ML031840445
| ML031840445 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/25/2003 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML031840445 (18) | |
Text
Duke Mftwftwer. Duke Power McGuire Nudcear Staton A D, _Co.- 12700 Hagers Ferry Road Huntersvillc, NC 28078-9340 (704) 875-4000 D. M. Janil Vice President,McGuire (704) 875-5333 OFFICE NuclearGenerationDepartment (704) 8754809 FAX June 25, 2003 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 License Amendment Request for Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 4.2.1, Design Features, Fuel Assemblies Pursuant to 10 CFR 50.4 and 10 CFR 50.90, Duke Energy Corporation (Duke) is requesting an amendment to the McGuire Nuclear Station Facility Operating Licenses and Technical Specifications (TS). As described below, this amendment will correct two inadvertent editorial changes made by Duke during the submittal of TS Amendment 194/175 which revised TS 3.3.1 (Reactor Trip System Instrumentation) and TS Amendment 197/178 which revised TS 4.2.1 (Design Features, Fuel Assemblies).
Regarding TS 3.3.1, TS Amendment 194/175 inadvertently changed the new, lower reactor coolant low flow values in Table 3.3.1-1 back to the previous values that had been revised by TS Amendment 191/172.
Regarding TS 4.2.1, TS Amendment 197/178 inadvertently removed ZIRLOe as an acceptable fuel rod cladding material which had been added by TS Amendment 188/169.
Please be advised that TS 4.2.1 has an additional pending revision related to the Mixed Oxide (MOX) fuel License Amendment Request submitted to the NRC on February 27, 2003.
The contents of this License Amendment Request (LAR) are as follows:
Attachment 1 provides a marked copy of the affected Technical Specifications showing the proposed changes.
AO1u
U.S. Nuclear Regulatory Commission Page 2 June 25, 2003 provides reprinted pages of the affected Technical Specifications with the proposed changes incorporated. provides a description of the proposed changes and justifications. , pursuant to 10 CFR 50.92, provides the determination that this LAR contains No Significant Hazards Consideration. , pursuant to 10 CFR 51.22, provides the basis for the categorical exclusion from performing an Environmental Assessment/Impact Statement.
Implementation of this proposed amendment to the McGuire Technical Specifications will not impact the McGuire Updated Final Safety Analysis Report (UFSAR).
Duke is requesting NRC review and approval of this LAR at its earliest convenience so that the identified Technical Specifications may be editorially corrected.
In accordance with Duke administrative procedures and the Quality Assurance Program Topical Report, this LAR has been reviewed and approved by the McGuire Plant Operations Review Committee Chairman and the Duke Corporate Nuclear Safety Review Board Director.
Pursuant to 10 CFR 50.91, a copy of this LAR is being forwarded to the appropriate North Carolina State officials.
Inquiries on this matter should be directed to Lee A. Hentz at 704-875-4187.
