ML17142A067

From kanterella
Jump to navigation Jump to search
Fuel Cycle 22, Core Operating Limits Report, Revision 37
ML17142A067
Person / Time
Site: Pilgrim
Issue date: 05/12/2017
From: Perkins E
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.17.037
Download: ML17142A067 (41)
v • d • e


Text

  • ===-Entergy May 12, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360

SUBJECT:

Fuel Cycle 22, Core Operating Limits Report, Revision 37 Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER 2.17.037

Dear Sir or Madam:

In accordance with Pilgrim Nuclear Power Station (PNPS) Technical Specification 5.6.5, Entergy Nuclear Operations, Inc. submits the attached Fuel Cycle 22, Core Operating Limits Report, Revision 37, which provides cycle-specific limits for operating PNPS during Cycle 22.

If you have any questions or require additional information, please contact me at (508) 830-8323.

There are no regulatory commitments contained in this letter.

Sincerely,

~~\\.~

Everett P. Perkins, Jr.

Manager, Regulatory Assurance EPP/rb

Attachment:

Pilgrim Nuclear Power Station Fuel Cycle 22, Core Operating Limits Report, Revision 37

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station cc:

Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Mr. John Lamb, Senior Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 8 B1A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Mr. John Giarrusso Jr.

Planning, Preparedness & Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 Letter No. 2.17.037 Page 2 of 2

Attachment Letter Number 2.17.037 PILGRIM NUCLEAR POWER STATION FUEL CYCLE 22, CORE OPERATING LIMITS REPORT REVISION 37

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT (CYCLE 22)

LBDCR2017-011 Documents Approvals Information Notice RTYPE: G4.02 This is a non-proprietary version of the Pilgrim Nuclear Power Station Core Operating Limits Report for Cycle 22, which has GNF proprietary information removed. Portions of the document that have been removed are indicated by white space inside open and closed bracket as shown here ((

)).

Revision 37 Cycle 22 COLR Page 1 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT TABLE OF CONTENTS RTYPE: G4.02 TITLE & COVER PAGE............................................................................................................. 1 TABLE OF CONTENTS............................................................................................................. 2 RECORD OF REVISIONS......................................................................................................... 3 LIST OF TABLES....................................................................................................................... 4 LIST OF FIGURES..................................................................................................................... 5

1.0 INTRODUCTION

............................................................................................................. 6 1.1 Stability Option 1-D Exclusion Region and Buffer Zone................................................. 6 2.0 INSTRUMENTATION TRIP SETTINGS.......................................................................... 7 2.1 APRM Flux Scram Trip Setting (Run Mode).................................................................. 7 2.2 APRM Rod Block Trip Setting (Run Mode).................................................................. 12 2.3 Rod Block Monitor Trip Setting..................................................................................... 12 3.0 CORE OPERATING LIMITS.......................................................................................... 17 3.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)........................ 17 3.2 Linear Heat Generation Rate (LHGR).......................................................................... 21 3.3 Minimum Critical Power Ratio (MCPR)........................................................................ 25 3.4 Power/Flow Relationship During Power Operation....................................................... 33 4.0 REACTOR VESSEL CORE DESIGN............................................................................ 36

5.0 REFERENCES

.............................................................................................................. 38 Revision 37 Cycle 22 COLR Page 2 of 38

Revision 11 B 11C 11D 12A 12B 12C 12D 13A 14A 15A 15B 16A 16B 25 26 27 28 29 30 31 32 33 34 35 36 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Effective Date Effective upon final approval Effective upon final approval Effective upon final approval License amendment by NRC for SLMCPR of 1.08 Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Description Applicable for use during Cycle 11 Operation Applicable for use during Cycle 11 Operation Applicable for use during Cycle 11 Operation Applicable for use during Cycle 12 Operation Renumbered Table 3.3-2 to 3.3-1, Sh. 2 of 2 and Table 3.3-1 to 3.3-1, Sh.. 1 of 2 Changed Tech Spec section numbers referenced due to Tech Amendment #177.

Pages affected: 6, 24 Incorporated stability log-term solution option I-A.

Applicable for use during Cycle 13 Operation Applicable for use during Cycle 14 Operation Applicable for use during Cycle 15 Operation Changed MAPLHGR Limits for GE14 fuel in response to an input error GE corrected.

Applicable for use during Cycle 15 Operation Applicable for use during Cycle 16 Operation Core Loading Change to replace leaking fuel bundle JLG621. Clarified P-F Map graphic on P.

36. Applicable for use during Cycle 16 Operation Limits for Single Loop Operation were incorporated. Rev number scheme changed to Merlin Convention Applicable for use during Cycle 17 Operation Corrected typographical errors on p. 30, 34,38,39 per CR-PNP-2008-256 and 285 Extended Tables 3.1-1 to 63.5 GWD/ST (70 GWD/MT), updated Fig. 3.1-1, section 3.1 &

references, addressed CR-PNP-2009-01066 Applicable for use during Cycle 18 Operation Applicable for use during Cycle 19 Operation Corrected typographical error on fig.3.4-1 MAPLHGR limits were revised to correct errors reported by 2011-02 and 2011-03, CR-PN P-2011-02556 Applicable for use during Cycle 20 Operation Applicable for use during Cycle 21 Operation Updated GESTAR Revision Number EC67983 scope of changes:

Updated Op Pressure Analytical Band Fig 3.3-5 Updated discussion in Section 3.3 Updated Reference 5.22 Applicable for use during Cycle 22 Operation Revision 37 Cycle 22 COLR Page 3 of 38

Number 2.1-1 2.1-2 2.2-1 2.2-2 3.1-1 3.1-2 3.1-3 3.3-1 Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT LIST OF TABLES Title Formulae for Allowable APRM Flux Scram Trip Settings in Figure 2.1-1, Two Loop Operation Formulae for Allowable APRM Flux Scram Trip Settings in Figure 2.1-2, Single Loop Operation Formulae for Allowable APRM Rod Block Trip Settings in Figure 2.2-1, Two Loop Operation Formulae for Allowable APRM Rod Block Trip Settings in Figure 2.2-2, Single Loop Operation MAPLHGR Limits for Two Loop Operation for all GNF2 Fuel MAPLHGR and LHGR Multipliers for Single Loop Operation Peak Pin LHGR Set Down from LOCA Analysis MCPR Operating Limits At Rated Power and Rated Flow RTYPE: G4.02 Page 8

9 13 14 18 19 19 27 Cycle 22 COLR Page 4 of 38

Number 2.1-1 2.1-2 2.2-1 2.2-2 3.1-1 3.2-1 3.2-2 3.2-3 3.3-1 3.3-2 3.3-3 3.3-4 3.3-5 3.4-1 3.4-2 4.0-1 Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT LIST OF FIGURES Title Allowable APRM Flux Scram Trip Settings - TLO (Normal Feedwater Temperature)

Allowable APRM Flux Scram Trip Settings - SLO (Normal Feedwater Temperature)

Allowable APRM Flux Rod Block Trip Settings - TLO (Normal Feed water Temperature)

