ML14163A024

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Response to Request for Additional Information - Review of the Cycle 20 Core Operating Limits Report
ML14163A024
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/10/2014
From: Jim Barstow
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-14-074
Download: ML14163A024 (40)
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Text

TMl-14-074 June 10, 2014 TS U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50

Subject:

Response to Request for Additional Information

-Review of the Three Mile Island Nuclear Station, Unit 1 Cycle 20 Core Operating Limits Report

References:

1) Letter from D. W. Atherholt to U.S. Nuclear Regulatory Commission, "Cycle 20 Core Operating Limits Report, COLA TMI 1, Revision 9," dated November 8, 2013. 2) Letter from J. A. Whited (Project Manager, U.S. Nuclear Regulatory Commission) to M.J. Pacilio (President and Chief Nuclear Officer, Exelon Nuclear), "Three Mile Island Nuclear Station, Unit 1 -Request for Additional Information Regarding Review of Cycle 20 Core Operating Limits Report (TAC No. MF3332)," dated May 22, 2014. In Reference 1, Exelon Generation Company, LLC (Exelon) submitted "Cycle 20 Core Operating Limits Report, COLA TMI 1, Revision 9," in accordance with TMl-1 Technical Specification (TS) Section 6.9.5.4. In Reference 2 the U.S. Nuclear Regulatory Commission requested additional information.

Attachment 1 is our response.

Should you have any questions concerning this letter, please contact Frank Mascitelli at (610) 765-5512.

U.S. Nuclear Regulatory Response to Request for Additional Information TMl-1 Cycle COLR June 10, 2014 2 Respectfully, James Barstow Director -Licensing

& Regulatory Affairs Exelon Generation Company, LLC Attachments:

1) Response to Request for Additional Information
2) Draft TMl-1 Cycle 20 Core Operating Limits Report cc: USNRC Administrator, Region I USNRC Senior Resident Inspector, TMl-1 USNRC Project Manager, TMl-1 Director, Bureau of Radiation Protection

-PA Department of Environmental Resources ATTACHMENT 1 Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 Response to Request for Additional Information Related To The Review Of The Three Mile Island Nuclear Station, Unit 1 Cycle 20 Core Operating Limits Report Response to Request for Additional Information Related To The Review Of The Three Mile Island Nuclear Station, Unit 1 Cycle 20 Core Operating Limits Report Page 1of3 In Company, LLC (Exelon) submitted "Cycle 20 Core Operating COLA TMI 1, Revision 9," in accordance with TMl-1 Technical Specification (TS) Section 6.9.5.4. The U.S. Nuclear Regulatory Commission reviewed the Cycle 20 Operating Limits Report, and identified and requested in Reference 2 the need for additional information in order to complete their evaluation.

The questions are restated below along with Exelon's response.

RAI Question 1 Please identify plant and cycle-specific parameters for TS 6.9.5.1 and show those core operating limits in the TMI C20 COLA. Response The following table identifies the plant and cycle-specific parameters for TMl-1 Technical Specification 6.9.5.1 and cross references these parameters to the figure, table, or section in the TMl-1 Cycle 20 COLA that contains those core operating limits. Parameter Current COLR Section Referred to by TS SL 2.1 Axial Power Imbalance Figure 10 TS 2.1.2 Protective Limits SL 2.3.1 Reactor Protection System Maximum Allowable Figure 11 TS 2.3.1 Setpoints for Axial Power Imbalance LCO 3.5.2 Full lncore System TS 3.5.2.4.a Full lncore System Operability Requirements TS 3.5.2. 7.a Operability Requirements (Paqe 6) LCO 3.5.2 Table 1 TS 3.5.2.4 Quadrant Power Tilt Limits TS 3.5.2.2.e LCO 3.5.2 Table 2 TS 3.5.2.4.e Power Peaking Factors -Figure 9 (Pages 1 & 2 of 3) TS 3.5.2.5.b Fa(Z) TS 3.5.2. 7.d TS 3.5.2.8 Response to Request for Additional Information Related To The Review Of The Three Mile Island Nuclear Station, Unit 1 Cycle 20 Core Operating Limits Report Page 2 of 3 3 Figure 1 -4 Pump LCO Operation Regulating Rod Insertion Figure 2 -3 Pump TS 3.5.2.4.e.3 Operation Limits Figure 3 2 Pump 0 eration Figure 4 -Full lncore System 4 Pump Operation Figure 5 -Full lncore System 3 Pump Operation LCO Figure 6 -Full lncore TS 3.5.2.4.e.4 Axial Power Imbalance Operating Limits System 2 Pump Operation TS 3.5.2.7 Figure 7 -Out-of-Core Detector System Figure 8 -Minimum lncore S stem SL 2.1.1 Bases Nuclear Power Peaking Enclosure 2, Item 2 TS 2.1 . 1 Bases Factors SL 2.1.2 Bases Maximum Allowable Local Enclosure 1 , Item 1 TS 2.1.2 Bases Linear Heat Rates SL 2.3.1 Bases Power-to-Flow Trip Enclosure 2, Item 1 TS 2.3.1 Bases Set oints LCO 3.5.2 Bases Allowable Moderator Figure 9 (Page 3 of 3) TS 3.5.2 Bases Temperature Coefficient MTC Alternate Minimum Boron Requirements for Cold Enclosure 1, Item 2 TS 3.3 Bases Shutdown RAI Question 2 Please justify that the use of any methodologies referenced in REFERENCES of the TMI C20 COLA to support the cycle-specific core operating limits (to be provided in RAl-1) is consistent with the TS 6.9.5.2.

