LR-N11-0022, Technical Specifications 6.9.1.1 and 6.9.1.3

Technical Specifications 6.9.1.1 and 6.9.1.3

ML110460685
Person / Time
Site:	Hope Creek
Issue date:	02/07/2011
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N11-0022
Download: ML110460685 (8)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC TS 6.9.1.1 TS 6.9.1.3 FEB 0 7 2011 LR-N 11-0022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Hope Creek Technical Specifications 6.9.1.1 and 6.9.1.3

Reference:

1) Hope Creek Generating Station - Issuance of Amendment Re: Use of Isotope Test Assemblies for Cobalt-60 production (TAC No. ME-2949)

Hope Creek Generating Station introduced a new fuel design, GE14i Isotope Test Assemblies (ITAs), in Cycle 17, which was authorized per reference 1. Hope Creek Technical Specification (TS) 6.9.1.1 requires a submittal of a startup report following the installation of fuel that has a different design. The Attachment to this letter provides the information for TS 6.9.1.1 in accordance with TS 6.9.1.3.

There are no new or revised regulatory commitments contained in this letter.

If you have any questions, please contact Mr. Philip J. Duca, Hope Creek Regulatory Assurance, at 856-339-1640.

Sincerely, F.iPerry Site Vice President - Hope Creek PSEG Nuclear LLC Aoc

/o 95-2168 REV. 7/99

Document Control Desk Page 2 LR-N11-0022

Attachment:

1) Hope Creek Cycle 17 Startup Report cc:

Mr. W. Dean, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager Salem and Hope Creek U.S. Nuclear Regulatory Commission One White Flint North M a il S to p 0 8 B l A -..

11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector - Hope Creek (X24)

P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625 Corporate Commitment Tracking Coordinator (N21)

Hope Creek Commitment Tracking Coordinator (H02)

Document Control Desk LR-N11-0022 Page 1 of 6 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Hope Creek Cycle 17 Startup Report Table of Contents 1.0 Introduction 2

2.0 Control Rod Drive System 2

2.1 Control Rod Scram Time 2

3.0 Full Core Shutdown Margin 3

3.1 Shutdown Margin Demonstration 3

4.0 Core Perfomance.

5 4.1 Thermal Limits 5

5.0 References 6

List of Tables Table 1: Individual Scram Time 3

Table 2: Acceptance Criteria 3

Table 3: BOC Variations in Measure vs. Calculated SDM 4

Table 4: Confirmation of GE14i ITA Non-limiting Shutdown Margin 4

Table 5: Cycle Management Report Predictions to CMS Thermal Limits Comparison for GE14 and GE14i ITA 6

List of Figures Figure 1: Confirmation of GE14i ITA Non-limiting Shutdown Margin 5

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Document Control Desk LR-N 11-0022 Page 2 of 6 1.0 Introduction Hope Creek Generating Station introduced a new fuel design, GE1 4i Isotope Test Assemblies (ITAs), in Cycle 17. There are twelve bundles of the GE14i ITA design operating in the core while the remaining fuel is of the GE14 fuel design. The GE14i ITA fuel consists of fuel rods, some cobalt isotope rods, and two large central water rods in a 10x10 array. The GE14 fuel is a 10x10 design with two large central water rods, consisting of 92 fuel rods. Hope Creek Technical Specification 6.9.1.1 requires a submittal of a startup report following the installation of fuel that has a different design.

This startup report will address each of the initial startup tests identified in the Final Safety Analysis Report (FSAR) that could be impacted by the introduction of the GE1 4i ITA fuel design.

During Hope Creek's sixteenth refueling outage (RF16), that began on October 15, 2010 and was completed on November 11,2010, 12 GE14i ITAs were loaded into the core.

The following sections provide a description of the test results for those initial startup tests described in the Hope Creek FSAR that could be impacted by the introduction of the GE14i ITA fuel design (Reference 5.1) 2.0 Control Rod Drive System The description of the initial startup testing for the control rod drive system is provided in Hope Creek FSAR section 14.2.12.3.5. The operability of the control rod system may be impacted by the introduction of a new fuel design. The new fuel design could cause additional friction on control rod movement, which may impact the scram speeds.

2.1 Control Rod Scram Time The control rod drive (CRD) scram times were measured in accordance with procedure HC.RE-ST.BF-0001(Q), "Control Rod Scram Time Surveillance". The objective of this test was to verify that the CRD scram times met all Technical Specification acceptance criteria. The measured scram times for control rod locations containing GE14i ITAs were compared against acceptance criteria for the purpose of determining control rod drive system performance. The acceptance criteria for the individual scram time to notch position 05, core average scram times to notch positions 45, 39, 25, and 05, and array average scram times to notch positions 45, 39, 25, and 05, are given in the Hope Creek Technical Specifications 3.1.3.2, 3.1.3.3, and 3.1.3.4 respectively. A summary of results for the control rod locations containing GE14i ITAs with the most limiting scram insertion time for each notch position is provided in Table 1. The results indicate that the measured scram times are faster than the acceptance criteria for individual scram time, core average scram times, and array average scram times shown in Table 2. This demonstrates that the introduction of the GE14i ITA fuel design did not have an adverse effect on control rod drive system performance.

