ML17244A256

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Fuel Cycle 20, Core Operating Limits Report, Revision 33
ML17244A256
Person / Time
Site: Pilgrim
Issue date: 08/28/2017
From: Perkins E
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.17.08
Download: ML17244A256 (51)
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Text

{{#Wiki_filter:* ~Entergy August 28, 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:

Pilgrim Fuel Cycle 20, Core Operating Limits Report, Revision 33 Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER 2.17.058

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 20, Core Operating Limits Report, Revision 33, which provides cycle-specific limits for operating PNPS during Cycle 20. PNPS requests that Attachment 2 to this letter, which contains Trade Secret Information, be withheld from public disclosure in accordance with 10 CFR 2.390(b )( 1 ). 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/mp This letter contains Proprietary Information - Attachment 2 is withheld from public disclosure per 10 CFR 2.390

Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station Attachments: Letter No. 2.17.058 Page 2 of 2

1.

GNF letter,KGO-ENO-HK1-17-081, Kimberly O'Connor (GNF) to Nela Szwarc (Entergy), entitled "Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report (COLR) Revision 33 and Cycle 21 COLR Revision 34, 35, and 36 - Proprietary and Non-Proprietary Versions," July 28, 2017.

2., KGO-ENO-HK1-17-081, Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report, Revision 33, GNF Proprietary Information - Class II (Internal)
3., KGO-ENO-HK1 081, Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report, Revision 33, Non-Proprietary Information - Class I (Public)
4., KGO-ENO-HK1-17-081, Affidavit for Enclosure 1, Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report, Revision 33, GNF Proprietary Information - Class II (Internal) 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 This letter contains Proprietary Information - Attachment 2 is withheld from public disclosure per 10 CFR 2.390

I L Letter Number 2.17.058 GNF letter,KGO-ENO-HK1-17-081, Kimberly O'Connor (GNF) to Nela Szwarc (Entergy), entitled "Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report (COLR) Revision 33 and Cycle 21 COLR Revision 34, 35, and 36-Proprietary and Non-Proprietary Versions," July 28, 2017

Proprietary Notice This letter transmits proprietary information in accordance with 10 CFR 2.390. Upon the removal of Enclosures 1, 4, 7, and 10, the balance of the letter may be considered non-proprietary. Kimberly O'Connor GNF Customer Project Manager KGO-ENO-HKl-17-081 July 28, 2017 Ms. Nela Szwarc Entergy Nuclear Northeast 440 Hamilton Road White Plains, NV 10601 GNi= Global Nuclear Fuel A.lnint V11ntnr.. nf r.F TMhiha A Hit.rhl Global Nuclear Fuel - Americas, LLC Castle Hayne Road, Wilmington, NC 28401 cc: Lynn Leatherwood Gary James

SUBJECT:

Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report (COLR) Revision 33 and Cycle 21 COLR Revision 34, 35, and 36 - Proprietary and Non-Proprietary Versions

REFERENCES:

1.

Email from Szwarc, Kornelia (Entergy) to O'Connor. Kimberly (GNF).

Subject:

FW: COLR Proprietary/Non-Proprietary Versions - Mail 1 of 4, July 25, 2017, 12:52 pm. Ms. Szwarc,

2.

Entergy Nuclear Operations, Inc. Fixed Services Agreement No. 50014434 for the Supply of Fuel and Fuel Related Work to PNP with Global Nuclear Fuel. as amended ("Fuel Contract"). By Reference 1, Global Nuclear Fuel - Americas, LLC (GNF) was requested to review and mark the proprietary content in the Pilgrim Nuclear Power Station (PNPS) Cycle 20 Core Operating Limits Report (COLR). Revision 33 and the PNPS Cycle 21 COLR Revisions 34, 35, and 36, prepare a corresponding non-proprietary version of each COLR, and provide an affidavit supporting the basis for the proprietary determination for each COLR. Enclosed are the COLRs marked to indicate the GNF proprietary information, corresponding non-proprietary versions of the COLRs, and affidavits supporting the basis for the proprietary determination. GNF's review is limited to a proprietary determination. GNF did not review the content of the COLRs for technical accuracy. Enclosures 1, 4, 7, and 10 of this transmittal contain GNF proprietary information that should be handled in accordance with the proprietary information provisions contained in the Fuel Contract listed above (Reference 2). GNF customarily maintains this information in confidence and withholds it from public disclosure. The affidavits provided in Enclosures 3, 6, 9, and 12 identify that the designated information in Enclosures 1, 4, 7, and 10 have been handled and classified as proprietary to GNF. The designated information is suitable for submittal to the NRC when accompanied by the attached affidavits. GNF hereby requests that the designated information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. Non-proprietary versions of the GNF information is provided in Enclosures 2, 5, 8, and 11, respectively.

KGO-ENO-H Kl-17-081 Page 2 of 3 GNF requests that any transmittal of this proprietary information to the NRC be accompanied by the enclosed affidavit and proprietary notice. In order to maintain the applicability of the affidavit and to meet the requirements of 10 CFR 2.390, the transmittal to the NRC should:

1) faithfully reproduce the proprietary information,
2) preserve the proprietary annotations, and
3) include, at the top of the transmittal letter or in the subject line, the words similar to "Proprietary Information." If a cover sheet for enclosures is used. then the cover sheet for the enclosure containing the proprietary information should also state "Proprietary Information."

Based on past discussions with the NRC, GNF has been encouraged to request its customers to provide a paragraph similar to the following paragraph in the customer letter transmitting proprietary information to the NRC in order to clearly indicate the proprietary nature of the information and to document the source of the proprietary information as indicated in the GN F affidavit. "The enclosed documentation contains proprietary information as defined by 10 CFR 2.390. GNF, as the owner of the proprietary information, has executed the enclosed affidavit. which identifies that the enclosed proprietary information has been handled and classified as proprietary, is customarily held in confidence. and has been withheld from public disclosure. The proprietary information was provided to Entergy in a GNF transmittal that is referenced by the affidavit. The proprietary information has been faithfully reproduced in the enclosed documentation such that the affidavit remains applicable. GNF hereby requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. A non-proprietary version of the documentation is also provided." A signed copy of this letter is included in PLM Specification 004N3963 RO. All information should be handled in accordance with the proprietary information provisions contained in the Fuel Contract listed above in Reference 2. Please let me know if you have questions or comments regarding this transmittal. Sincerely, Kimberly O'Connor GNF-A Customer Project Manager

Enclosures:

1.