Allowable APRM Flux Rod Block Trip Settings - SLO (Normal Feed water Temperature)

MAPLHGR Limit Most Limiting LHGR For GNF2 Fuel At Rated Power and Rated Core Flow Flow-Dependent LHGR Factor (LHGRFACF)

Power-Dependent LHGR Factors (LHGRFACp)

Flow-Dependent MCPR Limits (MCPRF)

Power-Dependent MCPR Limits (MCPRp I Kp), Turbine Bypass Assumed Operable Power-Dependent MCPR Limits (MCPRp I Kp), Turbine Bypass Assumed Out Of Service RTYPE: G4.02 Page 10 11 15 16 20 22 23 24 28 29 30 Feedwater Temperature vs. Core Thermal Power (Analytical 31 Bands)

Operating Dome Pressure Analytical Bands Power/Flow Operating Map, Scram and Rod Block Data Based on Allowable Values - TLO Power/Flow Operating Map, Scram and Rod Block Data Based on Allowable Values - SLO Reactor Vessel Core Loading Pattern 32 34 35 37 Cycle 22 COLR Page 5 of 38

1.0 INTRODUCTION

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 This report provides the cycle-specific limits for operation of the Pilgrim Nuclear Power Station (PNPS) during Cycle 22. In this report, Cycle 22 will be referred to as the present cycle.

The Technical Specifications refer to this report for the applicable values of the following fuel-related parameters:

Reference Technical Specification APRM Flux Scram Trip Setting (Run Mode)

APRM Rod Block Trip Setting (Run Mode)

Rod Block Monitor Trip Setting Average Planar Linear Heat Generation Rate Linear Heat Generation Rate (LHGR)

Minimum Critical Power Ratio (MCPR)

Power/Flow Relationship Reactor Vessel Core Design Table 3.1.1 Table 3.2.C-2 Table 3.2.C-2 3.11.A 3.11.B 3.11.C 3.11.D 4.2 If any of the core operating limits in this report are exceeded, actions will be taken as defined in the referenced Technical Specification.

The core operating limits in this report have been established for the present cycle using the NRC-approved methodology provided in the documents listed in Technical Specification 5.6.5. These limits are established such that the applicable limits of the plant safety analysis are met.

1.1 Stability Option 1-D Exclusion Region and Buffer Zone The reactor shall not be intentionally operated within the Exclusion Region given in Figure 3.4-1, for Two Loop Operation (TLO) and Figure 3.4-2 for Single Loop Operation (SLO). Immediate exit is required for inadvertent entry into the exclusion region.

The reactor shall not be intentionally operated within the Buffer Zone given in Figure 3.4-1 for TLO and Figure 3.4-2, for SLO when the on-line Stability Monitor is inoperable.

Allowable values for APRM Scram and Rod Block trip set points are defined in Section 2.

Revision 37 Cycle 22 COLR Page 6 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT 2.0 INSTRUMENTATION TRIP SETTINGS:

2.1 APRM Flux Scram Trip Setting (Run Mode)

Reference Technical Specifications: Table 3.1.1 RTYPE: G4.02 APRM flux scram Allowable Trip Set points (ATSP) for TLO are shown on Figure 2.1-1.

The scram set point curve clamps power at 120% of rated core thermal power.

Formulae used to develop Figure 2.1-1 are listed in Table 2.1-1.

APRM flux scram Allowable Trip Set points (ATSP) for SLO are shown on Figure 2.1-2.

The scram set point curve clamps power at 120% of rated core thermal power.

Formulae used to develop Figure 2.1-2 are listed in Table 2.1-2.

In accordance with Technical Specification Table 3.1.1, Note 15, for no combination of loop recirculation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of rated thermal power.

Drive Flow to Core Flow relationship:

APRM Trip settings use Drive flow to determine the power trip setting for both scrams and rod blocks, as the drive flow is a more reliable flow indication than core flow. The transient analysis uses the stability based trip settings based on Core Flow. Therefore, calibration of Drive flow vs. core flow is important to ensure that transient analysis assumptions for trip settings are implemented correctly.

Drive Flow (Wo) normalization with core flow shall be done such that 100% Drive Flow with Two Loops corresponds to 100% Rated Core Flow of 69 M#/hr.

Source: Reference 5.6, sec. 2.1 Revision 37 Cycle 22 COLR Page 7 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Table2.1-1 RTYPE: G4.02 Formulae for Allowable APRM Flux Scram Trip Settings in Figure 2.1-1 Two Loop Operation Allowable Trip Set Point Drive Flow Range (ATSP) c D

% Rated SLOPE INTERCEPT 0.20 71.5 0 :s; Wo :s; 22.5 0.71 60.0 22.5 < Wo :s; 55.9 0.65 70.6 55.9 < Wo :s; 76 0

120.0 76 < Wo :s; 125 Notes:

1. ATSP = C * % Wo + D, ATSP is in% Power.
2. Figure 2.1-1 shows the plot of ATSP vs. Wo.
3. Reference 5.6, Table 1.a is the basis for the values of constants listed in this Table.

Revision 37 Cycle 22 COLR Page 8 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Table 2.1-2 RTYPE: G4.02 Formulae for Allowable APRM Flux Scram Trip Settings in Figure 2.1-2 Single Loop Operation Allowable Trip Set Point Drive Flow Range (ATSP) c D

% Rated SLOPE INTERCEPT 0.20 69.5 0 s Wo s 32.5 0.71 52.9.

32.5 < Wo s 65.9 0.65 64.1 65.9 < Wo s 86 0

120.0 86 < Wo s 125 Notes:

1. ATSP = C * % Wo + D, ATSP is in% Power.
2. Figure 2.1-2 shows the plot of ATSP vs. W0.
3. Reference 5.6, Table 1.b is the basis for the values of constants listed in this Table.

Revision 37 Cycle 22 COLR Page 9 of 38

130.0 0

()'.

~ 120.0 c: -~ 110 0

~ 100.0

~ 90.0 0

fl)

E "

c...

<t 80.0 7

70.0 60.0 Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-1 Allowable APRM Flux Scram Trip Settings - TLO (Normal Feedwater Temperature) j

+ -

120.0 i

.-+-- -

T 106.9-y

~

(f

  • I I

/"

99~7

/

I v

~

I 16-.0

' 1.5 I

-~

I i

I 0

10 20 30 40 50 60 70 80 90 100 110 120 W0, Drive Flow, o/o Cycle 22 COLR Page 10 of 38

130.0

~

0.,; 120.0 c: -~ 110.0

~ 100.0 E

~ 90.0 I

0

~ 80.0

~

6 c..

70.0 I

9.5 I -

60.0 I

0 Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-2 Allowable APRM Flux Scram Trip Settings - SLO

{Normal Feedwater Temperature) i I

I

~

76.0

~

i 10 20 30 120.0 I

/

~

106.9 I

  • (

/~

99.7

~/

~

i 40 50 60 70 W0, Drive Flow, o/o t

80 I

t I

I i

l

l 90 100 110 120 Cycle 22 COLR Page 11 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT 2.2 APRM Rod Block Trip Setting (Run Mode)

Reference Technical Specifications: Table 3.2.C-2, 3.1.B.1 RTYPE: G4.02 When the mode switch is in the RUN position, the Average Power Range Monitor (APRM) rod block Allowable Trip setting (ATSPRs) as a function of drive flow for Two Loop Operation shall be as given by Figure 2.2-1. The ATSPRs is clamped at 115% of rated core thermal power. Formulae that form the basis of the Figure 2.2-1 are listed in Table 2.2-1.