Sincerely, D. M. Jamil Attachments
U.S. Nuclear Regulatory Commission Page 3 June 25, 2003 cc: w/attachments Mr. L. A. Reyes Regional Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30323 Mr. R. E. Martin Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop O-8G9 Washington, D.C. 20555 Mr. J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station Ms. B. 0. Hall Section Chief Division of Radiation Section 1645 Mail Service Center Raleigh, NC 27699
U.S. Nuclear Regulatory Commission Page 4 June 25, 2003 OATH AND AFFIRMATION D. M. Jamil affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
D. M Jamil, Site Vice President Subscribed and sworn to me: Snnc, Z5, 2003 Date LJ161 4A2.Wnu ",ks. Rtrft--
Notary Public My commission expires: 19, zop Date 1'
bxc: w/attachments N. T. Simms (MGO1RC)
J. W. Bryant (MGO1RC)
P. T. Vu (MGO1RC)
J. S. Warren (EC05N)
G. A. Copp (EC09A)
ELL (ECO50)
McGuire Master File # 1.3.2.9 NSRB Support Staff (EC05N)
ATTACHMENT 1 MARKED PAGES OF AFFECTED TECHNICAL SPECIFICATIONS
RTS Instumentation
.3&1 Table 3..1.1 (page 2 f 7)
Reacwo TUp Syste kislrmontaion APPUGA8LE MODES OR OTHER SPEOIRIED REOLKRED SURVEaANCE ALJ.D1VABL.E TZ FUNCTlN CONDMONS CHANNELS~-cONOMONS - -MUKIEUENT .VALUE -- S1Pt1T I
~
. _~ ~~~~~Reek
- 6. Overion~erahzm AT 1.2 E SR 3.1.1 Refortb tNloe I(pape Heoelb SR .1.3 SR 3.3i1.s 3.31-18) NOW I18 SR 3.3.7 SR 3.1.12 SR 3.3.1.16 SR 31.17
- 7. OverpowerAT 1.* 4 E 8RO.3.1 ReOW to - Refer to SR 3.31. N~OW2(page Note 2 SGR 1.6 3.3.1-19) (Pao SRS3.1.?
SR 3.31.12 SR 3.3.16 SA3..117
- 6. Psudz~or9 rosst
- a. Low 4 U SR33.1. kl9 3S5psig 1945 psig I SR3.1.7 SR 3.&O.10 SR =11.1t6
- b. Kih 1. 4 E SR 3l.1 12395 pcW 2385 pSi I SR3.31.
SR 3.31.10 SR 3.1.16
- . PfqssurbWater a M SR&M.1 12% 1 l&M -High sR3=1.7 SR131.10
- 10. P4ea rOoolant Row-LOW
- a. Shig Locop 1W 3~perbop N CR&L1.1 CR331.7 GR33.10 SRS33..16
- b. TM LOOq9 I" 3~~perbop M CR331.1 6R3.31.10 SR3t.16 II. Under~otg RoNs 1prbun 'A SR3.3..9 't6016V 608V I GR3.31.10 GRM3+/-.1
--(Coffigd)
(1) Above IO P.7 (Low Power ReactorTsign Sio1 ktadodc.
fig) Above ft P4 (Power Range Neuon PAO Mck Aboeto P-7 (Low Powef ReactorTUips Stodc) koidock and bMwt P8 (Power Rang Neutron Flut dok MoGuire UnKs I and 2 3.3.1-15 Amendment No)
Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The McGuire Nuclear Station site is located at latitude 35 degrees, 25 minutes, 59 seconds north and longitude 80 degrees, 56 minutes, 55 seconds west. The Universal Transverse Mercator Grid Coordinates are E 504, 669, 256, and N 3, 920, 870, 471.
The site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina.
4.2 Reactor Core l Street- Z IRL o f 4.2.1 Fuel Assemblies The rea r shall contain 193 fuel assemblies. Each assembly shall consist of matrix o rcalloy fuel rods with an initial composition of natural or slig Y-enriched urani dioxide (UO2) as fuel material. Umited substitution z sLO )j zirconium all o stainless steel filler rods for fuel rods, in accordance bith approved a ions of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control material shall be silver Indium cadmium (Unit 1) silver indium cadmium and boron carbide (Unit 2) as approved by the NRC.