Response to Request for Additional Information Related To The Review Of The Three Mile Island Nuclear Station, Unit 1 Cycle 20 Core Operating Limits Report Page 3 of 3 Response methodologies used to determine the core operating limits in the TMl-1 Cycle 20 COLA are contained in BAW-10179P-A, Rev. 8, Criteria and Methodology for Acceptable Cycle Reload Analyses, May 2010. This topical report is included in the reference section of the COLA as well as in Section of TMl-1 Technical Specifications.

BAW-10179P-A, Rev. 8, has been approved for use at all B&W-177 reactors.

Of the remaining methodologies listed in TS 6.9.5.2, BAW-10227P-A, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," has been incorporated into BAW-10179P-A, Rev. 8, and the in-house methodology topical reports TR-078-A, TR-087-A, TR-091-A, and TR-092P-A were not applied to Cycle 20 analyses.

RAI Question 3 Please organize the TMI C20 COLA in accordance to the TS 6.9.5.3 to include the proper TSs for cycle-specific core operating limits, the detailed limits, and their supporting methodologies listed in TS 6.9.5.2. Response A draft re-organization of the TMl-1 Cycle 20 COLA is provided in Attachment 2 to facilitate the NRC staff technical review of this document.

The draft COLA in Attachment 2 was also enhanced by condensing duplicate information.

The LOCA Limited Maximum Allowable Linear Heat Rate curves (Figure 9, Pages 1 and 2 in the current TMl-1 Cycle 20 COLA) were removed since the same information is provided in tabular format in Table 3 of the draft COLA.

ATTACHMENT 2 Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 Draft TMl-1 Cycle 20 Core Operating Limits Report TMI-1 Cycle 20 Core Operating Li1nits Report Preparer Review/SQR NF Approver ISR Director, Site Engineering COLRTMI 1 Draft Rev. X Date Date Date Date Date 1 2.0 .. ___ ,,,, ......

Rod Imbalance Operating Limits Factors ... "".._ .... ..,.,,.A.,..,..,'"',.,a.

Allowable Local Linear Heat Rates Power-to-Flow Trip Setpoints Allowable Moderator Temperature Coefficient (MTC) Minimum Boron Requirements for Cold Shutdown 1 Methodology BAW-10179P-A, 8, ---.... TL:l>T,,.

Criteria and Methodology for Acceptable Cycle Reload .. May 2010. 2.2 Other References Rev. 0, "Three Mile Island Unit 1 Cycle 20 Reload Report," August 2013. FRA-ANP Doc. No 86-11 72640-00, .. Detector Lifetime Extension Final Report for TMI-1," October 1989.

TABLE OF CONTENTS 1 4 7 2 Rector Protection Maximum Allowable Setpoints 8 for Axial Imbalance 1 Full (FIS) Operability Requirements 2 Quadrant Power Tilt Limits 3 Monitoring Bounding Values for LOCA Limited Maximum Allowable Linear Heat Table 4 LCO DNB Maximum Allowable Radial Peaking Limits 3 Rod Insertion Limits 4 Pump Operation 4 Regulating Rod Insertion Limits 3 Pump Operation Figure 5 Regulating Rod Insertion Limits 2 Pump Operation Figure 6 Axial Power Imbalance Operating Limits Full Incore System 4 Pump Figure 7 Axial Power Imbalance Operating Limits Full Incore System -3 Pump Figure 8 Axial Power Imbalance Operating Limits Full Incore System -2 Pump Figure 9 Axial Power Imbalance Operating Limits Out-of-Core Detector System Figure 10 Axial Power Imbalance Operating Limits Minimum Incore System Enclosure I Core Operating Limit Technical Specification Bases Descriptions Enclosure 2 Operating Limits Not Required by Technical Specifications 9 10 11 14 16 18 20 22 23 24 25 26 27 32 This with ABSTRACT COLR TMI I Draft Rev. X 4 of 33 Limits Report (COLR) has been prepared in accordance of TMI-1 Technical Specification 6.9.5. The core limits were methodologies described in Reference 1 and were documented in 2 and 3. The core operating limits and protection system limits and setpoints in this report have been for a maximum end-of-cycle (EOC) length of 715 EFPD. 1 provides the Axial Power Imbalance Protective Limits (APIPL) DNBR, Centerline Fuel Melt, and Cladding Transient Strain design criteria.