When the mode switch is in the RUN position, the Average Power Range Monitor (APRM) rod block Allowable Trip setting (ATSPRs) as a function of drive flow for Single Loop Operation shall be as given by Figure 2.2-2. The ATSPRs is clamped at 115% of rated core thermal power. Formulae that form the basis of the Figures 2.2-2 are listed in Table 2.2-2.

2.3 Rod Block Monitor Trip Setting

References:

Technical Specification Table 3.2.C-2, Ref. 5.15, Ref. 5.10 Table 4.5 (b)

Allowable values for the power-dependent Rod Block Monitor (RBM) trip set points shall be:

Reactor Power, P

(%of Rated) p :::; 25.9 25.9 < p :::; 62.0 62.0 < p :::; 82.0 82.0 < p Trip Set point (Allowable Value)

(% of Reference Level)

Not applicable (All RBM Trips Bypassed) 125 125 125 The allowable value for the RBM downscale trip set point shall be:::; 94.0% of the reference level. The RBM downscale trip is bypassed for reactor power:::; 25.9% of rated {Technical Specification Table 3.2.C-1, Note 5). The RBM trip set point of 125%

is justified as the OLMCPR is always greater than or equal to that established for an unblocked Rod Withdrawal Error for all setpoint ranges.

Revision 37 Cycle 22 COLR Page 12 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Table 2.2-1 RTYPE: G4.02 Formulae for Allowable APRM Rod Block Settings in Figure 2.2-1 Two Loop Operation APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRs) c D

% Rated SLOPE INTERCEPT 0.20 66.5 0 s W0 s 22.5 0.71 55.0 22.5 < Wo :5 55.9 0.65 63.6 55.9 < Wo s 79.1 0

115.0 79.1 < W0 :5 125 Notes:

1. ATSPRs = C * % Wo + D, ATSPRs is in% Power.
2. Figure 2.2-1 shows the plot of ATSPRs vs. Wo.
3. Reference 5.6, Table 1.a is the basis for the values of constants listed in this Table.

Revision 37 Cycle 22 COLR Page 13 of 38

Notes:

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Table 2.2-2 Formulae for Allowable APRM Rod Block Settings in Figure 2.2-2 Single Loop Operation APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRs) c D

% Rated SLOPE INTERCEPT 0.20 64.5 0 s W0 s 32.5 0.71 47.9 32.5 < Wo s 65.9 0.65 57.1 65.9 < Wo s 89.1 0

115.0 89.1 < Wo s 125 RTYPE: G4.02

1. ATSPRs = C * % Wo + D, ATSPRs is in% Power.
2. Figure 2.2-2 shows the plot of ATSPRs vs. Wo.
3. Reference 5.6, Table 1.b is the basis for the values of constants listed in this Table.

Revision 37 Cycle 22 COLR Page 14 of 38

120.0

~

..;110.0 r:: *-

0 a.

.. 100.0 Q,)

(/)

.::&. g 90.0 ca "C

0 80.0 a:::

~

?!

a::: a.

~

70.0 1_ru d -

60.0 0

Revision 37

+

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-1 Allowable APRM Flux Rod Block Trip Settings - TLO (Normal Feedwater Temperature)

I I

v,,,

'71.0

--+--t--

10 20 30 r 1z.o=

+

I

/

I v~

99J--

lJ_g'fff

/ v t -

40 50 60 70 80 W0, Drive Flow, %

I I

i I

t

-~

90 100 110 120 Cycle 22 COLR Page 15 of 38

120.0

.,j 110.0 c: *-

0 a..

Q) 100.0 en

.:iii:: g 90.0

-co "C

0 80.0 a:::

~

a:::

a..

<(

70.0 60.0 Revision 37 6

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 2.2-2 Allowable APRM Flux Rod Block Trip Settings - SLO (Normal Feedwater Temperature) 1H.0

... -- -~

-+

c-

- -t

+-

~** -- ***** - -

/

I

/~ '

t-- --

t--

    • +--

-+-

-~ -

99~ "

)941

- v

/

~

l/

I

~.5 71.0 I

II"""""'"""

+

t I

RTYPE: G4.02

- ** ~ -

+-----

0 10 20 30 40 50 60 70 80 90 100 110 120 W0, Drive Flow,%

Cycle 22 COLR Page 16 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT 3.0 CORE OPERATING LIMITS 3.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Reference Technical Specification: 3.11.A RTYPE: G4.02 During operation at ~25% of rated thermal power, MAPLHGR as a function of axial location and average planar exposure shall not exceed the applicable limiting value.

MAPLHGR limits for Two Loop Operation (TLO) are given in Table 3.1-1. Flow and power dependent multipliers used to be necessary only as a result of applying pin based limit using lattice local peaking factors. Beginning with Cycle 20, the peak pin LHGR setdown is applied to the pin based LHGR limit. Therefore, there is no need for power and flow dependent multipliers on the MAPLHGR limit (Reference 5.11). Peak pin LHGR limit based on LOCA analysis is listed in Table 3.1-3.

TLO MAPLHGR limits are presented in Figure 3.1-1. MAPLHGR limits are based on ECCS-LOCA considerations. The MAPLHGR values are listed in Table 3.1-1 are obtained from the Supplemental Reload Licensing Report (Ref. 5.15}. Licensing basis PCT based on the MAPLHGR Limits in this report for GNF2 is 2150 °F (Ref. 5.15).

Since the thermal-mechanical LHGR is no longer composited with MAPLHGR limits, there is no power or flow dependent aspect to MAPLHGR limits. The pLHGR limit is applied to LHGR which makes MAPLHGR fuel design type dependent, rather than lattice dependent. Therefore the power & flow dependent multipliers only apply to LHGR limits.

When in Single Loop Operation, an SLO Multiplier of 0.89 (Table 3.1-2) applies to the TLO MAPLHGR limit.

Revision 37 Cycle 22 COLR Page 17 of 38

Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Table 3.1-1 RTYPE: G4.02 MAPLHGR Limits for Two Loop Operation for all GNF2 Fuel Average Planar Exposure GWd/MT GWd/ST 0.0 0.0 40.85 37.06 67.0 60.78 70.0 63.50 MAPLHGR Limit kW/ft 10.63 10.63 6.87 5.50 Cycle 22 COLR Page 18 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Table 3.1-2 MAPLHGR and LHGR Multipliers for Single Loop Operation RTYPE: G4.02 The single loop operation multipliers on LHGR and MAPLHGR applicable to all fuel types are shown in the following table.

