ML22213A122

Startup Test Report for Cycle 22

ML22213A122
Person / Time
Site:	Millstone
Issue date:	07/28/2022
From:	Armstrong L Dominion Energy Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
22-235
Download: ML22213A122 (14)

Text

Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station 314 Rope Ferry Road, Waterford, CT 06385 Dominion Energy.com U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

. DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 STARTUP TEST REPORT FOR CYCLE 22 Dominion

iiiiiii" Energy Serial No.

MPS Lic/CRD Docket No.

License No.22-235 RO 50-423 NPF-49 JUL 2 8 2022 Pursuant to Millstone Power Station Unit 3 Technical Specification 6.9.1.1, Dominion Energy Nuclear Connecticut, Inc. submits the enclosed Startup Test Report for Cycle

22.

If you have any questions or require additional information, please contact Mr. Dean E.

Rowe at (860) 444-5292.

Sincerely,

~ -CL~

Lori Armstrong Director, Nuclear Safety and Licensing - Millstone

Enclosure:

(1)

Commitments made in this letter: None

cc:

U.S. Nuclear Regulatory Commission Region I Administrator 475 Allendale Road, Suite 102 King of Prussia, PA 19406-1415 R. V. Guzman Senior Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No.22-235 Docket No. 50-423 Page 2 of 2

ENCLOSURE STARTUPTESTREPORTFORCYCLE22 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 Serial No.22-235 Docket No. 50-423

~

Dominion

=

!~ Energy

1. Stations:

18]MP NA SU ovc 8.

Title:

2. Doc Type: 3. Sub Type:

ETE 000 Millstone Unit 3 Cycle 22 Startup Physics Tests Report

9. ETE Level:

10. Unit(s):

18]Level 1 Unit 1 Unit 2 18]Unit 3 OISFSI Level 2 Serial No.22-235 Docket No. 50-423 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 ATTACHMENT 2 Page 1 of 11

4. Document Number:

5. Rev.: 6. Add:

7. Decomm?

ETE-NAF-2022-0067 0

NIA Yes 18]No

11. Quality

12. FSRC

13. Risk Assessment:

Classification:

Approval:

Low Medium 18]SR NS ONSQ 1 Yes 18]No High 18] NIA

14. Preparation, Review, and Approval Signatures (add or delete rows as needed)

Prepared by/Affiliation: (Print)

Signature:

B. R. Kinney/ NEF INDEX AUTHENTICATION Reviewed by/Affiliation: (Print) 18JIND PEER Signature:

I. A. Sayre I NEF INDEX AUTHENTICATION Program/Other Reviewer/Affiliation: (Print) OIND PEER 18]SME Signature:

M. G. Jones /MPS INDEX AUTHENTICATION Supervisor Approval/Affiliation: (Print)

Signature:

B. J. Vitiello/ NEF INDEX AUTHENTICATION Standard Attachments Attachment

1. of pages Reviewed D No impact

15. Design Effects and Considerations (DNES-AA-GN-1003) 2 D Addressed

16. Document Impact Summary (DRUL) (DNES-AA-GN-1002) 3

17. Considerations and Conditions for Document Updates (check 18]N/A if no document updates are noted on the DRUL)

D All Document updates noted on the DRUL can be initiated immediately D Document updates noted on DRUL are delayed until the following documents/actions are completed (e.g., WO, CR, etc.)

(See DRUL Remarks section) 10CFR50.59 Attachments

18. 1 0CFR50.59/72.48 applicability review forms (CM AA-400) 4

19. 10CFR50.59/72.48 screen form (CM-AA-400) 4

20. 10CFR50.59/72.48 evaluation form (CM-AA-400) 4

21. Additional Attachments Attachment N/A 1 Or at VC Summer, Quality Related (QR), per ES-0411, if effective 2 Or at VC Summer, EC-01, if effective 3 Or at VC Summer, EC-02, Attachment 11, if effective 4 Or at VC Summer, SAP-0107, if effective

1. of pages N/A Attachment

1. of pages Description N/A Date:

INDEX DATE Date:

INDEX DATE Date:

INDEX DATE Date:

INDEX DATE Not Req.

18]

18]

Not Req.