4.3 Fuel Storage 4.3.1 Criticalit!
4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum nominal U-235 enrichment of 4.75 weight percent;
- b. kiff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
- c. kff < 0.95 If fully flooded with water borated to 850 ppm, which l Includes an allowance for uncertainties as described In Section 9.1 of the UFSAR; McGuire Units 1 and 2 4.0-1 Amendment Nosed
ATTACHMENT 2 REPRINTED PAGES OF AFFECTED TECHNICAL SPECIFICATIONS
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 7)
Reactor Trip System Instrumentation APPUCABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDmONS CHANNELS CONDmONS REQUIREMENTS VALUE SETPOINT
- 6. Overtemperature AT 1.2 4 E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 1 (Page Note 1 SR 3.3.1.6 3.3.1-18) (Page SR 3.3.1.7 3.3.1-18)
SR 3.3.1.12 SR 3.3.1.16 SR 3.3.1.17
- 7. Overpower AT 1.2 4 E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 2 (Page Note 2 SR 3.3.1.6 3.3.1-19) (Page SR 3.3.1.7 3.3.1-19)
SR 3.3..12 SR 3.3.1.16 SR 3.3..17
- 8. Pressurizer Pressure
- a. Low 4 M SR 3.3.1.1 a 1935 psig 1945 psig
'SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16
- b. High 1,2 4 E SR 3.3.1.1 12395 psig 2385 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16
- 9. Pressurizer Water 1(f) 3 M SR 3.3.1.1 S 93% 92%
Level - High SR 3.3.1.7 SR 3.3.1.10
- 10. Reactor Coolant Flow -
Low
- a. Single Loop 1(g) 3 per loop N SR 3.3.1.1 2 87% 88% I SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16
- b. Two Loops I(h) 3 per loop M SR 3.3.1.1 2 87% 88%
SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16
- 11. Undervoltage RCPs I per bus M SR 3.3.1.9 _5016V 5082 V SR 3.3.1.10 SR 3.3.1.16 (continued)
(f) Above the P-7 (Low Power Reactor Trips Block) Interlock.
(g) Above the P-8 (Power Range Neutron Flux) Interlock.
(h) Above the P-7 (Low Power Reactor Trips Block) Interlock and below the P-8 (Power Range Neutron Flux) interlock.
McGuire Units 1 and 2 3.3.1 -15 Amendment Nos.
Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The McGuire Nuclear Station site is located at latitude 35 degrees, 25 minutes, 59 seconds north and longitude 80 degrees, 56 minutes, 55 seconds west. The Universal Transverse Mercator Grid Coordinates are E 504, 669, 256, and N 3, 920, 870, 471.
The site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina.
4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of either ZIRLOC or Zircalloy fuel rods with an initial composition of I natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of ZIRLObT, zirconium alloy, or stainless steel filler rods for fuel I rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control material shall be silver indium cadmium (Unit 1) silver indium cadmium and boron carbide (Unit 2) as approved by the NRC.
4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum nominal U-235 enrichment of 4.75 weight percent;
- b. kff < 1.0 If fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
- c. kff c 0.95 if fully flooded with water borated to 850 ppm, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; McGuire Units 1 and 2 4.0-1 Amendment Nos
ATTACHMENT 3 DESCRIPTION OF PROPOSED CHANGES AND TECHNICAL JUSTIFICATION
DESCRIPTION OF PROPOSED CHANGES AND JUSTIFICATIONS TS 3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION This proposed TS change will replace the reactor coolant low flow values in Table 3.3.1-1 with the values approved by TS Amendment 191/172 but were inadvertently revised by TS Amendment 194/175.
On June 24, 1999, and supplemented on November 24, 1999, Duke submitted an LAR to reduce the reactor coolant low flow trip setpoints and allowable values listed in Table 3.3.1-1, on page 3.3.1-15, from 91% to 88% and 90% to 87%,
respectively, to preclude spurious reactor trips. This LAR was approved by the NRC on March 2, 2000 and became TS Amendment 191/172.
On January 6, 2000, and supplemented on July 20, 2000, Duke submitted an LAR to remove the inequalities associated with various instrumentation trip setpoints. This LAR affected the reactor coolant low flow values listed in TS Table 3.3.1-1 on page 3.3.1-15. When these proposed changes were submitted, they did not incorporate the pending changes to Table 3.3.1-1 described above. Due to an oversight, Duke failed to supplement this submittal with an updated TS page 3.3.1-15 upon issuance of TS Amendment 191/172. Therefore, when the LAR associated with the removal of inequalities was approved by the NRC on September 18, 2000 under TS Amendment 194/175, the reactor coolant low flow values listed in Table 3.3.1-1 were inadvertently changed back to the higher values.