Single Loop Operation Multiplier on LHGR and MAPLHGR 0.89 Table 3.1-3 Peak Pin LHGR Set Down from LOCA Analysis Pilgrim has an ECCS-LOCA set down on LHGR as shown in the Table below. This limit is applied to the LHGR limit.

Peak Pin LHGR, kW/ft 11.81 Revision 37 Cycle 22 COLR Page 19 of 38

12.5 12.0 11.5 11.0 I 10 63 l 10.5.

10.0 9.5 i:

~ 9.0

~

~

(!) 8.5

c

~

Cl.

ct 8.0

s 7.5 7.0 6.5 6.0 5.5 5.0 0

5 10 15 20 Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.1-1 MAPLHGR Limit I

O!ill

~

~

~,

'\\

RTYPE: G4.02 I..... GrlF2:

I 25 30 35 40 45 50 Average Planar Exposure (GWd/sT)

' ' ~

,~

55 60

\\

\\~

65 70 Cycle 22 COLR Page 20 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT 3.2 Linear Heat Generation Rate (LHGR)

Reference Technical Specification: 3.11.B RTYPE: G4.02 During operation at ;::253 of rated thermal power, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the rated power and rated core flow limits presented in Figure 3.2-1. Proprietary detailed values are in Reference 5.17. At other than rated power and rated flow conditions, the applicable limiting LHGR value by fuel type is the smaller of the flow-and power-dependent LHGR limits, LHGRf and LHGRp. The flow-dependent LHGR limit, LHGRf, is the product of the LHGR flow factor, LHGRFACf, shown in Figure 3.2-2 and the LHGR for rated power and flow conditions. The power-dependent LHGR limit, LHGRp, is the product of the LHGR power factor, LHGRFACp, shown in Figure 3.2-3 and the LHGR for rated power and flow conditions.

LHGR Curves in Figure 3.2-1 are representative curves for U02 fuel rods and the highest weight % Gd rods. Reference 5.17 documents the applicable LHGR limits for Gd fuel rods by weight%. Reference 5.23 documents the GESTAR II compliance of GNF2 fuel, as amended, GESTAR II, (Reference 5.1) includes Prime T-M methods.

Cycle 22 LHGR limits are based on using PRIME for U02 fuel rods and Gd rods.

Pbypass is the power level below which more restrictive thermal limits are applied, as Turbine Stop Valve closure and Turbine Control Valve Fast Closure scrams are bypassed. Pbypass can be set anywhere in the range <32.5% core thermal power (TS Table 3.1.1). However, the applicable less restrictive LHGRFACp limits in the upper curve in Figure 3.2-3 can be used whenever the Turbine Stop Valve closure and the Turbine Control Valve Fast Closure scrams are enabled.

When in Single Loop Operation, an SLO Multiplier of 0.89 (Table 3.1-3) applies to the TLO LHGR limit. The applicable off-rated LHGR limit is the Rated TLO LHGR Limit multiplied by the most limiting between the LHGRFACp, LHGRFACf and the SLO Multiplier of 0.89.

In modeling the Feedwater Level Control Failure with maximum demand transient, an automatic Reactor Feed pump trip is not assumed because the trip may not occur during the transient. The trip is also not credited in the event of a system malfunction and therefore the results of the integrated plant response assume that the feed pump trip does not occur on high level. For example, a low reactor water level indication on one of the feed water level sensing channels may be present that could be the cause of the maximum Feedwater demand. This becomes important for lower power levels where the Turbine Stop Valve closure and the Turbine Control Valve Fast Closure scrams are bypassed. The off-rated limits in this COLR revision reflect this consideration (Ref. 5.25).

Revision 37 Cycle 22 COLR Page 21 of 38

((

Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02

))

Cycle 22 COLR Page 22 of 38

1.05 1.00 0.95 0.90 0.85 0

~ 0.80 0:::

(!)

c 0.75 0.70 0.65 0.60 0.55

.L

-+-

- t-4 l

I I

I I

~

I i--

I

~7 v

.,, I

~

v I 30. 0.626 I

- n-I

-r-PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.2-2 Flow Dependent LHGR Factor (LHGRFACF)

I -+

_L I

I _j_

I H-I I

I I

I l

/

I

-+-

J 85, 1 000 I

-+

/.,,

I I

I

~

I~

v I

--I- --

-1'- -

+-

~

I

~

.... v

/

---.--/ -

~

V _

~ -

r-

... ---+- -

-+-

... *- --+

i

~-

--.... "'t-I

--,---r -r --

r~, *-r -r--

- -r RTYPE: G4.02 I

I I

-t-I I

I

_1 112. 1 ooo I

--I-I

+-

I

- --t-- -

~

I -

I T-25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 115 Core FJow (%)

Revision 37 Cycle 22 COLR Page 23 of 38

0.
u.

ex:

J:

...J 1.05 I

1.00 0.95 I

j... -i-~*

~

0.00 i0933 ;.____jo 940 I I

0.85 i

I 0.80 I

0.75 0.70 I

I I

0.65 0.60 0.55 I

10 4901 0.50 0.45 0.40 0.3-5

/

0.351 ~

i/

/ y.,

I0.408JI

~ t" i 0.30 Ho.33o i

0.25 25 30 35 Revision 37 40 l

I PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.2-3 Power Dependent LHGR Factors {LHGRFACp)

(Note: Ps

  • P *. Bypass}

I I

I I

I i

I RTYPE: G4.02 I

11000 1 I I I

0.967 1 10951 1 '

lo.9511 I

I 10.9s11 l

l I

I I

I i

T I

I j

I 45 50 55 60 t

I I

I I

l i

i I

I I

i IS.VffQV S.Q:im EHA!U,EQ {All Cor~ FIQ~}

Solid line: LHGRFACp with P :t 32.5 %CTP Dotted line: LHGRFACp '11th P < 32.5 %CTP i

rs.vrrr;.v S.!lim DISABLED ~gr~ Fig~

  • ~ ~Q~)

%CTPs Pe. 32.5 > Pe ? 25%CTP Ps =po ier level below which TSV/TOI scrams are DISABLED i

I rsvrrr.;.v ~ctimQt~aLEQ rn2%~ Qore F12wp~Q~l

%CTPs P 32.5> Pei 25%CTP Pe= power level below which TSV/TOI scrams are DISABLED I

i I

l I

i I

i 65

% CTP 70 75 80 85 90 95 I

j I

i I

i i

I I

I

' ' I

' i I

I I

I i

I 100 105 Cycle 22 COLR Page 24 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT 3.3 Minimum Critical Power Ratio (MCPR)

Reference Technical Specification: 3.11.C RTYPE: G4.02 During operation at ~25% of rated thermal power, the MCPR shall be greater than or equal to the Operating Limit MCPR (OLMCPR). The operating limit MCPR is the greater of the flow-and power-dependent MCPR operating limits, MCPRf and MCPRp.

The flow-dependent MCPR operating limit, MCPRf, is provided in Figure 3.3-1. For power level less than Pbypass. the MCPRp can be directly read from Figure 3.3-2, when I Turbine Bypass is operable or from Figure 3.3-3, when Turbine Bypass is out of service.