COLR Figure 2 provides the Protection System Maximum Allowable Setpoints for Axial Power Imbalance which combine the power/flow and error-adjusted axial imbalance trip setpoints that ensure the APIPL of Figure 1 are not The Full Incore System (FIS) operability requirements contained in Table 1 describe the number and location of Self-Powered Neutron Detector (SPND) strings that must be operable in order to monitor imbalance and quadrant tilt using the FIS. Quadrant power tilt limits for FIS, out-of-core detector [OCD] system and nnn1mum incore system [MIS] are given in Table 2. Technical Specification requirements related to quadrant tilt, including operator actions that must be taken in the event quadrant tilt limits are exceeded, are stated in T.S. 3.5.2.4. Table 3 contains the total peaking hot channel factor Fg(Z) limits (i.e., ECCS power peaking limits) for core monitoring.

Table 4 contains the nuclear enthalpy rise hot channel factor limits (i.e., initial condition DNB peaking) for core monitoring.

During normal conditions, operation within quadrant tilt (Table 2), rod insertion (Figures 3-5), and imbalance (Figures 6-10) limits ensure Fg(Z) and limits are met. However, verification that positive margin to Fg(Z) and limits exists may be required during the following abnormal conditions:

T.S. 3.5.2.2.e (operation with an inoperable rod) T.S. 3.5.2.4.e (operation with quadrant tilt in excess of steady-state limits) T.S. 3.5.2.5.b (operation with control rods in the Restricted Region) T.S. 3.5.2.7.d (operation with imbalance in the Restricted Region) Display 4 of the Core Monitoring System provides the minimum margin to Fg(Z) limits on the Thermal Limiting Condition Core Summary page and to limits on the Thermal Limiting Condition Hot Channel Factor page.

COLR TMI 1 Draft Rev. X of are provided in 3 to 5 to ensure that for DNBR protection, LOCA kw/ft limits, shutdown and ejected rod worth are met. Technical Specification requirements related to control rod

.... operator actions that must taken in the control or Not Allowed are in T.S. Imbalance limits for FIS. OCD and MIS are given in Figures 6 to 10. Technical Specification requirements related to axial power imbalance, including operator actions that be taken in the event imbalance enters the Restricted ....

are 7. COLR 1. 2. 3. 3 through 10 may have three distinctly defined regions: Permissible Region Restricted Region Not Allowed Region (Operation in this region is not allowed) The limiting criteria within the Restricted Region are ECCS power peaking, initial condition DNB peaking, and potential ejected rod worth. Since the probability of accidents related to these criteria is very low, especially in a twenty-four (24) hour time frame, inadvertent operation within the Restricted Region for a period not exceeding twenty-four (24) hours is allowed [T.S. 3.5.2.5.b and 3.5.2.7.e], provided that hot channel factors are within the limits given in Tables 3 and 4. Similarly, continued operation with quadrant tilt greater than the steady-state tilt limit for a period not exceeding twenty-four (24) hours is allowed [T.S. 3.5.2.4.e]

provided that hot channel factors are within the limits given in Tables 3 and 4, with the added requirement that reactor power must be reduced 2% for each 1 % tilt in excess of the tilt limit [T.S. 3.5.2.4.d]. (Note that continued operation with quadrant tilt greater than the steady-state tilt limit is also permitted without hot channel factor verification as long as the alternate guidance in T.S. 3.5.2.4.e is followed).

The limiting criterion within the Not Allowed Region is the shutdown margin limit. Inadvertent operation in this region is not permitted and requires immediate action to exit the region. Acceptable control rod positions shall be attained within two (2) hours [T.S. 3.5.2.5.b.2].

Enclosure 1 contains descriptions of limits and factors related to core operating limit TS bases. The Nuclear Power Peaking Factors for axial flux shape (FNz) and hot channel nuclear enthalpy rise (FN LlH) define the reference design peaking condition in the core. The Maximum Allowable Local Linear Heat Rate limits for centerline fuel melt and cladding transient strain are the basis for the imbalance portions of the Axial Power Imbalance Protective Limits and Setpoints.