18]

18]

18]

Form No. 730801 (May 2020)

22. Distribution Primary Recipient(s): D. C. Beachy, Supervisor - Nuclear Licensing, MPS (Enter Name/Dept. or Location for EACH Primary Recipient in this block.)

Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 2 of 11 ETE-NAF-2022-0067 Rev.O Copy To?

other RecipienUDepartment or Location Copy To?

Other RecipienUDepartment Location

~

B. R. Kinney/ INNS

~

A. D. Gailis I MPS

~

I. A. Sayre / INNS

~

M. S. Vinyard/ MPS

~

D. T. Smith / INNS

~

M. G. Jones /MPS

~

J. Stanley/ INNS

~

T. F. Olsowy I MPS

~

B. J. Vitiello/ INNS

~

S. Sinha/ INNS If the ETE contains Safeguards, Security-Related, or Controlled Unclassified Information this shall be noted in accordance with SY-AA-106 (Ref. 5.4.18) and RM-AA-101 (Ref. 5.4.4) (or at VC Summer, VCS-SAP-0135 and SAP-0126, if effective).

If the ETE contains Confidential (Proprietary) Information for limited access, this shall be noted in accordance with RM-AA-101 (or at VC Summer, SAP-0126, if effective) (Ref. 5.4.4). Some examples of this notation are shown in the box below. If applicable, include a notation in this box. If no Confidential (Proprietary) Information is included in the ETE, the box should be deleted.

Source Document DNES-AA-NAF-NCD-5007, Rev. 4 Record of Revision Original Revision Purpose This Engineering Technical Evaluation (ETE) documents the Millstone Unit 3 Cycle 22 (M3C22) Startup Physics Tests Report (SPTR) in accordance with the Source Document. It is provided as information only. As such, in accordance with CM-AA-ETE-101, Rev. 14 step 2.4.i, this ETE is classified as a Level 1 ETE and no controlled document, programs, or 10 CFR 50.59/72.48 screening is required. In addition, a risk assessment is not required for a Level 1 ETE per CM-AA-RSK-1001, Rev. 23.

This startup test report is to be submitted to the NRC In accordance with TS 6.9.1.1 due to the Implementation of the measurement uncertainty recapture (MUR) power uprate (Reference 8).

Form No. 730801 (May 2020)

Discussion Introduction and Summary Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 3 of 11 ETE-NAF-2022-0067 Rev.O The Millstone Unit 3 Cycle 22 (M3C22) fuel reload was completed in April 2022 and went critical on May 21, 2022 at 00:03. The core map detailed in Figure 1 at the end of the discussion section shows the final core configuration. Reference 3 documents that Cycle 22 uses a low leakage loading pattern (L3P) consisting of 85 new Region 24 fuel assemblies, 84 Region 23 once-burned fuel assemblies, and 24 Region 22 twice-burned fuel assemblies. All 193 fuel assemblies in the Cycle 22 core are the Westinghouse 17x17 robust fuel assembly (RFA-2) design.

M3C22 will be the first cycle to operate at 3709 MWt due the implementation of the Measurement Uncertainty Recapture (MUR) power uprate.

The 85 new Region 24 fuel assemblies are comprised of 57 fuel assemblies (designated Region 24A) enriched to 4.00 weight percent Uranium-235 (w/o U235), 28 fuel assemblies (designated Region 24B) enriched to 4.80 w/o U235. The top and bottom regions of all fuel assemblies in the Cycle 22 core are comprised of a 6-inch annular blanket region enriched to 2.6 w/o U235 (Region 24 and 22) or 2.4 w/o U235 (Region 23).

The 108 re-inserted fuel assemblies were ultrasonically cleaned during the refueling outage. The purpose of the ultrasonic fuel cleaning was to remove adhered crud (primarily nickel and iron-based deposits) from the surface of fuel rods that have previous core exposure in order to reduce the probability of occurrence of crud-induced power shift (CIPS).

Every fuel assembly in Cycle 22 contains an insert. The inserts consist of 61 rod cluster control assemblies (RCCAs),

130 thimble plugs, and 2 secondary source assemblies.

Subsequent operational and testing milestones were completed as follows:

Fuel Design Hot Rod Drops Initial Criticality Low Power Physics Testing completed Main Turbine Online Less than 50% Power Testing completed Less than 75% Power Testing completed 100% Power Testing completed May 20, 2022 May 21, 2022 May 21, 2022 June 4, 2022 June 4, 2022 June 5, 2022 June 13, 2022 All of the 193 assemblies in the Cycle 22 core are of the RFA-2 design. This fuel design is the same as that used in Cycle

21.