Above Pbypass* MCPRp is the product of the rated power and flow MCPR operating limit presented in Table 3.3-1, and the Kp factor presented in Figure 3.3-2, when Turbine Bypass is in service and from Figure 3.3-3, when Turbine Bypass is out of service. The rated power and flow MCPR operating limits presented in Table 3.3-1 are functions of 't.

For SLO, MCPRp and MCPRf are raised by 0.02 compared to TLO values shown in Figures 3.3-2 and 3.3-3.

The value of 't in Table 3.3-1 shall be equal to 1.0, unless it is calculated from the results of the surveillance testing of Technical Specification 4.3.C. TS 4.11.C defines 't.

Turbine Bypass out of service describes a Turbine Bypass Valve Out-of-Service (TBVOOS) event where the turbine bypass valves fast opening function does not operate to mitigate fast pressurization transients.. TBVOOS OLMCPR provided in Table 3.3-1 and Figure 3.3-3 are for thermal limits assessments only.

Pbypass is the power level below which 3DMonicore applies more restrictive thermal limits, as Turbine Stop Valve Closure and Turbine Control Valve Fast Closure scrams are bypassed. Pbypass can be set anywhere in the range< 32.5% core thermal power.

Pbypass is set at 32.5% by default in 3DMonicore. However, the less restrictive MCPRp limits (the lower curve) in Figures 3.3-2 & 3.3-3 can be applied whenever the Turbine Stop Valve closure and the Turbine Control Valve Fast Closure scrams are enabled.

Transient Analysis assumes that a transient initiates from operation within the Feedwater Temperature vs. Reactor Power band (Figure 3.3-4). Also, Transient Analysis considers the initial pressure when a transient initiates. Figure 3.3-5 presents four curves:

1. A constant "Analysis Upper Pressure Bound" equal to 1046 psig, and
2. A representative nominal I expected dome pressure curve which has a dome pressure of 1035 psig at 100% core thermal power, and
3. A standard lower band labeled"(-) 10 psi Analysis Pressure Bound", and
4. An expanded pressure band labeled"(-) 20 psi Analysis Pressure Lower Bound" If dome pressure is within the expanded pressure band on Figure 3.3-5 which is below the"(-) 10 psi Analysis Pressure Bound" and above the"(-) 20 psi Analysis Lower Bound" an OLMCPR penalty of +0.01 must be applied to the value in Table 3.3-1. The Revision 37 Cycle 22 COLR Page 25 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 SRLR (Reference 5.15) provides the pressure boundaries on Figure 3.3-5 based on Reference 5.22. The OLMCPR penalty of +0.01 when operating in the expanded range pressure range between (-)1 O psi and (-)20 psi is required per Reference 5.15.

In modeling the Feedwater Level Control Failure with maximum demand Transient, an automatic Reactor Feed pump trip is not assumed because the trip may not occur during the transient. The trip is also not credited in the event of a system malfunction and therefore the results of the integrated plant response assume that the feed pump trip does not occur on high level. For example, a low reactor water level indication on one of the feed water level sensing channels may be present that could be the cause of the maximum Feedwater demand. This becomes important for lower power levels where the Turbine Stop Valve closure and the Turbine Control Valve Fast Closure scrams are bypassed. The off-rated limits in this COLR revision reflect this consideration (Ref. 5.25).

Revision 37 Cycle 22 COLR Page 26 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Table 3.3-1 RTYPE: G4.02 MCPR Operating Limits At Rated Power and Rated Flow The MCPR Operating Limit for Two Loop Operation (OLMCPRrLO) is a function of cycle exposure, and -r, which is derived from scram timing measurements (TS 3/4.11.C)

Tau OLMCPR For GNF2 Fuel Two Loop Operation Equipment in Service TBVOOS From To BOC to MOC MOC to EOC MOC to EOC 0.0 1.52 1.55 1.56 0.0 0.1 1.52 1.56 1.57 0.1 0.2 1.52 1.57 1.58 0.2 0.3 1.53 1.58 1.59 0.3 0.4 1.54 1.59 1.60 0.4 0.5 1.55 1.60 1.61 0.5 0.6 1.56 1.61 1.62 0.6 0.7 1.57 1.62 1.63 0.7 0.8 1.58 1.63 1.64 0.8 0.9 1.59 1.64 1.65 0.9 1.0 1.60 1.65 1.66 BOC = Beginning Of Cycle MOC = Middle of Cycle = End of Rated Power Operation at Rated Flow (EOR) - 2.392 GWd/ST EOC =End Of Cycle Note: Off rated MCPR limits are given in Figures 3.3-1, 3.3-2 and 3.3-3 as taken from the Supplemental Reload Licensing Report (Reference 5.15).

Single Loop Operation OLMCPR sLo = 0.02 + OLMCPR rLo, where OLMCPR rLo is selected from the Table above.

Revision 37 Cycle 22 COLR Page 27 of 38

1.65 1.60 1.5.5 1.50 1.45 ct1 40 a..

0

E 1 3.5 1 30 1.25 1 20 1.15 110 30.0, 1.61 I

I r

I '

I I

..... ~

I

~

i I

I l

i i

I I

j I

I I

I I

I PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.3-1 Flow Dependent MCPR Limits (MCPRF)

I i

I I

I I

I I

I I

SLO MCPRF = TLO MCPRF + 0.02, for all values.

..... ~

I I

I "

I I " ~

"'i'.....

Iii.. 192.7, 1.22 I I

I

~

RTYPE : G4.02 I

' I I

I I

I I

1112.0, 1.22 1 I

30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 115 Core Flow(%)

Revision 37 Cycle 22 COLR Page 28 of 38

4.50

4. 25
4. 00 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.3*2 Power Dependent MCPR Limits (MCPRp I Kp)

The l

~Q2!z ~ 2Q~) 25% s %CTP s Ps < 32.5% RTYPE: G4.02

3.
3.

75 I I I P11 :: power level below which TSV/TOI scrams are DISABLED I 50 ,~ I l I I .,5..a I I I I TSVfTCV Scram DISABLED (Core Flows s50%} ~ I I i I I 25%S %CTP S Ps < 32.5%

3.

... 3. ~ 00 ' " 713.081" 13.011 I i Pa= power level below which TSV/TOI scrams are DISABLED ~ 2.

a.