Pilgrim Nuclear Power Station Cycle 20- Core Operating Limits Report, Revision 33 - Proprietary

2.

Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report. Revision 33 - Non-Proprietary

KGO-ENO-HKl-17-081 Page 3 of 3

3.

Affidavit for Enclosure 1

4.

Pilgrim Nuclear Power Station Cycle 21 Core Operating Limits Report, Revision 34 - Proprietary

5.

Pilgrim Nuclear Power Station Cycle 21 Core Operating Limits Report, Revision 34 - Non-Proprietary

6.

Affidavit for Enclosure 4

7.

Pilgrim Nuclear Power Station Cycle 21 Core Operating Limits Report, Revision 35 - Proprietary

8.

Pilgrim Nuclear Power Station Cycle 21 Core Operating Limits Report, Revision 35 - Non-Proprietary

9.

Affidavit for Enclosure 7

10.

Pilgrim Nuclear Power Station Cycle 21 Core Operating Limits Report, Revision 36 - Proprietary

11.

Pilgrim Nuclear Power Station Cycle 21 Core Operating Limits Report, Revision 36 - Non-Proprietary

12.

Affidavit for Enclosure 10 Letter Number 2.17.058, KGO-ENO-HK1-17-081, Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report, Revision 33, Non-Proprietary Information - Class I (Public)

ENCLOSURE 2 KGO-ENO-H K 1-17-081 Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report, Revision 33 Non-Proprietary Information - Class I (Public) INFORMATION NOTICE This is a non-proprietary version of Enclosure 1 of KGO-ENO-HK1-17-081, which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside an open and closed bracket as shown here (( )).

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERA TING LIMITS REPORT (CYCLE 20) LBDCR2013-07 Documents Approvals Proprietary Information Notice RTYPE: G4.02 This is a non-proprietary version of the Pilgrim Nuclear Power Station Core Operating Limits Report for Cycle 20, 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 33 Cycle 20 COLR Page 1 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT TABLE OF CONTENTS RTYPE: G4.02 TITLE & COVER PAGE.......................................................................................................................... 1 TABLE OF CONTENTS.......................................................................................................................... 2 RECORD OF REV IS 10 NS...................................................................................................................... 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)................................................................................... 22 3.3 Minimum Critical Power Ratio (MCPR)................................................................................. 26 3.4 Power/Flow Relationship During Power Operation............................................................. 33 4.0 REACTOR VESSEL CORE DESIGN..................................................................................... 36

5.0 REFERENCES

........................................................................................................................... 38 Revision 33 Cycle 20 C OLR Page 2 of 38

Revision BA 9A 10A 11A 118 11C 11 D 12A 128 12C 120 13A 14A 15A 158 16A 168 25 26 27 28 29 30 31 32 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Effective Date Effective date based on issuance of license amendment by NRC License amendment by NRC for ARTS and SAFER/GESTR Effective upon final approval Effective upon final approval 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 Description Applicable for use during Cycle 8 Operation Applicable for use during Cycle 9 operation Applicable for use during Cycle 10 Operation 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 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. 1of2 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 tv'iap graphic on P.

36. Applicable for use during Cycle 16 Operation Limits for Single Loop Operation were incorporated. Rev number scheme changed to l'v1erlin 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 by2011-02 and 2011-03, CR-PNP-2011-02556 Applicable for use during Cycle 20 Operation Revision 33 Cycle 20 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 3.1.4 3.3-1 Revision 33 PILGRIM NUCLEAR POWER STATION PNPS 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 Rated Power and Rated Flow for GE14 Fuel MAPLHGR Limits for Rated Power and Rated Flow for 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 20 20 27 Cycle 20 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 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF FIGURES Title Pa g_g Allowable APRM Flux Scram Trip Settings - TLO 10 (Normal Feedwater Temperature) Allowable APRM Flux Scram Trip Settings - SLO 11 (Normal Feedwater Temperature) Allowable APRM Rod Block Trip Settings - TLO 15 (Normal Feed water Temperature) Allowable APRM Rod Block Trip Settings - SLO 16 (Normal Feed water Temperature) MAPLHGR Limit 21 Most Limiting LHGR for GE 14 Fuel at Rated Power and Rated 23 Core Flow Flow-Dependent LHGR Factor (LHGRFACF) 24 Power-Dependent LHGR Factors 25 Flow-Dependent MCPR Limits (MCPRF) 28 Power-Dependent MCPR Limits (MCPRp), Turbine Bypass 29 Assumed Operable and Normal Feedwater Temperature Power-Dependent MCPR Limits (MCPRp), Turbine Bypass 30 Assumed Out Of Service and Normal Feedwater Temperature Feedwater Temperature Analytical Bands 31 Operating Dome Pressure Analytical Band 32 Power/Flow Operating Map, Scram and Rod Block Data 34 Based on Allowable Values - TLO Power/Flow Operating Map, Scram and Rod Block Data 35 Based on Allowable Values - SLO Reactor Vessel Core Loading Pattern 37 Cycle 20 COLR Page 5 of 38

1.0 INTRODUCTION

PILGRIM NUCLEAR POWER STATION PNPS 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 20. In this report, Cycle 20 will be referred to as the present cycle. Although this report is not a part of the PNPS Technical Specifications, 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 is 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 NRG-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 33 Cycle 20 COLR Page 6 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT 2.0 INSTRUMENTATION TRIP SETTINGS: 2.1 APRM Flux Scram Trip Setting (Run Mode) Ref. 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. Flow clamp feature is not used in Cycle 20. 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 (W0 ) 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 33 Cycle 20 COLR Page 7 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Notes: Table 2.1-1 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 $ Wo $ 22.5 0.71 60.0 22.5 < Wo $ 55.9 0.65 70.6 55.9 < Wo $ 76 0 120.0 76 < Wo $ 125

1. A TSP = 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 33 Cycle 20 COLR Page 8 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Notes: Table 2.1-2 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

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

Revision 33 Cycle 20 COLR Page 9 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-1 Allowable APRM Flux Scram Trip Settings - TLO (Normal Feedwater Temperature) 130.0 ~-~--~-~-~~~----~~~-~~ ~ l-l - l- -~ 't20.cii--- o - 120.0 i i I ~ 110.0 ----~t~ r--- I I rui.si- -~T-1--* ---- ~-,----_ l, . I _j

  • 1.