The Power-to-Flow Trip Setpoint, in combination with the axial power imbalance trip, protects against violation of steady-state DNBR criteria.

volumes Boric Acid are the boron levels shutdown throughout the tanks.

Figure 1 SL 2.1.2 Axial Power Imbalance Protective Limits (-64.2, 67.1) (-64.2, 39.8) Thermal Power Level % (-47.9, 112.0) ACCEPTABLE 4PUMP OPERATION

(-47.9, 89.6) ACCEPTABLE AND4PUMP OPERATION

(-47.9, 62.3) ACCEPTABLE 2, 3 AND 4 PUMP OPERATION 3 120 100 60 40 20 (36.0, 112.0) (36.0, 89.6) (36.0, 62.3) setpoint curves allowable values for an aoor*oxinnate 25% and flow reduction for 3-and 2-pump operation respectively.

The actual setpoint curve will be calculated by the RPS and will be directly proportional to the indicated flow. 70 50 30 10 0 10 20 30 40 CURVE 1 2 3 Axial Power Imbalance,%

EXPECTED MINIMUM REACTOR COOLANT FLOW (lb/hr) 140.87 x 10 6 105.60 x 10 6 69.74 x 10 6 50 Referred to by Technical Specification 2.1.2 (64.2, 89.5) (64.2, 67.1) (64.2, 39.8) 60 70 80

-80 Figure 2 SL 2.3.1 Reactor Protection System Maximum Allowable Setpoints for Axial Power Imbalance m (-50.52, 71.50) (-50.52, 44.18) (-50.52, 16.64) C\J LO 0 u;> en 60 0 LO '? II C\J co 40 Thermal Power Level % 120 108.0) ACCEPTABLE 4PUMP OPERATION

(-33.50, 80.68) ACCEPTABLE 3 AND4 PUMP OPERATION (13.11, 108.0) 100 60 (-33.50, 53.14) (13.11, 53.14) ACCEPTABLE 2, 3 AND 4 PUMP OPERATION The 3-or 2-pump example 40 setpoint curves show allowable values for an approximate 25% and 51% flow reduction for 3-and 2-pump operation respectively.

20 The actual setpoint curve will be calculated by the RPS and will ,.-be directly proportional to the indicated II Cl) flow. co 20 -10 0 10 20 30 Axial Power Imbalance, % 40 50 Referred to by Technical Specification 2.3.1 (50.00, 71.50) (50.00, 44.18) (50.00, 16.64) 0 0 0 LO II """" co 60 70 80 Table 1 COLR TMI I Draft Rev. X 9 LCO 3.5.2 Full Incore System (FIS) Operability Requirements (FIS) operable for monitoring power number of valid Powered Neutron Detector (SPND) in one quadrant not than 75% of the total number of SPNDs in the quadrant.

Quadrant SPNDs 75°/o wx 85.75 64.5 XY 99.75 75.0 YZ 89.25 67.1) zw 89.25 67.0 Referred to by Technical Specification 3.5.2.4.a

  • The Full Incore System (FIS) is operable for monitoring quadrant tilt provided the number of valid symmetric string individual SPND signals in any one quadrant is not less than 75% (21) of the total number of SPNDs in the quadrant (28). Quadrant Symmetric Strings wx 7,9,32,35 XY 5,23,25,28 YZ 16, 19,47,50 zw 11, 13,39,43 Referred to by Technical Specification 3.5.2.7.a Source Document:

B&W 86-11 72640-00 Full Incore System (FIS) Minimum Incore System (MIS)Ca> TABLE2 COLR TMI I Draft Rev. X IO of 33 LCO 3.5.2 Quadrant Power Tilt Limits Steady State Limit Steady State Limit Maximum Limit 15 < Power ::;; 60% Power> 60% Power > 15% 6.83 4.53 16.8 2.78 1.90 9.5 Referred to by Technical Specification 3.5.2.4 (a) No individual long emitter detector affecting the minimum in-core tilt calculation exceeds 73% sensitivity depletion; therefore, reduced limits are not applicable and are not shown. Note: If the Full Incore System (FIS) is inoperable, FIS tilt limits are applicable to the Out-of-Core (OCD) Detector System following the guidance in OP-TM-300-202, Quadrant Power Tilt and Axial Power Imbalance using the Out-of-Core Detector System.

