend to License DPR-49,revising TS Re Reactor Vessel Pressure-Temp Curve Update
| author name = Franz J
| author affiliation = IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000331
| license number =
| contact person =
| document report number = NG-98-0493, NG-98-493, NUDOCS 9804230131
| package number = ML20217B803
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 5
| project =
| stage = Request
}}
 
=Text=
{{#Wiki_filter:IES Utskties Inc.
        ,'                                                                              200 Ftrst Street SE.
PO Box 351 Cedar Rapids, !A 52406-0351 f                                                                                        Telephone 319 398 8162 Fax 319 398 8192 UTILITIES                                                                ,,,,,,,,,,,,,,_
Mce President. Nuclear April 15,1998 NG-98-0493 l            Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission I
Attn: Document Control Desk l            Mail Station PI-37 l              Washington, DC 20555-0001
 
==Subject:==
Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 l
Request for Technical Specification Change (RTS-300):
                              " Reactor Vessel Pressure-Temperature Curve Update"
 
==Reference:==
Letter, K. Peveler (IES) to NRC, " Reactor Pressure Vessel Surveillance Materials Testing and Analysis," NG-97-1834, dated October 17,1997 File:          A-l l 7
 
==Dear Sir (s):==
 
In accordance with the Code of Federal Regulations, Title 10, Sections 50.59 and 50.90, IES Utilities Inc. hereby requests revision to the pending improved Technical Specifications (ITS) for the Duane Arnold Energy Center (DAEC).
The proposed amendment updates the existing pressure-temperature curves in the proposed ITS with new curves with values from 18 to 32 effective full power years based on the referenced submittal. Surveillance requirements (SRs) and the Bases are also revised to reflect operation with the new curves.
This application has been reviewed by the DAEC Operations Committee and the Safety Committee. A copy of this submittal, along with the evaluation of No Significant Ilazards Consideration, is being forwarded to our appointed state official pursuant to 10 CFR Section 50.91. We request approval of this application no later than September 28, i              1998 to ensure implementation prior to the expiration of the existing curves.
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9804230131 980415 l          PDR    ADOCK 05000331
:          p                      PDR An IES Industnes Company
 
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NG-98-0493 April 15,1998                                                                              ,
Page 2 1
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This letter is true and accurate to the best of my knowledge and belief.
;        IES UTILITIES INC.
By                    M      #
                  /ohn F. Fra'nz Vice President, Nuclear State ofIowa (County) of Linn Signed and sworn to before me on this /6            day of  ADri/              ,1998, by $8in { [rttn t
              ..                                                0/Hfl.h            A/1MLl>
l      i      NANCY S. FMNCK NotaNy PublM in and for the State oflowa
              ~
Q-g78 Qf Commission Expires Attachments: 1)            EVALUATION OF CHANGE PURSUANT TO 10 CFR SECTION 50.92
: 2)      PROPOSED CHANGE RTS-300 TO THE DUANE ARNOLD ENERGY CENTER IMPROVED TECHNICAL SPECIFICATIONS
: 3)      SAFETY ASSESSMENT
: 4)      ENVIRONMENTAL CONSIDERATION LLS/lls cc:      L. Sueper L. Root (w/o)
D. Wilson (w/o)
R. Laufer (NRC-NRR)
A. B. Beach (Region Ill)
P. Baig (State ofIowa)                                                              i NRC Resident Office Docu
                                                                                                      ]
                                                                                                      )
 