[ ~ 100.0. -- - . ~-t*-:- ---Jr* --+- _J_ I -f--~ ---t- ---- ~ 90.0

~

-~I*-. -- ~ 80.0 - - -- -:r-- I ~ 7µ I I ~ 7 0. 0 ,.. ~ 1----- T!

      • - l -- :. -I.

I I I f I

  • --+

!---;--+--+---+----. ---- --- -----+*----* *--*----

  • I 60.0 0

10 20 30 40 50 60 70 80 90 100 110 120 W0, Drive Flow, % Revision 33 Cycle 20 COLR Page 10 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-2 Allowable APRM Flux Scram Trip Settings - SLO (Normal Feedwater Temperature) 130.0 i-1 I i } ( r-11-*- I ~ ~ 120.0 -t---;----;-~ t----;---j----j---::;;;;ii ____ c r Q. 70.0 - i l I i I I <( so.a

r-- -+--~ -:-=i=t- _1--- t-*---r*--:--*r-- --- --

~----r=~r ----. ---r ::_:__:__

=~ -=----

Revision 33 0 10 20 30 40 50 60 70 80 90 100 110 120 W0, Drive Flow, % Cycle 20 COLR Page 11of38

PILGRIM NUCLEAR POWER STATION PNPS 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 thennal power. Formulae that form the basis of the Figure 2.2-1 are listed in Table 2.2-1. The flow clamp feature is not used in Cycle 20. 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 A TSP Rs is clamped at 115% of rated core thennal power. Formulae that form the basis of the Figures 2.2-2 are listed in Table 2.2-2. The flow clamp feature is not used in Cycle 20. 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 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) 122 118 113 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 most limiting Analytical Value of Rod Block set point of 117% is justified as the Rod Withdrawal Error is expected to reduce MCPR by 0.28 if this set point is used. Since the minimum OLMCPR value is 1.46, a reduction of 0.28 in MCPR, starting with operation at OLMCPR, is expected to lower MCPR to 1.18. This is substantially above the Safety Limit MCPR of 1.08. Allowable value of the HTSP is set at 113 % to provide additional conservatism to account for uncertainties. Table 4-5(b) of Reference 5.10 with a more restrictive OLMCPR of 1.35 was used to detennine the RBM set points with margin. Revision 33 Cycle 20 COLR Page 12 of 38

Notes: PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 2.2-1 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 (A TSP RB) c D % Rated SLOPE INTERCEPT 0.20 66.5 0 s Wo s 22.5 0.71 55.0 22.5 < Wo s 55.9 0.65 63.6 55.9 < Wo s 79.1 0 115.0 79.1 < Wo s 125

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

Revision 33 RTYPE: G4.02 Cycle 20 COLR Page 13 of 38

Notes: PILGRIM NUCLEAR POWER STATION PNPS 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 (A TSPRB) c D % Rated SLOPE INTERCEPT 0.20 64.5 0 ~ Wo ~ 32.5 0.71 47.9 32.5 < Wo ~ 65.9 0.65 57.1 65.9 < Wo ~ 89.1 0 115.0 89.1 < Wo ~ 125

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

Revision 33 RTYPE: G4.02 Cycle 20 COLR Page 14 of 38

..¥: (.) 90.0 0 -al "'C 80.0 0 ~

E

~ Q. <( 60.0 0 Revision 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-1 Allowable APRM Flux Rod Block Trip Settings - TLO (Normal Feedwater Temperature) 10 20 30 40 50 60 70 W0, Drive Flow, % 80 90 100 110 120 Cycle 20 COLR Page 15 of 38

Revision 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2*2 Allowable APRM Flux Rod Block Trip Settings

  • SLO (Normal Feedwater Temperature) 120.0 ~~

. --r~--,-- ! R t ,-+! - i-rl.* . j~ ~--,--.-,..-- l ~ I j I i <.:i..'km - ~~ *: ~ --t-- -:"- 1---r-

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--:--.' - -- i ---;------1 T---..-.-.i1-..-"8!!'!~-. 0 i I i I f 10.0 ---r-- -~-- ! r ~ *-++. +I"-+-.-+- _:_~-~~ --~--:_-_:-_~_.. -~

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a.

I I I I i ~ 100.0 1 . I ! i 1 ~ --r ~-T;--rt: g 90. 0 +---r-1 --+-~-+---+- 1 -,-' -t---,-i ---t----+--.lf---t-I aJ . *-**t**.. -* --*--"-- -- -**-+--- --,-- I -----i--** "C I l I 0 80.0 -+---*..---f---+

  • --t----.---+------t---;--.,.....--+--+-*

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a.

<( 0 10 20 30 40 50 60 70 80 90 100 110 120 W0, Drive Flow,% Cycle 20 COLR Page 16 of 38