~ 2

2.
2.
1.
1.
1.
1.

i "\\ I I 50 i\\. I I ~ I 25 I 00 1 I 75 I I j I I 50 @El .. ~ t I ~ [1.1~ 25 ---- - 00 I 25 30 35 40 45 50 55 GO 65 %CTP WHEN IN Single loop Operation (SLO): For P < Pbypass MCPRp is raised by 0.02 compared to TlO values. I I I T~V!J:Q! ~~m ENAB!.EQ {~! ~Qr§ FIQW~) Solidline: Kpwi1h P~ 32.5%CTP Dotted line: Kp with P < 32.5 %CTP I I I I I L~ 70 75 80 85 90 For P~ Pbypass, the rated OLMCPR is raised by 0.02 before multiplying by Kp to calculate MCPRp Revision 37 I I I I I - ~ I ~ 95 100 Cycle 22 COLR Page 29 of 38 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.3-3 Power Dependent MCPR limits (MCPRp I Kp) [Note 1: Turbine Bypass is Assumed Out of ervice J RTYPE: G4.02 [Note 2: The l(p multiplier is applied to the rated MCPR w hen %CTP ~ Pa. where Pa = P-Bypass, TSC/TCV Scram enabled) 4.50 4.25 4.00 j~ I \\ I I I \\ 3.75 3.50 I \\. 'ii!?!.1 I i I 3.25 ..;- 3.00

a.

a:: 2.75 a.. 0

  • ~ I I

~... I ~ i - 'i1263 ~ 2.50 I 2.25 2.00 1.75 i i I I l I i I I 1.50 I ~ 11.253 I 1.25 1.00 25 30 35 I I I I I I l I I I I I I I I l I I I r1.'2061 T I 40 45 WHEN IN Single Loop Operation (SLO}: I l j I I I I I I I I I i I i I I I I I I I I l I I I I l I 50 55 I I I I I I I I I I TSVITCV Sgam OISABLEO CCore Flows > 50% s: 90%) 25% s %CT? S Pa < 32.5% P9 =power level below which TSV/TCV scrams are DI AB LED T I I I I I I I TSVITQV ~g2m 121~A6LE!2 (QQr~ FIQW~ :i :2Q2f!} 25% s %CTP s Ps < 32.5% P0 =power level belowwhichTSV/TCVscramsare DISABLED I I T I I I I I ' I I I I T~VITQV ~cr2m ENAB!.EQ (All CQre Flows) Solid line: Kp with P ? 32.5 %CTP Dotted line: Kp With p < 32.5 %CTP I I I I I I I l i T f1.195l I I

  • ~
  • r I

r T 60 65 70 75 80 85 90 % ClP For P < Pbypass MCPRp is raised by 0.02 compared to TI..O values For P ~ Pbypass

  • the rated OLMCPR is raised by 0.02 before multiplying by Kp to calculate MCPRp.

Revision 37 I I 1.000 I 95 100 Cycle 22 COLR Page 30 of 38 --~ -- PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-4, Feedwater Temperature vs. Core Thermal Power(Analytical Bands) 375 I I I I 365 355 345 335 I LL' 325 0 I Cl> 315

J 1G Cl>

305

a.

E ~ 295 Cl> 1G ~ 285 "'C Cl> Cl> / ,// / / v ~ ~ ~ LL. (ij 275 c / /. / v ~,,. /' LL. 265 / / v v ~ 255 / v 245 25 30 35 Revision 37 I I I I I I I .,,/" / / ../ / / / / /"" ~,, / /, / / I 1 11 I 11 I' 11 I 11 40 45 50 I I / / / ~ / / 11 55 I I ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ _/' ~ ~ , I ,./~ ~ ~ ' I I / / / ~ ~""" ~ I ~ ,/ /i"'" / v i I I Nominal FeedWaterTemperature I +/- 10 °F {Fee<l\\vaterTemp Analytical Limits) I Operation outside of the+/- 10 °F Feedwater I I Temperature Analytical Limits is prohibited I I j I I

  • I 11 I* I 60 65 70 75 80 85 90 95 100

%CTP Cycle 22 COLR Page 31 of 38 10t50 1050 1040 1030 1020

i 1010

~ ~

0 100) 2!

Q. 990 Q.I E 8 980 0 ti 1' 970 ~ 960 950 940 930 920 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.3-5 Reactor Dome Pres.sure Operating Domain Analy5isUpper Prl5S!Ie Booro 10% pi;lg Expected Dane Pre55Ure RTYPE : G4.02 7 ~ ';I' /

* (-1 lOpsi.o'.natysis Pres.sure Bounod

/

/

/

-- (-) 20psi ~.n a lysis P ressure LO\\va Bound

/

Thet" rnal-Li1 nits 7

V"

/

.,~

-~

/

./

_/'

~v,/

a-:;;!

/

c-;..imi

~

-w illlC' 1 __...,

_./

/

Non ~pp1i-c trl.,,

~

,./'

IJe1u...,

~

/

~,..~..

L ;

/

,/

~

_,.,.. r

../

  1. '.n additicnal penattyof+O.Olmusrbe

./"

applied totheOLMCPR to ope ram in t he

~

lo<""'""

-~

..,.,..,..~

high I ighted area benveen the

~

-~

"(-)10 psi.~.n a lysis PrE55UI<! Bound" andth.e

~H2opsi.nalysisPrE55UI<! LO\\Ver Bound-

--~

_...,i ~

~

~

~

~ -

-f-f--

~-

~~

- ~

-~

1- -

0 5

10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Core Thermal Power 1% GfP)

Revision 37 Cycle 22 COLR Page 32 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT 3.4 Power/Flow Relationship During Power Operation Reference Technical Specification: 3.11. D RTYPE: G4.02 The power/flow relationship shall not exceed the limiting values shown on the Power/Flow Operating Maps in Figures 3.4-1 when in Two Loop Operation and 3.4-2 when in Single Loop Operation. APRM Flux scram and Rod Block curves without the flow clamp are applicable to Cycle 22. Figures 3.4-1 and 3.4-2 show APRM Scram and Rod Block lines using allowable values as a function of Core Flow.

The Exclusion and the Buffer regions shown in Figures 3.4-1 and 3.4-2 are based on Stability Solution 1-D (References 5.4, 5.12, 5.15 and 5.20).

Single Loop Analysis limits maximum Core Flow to 52% of Rated Core Flow and maximum Power to 65% of Rated due to SLO vessel internal vibration (Ref. 5.7, p. 1-2).

Various lines on the Power to flow map are described in Ref. 5.14.

Revision 37 Cycle 22 COLR Page 33 of 38

c w

l-et a::

0 0

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.4-1 PILGRIM POWER I FLOW MAP - Two Loop Operation Scram and Rod Block Data based on Allowable Values CORE FLOW, MLB/HR 0

5 10 15 20 25 30 35 40 45 so 55 60 65 70 75 80 125,._....,_.............................. ~~