TABLES LCO 3.5 .. 2 Power Peaking Factors -Fg(Z) COLR TMI I Draft Rev. X I 1 Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW /ft Cal) Referred to by Technical Specification 3.5.2.2.e, 3.5.2.4.e, 3.5.2.5.b, 3.5.2. 7 .d, 3.5.2.8 LOCA Limits Batches 20 (Except Batch 20B), 21 and 22 Core Elevation 0 34,000 62,000 MWd/mtU MWd/mtU MWd/mtU 0.000 15.7 15.7 11.8 2.506 16.6 16.6 11.8 4.264 16.8 16.8 12.0 6.021 17.0 17.0 12.0 7.779 17.0 17.0 12.0 9.536 16.8 16.8 12.0 12.000 15.9 15.9 12.0 Batch 20B Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 15.6 15.6 11.8 2.506 16.5 16.5 11.8 4.264 16.7 16.7 12.0 6.021 16.9 16.9 12.0 7.779 16.9 16.9 12.0 9.536 16.4 16.4 12.0 12.000 15.5 15.5 12.0 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. All values at 0.000 and 2.506 feet have been reduced by 0.2 kW/ft based on compliance with SER to BAW-10192-A.

NOTE: LHR limits provided are based on nuclear power source.

Table 3 (Continued)

Gadolinia Fuel LOCA Limits Batches 20, 21 and 22 -2 wt.% Gadolinia Elevation 0 34,000 62,000 MWd/mtU MWd/mtU MWd/mtU 0.000 14.9 14.9 11.4 2.506 15.7 15.7 11.4 4.264 15.9 15.9 11.6 6.021 16.1 16.1 11.6 7.779 16.1 16.1 11.6 9.536 15.9 15.9 11.6 12.000 15.1 15.1 11.6 Batches 20, 21 and 22 -3 wt.% Gadolinia Core Elevation 0 34,000 62,000 MWd/mtU MWd/mtU MWd/mtU 0.000 14.2 14.2 11.1 2.506 15.0 15.0 11.1 4.264 15.2 15.2 11.3 6.021 15.4 15.4 11.3 7.779 15.4 15.4 11.3 9.536 15.2 15.2 11.3 12.000 14.4 14.4 11.3 Batch 21 -6 wt.% Gadolinia Core Elevation 0 34,000 62,000 (feet) MWd/mtU MWd/mtU MWd/mtU 0.000 13.3 13.3 10.4 2.506 14.0 14.0 10.4 4.264 14.2 14.2 10.6 6.021 14.4 14.4 10.6 7.779 14.4 14.4 10.6 9.536 14.2 14.2 10.6 12.000 13.5 13.5 10.6 COLR TMI l Draft Rev. X 12 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. All values at 0.000 and 2.506 feet have been reduced by 0.2 kW/ft based on compliance with SER to BAW-10192-A.

NOTE: LHR limits provided are based on nuclear power source.

COLR TMI l Table 3 (Continued)

Gadolinla Fuel LOCA Limits Batches 21 and 22 -8 wt.% Core Elevation 0 34,000 62,000 MWd/mtU MWd/mtU 0.000 13.3 13.3 10.4 2.506 14.0 14.0 10.4 4.264 14.2 14.2 10.6 6.021 14.4 14.4 10.6 7.779 14.4 14.4 10.6 9.536 14.2 14.2 10.6 12.000 13.5 13.5 10.6 (a) Linear interpolation for allowable linear heat rate limits between specified burnup points and core elevation points is valid for these tables. All values at 0.000 and 2.506 feet have been reduced by 0.2 kW/ft based on compliance with SER to BAW-10192-A.

NOTE: LHR limits provided are based on nuclear power source. The maximum linear heat rate for each CMS level, as measured with the FIDMS Thermal Hydraulic should not be greater than the corresponding bounding value from Table 2 above. FIDMS Display 4, Thermal Limiting Condition Core Summary, shows the minimum margin to F Q(Z) limits for each axial level. Notes: The LHR limits above are equivalent to the total peaking hot channel factor limits, F g(Z), referred to in T.S. 3.5.2 by dividing the LHR limits by the product of the core average linear heat rate and the current fraction of rated power. The core average linear heat rate for F g(Z) calculations is fuel batch specific and is based on nuclear source power to be consistent with the LHR limits above.

TABLE4 LCO 3.5.2 Power Peaking Factors -FNL\11 COLR TMI 1 Rev. X 1 of LCO DNB Maximum Allowable Radial Peaking (MARP) Limits Referred to by Technical Specification 3.5.2.2.e, 3.5.2.4.e, 3.5.2.5.b, 3.5.2. 7 .d, 3.5.2.8 minimum ,J .. "1.JlLU.i'\vU\,. (or negative) margin. limits for Notes: LCO DNB Maximum Allowable Radial Peaking (MARP) limits below are equivalent to nuclear enthalpy rise hot channel factor limits, referred to in by following conversion:

limit (LCO DNB MARP) * [ 1 + 0.3 * ( 1 P /Pm)] where: P = current fraction of power and, = power adjustment factor for RC Pump combination ( 1.0 for 4 pump, 0. 75 for 3 pump) limits are applicable to all fuel in the core for 3 and 4 RC pump operation.