PILGRIM NUCLEAR POWER ST A TION PNPS CORE OPERATING LIMITS REPORT 3.0 CORE OPERATING LIMITS RTYPE: G4.02 3.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR} Reference Technical Specification: 3.11.A During power operation, MAPLHGR for each fuel type as a function of axial location and average planar exposure shall not exceed the appli cable limiting value. MAPLHGR limits for rated power and flow conditions are given in Tables 3.1-1and3.1-2. Flow and power dependent multipliers used to be necessary only as a result 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 5.10). Peak pin LHGR limits based on L OCA analysis are listed in Table 3.1-4. MAPLHGR for rated power and flow conditions for both fuel types, GE14 and GNF2 are presented in Figure 3.1-1. MAPLHGR limits are based on ECCS-LOCA considerations. The MAPLHGR values for rated power and flow conditions are listed in Tables 3.1-1 for GE14 and 3.1 -2 for GNF2, which are obtained from the Supplemental Reload Licensing Report, Rev1 (Ref. 5.15). SRLR, Rev.1 corrected MAPLHGR tables for LOCA analytical error reports 2012-01 and 2011-02 to restore the Peak Clad Temperature to 2150 °F for both GE14 and GNF2 fuels. Beginning with Cycle 20, peak pin LHGR (pLHGR) set down in the LOCA analysis is applied to the LHGR limit as it is a pin based limit. Therefore there is no need to composite the pLHGR with assumed Lattice Local Peaking factors to arrive at lattice based limits. Applying pLHGR to LHGR limit simplifies the MAPLHGR limits and makes these fuel type dependent, rather than lattice dependent. Licensing basis PCT based on the MAPLHGR Limits in this report for both fuel types, GE14 and GNF2 is 2150 °F (Ref. 5.15). All PCT determination errors reported under 10CFR50.46 up to 12/31 /2012 have been accounted for. Pbypass is the power level below which more restrictive thermal limits are applied, as the Turbine Stop Valve closure and Turbine Control Valve fast closure scrams are assumed to be bypassed. It can be set anywhere in the range from 32.5% power to 45% power. Pbypass is currently set at 32.5% power. If this setting is changed in the future, then the appropriate thermal limits can be determined using Tables 3.1-1 and 3.1-2 with Figure 3.1-3. When in Single Loop Operation, an SLO Multiplier of 0.8 for GE14 fuel and 0.89 (Table 3.1-3) for GNF2 fuel applies to the Rated MAPLHGR limit. At off rated conditions, MAPLHGR limit is the lower of the SLO Multiplier times the rated MAPLHGR limit, the MAPLHGRP or MAPLHGRF. Revision 33 Cycle 20 COLR Page 17 of 38

Revision 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow forGE14 Fuel Bundle Type(s): GE14-P10DNAB404-5G6.0/10G5.0-100T-145-T6-2960 (GE14C) GE14-P10DNAB398-5G6.0/10G5.0-100T-145-T6-2958 (GE14C) GE14-P100NAB400-13GZ-100T-145-T6-2959 (GE14C) GE14-P10DNAB399-15GZ-100T-145-T6-2957 (GE14C) GE14-P10DNAB400-12G6.0/3G5.0-100T-145-T6-2961 (GE14C) Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 11.21 16.00 14.51 11.21 23.00 20.87 11.12 35.26 31.99 11.21 63.50 57.61 8.00 70.00 63.50 5.00 -- RTYPE: G4.02 Cycle 20 COLR Page 18 of 38

Revision 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1*2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel Bundle Type(s): GNF2-P1 ODG2B388-6G6.0/7G5.0*1 OOT2-145-T6-3143 (GNF2) GNF2-P1 ODG2B395-6G6.0/9G5.0-1 OOT2-145-T6-3422 (GNF2) GNF2-P1 ODG2B401-6G6.0/8G5.0/1 G4.0-1 OOT2-145-T6-3421 (GNF2) GNF2-P10DG2B389-6G6.0/8G5.0-100T2-145-T6-3141 (GNF2) GNF2-P1 ODG2B407-6G6.0/2G5.0/6G4.0-1 OOT2-145-T6-3642 (GNF2) GNF2-P 1 ODG28406-6G6.0/6G5.0/2G4.0-1 OOT2*145-T6-3641 (GN F2) GN F2-P 1 ODG2B401-6G6.0/2G5.0/6G4.0-1 OOT2-145-T6-3640 (GN F2) GNF2-P1 ODG2B389-6G6.0/2G5.0/6G4.0-1 OOT2-145-T6-3142 (GNF2) GNF2-P10DG2B375-6G6.0/7G5.0-100T2-145-T6-3434 (GNF2) GNF2-P10DG28406-6G6.0/2G5.0/6G4.0-100T2-145-T6-4171 (GNF2) GNF2-P1 ODG2B398-5G6.0/8G5.0-1 OOT2-145-T6-4172 (GNF2) GNF2-P10DG28389-15G5.0-100T2-145-T6-4173 (GNF2) GNF2-P1 ODG2B375-7G6.0/6G5.0-1OOT2-145-T6-4174 (GNF2) Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 10.63 40.85 37.06 10.63 67.00 60.78 6.87 70.00 63.50 5.50 Cycle 20 COLR Page 19 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.1-3 MAPUIGR and LHGR Multipliers for Single Loop Operation RTYPE: G4.02 The single loop operation muhipliers on LHGR and MAPLHGR and the ECCS-LOCA analytical initial MCPR values applicable to each fuel type in the new cycle core are shown in the following table. Fuel Type Single Loop Operation Multiplier on LHGR and MAPLHGR GE14C 0.80 GNF2 0.89 GNF2 (Re load 17, Cycle 18) 0.89 Table 3.1-4 Peak Pin LHGR Set Domi from WCA Analysis Pilgrim has an ECCS-LOCA set down on Peak Pin LHGRas shown in the Table below. This limit is therefore applied to LHGR which is a pin based limit. Fuel Type GE14C GNF2 Revision 33 Peak Pin LHGR, kW/ft 11.72 11.81 Cycle 20 COLR Page 20 of 38

~ PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.1-1 MAPLHGR Limit RTYPE: G4.02 12.0 ~1-,..., 1 ..,...,..~~..,...,..,...,..,.-11'"""T 1 -....,. 1 1..,...,...,-i l li"""!'" l ~l..,...,..T""'T-r"""T'".,..'i"""11'"""T 1 -,....,. 1 """i"""!""'~l'"""T""'li"~,....,........... ~l'"""T...,........,....,""""l"...,........,....,""""1"...,....-'1"""'1...,....,....,, 11. 21,__,__ _._ _,__'- __._ _ f-11.2 1 1 _,__I-_ 11. 12 +-l-+-+-+-4f-+-t 11. 21 ~1--1--l-.J__,r_J+-1--W-l-l-.~W-l--l--+rL_J__.._~7;:::~~~-,__,_ _ _.__,, - ~ _ _.__ -* 1-----

  • -1-.