..... --.........................,................................... -...... ~~~C~RA~M~C~L~AM~P~A~T~12~0°~

~ ---~--.,.._...... 2535 120 2434 115 1

2332 110 2231 105 2129 100 2028 95 1927 90 1825

~

~~~ ~

75 OPERATION PROHIBITED LOWER BOUND NAT CIRC LINE CORE FLOW, MLB/HR 1621 a::

1420 1318 1217 1115 1014 913 811 710 608 507

~

0 a.

..J

~

a:: w

~

w a::

0

(.)

Revision 37 Cycle 22 COLR Page 34 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT Figure 3.4-2 PILGRIM POWER I FLOW MAP - Single Loop Operation Scram and Rod Block Data based on Allowable Value Setpolnt CORE FLOW, MLB/HR RTYPE: G4.02 0

5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 125 T-...... --.-....--.--...... ~----.

............ -,..--...... ~.-.-..__, __...._...._.._.....,...... '""'""'!.....,...........

.._.......,.7.

~=R~

M~C~RAM

~C~lAM

~

P~~~1~2m~~~~~--i-r 2535 120 2434 115 2332 110 j APRM ROD BLOCK CLMIP AT11~'4 2231 105 2129 100 2028 95 1927 fa 90 1825 t-

~ 85 1724 ~

~ 80 1622,..,;

0 w

~ 75 1521

~

w 70 1420 0

~ 65 1318 ~

~ 60 1217 ~

55 OPERATION PROHIBITES 1115 Q:'.

~ 50 1014 ~

w 45 913

~

w W

40 LOWER BOUNO 811

~

Q:'.

35 NAT CIRC LINE 710 O

8 30 608 25 507 20 406 15

~~TC JMINIMUM POWER INTERLOCK 304 10 LINE 203 5

101 0

0 0

5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 CORE FLOW, MLB/HR Revision 37 Cycle 22 COLR Page 35 of 38

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT 4.0 REACTOR VESSEL CORE DESIGN Reference Technical Specification: 4.2 RTYPE: G4.02 The reactor vessel core for the present cycle consists of 580 fuel assemblies of the types listed below. The present cycle core loading pattern {derived from Ref. 5.15) for each type of fuel is shown in Figure 4.0-1.

Cycle 22 fresh GNF2-P10DG2B397-2G7.0/11G6.0-100T2-145-T6-4474 batch was initially intended to use Zr-4 channels only designated as fuel type IAT =33 (table below, Ref. 5.15).

Fuel Type Cycle Number Loaded Irradiated:

GNF2-PlODG28395-6G6 0/9G5 0- 100T2-145-T6-3422 (GNF2) 19 16 GNF2-P lODG28401-6G6.0/8G5.0/ 1G4 0- 100T2-145-T6-342 1 (GNF2) 19 16 GNF2 -PlODG28407-6G6.0/2G5.0/6G4.0-lOOT2-145-T6-3642 (GNF2) 19 34 GNF2-P lODG28401-6G6.0/2G5 0/6G4 0-100T2-145-T6-3640 (GNF2) 19 20 GNF2 -PlODG28406-6G6.0/6G5 0/2G4.0-100T2-145-T6 -364 1 (GNF2) 19 16 GNF2-PlODG28375-6G6.0/7G5.0- IOOT2-145-T6-3434 (GNF2) 19 14 GNF2-PlODG28406-6G6.0/2G5.0/6G4.0-lOOT2-145-T6-4 171 (GNF2) 20 56 GNF2-PlODG28398-5G6.0/8G5.0- lOOT2-145-T6-4 172 (GNF2) 20 24 GNF2-PlODG28389-15G5.0-lOOT2-145-T6-4 173 (GNF2) 20 40 GNF2-P lODG28375-7G6.0/6G5.0- lOOT2-145-T6-4 174 (GNF2) 20 32 GNF2-Pl0DG28387-15G6.0- 100T2-145-T6-4308 (GNF2) 21 32 GNF2-PlODG2B387-12G6.0/4G5.0- lOOT2-145-T6-4309 (GNF2) 21 40 GNF2-PlODG28398-14G5.0- lOOT2-145-T6-43 10 (GNF2) 21 48 GNF2-P lODG28387-13G6 0- 100T2-145-T6-43 11 (GNF2) 21 24 New :

GNF2-P lODG28372-14G6.0- lOOT2-145-T6-4477 (GNF2) 22 24 GNF2-P lODG2B379-14G6.0-lOOT2-145-T6-4476 (GNF2) 22 56 GNF2-PlODG2838 1-2G7 0/ 11 G6 0- 100T2-145-T6-4475 (GNF2) 22 24 GNF2-P lODG28397-2G7 0/ 11G6.0- 100T2-145-T6-4474 (GNF2) 22 64 Total:

580 As fabricated and installed, this batch was split to two fuel types IAT =1 for Zr-2 channels and IAT =33 for Zr-4 channels (Reference 5.27). This split designates different channel materials for the same nuclear type. Thermal limits are identical, but separate IA Ts allow proper application of CFM models. Each bundle type initially loaded at BOC21 is similarly split between Zr-2 and NSF channels. Figure 4.0-1 and the table below show Cycle 22 core content updated for fresh fuel batch GNF2-P1 ODG2B397-2G7.0/11 G6.0-1OOT2-145-T6-447 4 split into IAT =1 and IAT =33.

Revision 37 Cycle 22 COLR Page 36 of 38

Revision 37 PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT FIGURE 4.0-1, Reactor Vessel Core Loadin 1

2 3

4 5

6 7

8 g

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24

!O 12 12 20 12 15 8

8 15 12 20 12 13 20 IS 7

24 22 21 23 24 24 23 21 22 24 7

lS 12 7

a 13 23 27 24 31 21 21 31 2.. 27 23 23 a 7

12 n

13 l4 31 33 33 33 33 33 33 33 33 33 )) 31 24 13 13 12 n 12 21 l7 l

31 34 28 l

27 27 I

28 34 31 l

27 21 12 13 12 7

13 21 22 1

26 36 21 35 25 21 21 25 35 21 36 26 1

22 21 13 7

13 a 8

24 27 1

lO 35 30 36 29 35 26 26 35 29 36 30 35 26 1

27 24 a l2 7 2J 31 1

26 lS 26 35 26 36 25 35 35 25 36 26 35 26 3S )6 1

31 23 12 24 23 33 27 36 lO 35 23 21 25 35 21 21 35 25 21 23 35 30 36 27 33 23 20 :u 27 33 34 21 l6 26 21 22 34 32 22 22 32 34 22 21 26 36 21 34 n 27 11 23 24 33 28 35 19 36 25 34 28 34 21 21 34 28 34 25 36 2, 35 28 33 24 15 23 31 33 1

25 lS 25 35 32 34 28 35 35 28 34 32 35 25 35 is 1

33 31 8

24 23 I

27 21 16 35 21 22 21 35 23 23 35 21 22 21 3S 2& 21 27 1

23 8

24 23 I

27 21 16 35 21 22 21 35 23 23 35 21 22 21 35 26 l1 27 1

23 15 23 31 33 1

25 lS 25 35 32 34 28 35 35 28 34 32 35 25 35 25 l