Control Rod Drop Time Measurements As directed in Reference 7, the drop time of each control rod was measured as hot shutdown (HSD) at hot full-flow reactor coolant system (RCS) conditions before criticality in order to verify that the time to the entry of the rod into the dashpot was less than or equal to, 2.7 seconds, the maximum allowed by Technical Specification 3.1.3.4. All the rods dropped as predicted and the times satisfied the Technical Specifications.

Form No. 730801 (May 2020)

Serial No.22-235 Docket No. 50-423 CM-M-ETE-101 ATTACHMENT2 Page4of11 ETE-NAF-2022-0067 Hot Rod Drop Time Summary Rev.O Slowest Rod (sec)

Fastest Rod (sec)

Average Time (sec)

M-14, P-04, P-12, G-15 2.07 H-10 1.92 2.00 Low Power Physics Testing The low power physics testing program for Cycle 22 is defined in Reference 5 and completed using the procedure in Reference 1. The program defined in Reference 5 consisted of the following: total core reactivity check, moderator/isothermal temperature coefficient measurements, and a conditional requirement for control and shutdown bank worth measurements. Low power physics testing was performed at a power level below the point of nuclear heat to avoid nuclear heating reactivity feedback effects.

As discussed in Reference 6 rod worth measurements were not required for Cycle 22. Specifically, the MUR was considered a Significant Design Change, however, the conditions (e.g., zero power average moderator temperature) during Reload Physics Testing remained the same as prior cycles. For M3C22, the overall core reactivity conditions at zero power were the same as previous cycles, there is no reason to suspect degradation of RCCA neutron absorption properties, and the capability of the core design methods to predict RCCA worth are unchanged. Core reactivity changes measured during physics testing for M3C22 are within normal cycle-to-cycle variation in core designs.

The total core reactivity check verifies critical boron concentration with control bank D inserted at least 400 pcm of predicted rod worth. The measured values include corrections to account for differences between the measured critical configuration and the expected configuration. The review and acceptance criteria of +/-300 and +/-1000 percent milliRho (pcm), respectively, were met.

Summary of Total Core Reactivity Check Results Control Bank Measured Predicted M-P M-P Acceptance D Position (ppm)

(ppm)

(ppm)

(pcm)

Criteria (pcm)

(Steps) 97 1977.7 1999

-21.3 138.4

.:!: 1000 The Isothermal Temperature Coefficient (ITC) data was measured with Control Bank D at 97 steps withdrawn. The review criteria of +/-2 pcm/degrees Fahrenheit (°F) to the predictions were met. The TS limit of Moderator Temperature Coefficient (MTG) < +5.0 pcml°F at ARO hot zero power (HZP) was met.

Isothermal/Moderator Temperature Coefficient Results Measured Predicted Measured MTG Measured MTG Acceptance ITC ITC M-P OTC

[ITC-OTC]

Adjusted to All (pcm/°F)

(pcml°F)

Criteria (pcm/°F)

(pcml°F)

(pcm/°F) rods out (pcm/°F)

(pcm/°F)

-1.825

-2.430 0.605

-1.76

-0.065 0.745 MTG< 5.0 Form No. 730801 (May 2020)

Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 5 of 11 ETE-NAF-2022-0067 Rev.o Power Ascension Testing I Power Distribution Measurements The core power distribution was measured through the performance of a series of flux maps during the power ascension, as specified in Reference 2. The results from the flux maps were used to verify compliance with the power distribution Technical Specifications.

A low power flux map at approximately 32.50% RTP was performed to determine if any gross neutron flux abnormalities existed. The 73.86% and 99.91% RTP plateau flux map were performed to support TS Surveillance requirements and to verify that core power distributions were within the design limits.

A summary of the measured axial offset (AO) and incore tilt for the flux maps performed during the power ascension is provided below. Additional tables provide comparisons of the most limiting measured heat flux hot channel factor (Fa) and nuclear enthalpy rise hot channel factor (Fah), including uncertainties, to their respective limits from each of the flux maps performed during the power ascension. The most limiting Fa reported is based on minimum margin to the limit that varies as a function of core height.