, j, I t:t:l:t:t:l:tt1:to:tt+/-+/-t+/-~~~~:t:1~t:ttt'~ I, 1 1 1 1.... -GNF2-c20 1 10.63 ..., 10.63 1-1--+-+-.+-1--&.-1-+--+-1-*._ _ _.._ GE14-C20 IH-+-+--11 I [.~ - -- ~ I.::::~*--* .... ~-!o-~... -..... .: ;: r:*~.= ~ -~~.~~ ~ r-,L 1. 10.0 - t-I-- --*l-l-+--1-+-l--+-1... -!--*+-+-*. -- -- 1--- **- -- - - f-I- - i--1--..._ ~ -*- --

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_J Cl... c( 4.0 Revision 33 t-- f-- 1-- - r- -- I-f- ---+- - +--1-- t--

  • 11-11-+-f-+--- +**-

--' -+- - --* *. t-- *- 1-- .i.-. - -. 1........

    • i--

... _.__ \\'5'- _._,_.._~. ~ Note : MAPLHGR limits used by 30 Monicore are fuel product line specific. Use tables 3.1-1 through 3.1-4 in COLR for accurate calculations if 1-- -L-...1--- - l- _1---- 1-- 1-1-~ 1- "--~~~ --~ necessary. 1 t- "-

  • _.L.....

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  • l--

L-60 65 Cycle 20 COLR Page 21 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT 3.2 Linear Heat Generation Rate (LHGR) Reference Technical Specification: 3.11.B RTYPE: G4.02 When reactor power is greater than 25%, 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 Reference 5.17. Figure 3.2-1 represents LHGR curves for GE14 fuel. Proprietary detailed values for both GE14 and GNF2 fuels are in Reference 5.17. At other than rated power and rated flow conditions, the applicable limiting LHGR value for each 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 in Reference 5.17. 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 in Reference 5.17. LHGR Curves in Figure 3.2-1 are representative curves for U02 fuel rods and Gd containing rods for GE14 Fuel. A Figure comparable to Figure 3.2-1 for GNF2 is not included because GNF has requested Entergy to protect this proprietary information. Gd containing fuel rods have different LHGR limits that are also exposure dependent. Reference 5.17 documents the detailed proprietary curves and values for both GE14 and GNF2 fuels. Reference 5.23 documents the GESTAR II compliance of GNF2 fuel, as amended. Amendment 33 to GESTAR II incorporated Prime T-M methods. Cycle 20 LHGR limits are based on using PRIME for U02 fuel rods and GESTR-M for Gd rods, as GESTR-M limits for Gd rods are more conservative. 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 assumed to be bypassed. Pbypass can be set in anywhere in the range 32.5 to 45% core thermal power. Pbypass is currently set at 32.5% power. Revision 33 Cycle 20 COLR Page 22 of 38

(( Revision 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERA TING LIMITS REPORT RTYPE: G4.02 Cycle 20 COLR Page 23 of 38 ))

1.1 1.0 0.9 0 ~ 0.8 ~ (!) l: 0.7 -I 0.6 Revision 33 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-2 Flow Dependent LHGR Factor (LHGRFACF) Core Flow% Cycle 20 COLR Page 24 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-3 Power Dependent LHGR Factors Note: These LHGRFACp factors are valid for Turbine bypass in or out of service and for Normal Feedwater heating 0.9 1 1100. 1.oL i:::::~ 5 60, 0.935 1 ~ ~ ' .1 90, 0.957 9 ~ '~ 185, 0.935 1 I 32.5, 0.83 ~ 5

0.

0.8

0. 8 45, 0.84 ~ P > Pbypass, 0.7 5 For P, % power > Pbypass, 45% > Pbypass > 32.5%
0. 0. 7

/ " Core Flow s 50%, P s Pbypass, where 5 -f-------- 1--*---~ v 45% > Pbypass > 32.5% ~--- -- / 6 /r 10.! 57 1 5 fo.491 -,,,,,,, -"'.10.53 I t; ,y ro:. li5l --~,. ~ ~ 0.6 Cl 3 0. 0.5

0.

5... J I/- 10.439 Core Flow > 50%, P s Pbypass, where 0.4 4 45% > Pbypass > 32.5%- / 5 ~ p

0.

0.3 lj 0.345 I

0. 3 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100

% Power Revision 33 Cycle 20 COLR Page 25 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT 3.3 Minimum Critical Power Ratio (MCPR) Reference Technical Specification: 3.11.C RTYPE: G4.02 During power operation, 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 is independent of the fuel type and can be directly read from Figure 3.3-2, when Turbine Bypass is operable and from Figure 3.3-3, when Turbine Bypass is out of service. Above Psypa_ss. 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 Tables 3.3-1 are functions of "'C. Both Figures 3.3-2 and 3.3-3 include normal and reduced feed water temperature operating modes. For SLO MCPRp and MCPRF are raised by 0.03 compared to TLO values shown in Figures 3.3-2 and 3.3-3. The value of r 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 "'C. 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 assumed to be bypassed. Pbypass can be set anywhere in the range 32.5% to 45% core thermal power. Pbypass is currently set at 32.5%. Transient Analysis assumes that the transient initiates from operation within the Feedwater temperature vs. Reactor Power band (Figure 3.3-4 ). Transient Analysis also assumes that the transient initiates from operation at a Reactor Pressure within the upper & lower limit curves defined by Figure 3.3-5. If operating at 95% power and Reactor pressure between 1015 psig and the lower pressure band in Figure 3.3-5, an OLMCPR penalty of 0.01 must be applied (Reference 5.22). To operate above the lower pressure curve (not including the flat portion of the curve at 1015 psig above 95% power) in Figure 3.3-5, there is no OLMCPR penalty. Revision 33 Cycle 20 COLR Page 26 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.3-1 MCPR Operating Limits At Rated Power and Rated Flow RTYPE: G4.02 The MCPR Operating Limit for Two Loop Operation (OLMCPRTLo) is a function of fuel type, exposure, and 't, which is derived from scram timing measurements. Tau GNF2 GE14 BOC to MOC MOC to EOC BOC to MOC MOC to EOC From To 0.0 1.51 1.55 1.46 1.52 0.0 0.1 1.52 1.56 1.47 1.54 0.1 0.2 1.53 1.57 1.48 1.55 0.2 0.3 1.54 1.58 1.49 1.57 0.3 0.4 1.55 1.59 1.50 1.59 0.4 0.5 1.56 1.60 1.52 1.61 0.5 0.6 1.57 1.61 1.53 1.62 0.6 0.7 1.58 1.62 1.54 1.64 0.7 0.8 1.59 1.63 1.55 1.66 0.8 0.9 1.60 1.64 1.56 1.67 0.9 1.0 1.61 1.65 1.57 1.69 BOC = Beginning Of Cycle MOC= Middle of Cycle= End Of Rated Power Operation At Rated Flow (EOR) - 1.586 GWd/ST EOC =End Of Cycle Note: The rated OLMCPR Limits given above apply to both normal and reduced Feedwater Temperature as well as Turbine Bypass Valve OOS and Turbine bypass Valves in service. 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 = 0.03 + OLMCPR TLO, where OLMCPR TLo is selected from the Table above. Revision 33 Cycle 20 COLR Page 27 of 38