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Document Control Desk LR-N1 1-0022 Page 3 of 6 Table 1: Individual Scram Time Notch Control Rod Most Limiting Scram Insertion Position Time (seconds) 45 50-11 0.278 39 50-11 0.590 25 50-11 1.328 05 50-11 2.488 Table 2: Acceptance Criteria Test Notch Acceptance Criteria (seconds)

Position Individual Scram Time 05

< 7 Core Average Scram Time 45

< 0.430 39

< 0.860 25

< 1.930 05

< 3.490 Array Average Scram Time 45 5 0.450 39 50.920 25

< 2.050 05

< 3.700 3.0 Full Core Shutdown Margin The description of the initial startup testing for the full core shutdown margin demonstration is provided in the Hope Creek FSAR section 14.2.12.3.4. The Cycle 17 startup testing demonstrated that the shutdown margin was greater than 0.38% Ak/k.

3.1 Shutdown Margin Demonstration The core shutdown margin (SDM) was demonstrated in accordance with procedure HC.RE-ST.ZZ-0007(Q), "Shutdown Margin Surveillance". The objective of the test, as required by Technical Specifications, is to demonstrate that the core will remain subcritical by at least 0.38% Ak/k throughout the cycle at cold xenon free conditions, with the strongest worth control rod withdrawn. The core SDM was demonstrated during the in-sequence critical SDM measurement. The measured SDM for Cycle 17 was 1.06%

Ak/k, which meets the Technical Specification minimum requirement of 0.38% Ak/k and was within the expected range for the minimum core shutdown margin at beginning of cycle based upon the cycle management predictions and from comparison to previous cycle's data as shown in Table 3. The cycle management predictions were performed in a manner that required the GE1 4i ITAs be non-limiting (Table 4 and Figure 1) with respect to minimum shutdown margin including consideration of a 0.001 Ak shutdown margin adder to ensure a conservative shutdown margin demonstration (Reference 5.4).

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Document Control Desk LR-N11-0022 Page 4 of 6 Table 3: BOC Variations in Measured vs. Predicted Cold Target Keff Cycle Measured Assumed Delta K Delta %

13 1.0004 1.00100

-0.00060

-0.06 14 0.99849 1.00100

-0.00251

-0.251 15 1.00160 0.99950 0.00210 0.21 16 1.00038 1.00100

-0.00062

-0.062 17 0.99975 1.00100

-0.00125

-0.125 Table 4: Confirmation of GE14i ITA Non-limiting Shutdown Margin EXP SDM SDM GE14i MWD/ST

%dK

%dK 0

1.26 1.62 200 1.40 1.69 500 1.45 1.74 1000 1.53 1.80 2000 1.63 1.87 2500 1.67 1.90 3000 1.73 1.94 4000 1.78 2.01 5000 1.85 2.18 6000 1.87 2.33 7000 1.84 2.45 7700 1.77 2.51 8000 1.71 2.53 9000 1.43 2.57 10000 1.23 2.63 10000 1.23 2.63 10500 1.19 2.69 11000 1.21 2.78 11500 1.28 2.89 11600 1.30 2.92 11785 1.34 2.97 12265 1.45 3.14 12505 1.52 3.23 12745 1.60 3.34 13017 1.71 3.47 4

Document Control Desk LR-N11-0022 Page 5 of 6 GE14i ITA Non-limiting Shutdown Margin Figure 1: Confirmatidn of 3.60-3.40-SDM 3.20 SDM GE14i 3.00 -

- Design Limit 2.80 1

S2.40 2.20 2.00 c,1.80-1.60 1.40 1.20 1.00 0.80 0

2000 4090 6000 8000 10000 12000 14000 Exposure (MWD/ST) 4.0 Core Performance The description of the initial star respect to thermal limits, is prov objective of the test is to calcula associated with core behavior.s 4.1 Thermal Limits

ýup testing to evaluate the core performance, with ded in the Hope Creek FSAR section 14.2.12.3.16. The te the principal thermal and hydraulic parameters The GE14i ITAs were designed for mechanical, nuclear, and thermal-hydraulic compatibility with the GE14 fuel design currently in the core and are required to be located in non-limiting locations iwith respect to thermal limits (Reference 5.4). The thermal limits at full power conditions were obtained from the Core Monitoring System (CMS). According to Referenc* 5.4, the NRC staff has determined that the GE14i ITAs will not have any significant impact on the incore instrumentation and core monitoring system in the Hope Creek core.' The Core Monitoring System (CMS) data was obtained from an edit generated on 11/2?/2010 23:32, at a cycle exposure of 244.9 Mwd/St. The CMS data validated the predicted results for Cycle 17 as documented in reference 5.5.

Table 5 shows the maximum GE14i ITA values from the CMS are below the maximum GE14 CMS values, which demonstrate the GE14 fuel assemblies are more limiting than the GE14i ITAs.

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Document Control Desk LR-N 11-0022 Table 5: CMS Thermal Lin Maximum C MFLCPR 0.85 MFLPD 0.87 MAPRAT 0.67 Page 6 of 6 nits Comparison for GE14 and GE14i ITA MS GE14 Maximum CMS GE14i ITA 1

0.748

'7 0.806

'7 0.614 5.0 References 5.1 NFS-0257, HCGS Cycle 17 Evaluation of the UFSAR Chapter 14 Initial Cycle Startup Tests 5.2 HCC17CMR, PSEG Nuclear, LLC Cycle Management Report Hope Creek Cycle 17 5.3 HCG.5-0138, Hope Creek Cycle 17 Startup Data 5.4 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment 184 to Facility Operating License No. NPF-57, PSEG Nuclear LLC, Hope Creek Generating Station, Docket No. 50-354, October 7, 2010.

5.5 HCP.6-0244, Hope Creek Cycle 17 Rod Pattern Design Analysis Revision 0 6