TS 4.2.1, DESIGN FEATURES, FUEL ASSEMBLIES This proposed TS change will replace ZIRLOm as an acceptable fuel rod cladding material in TS 4.2.1 which was added and approved under TS Amendment 188/169 but was inadvertently removed by TS Amendment 197/178.
On July 22, 1998, and supplemented on October 22, 1998, Duke submitted an LAR related to the transition to Westinghouse fuel at McGuire and Catawba. This LAR included a change to TS 4.2.1, Fuel Assemblies, to include ZIRLOe as an acceptable fuel cladding material on TS page 4.0-1. This LAR was approved by the NRC on September 22, 1999 and became TS Amendment 188/169.
On April 5, 1999, and supplemented on August 1, 2000, Duke submitted an LAR related to spent fuel storage. This LAR included a change to TS 4.3.1, Criticality, also on page 4.0-1, which added a new k.ff value. When the proposed
change to TS 4.3.1 was submitted, it did not incorporate the pending changes to TS 4.2.1 described above. Due to an oversight, Duke failed to supplement this submittal with an updated page 4.0-1 upon the issuance of TS Amendment 188/169. Therefore, when the spent fuel storage LAR was approved by the NRC on November 27, 2000 under TS Amendment 197/178, the reference to ZIRLO was inadvertently removed.
Please be advised that TS 4.2.1 on page 4.0-1, has an additional pending change related to the Mixed Oxide (MOX) fuel LAR submitted to the NRC on February 27, 2003.
ATTACHMENT 4 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION
NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION As required by 10 CFR 50.91(a)(1), this analysis is provided to demonstrate this License Amendment Request (LAR) does not involve a significant hazards consideration.
This LAR will correct inadvertent editorial changes made by Duke during subsequent License Amendments.
Conformance of this LAR to the standards for a determination of no significant hazards, as defined in 10 CFR 50.92, is shown in the following:
- 1. Does this LAR involve a significant increase in the probability or consequences of an accident previously evaluated ?
No. Approval and implementation of this LAR will have no affect on accident probabilities or consequences since the proposed changes are editorial in nature and were previously reviewed and approved by the NRC.
- 2. Does this LAR create the possibility of a new or different kind of accident from any accident previously evaluated ?
No. This LAR does not involve any physical changes to the plant. Therefore, no new accident causal mechanisms will be generated. The proposed changes are editorial in nature and were previously reviewed and approved by the NRC.
Consequently, plant accident analyses will not be affected by these changes.
- 3. Does this LAR involve a significant reduction in a margin of safety ?
No. Margin of safety is related to the confidence in the ability of the fission product barriers to perform their design functions during and following accident conditions.
These barriers include the fuel cladding, the reactor coolant system, and the containment system. The performance of these barriers will not be affected by the proposed changes since they are editorial in nature and have been previously reviewed and approved by the NRC.
CONCLUSION Based on the preceding analysis, it can be concluded that this LAR does not involve a significant hazards consideration as defined in 10 CFR 50.92.
ATTACHMENT 5 ENVIROMENTAL ASSESSMENT/IMPACT STATEMENT
ENVIRONMENTAL ASSESSMENT / IMPACT STATEMENT This License Amendment Request (LAR) has been reviewed against the criteria of 10 CFR 51.22 for environmental considerations. This LAR does not involve a significant hazards consideration, increase the types and amounts of effluents that may be released offsite, or result in the increase of individual or cumulative occupational radiation exposures. Therefore, this LAR to the McGuire Technical Specifications meets the criteria provided by 10 CFR 51.22(c)(9) for categorical exclusion from the requirement for an Environmental Impact Statement.