As shown below, all TS limits were met and no abnormalities in core power distribution were observed during power ascension.

Summary of Measured Axial Offset and lncore Tilt Power Bumup D-Bank AO{%)

lncore Tilt (o/oRTP)

(MWD/MTU)

Position (steps) 32.50 14.0 213 15.865 1.0054 73.86 41.0 216 5.879 1.0030 99.91 353 216 1.400 1.0022 Comparison of Measured FQ to FQ RTP Limit Power Burnup Measured Fa FoRTP steady state Measured Transient Transient Fo Limit (o/oRTP)

(MWD/MTU) limit Fo 32.50 14.0 2.123 4.984 2.119 2.530 73.86 41.0 1.878 3.402 1.878 2.286 99.91 353.0 1.819 2.548 1.846 2.182 Form No. 730801 (May 2020)

Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 6 of 11 ETE-NAF-2022-0067 Comparison of Measured Ft:.h to Ft:.h Limit Power Burnup Ft:.h Ft:.h Limit (o/oRTP)

(MWD/MTU) 32.50 14.0 1.487 1.907 73.86 41.0 1.457 1.710 99.91 353.0 1.435 1.586 Rev.o Presented at the end of the discussion section, Figures 2, 3, and 4 are measured power distribution maps showing percent difference from the predicted power for approximately 32.50%, 73.86% and 99.91 % RTP plateaus. These figures show there is good agreement between the measured and predicted assembly powers.

Per TS Surveillance 4.2.3.1.3, the RCS flow was measured within 7 days after exceeding 90% RTP using Reference 4.

The measured flow at 100% RTP was 404,795 gallons per minute (gpm) with a minimum required flow of 379,200 gpm.

All TS limits were met.

Form No. 730801 (May 2020)

R p

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REGK>N '22A (4.1Ow'o)

REGK>N '22B

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Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 7 of 11 ETE-NAF-2022-0067 Figure 1 Core Loading Pattern K

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REGION 23A REGION 24A

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( 4.80w/o)

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B A

2 3

4 5

6 7

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10 11 12 13 14 15 Form No. 730801 (May 2020)

Figure 2 Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 8 of 11 ETE-NAF-2022-0067 Rev.O Power Distribution - 32.50%

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Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 9 of 11 ETE-NAF-2022-0067 Rev.o Figure 3 Power Distribution - 73.86%

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Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 10 of 11 ETE-NAF-2022-0067 Rev.O Figure 4 Power Distribution - 99.91 %

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-2.0 2 1 Form No. 730801 (May 2020)

Serial No.22-235 Docket No. 50-423 CM-AA-ETE-101 ATTACHMENT 2 Page 11 of 11 ETE-NAF-2022-0067 Rev.a Conclusions All results associated with M3C22 BOC zero power physics testing and power ascension flux mapping were acceptable and within associated design tolerances, Technical Specification limits, and Core Operating Limits Report (COLR) limits.

References

1.

Procedure, SP 31008, Rev. 014-00, "Low Power Physics Testing (ICCE)."

2.

Procedure, EN 31015, Rev. 010-00, "Power Ascension Testing of Millstone Unit 3."

3.

Engineering Technical Evaluation, ETE-NAF-2022-0035, Rev. 0, "Millstone Unit 3 Cycle 22 Nuclear Design Report." April 2022.

4.

Procedure, SP 31004 Rev. 13, Att. 2, "Reactor Coolant System Flow Measurement-Precision." 06/14/2022.

5.

Engineering Technical Evaluation, ETE-NAF-2020-0032, Rev 0, "Dominion Energy Nuclear Units Reload Physics Testing Program" August 2020.

6.

Reload Safety Evaluation, EVAL-ENG-RSE-M3C22, Rev. 0, "Reload Safety Evaluation Millstone Unit 3 Cycle 22" April 2022.

7.

Procedure, SP3451N22 Rev. 12, Att. 3 "Multiple Rod Drop Time Test Using AMS" 05/20/2022

8.

Letter from NRG to Dominion Energy, Serial No.21-383, "Millstone Power Station Unit No. 3 - Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate (EPID L-2020-LLS-0002),"

November 9, 2021. (ADAMS Accession Number ML21262A001)

Form No. 730801 (May 2020)