These limits have been increased to reflect the 3.8% peaking uncertainty treated by Statistical Core Design (SCD) methodology.

1.1 0.50 0.60 0.70 0.80 0.01 0.14 0.20 0.30 0.40 1.2 0.50 0.60 0.70 0.80 0.89 0.99 0.01 0.14 0.20 0.30 0.40 1.3 0.50 0.60 0.70 0.80 0.89 0.99 TABLE 4 (Continued)

MARP Limits -Mark-B-HTP Assemblies Maximum Allowable 1.91833 1.91766 1 1739 1.91696 2.00471 2.00393 1.99966 1.99860 1.95423 1.87113 1.81351 1.73614 2.09686 2.09445 2.09300 2.09129 2.08973 2.04596 1.96946 1.89528 1.80831 1.74678 1.67928 1.4 1.5 1.6 Maximum x/L Allowable Radial 2.11538 2.04869 1.97877 1.7 1.89956 1.82744 0.80 1.74222 0.89 1.68344 0.99 1.62376 0.01 2.17980 2.14346 0.20 2.10932 0.30 2.03998 0.40 1.96913 0.50 1.90702 1.8 0.60 1.82932 0.70 1.76040 0.80 1.67984 0.89 1.62369 0.99 1.57357 0.01 2.13561 0.14 2.05463 0.20 2.02055 0.30 1.96229 0.40 1.89306 0.50 1.83577 1.9 0.60 1.76136 0.70 1.69541 0.80 1.62108 0.89 1.56920 0.99 1.52433 COLR TMI l Rev. X 15 0.80 0.89 0.99 0.01 0.14 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.89 0.99 0.01 0.40 0.50 0.60 0.70 0.80 0.89 0.99 Maximum Allowable Radial 1.69761 1.63401 1.56668 1 1767 1.47619 1.95940 1.89208 1.86073 1.81433 1.75302 1.69943 1.63696 1.57725 1.51627 1.46966 1.43130 1.87531 1.81763 1.78748 1.74390 1.68924 1.63873 1.58064 1.52546 1.46766 1.42427 1.38821

"" G> 0 Q. "O G> -CG a: -0 0 "O G> -co (,) :s .5 110 100 90 80 70 -60 50 -40 30 -20 10 Figure 3 (Page 1 of 2) LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400 +/-10 EFPD; 4 Pump Operation)

COLR TMI 1 Draft Rev. X Page 16 of 33 (3 00 , 1 02) (100.8, 102) (270, 102) Not Allowed Re ion Restricted Re ion Permissible Re ion (0, 11.7) 0 -J-l-................... .................

--. .......................

.........

.._. ..........................................................

""-+-...........................

-....--1--'-.-......

...................

0 25 50 75 100 125 150 175 200 225 250 275 Indicated Rod Index, % Withdrawn A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.

This figure is referred to by TS 3.5.2.5.b & 3.5.2.4.e.3 300

... CD 3: 0 fl.. ,, CD -co cc 0 0 ,, CD -co u :a .5 110 100 90 80 70 60 50 40 30 20 10 0 ' 0 25 Figure 3 (Page 2 of 2) LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 4 Pump Operation)

(86, 18) Permissible Re ion COLR TMI 1 Draft Rev. 17 33 (300, 102) 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.

This figure is referred to by TS 3.5.2.5.b

& 3.5.2.4.e.3 110 100 90 ... 80 CD 3: 0 70 a.. "C CD ..... 60 as a: -0 50 0 "C CD 40 ..... as (.) :s .5 30 20 10 0 0 (0,8.8) 25 Figure 4 (Page 1 of 2) LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400 +/-10 EFPD; 3 Pump Operation)

TMI l Draft Rev. X 18 (300,77) 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.

... OJ ;: 0 Q. "CJ .! ca a: -0 0 "CJ OJ -ca (.) :s .5 110 100 90 80 70 60 50 40 30 20 10 (0,3.9) Figure 4 (Page 2 of 2) TMI l Draft Rev. X 19 of 33 LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 3 Pump Operation)

(202.8,77)

Restricted Region Permissible Re ion 0 +-'-..................................

+-'-........

..................................

-+-'-........ 0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.

110 100 90 .. 80 cu 0 70 c.. ,, Cl> -60 ca a: -0 50 0 ,, s 40 -ca (,) :s 30 ..5 20 10 Figure 5 (Page I of 2) COLR TMI l Draft Rev. X Page 20 of 33 LCO 3.5.2 Regulating Rod Insertion Limits (0 to 400 +/-10 EFPD; 2 Pump Operation)

Not Allowed R i on (102.6,52)

Restricted Region Perm i s s ible Re ion (300 , 52) (0, 5.9) 0 0 25 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.