33 31 12 23 24 33 28 35 19 36 25 34 28 34 21 21 34 28 34 25 36 29 35 28 33 24 20 22 27 l3 34 21 l6 26 21 22 34 32 22 22 32 34 22 21 26 36 21 34 l3 27 12 24 23 33 27 36 lO 3S 23 21 25 3S 21 21 35 2S 21 23 3S 30 36 27 33 23 13 1

23 31 1

26 lS u 35 26 36 25 35 35 lS 36 26 35 26 35 26 1

31 23 20 is 8 24 27 1

lO 35 30 36 29 l5 26 26 35 29 36 30 35 26 1

27 24 a 13 7

21 22 1

26 36 21 35 25 21 21 25 35 21 36 26 1

22 21 7

13 12 13 12 21 17 1

31 34 28 1

27 27 1

28 34 31 1

27 21 12 u 12 13 13 14 31 33 33 33 33 33 33 33 33 33 33 31 24 1

13 12 7

a 23 23 27 24 31 21 21 31,.. 27 H 23 a 24 12 15 7

24 22 21 23 24 24 23 21 22 24 7

15 ll 12 12 20 12 lS 8

8 lS 12 20 u 12 20 IAT Bundle Description ti or Bundles 1

GNF2*P10DG28397*2G7.0111G6.0-100T2-145-T6-4474 28 7

GNF2-P10DG20395-6G6.019G5.0-100T2-145-T6-3422 16 8

GNF2-P100G20401-6G6.018G5.0J1G4.0-100T2-145-T6-3421 16 12 GNF2-P10DG28-<07-6G6.012G5.0J6G4.0*100T2-145-T6-3642 34 13 GNF2*P 10DG20401-6G6.012G5.016G4.0-1 OOT2-145-T6-3640 20 15 GNF2-P1 ODG28406-6G6.016G5.012G4.0-1OOT2*145-T6-3641 16 20 GNF2-P1OOG2B375-6G6.0nG5.0-100T2*145-T6-3434 14 21 GNF2-P1 ODG20406-6G6.012GS.0.16G4.0-1 OOT2-145-Tt>-4171 56 22 GNF2-P10DG2B398-5G6.0/8G5.0-100T2-145-T6-4172 24 23 GNF2-P100G28389-15G5.0* 1 OOT2-145-Tt>-4173 40 24 GNF2-P1 ODG28375-7G6.016G5.0*1OOT2-145-T6-4174 32 25 GNF2-P10DG2B387 -15G6.0-100T2-145-T6-4308 24 26 GNF2-P1 ODG2B387*12G6.0/4G5.0*1OOT2*145-T6-4309 30 27 GNF2-P1ODG2B398-14G5.0-100T2*145-T6-4310 28 28 GNF2-P1ODG2B387*13G6.0* 100T2-145-T6-4311 16 29 GNF2*P1OOG29387*15G6.0-100T2*145-T6*4308 8

30 GNF2.P10DG2B387*12G6.0/4G5.0-100T2*145-T6-4309 10 31 GNF2-P10DG2B398-14G5.0*100T2-145-T6-4310 20 32 GNF2-P10DG2B387-13G6.0-1 OOT2-145-T6-4311 8

33 GNF2-P10DG2B397-2G7.0111G6.0-100T2-145-T6*4474 36 34 GNF2-P1 ODG29381*2G7.0111 G6.0-1 OOT2-145-T6-4475 24 35 GNF2.P10DG2B379-14G6.0-100T2-145-T6-4476 56 36 GNF2-P10DG2B372-14G6.0-100T2*145-T6-4477 24 RTYPE : G4.02 lS 20 7

12 24 12 22 20 23 12 23 15 24 8

24 8

23 15 23 12 22 20 13 12 7

12 15 20 Cycle Loaded 22 19 19 19 19 19 19 20 20 20 20 21 21 21 21 21 21 21 21 22 22 22 22 Cycle 22 COLR Page 37 of 38

5.0 REFERENCES

PILGRIM NUCLEAR POWER STATION CORE OPERATING LIMITS REPORT RTYPE: G4.02 5.1 NEDE-24011-P-A-23 and NEDE-24011-P-A-23-US, General Electric Standard Application for Reactor Fuel, Sept. 2016 (eB library record: KGO-ENO-GEN-16-122).

5.2.

EC63151, Cycle 22 Reload Core Design.

5.3.

NEDC-31852-P, Rev. 4, Pilgrim Nuclear Power Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for PNPS, January 2008.

5.4.

NEDC-33155P, Rev.a, Application of Stability Long-Term Solution Option 1-D To Pilgrim Nuclear Power Station, October 2004.

5.5.

Not Used 5.6.

GE-NE-GENE-0000-0033-6871-01, Rev. 0, Pilgrim Option 1-D APRM Flow Biased Setpoints, October 2004.

5.7.

GE-NE-0000-0027-5301, Rev 2, Pilgrim Nuclear Power Station Single Loop Operation, April 2006.

5.8.

S&SA-186, % ft.Wo for use with Stability Option 1-D for Pilgrim (applicable to SLO).

5.9.

SUDDS/RF 94-42, NEDC-32306P, Maximum Extended Load Line Limit Analyses, March 1994.

5.10. SUDDS/RF 88-160, NEDC-31312-P, ARTS Improvement Program Analysis for Pilgrim Nuclear Power Station, September 1987.

5.11. GEH 002N4732-RO, LHGR/MAPLHGR vs. Exposure Curve Calculation for Pilgrim GNF2 Fuel, Feb. 2015, (eB library record: KGO-ENO-HK1-15-055).

5.12. ECH-NE-09-00019 R2, GNF2 Fuel Design Cycle-Independent Analyses for Entergy PNPS, GEH-0000-0085-9069-R2, March 2011, (EC17226).

5.13. ER 03110960, Stability 1-D implementation.

5.14. PNPS-RPT-03-00001, Rev 7, Power Flow Map Report, (EC47669).

5.15. ECH-NE-17-00007, RO, Supplemental Reload Licensing Report for PNPS Reload 21Cycle22, 002N6994 Rev.a, Feb. 2017, (EC69737).

5.16. ECH-NE-16-00023, RO, PNPS Cycle 22 OPL-3 Form, (EC65671 ).

5.17. ECH-NE-17-00008, RO, PNPS Cycle 22 Fuel Bundle Information Report (FBIR),

OOON6995-FBIR Rev.O, Jan. 2017, (EC69737).

5.18. SUDDS/RF 02-86, GNF SER issued by NRC approving elimination of Upper Bound PCT limit requirement.

5.19. EC7933 documents OPL-4 & 5 LOCA Inputs.

5.20. NED0-32465A, Licensing Topical Report, Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application, August 1996.

5.21. ECH-NE-09-00018, RO, PNPS GNF2 ECCS-LOCA Evaluation, 0000-0095-4071-RO, Feb.

2009, (EC15745).

5.22. ECH-NE-16-00036, RO, Pilgrim Expanded Dome Pressure Band for All Off-Rated Powers.

5.23. NEDE-33270P, Rev. 7, GNF2 Advantage Generic Compliance with GESTAR II, October 2016, (eB library record: KGO-ENO-EP1-16-141) 5.24. NEDE-33213, ODYSY Application for Stability Licensing Calculations Including Option 1-D and II Long Term Solutions, April 2009 5.25. CR-PNP-2014-5904, Inappropriate Use of Reactor Feed Pump Trip in transient analysis 5.26. EC47669-7.010, 002N3765-00, GNF2-B36-P3-HK1-18PDN Limits Tables 5.27. KGO-ENO-HK1 136, Pilgrim Cycle 22 Reload Channel Material, Dec. 2016 (eB lib).

Cycle 22 COLR Revision 37 Page 38 of 38

Retrieved from "https://kanterella.com/w/index.php?title=ML17142A067&oldid=5138402"