0::: a.. (..) ~ - c: Q,),, c: Cl,) c. Cl,) 0 ~ 0 u.. 0::: a.. u ~ Revision 33 u 1.6 1 5 1 4 1.3 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.3-1 Flow Dependent MCPR Limits (MCPR Fl RTYPE: G4.02 1.1 4--Lw...+.:-J....LL.j....!J..L..Lj....L.L..L.L.j....LL.J....l.4...L.L.u.+.L.LJ.-4-.1....L.l.-4-L..Ll..-4-J......_,_.L+-1...LL'--f-'--'--'-l'-t-'--'--'-'+-'-............ -t-'-'-'-'--t-'-'-"-'-+'-'""""-'--1 30 35 40 45 50 55 75 80 85 90 Core Fl ow, % Of Rated 100 105 110 115 Cycle 20 COLR Page 28of38

a.

0:::

0.

(.)

E

...J 0 ~ 3.50 3.00 2.50 02.00

a.

1.50 1.00 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.3-2 RTYPE: G4.02 Power Dependent MCPR Limits (MCPRp) Turbine Bypass ls Assumed Operable and Normal and Reduced Feedwater Temperature i 25 T~1~l-T-l==F~F+=t==j~- :::l==l-i= =f l~~r* 1r:f~~~~,~; -~:-)~:::~~~****:~~::~~,:;~ - I 50% ---1--'---,----------------------r .... J..... L '\\ j J.

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', i 50%

.__...,.r-.. ---*-.....,..:-..... -..... -. -.-.,.. -... -.. --r----r-----.--....,...----,..--......---1 ....,. ~..... d 45, 2.01 i.j I i l--** i When P s Pbypass and in SLO, OLMCPRp is

    • -r-..

raised by 0.03 compared to TLO values. When P > .. L..... Pbypass and in SLO, the rated OLMCPR is raised I by 0.03 before multiplying by Kp to calculate -r* --

  • OLMCPRp.

-l-L I 45

        • Kp for P > Pbypass P = % Power and 45% > Pbypass >

65 Power (°lo) I I I J as.1.o66 I*** t 85 100, 1.0 Revision 33 Cycle 20 COLR Page 29 of 38

1----- PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.3-3 Power Dependent MCPR Limits (MCPRp) Turbine Bypass is Assumed Out of Service and Normal and Reduced Feedwater Temperature RTYPE: G4.02 125. oe I 4.50 -===:;::::..._..---..,.._--.....--.--.... _1-__ -____ -_.... _;,._.-... -.... _-_.... ~_-... -..... -....... _,_i_-, ___ - __ -_.. -.. l.-... _-__ -__ -.-' --**--- * --**-*****-~*r-- -***-*" *-r-J 1 i ~ l A- ~ ~-*_.. _,,! ~ 4,()f) 3.50

0.

er: ~3.00

E

...J 0... 0 ~.50 2.00 1.50 1

* \\lllhen PS Pbypass and in SLO, OLMCPRp is raised by 0.03

'-~-- i compared to TLO values. When P > Pbypass and in SLO, the 1 1 * * '. rated OLMCPR is raised by 0.03 before multiplying by Kp hi 1 c~~~ Ol... m'.:.PR~. ......... l:=.~=r~~:.. ~ ~~--_---~I 1 t '---------~--..--...--,..---...------.----r-' -~~.. :.*-.-.-.1_~- J ::!.;:;1,~=~]=-~~~:~:'t;*..... *~.: :E:~=c~-~-~~~::-.; :~: .r:~~~tF-~T~ *- ~~~-:~r..... I ~ l I ~ l l * * *----*... -r--*--... -.... - !_._........... ___,

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  • 1*.

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J, Kp for P > Pbypass . i " ' + I -+* ~...... P =%Power and 45% > Pbypass > 32.5% 45 55 i 65 Power(%) 75 l 85 1* .l 1 ). J 95 Revision 33 Cycle 20 COLR Page 30 of 38

380 360 340

u. 320 0

Q)

s co Q)
0.

Q) E ~ 300 280 260 240 - +,___ PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.3-4, Feedwater Temperature Analytical Bands -* f--

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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.3-5 Operating Dome Pressure Analytical Bands 1060 0 -+..,-+ ""'-+-_;-__:-__.,...,. ,_"""~""',_-..-.... _.,... __ """1--""'-""'lf-_ !- ,... +- .,... +- .,... +.,.. + .... -+ ""l'-J """l-j~-..... _ +- .,... +.,.. + "'T"-""1'"""1 1-1~1,...,... 1 1 .,...,.1 1 """1 ""'1:::::::: . :_:~~ 1050.o 1--+-1-+-+-++-+-+-11-+-+-+-+-+-+-1-+-+-+++-+-+-+-1--+--++-+-+- 1 045 Ps ig +-+-+-1-+-+-++-+-+--t--t--++-+-+-+-1-+-++-+-+-+-+-+*-r-t~H 1030.0 Analysis Upper Pressure Bound l.--r- ~ 020 0 11.ITlll I I I ITfTl,-nm 11 111 *1-11 1 1111 1 ! 111111 ..,,-:-_ - -~ ::, -* ,__ _ OLMCPR Penalty of0.01 must be applied to operate in this area, pdwer :- -++_+_-+- _ f-_+-+/-_:-::f-=-. _ Tr+ _:....,~q::..+-+~-+l~ I,_,...,....,.., ~ 010 0 '"",_ >:;:95% and pressure betwen 1015 to 1025 psig, Op.eration in the riorrnal' 1...-""