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RTS-300                                                                              Attachment I to
  '                                                                                                                l NG-98-0493 Page1of3 EVALUATION OF CIIANGE PURSUANT TO 10 CFR SECTION 50.92 Backuround:
By letter dated October 17,1997 (NG-97-1834), the methods and results of testing performed on the second materials surveillance capsule removed from the Duane Arnold Energy Center (DAEC) reactor pressure vessel were transmitted in accordance with 10 CFR 50, Appendices G and 11. Included in the report were Pressure-Temperature (P-T) curves valid for 18,20,24,28, and 32 effective full power years (EFPY) which were developed based on the surveillance data. The purpose of this Technical Specification amendment request is to incorporate the new curves in the pending improved Technical Specifications (ITS) prior to exceeding the limit of the current curves,16 EFPY.
Surveillance requirements (SRs) and the Bases are also revised to reflect operation with the new curves.
I IES Utilities Inc.. Docket No. 50-331.
Duane Arnold Eneruv Center. Linn County, Iowa                                                        '
Date of Amendment Reauest: April 15.1998 Description of Amendment Reauest:
1 The proposed amendment:
i
: 1. Revises SR 3.4.9.1.b. to state "RCS heatup and cooldown rates are s 20 F in any 1                !
hour period during inservice Leak and Hydrostatic testing (Curve A)."
: 2. Adds SR 3.4.9.1.c,"RCS heatup and cooldown rates are s 100 F in any I hour period during Non-Nuclear IIeating (Curve B) and Nuclear Heating (Curve C)."
: 3. Replaces Figure 3.4.9-1," Pressure Versus Minimum Temperature Valid to Sixteen Full Power Years, per Appendix G of 10 CFR 50," with updated curves titled " Pressure Versus Minimum Temperature Valid to Thirty-Two Full Power Years, per Appendix G of 10CFR50."
: 4. Revises Bases page 3.4-51 LCO " element a" to state, "RCS pressure and temperatures are within the limits of Figure 3.4.9-1 and heatup or cooldown rates are s 100 F/hr during RCS heatup and cooldown, and s 20 F/hr during inservice leak and hydrostatic testing;"
: 5. Revises Bases page 3.4-54 and 3.4-55 SR 3.4.9.1 to insert " initiated and" and " starting and" in the sentence, " Surveillance for heatup, cooldown, or inservice leakage and hydrostatic testing may be initiated and discontinued when the criteria given in the relevant plant procedure for starting and ending the activity are satisfied."
 
RTS-300
~                                                                                                Attachment I to NG-98-0493 Page 2 of 3
: 5. Revises 3.4 Bases Reference 1 to state,"10 CFR 50, Appendix G, December 1995"
: 6. Revises 3.4 Bases Reference 7 to reflect proposed Technical Specification Amendment.
Basis for proposed No Sinnificant Hazards Consideration:
The Commission has provided standards (10 CFR Section 50.92(c)) for detennining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the moposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
After reviewing this proposed amendment, we have concluded:
: 1) The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. The pressure-temperature limits are not derived from Design Basis Accident (DBA) analyses. They are prescribed by the ASME B&PV Code and 10 CFR 50 Appendix G and H as restrictions on nomial                                I operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the reactor coolant pressure boundary.
: 2) The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated. The amendment will merely update the pressure-temperature curves (and associated SRs and Bases) already existing in the plant Improved Technical Specifications to provide limits from 18 to 32 EFPY ofoperation, which are based upon evaluation and analysis of actual in-vessel material specimens, per 10 CFR 50, Appendices G and II. The pressure-temperature curves are established to the requirements of 10 CFR 50, Appendix G to assure that brittle fracture of the reactor vesse! is prevented.
: 3) The proposed amendment will not involve a significant reduction in a margin of safety.10 CFR 50, Appendix G specifies fracture toughness requirements to provide adequate margins of safety during operation over the service lifetime. The values of adjusted reference temperature and upper shelf energy determined as a result of the 10 CFR 50, Appendices G and H analysis are expected to remain within the limits of Regulatory Guide 1.99, Revision 2 and Appendix G of 10 CFR 50 (less than 200 F and greater than 50 ft-lbs respectively) for at least 32 EFPY of operation.
 
f RTS-300                                                                        Attachment I to NG-98-0493 Page 3 of 3 Based upon the above, we have determined that the proposed amendment will not involve a significant hazards consideration.
Local Public Document Room Location: Cedar Rapids Public Library,500 First Street SE, Cedar Rapids, Iowa 52401 Attorney for Licensee: Al Gutterman; Morgan, Lewis & Bockius,1800 M Street NW, Washington, D.C. 20036-5869 l
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