This figure is referred to by TS 3.5.2.5.b

& 3.5.2.4.e.3 110 100 90 ... 80 Q) == 0 D.. 70 "O Q) -ca 60 cc 0 >!!!. 0 50 "O ! 40 ca (,) =s .5 30 20 10 0 0 25 Figure 5 (Page 2 of 2) LCO 3.5.2 Regulating Rod Insertion Limits (400 +/-10 EFPD to EOC; 2 Pump Operation)

Permissible Re ion (300,52) 50 75 100 125 150 175 200 225 250 275 300 Indicated Rod Index, % Withdrawn A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained.

,80) (-37.40,60)

Figure 6 LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -4 Pump (0 EFPD to EOC) 110 (15.23, 102) 100 90 80 70 60 ... Q) 3: 0 50 c.. ,, Q) -0 0 ,, Jg <ti <.> =s .E (36.51,80)

(44.41,60)

(-37.40,0)

This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 (44.41,0)

...........

.......... 45 35 25 15 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP

.81 (-37.54,0)

Figure 7 LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -3 Pump (O EFPD to EOC) I.. Cl) == 0 D. ,, Cl) == 0 -0 0 ,, Cl) -<G (.) :a .5 This Figure is referred to by T.S. 3.5.2.7 & 3.5.2.4.e.4 90 80 70 60 50 40 30 20 10 (44.55,45)

(44.55,0) 45 35 25 15 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP

(-37.68,0)

Figure 8 LCO 3.5.2 Axial Power Imbalance Operating Limits Full Incore System -2 Pump (0 EFPD to EOC) 60 50 40 .... (1) 30 ;: 0 CL. 'tJ (1) ;: 0 0 20 0 'tJ (1) -CCI (J :e; .E 10 (34.34,30)

(34.34,0) 45 35 25 15 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power Imbalance, %FP

(-31.39,60)

Figure 9 LCO 3.5.2 Axial Power Imbalance Operating Limits Out-of-Core Detector System (O EFPD to EOC) 110 (-17.41!102)

(9.21,102) 100 90 80 70 ... CD

  • if 60 "C .! &! 50 -0 0 'i 40 -fJ iS .E 30 20 10 (30.04,80)

(38.06, 60) (38.06, 0) 35 25 15 5 0 5 10 15 20 25 30 35 40 45 Power (%FPl 77 69 60 45 0 Indicated Axial Power Imbalance, %FP Out-of-Core Detector System Imbalance Limits (0 EFPD to EOC) for 3 and 2 Pump Operation Neg. lmb. Pos. lmb. Power Neg. lmb. (%FPl (%FP) (%FPl (%FP) 3 Pump Operation 2 Pump Operation

-18.22 9.41 52 -19.02 -25.84 17.39 46 -26.58 -31.39 26.23 40 -32.03 -31.87 38.55 30 -32.35 -31.87 38.55 0 -32.35 Pos. lmb. (%FP) 7.48 13.26 19.31 29.12 29.12 Figure 10 LCO 3.5.2 Axial Power Imbalance Operating Limits (-21 (-27.29,80)

(-27.99,60)

Minimum Incore System (0 EFPD to EOC) 110 90 80 70 "" II) ;: 60 0 a. i -; 50 a: 0 :::!? 0 i 40 ..... cu (.) :a .5 30 20 10 Restricted Operation (26.53,80)

(34.04,60)

(-27.99,0)

(34.04,0)

...................................................................................................................................

  • "'"' .................................................................................................................... ........ ......... 35 25 15 5 0 5 10 15 20 25 30 35 40 Power C%FP) 77 69 60 45 0 Indicated Axial Power Imbalance, %FP Minimum lncore System Imbalance Limits (0 EFPD to EOG) for 3 and 2 Pump Operation Neg. lmb. Pos. lmb. Power Neg. lmb. (%FP) (%FP) (%FP) (%FP) 3 Pump Operation 2 Pump Operation

-15.82 7.89 52 -16.50 -22.77 15.15 46 -23.37 -27.84 23.19 40 -28.54 -28.51 34.42 30 -29.04 -28.51 34.42 0 -29.04 Pos. lmb. C%FP) 6.33 11.58 17.09 26.00 26.00 NOTE: No individual long emitter detector affecting the minimum in-core system imbalance calculation exceeds 73% sensitivity depletion; therefore, reduced limits are not applicable and are not shown.