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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT 3.4 Power/Flow Relationship During Power Operation Reference Technical Specification: 3.11.D RTYPE: G4.02 The Cycle 20 stability analysis does not credit the flow clamp feature of the FCTR cards. The dominance of Core Wide Oscillations was demonstrated without the use of the flow clamp. APRM Flux scram and Rod Block curves without the flow clamp are therefore applicable to Cycle 20. 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. Cycle 20 operation is not fully analyzed for reduced feedwater temperature for issues other than thermal limits. The SRLR (Reference 5.15) contains only the thermal limit analysis results for reduced feed water temperature mode. The exclusion and the buffer regions shown in Figures 3.4-1 and 3.4-2 are based on Stability Solution 1-0 (references 5.4, 5.12, 5.15 and 5.20). Cycle 20 Stability Analysis summarized in the SRLR (Reference 5.15, Section 15) utilizes ODYSY LTR (Reference 5.24) that removed the decay ratio adder of 0.15.Figures 3.4-1 and 3.4-2 show APRM Scram and Rod Block lines using Allowable values as a function of Core Flow. 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 33 Cycle 20 COLR Page 33 of 38

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45 I-w 40 ~ 35 0 0 30 25 20 15 10 5 0 0 5 10 15 Revision 33 PILGRIM NUCLEAR POWER STATION PNPS 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 Setpoint CORE FLOW, MLB/HR 20 25 30 35 40 45 50 55 60 20 25 30 35 40 45 50 55 60 CORE FLOW, MLB/HR 65 65 RTYPE: G4.02 70 75 70 75 80 2535 2434 2332 2231 2129 2028 1927 ~ 1825 1724 1622 rt uJ 1521 ~ 1420 D-1318 -a 1217 :IE 1115 ffi 1014 :i: I-913 ~ 811 0 710 () 608 507 406 304 203 101 0 80 Cycle 20 COLR Page 35 of 38

PILGRIM NUCLEAR POWER STATION PNPS 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 core loading pattern (Ref. 5.15) for each type of fuel is shown for the present cycle in Figure 4.0-1. Core Loading Pattern differs from that in the SRLR (Reference 5.15) due to a minor rearrangement, accepted through a GESTAR II Assessment (Reference 5.15) for the purposes of reducing the impact of channel bow and NEXRAT. Fuel Type Irradiated: GE14-P1 ODNAB399-15GZ-100T-145-T6-2957 (GE14C) GE 14-P1 ODNAB398-5G6.0/1 OG5.0-1 OOT-145-T6-2958 (GE 14C) GE14-P1 ODNAB400-13GZ-100T-145-T6-2959 (GE14C) GE14-P1 ODNAB404-5G6.0/1 OG5.0-1 OOT-145-T6-2960 (GE14C) GE14-P1 ODNAB400-12G6.0/3G5.0-1 OOT-145-T6-2961 (GE14C) GNF2-P1 ODG28389-6G6.0/8G5.0-1 OOT2-145-T6-3141 (GNF2) GNF2-P1 OOG28389-6G6.0/2G5.0/6G4.0-1 OOT2-145-T6-3142 (GNF2) GNF2-P 1 ODG28388-6G6.0/7G5.0-1 OOT2-145-T6-3143 (GNF2) GNF2-P1 ODG28401-6G6.0/8G5.0/1 G4.0-1 OOT2-145-T6-3421 (GNF2) GNF2-P 1 ODG28395-6G6.0/9G5.0-1 OOT2-145-T6-3422 (GNF2) GNF2-P 1ODG28375-6G6.0/7G5.0-1 OOT2-145-T6-3434 (GNF2) GNF2-P 1 ODG28401-6G6.0/2G5.0/6G4.0-1 OOT2-145-T6-3640 (GNF2) GNF2-P1 ODG28406-6G6.0/6G5.0/2G4.0-1 OOT2-145-T6-3641 (GNF2) GNF2-P1 ODG28407-6G6.0/2G5.0/6G4.0-1 OOT2-145-T6-3642 (GNF2) New: GNF2-P 1 ODG28406-6G6.0/2 GS.0/6G4.0-1 OOT2-145-T6-4171 GNF2-P 1 OOG28398-5G6.0/8G5.0-1 OOT2-145-T6-4172 GNF2-P1 ODG28389-15G5.0-1 OOT2-145-T6-4173 GNF2-P1 ODG28375-7G6.0/6G5.0-1 OOT2-145-T6-4174 Total: Revision 33 Cycle Number Load 17 14 17 29 17 24 17 33 17 20 18 16 18 104 18 36 19 24 19 16 19 16 19 36 19 16 19 44 56 24 40 32 580 Cycle 20 COLR Page 36 of 38

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT FIGURE 4.0-1 Reactor Vessel Core Loading Pattern ' Sltl¥:2.<~~5~t;~~"7:,;lrW.E!l~!f:'!.*~:~J~ll~S.2!/X £r!'l~F.lJ,'!i~~rLJ9.'.:'.~tt:~JEi~~~- "l'!t~f.~

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. ie *,,~~li<-"li' t "._,c-,*_*-r : ;>;w,.~i.,_,.;., _:r.:; ,:19:>>*~. 2!Ji.2 _ ~ 217,:1 Q ~, ~t>'.,in ":'~'~~fa * .r ~y,, ~").,. ,, 'W"~-~ >.~~~ .. r.~~ ~ -""'- ~- ~ ~ *~~.J -4"'\\.,~!-:~ !AT Bundle Oesaiption 1 GE14-P10DNAB404-5G6.0l1OG5.0-10ITT-145-TS-2960 2 GE14-P10DNAB39S-5G5.0/10G5.0-10ITT-14> T&-2958 5 GNF2-P1 ODG2B388-6G6.017G5.0-100T2-145-TS-3143 GNF2-P1ODG2B395-6G6.0/9G5.0-100T2* 145-T&-3422 GNF2-P10DG2B401*6G6.0/8G5.0/1G4.0-100T2-145-T&-3421 GE1+P10DNA8400-13GZ *1 OOT-1 45-T&-2959 10 GE 14-P10DNAB399' 15GZ-1 OOT-145-T&-2957 11 GNF2-P10DG2B389-6G6.0/8G5.0-100T2-145-T6-3141 12 GNF2-P10DG2B407-6G6.0l2G5.016G4.0- I OOT2-145-TB-3642 13 GNF2-P1ODG2B401*6G6012G5.0/6G4.0- I OOT2-14!>-TS-3640 15 GNF2-P10DG2B406-6G6.0/6G5.0/2G4.0-1OOT2*14!>-TS-3641 16 GNF2*P10DG2B401-6G6.012G5.0/6G4.0-1 OOT2-14!>-T6-3640 18 GE14-P10DNAB400-12G6.Cl/3G5.0-100T* 145-T&-2961 19 GNF2-P1ODG28389'6G6.0l2G5.0/6G4.0-100T2-14!>-TS-3142 20 GNF2-P 10DG2B375-6G6.017G5 0-100T2-145-T6-3434 21 GN F2-P1ODG2B406-6G6.012G5.0/6G4.0-1 OOT2-145-T6-4171 22 GNF2-P10DG2B398-5G6.0IBG5.0- 100T2-145-TtH172 Zl GNF2-P10DG2B389-15G5.0-100T2-145-T6-4173 24 GNF2*P10DG2B375-7G6.016G5.0-100T2*14!>-T6-4174