Enclosure 1 Core Operating Limit Technical Specification Bases Descriptions SL 2.1.1 Bases Nuclear Power Peaking Factors COLR TMI l Draft Rev. X 28 of nuclear power peaking factors below define the peaking condition in the core for operation at the maximum overpower.

These peaking factors serve as the basis for the pressure/temperature core protection limits and the power-to-flow limit that prevent cladding failure due to DNB overheating.

  • Nuclear Enthalpy Rise Hot Channel Factor (Radial-Local Peaking Factor), = 1.80
  • Axial Flux Shape Peaking Factor, FNz FNz = 1.65 (cosine with tails)
  • Total Nuclear Power Peaking Factor, FNg FNg = 2.97 COLR TMI l x SL 2.1.2 Bases Maximum Allowable Local Linear Heat Rates
  • AREVA ,11rn11n " (MWd/mtU) 0 50 1000 10000 15000 20000 25000 30000 40000 50000 60000 62000 limit is the minimum LHR rod or cause the fuel rod

.. ,., ""y_,,..,,_

limit. limits are the Power Imbalance Protective COLR, respectively.

The for the most limiting fuel design for monitoring as below: Linear Heat Rate Linear Heat Rate to to Melt (LHRTM) 1 % Transient (kW /ft) Strain (kW /ft) 25.16 23.99 25.16 25.36 25.24 24.54 24.09 23.99 23.61 23.13 22.80 22.17 21.92 20.99 20.57 18.65 19.57 18.40 SL 2.3.1 Bases Power-to-Flow Trip Setpoints overpower trip setpoint based on RCS flow (power/flow or trip) for current cycle 1.08. This setpoint applies to four-, two-pump operation as described in T.S. Table 1 and 2 of the COLR. power/flow trip, in combination with the axial power imbalance trip, DNB protection for the Axial Power Imbalance Limit (Figure 1). A reactor trip initiated when the core ,,,.r'i,.TTLJ*-

.,,., *

... -.. and reactor coolant flow conditions indicate an approach to the DNBR limit. The power /flow trip also provides \AJ. ... ._, ... ,,_,i,"'"'

protection for loss of reactor coolant flow events, such as loss of one RC pump from a four RC pump operating condition and a locked rotor accident.

Power level and reactor flow rate combinations for four-, three-and pump operating conditions are as follows: 1. Trip would occur when four reactor coolant pumps are operating if power level is 108 percent and flow rate is 100 percent, or power level is 100 percent and flow rate is 92.5 percent. 2. Trip would occur when three reactor coolant pumps are operating if power level is 80.68 percent and flow rate is 74.7 percent or power level is 75 percent and flow rate is 69 .4 percent. 3. Trip would occur when one reactor coolant pump is operating in each loop (total of two pumps operating) if power level is 53.14 percent and flow rate is 49.2 percent or power level is 49 percent and flow rate is 45.4 percent. The power level trip and associated reactor power/axial power imbalance boundaries are reduced by the power-to-flow ratio as a percent (1.08 percent) for each one percent flow reduction.

COLR TMI I LCO 3.5.2 Bases -Allowable MTC Limit vs. Power Level 10 ..... 9 c .!!! CJ 8 ;:: ..... 7 0 CD ... 6 :::s-...., LL 5 E .S 4 CD I-... 3 0 ..... &'CS ... 2 CD "CJ 0 :i5 0 0 20 40 60 80 100 Percent Full Power The LOCA Limited Maximum Allowable Linear Heat Rate limits in COLR Table 3 can be maintained for partial power and three pump operation as long as the maximum allowable positive moderator temperature coefficient (MTC) as a function of power level shown above is preserved.

Note that additional MTC limits are defined in TMI-1 Technical Specification 3.1. 7.

Enclosure 2 COLR TMI 1 Rev.X 32 of 33 Operating Limits Not Required by Technical Specifications Alternate Minimum Boron Requirements for Cold Shutdown T.S. l. l.a, T.S. FSAR 1.2) Tank (BWST) by Technical 1. 1. a to be available as a source of borated water to LOCA criteria.

The T.S. 3.3.1.1.a requirements also ensure a sufficient source of borated water available to bring the ._'-A._,,"',,."" to cold shutdown under normal operating conditions.

Although not required by T.S., other sources of borated water can be used in lieu of for the purpose of cold shutdown under normal operating conditions.

The alternate source of borated water shall contain the equivalent of at least 755 ft3 of 12,500 ppm boron. There is no T.S. requirement to maintain an alternate source tank at this level, however out-of-service time for this tank should be minimized.

The design bases for this tank are described in FSAR Section 9. 2. 1. 2. The Boric Acid Mix Tank (BAMT) or one of the Reclaimed Boric Acid Tanks (RBAT) can be used as the alternate source of borated water.

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