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Bundles Loaded 33 17 29 17 36 13 16 19 24 24 14 16 44 28 16 8 20 104 16 56 24 40 32 19 17 17 18 19 19 19 19 17 18 19 20 20 20 20 ta al 580 ~* ' RTYPE: G4.02 Revision 33 Cycle 20 COLR Page 37 of 38

5.0 REFERENCES

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 5.1. NEDE-24011 -P-A-19 and NEDE-24011 -P-A-19-US, "General Electric Standard Application for Reactor Fuel", May 2012, eB record: LRW-ENO-GEN-12-081. 5.2. EC41182, Cycle 20 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.O, Application of Stability Long-Term Solution Option 1-D To Pilgrim Nuclear Power Station, October 2004. 5.5. Letter 1.09.015, Letter from the NRC approving TS Amendment 232 for Cycle 18 SLMCPR. 5.6. GE-NE-GENE-0000-0033-6871-01, Rev. 0, Pilgrim Option 1-D APRM Flow Biased Set points, 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, % t.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 4, 1987. 5.11. A22-00109-00 MAPLHGR set down process explanation for Pilgrim, November 2001. 5.12. GNF2NFI, GEH-0000-0085-9069-RO, GNF2 Fuel Design Cycle Independent Analyses for Entergy PNPS, February 2009. 5.13. ER 03110960, Stability 1-D implementation. 5.14. PNPS-RPT-03-00001, Rev. 6, "Pilgrim Power To Flow Map Report."(EC27443) 5.15. ECH-NE-13-00002, "Supplemental Reload Licensing Report, Reload 19, Cycle 20, April 2013", 0000-0147-0084-SRLR-R1 and Updated Loading Pattern GESTAR II Licensing Assessment, GNF-S-0000-0160-1647 Rev. 0 (EC41854). 5.16. ECH-NE-12-00068, EC34869, PNPS Cycle 20 OPL-3 Form. 5.17. ECH-NE-13-00003, 0000-0147-0084-FBIR-R1, April 2013, "PNPS Cycle 20 Fuel Bundle Information Report (FBIR)" (EC41862). 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, PNPS GNF2 ECCS-LOCA Evaluation. 5.22. ECH-NE-2013-00026, "Increased Operating Dome Pressure Band For Pilgrim". 5.23. NEDE-33270P, GNF2 Advantage Generic Compliance with GESTAR II), Revision 3, March 2010 (This reference is also known as Amendment 22 report for GNF2). (record in eB: RA-ENO-GEN-10-040) 5.24. NEDE-33213, ODYSY Application for Stability Licensing Calculations Including Optiorr 1-D and II Long Term Solutions, April 2009 Revision 33 Cycle 20 COLR Page 38 of 38 Letter Number 2.17.058, KGO-ENO-HK1-17-081, Affidavit for Enclosure 1, Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report, Revision 33, GNF Proprietary Information - Class II (Internal)

ENCLOSURE 3 KGO-ENO-H K 1-17-081 Affidavit for Enclosure 1

Global Nuclear Fuel - Americas AFFIDAVIT I, Brian R. Moore, state as follows: (1) I am General Manager, Core & Fuel Engineering, Global Nuclear Fuel - Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding. (2) The information sought to be withheld is contained in Enclosure 1 of GNF's letter, KGO-ENO-HKl-17-081, Kimberly O'Connor (GNF) to Nela Szwarc (Entergy), entitled "Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report (COLR) Revision 33 and Cycle 21 COLR Revision 34, 35, and 36 - Proprietary and Non-Proprietary Versions," July 28, 2017. GNF proprietary information in Enclosure I, which is entitled "Pilgrim Nuclear Power Station Cycle 20 Core Operating Limits Report, Revision 33," is identified by a dotted underline inside double square brackets. ((TbJ.~.. ?.~n.t.~nf~..!?... f:l.D. ~~!'!!TIP.!~, ~~_}_)) A "((" marking at the beginning of a table, figure, or paragraph closed with a ")) marking at the end of the table, figure or paragraph is used to indicate that the entire content between the double brackets is proprietary. In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination. (3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.l 7(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d87 l (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2dl280 (DC Cir. 1983). (4) Some examples of categories of information which fit into the definition of proprietary information are:

a.

Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;

b.

Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, ship~ent, installation, assurance of quality, or licensing of a similar product;

c.

Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A; KGO-ENO-HKl-17-081Enclosure1 Affidavit Page I of 3

l -

d.

Information which discloses patentable subject matter for which it may be desirable to obtain patent protection. The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above. (5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following. (6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. (7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements. (8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology. The development of this methodology, along with the testing, development and approval was achieved at a significant cost to GNF-A. The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from an extensive experience database that constitutes a major GNF-A asset. (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and KGO-ENO-HK 1-17-081 Enclosure 1 Affidavit Page 2 of 3

L analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods. The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions. The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools. I declare under penalty of perjury that the foregoing is true and correct. Executed on this 28th day of July 2017. KGO-ENO-HKl-17-081 Enclosure l Brian R. Moore General Manager, Core & Fuel Engineering Global Nuclear Fuel - Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 Brian.Moore@ge.com Affidavit Page 3 of 3}}

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