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| number = ML12250A664
| number = ML12250A664
| issue date = 08/28/2012
| issue date = 08/28/2012
| title = Millstone, Unit 3, Correction to Proposed Technical Specifications to Adopt TSTF-510
| title = Correction to Proposed Technical Specifications to Adopt TSTF-510
| author name = Price J A
| author name = Price J
| author affiliation = Dominion, Dominion Nuclear Connecticut, Inc
| author affiliation = Dominion, Dominion Nuclear Connecticut, Inc
| addressee name =  
| addressee name =  
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:Dominion Nuclear Connecticut, Inc. AUG cO eDominion Millstone Power Station A 2821 Rope Ferry Road Waterford, CT 06385 U.S. Nuclear Regulatory Commission Serial No. 12-485A Attention:
{{#Wiki_filter:Dominion Nuclear Connecticut, Inc.               AUG   cO eDominion 2821 Millstone Power Station                           A Rope Ferry Road Waterford, CT 06385 U.S. Nuclear Regulatory Commission                                   Serial No. 12-485A Attention: Document Control Desk                                     NSS&L/MLC     RO Washington, DC 20555                                                 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 CORRECTION TO PROPOSED TECHNICAL SPECIFICATIONS TO ADOPT TSTF-510 In a letter dated July 31, 2012 (Serial No. 12-485), Dominion Nuclear Connecticut, Inc.(DNC) submitted a license amendment request for Facility Operating License NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed amendment would modify technical specification (TS) requirements regarding steam generator tube inspections and reporting as described in Technical Specifications Task Force (TSTF) Traveler TSTF-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection." After submittal, an error in Attachment 2, "Marked-up Technical Specification Changes," was identified.
MILLSTONE POWER STATION UNIT 3 CORRECTION TO PROPOSED TECHNICAL SPECIFICATIONS TO ADOPT TSTF-510 In a letter dated July 31, 2012 (Serial No. 12-485), Dominion Nuclear Connecticut, Inc.
Specifically, the error involves omission of the word "percentage" in the newly proposed text for TS 6.9.1.7f.
(DNC) submitted a license amendment request for Facility Operating License NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed amendment would modify technical specification (TS) requirements regarding steam generator tube inspections and reporting as described in Technical Specifications Task Force (TSTF) Traveler TSTF-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."
which appears on Page 6-21. To correct this error, a new marked-up TS Page 6-21 is being resubmitted as Attachment 1 to this letter.If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687.Sincerely, Vice President  
After submittal,         an error in Attachment 2, "Marked-up Technical Specification Changes,"
-Nuclear Engineering STATE OF CONNECTICUT  
was identified.         Specifically, the error involves omission of the word "percentage" in the newly proposed         text for TS 6.9.1.7f. which appears on Page 6-21. To correct this error, a new marked-up           TS Page 6-21 is being resubmitted as Attachment 1 to this letter.
)) P COUNTY OF NEW LONDON )The foregoing document was acknowledged before me, in and for the County and State aforesaid, today by J. Alan Price, who is Vice President  
If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687.
-Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.Acknowledged before me this 2Z day of " 2012.My Commission Expires: ., .WM. E. BROWN Nota ublic NOTARYPPUBUC Notalr MY COMMISION EXPIRES MAR. 31,2016 Serial No. 12-485A Docket No. 50-423 Correction to TSTF-51 0 Submittal Page 2 of 2  
Sincerely, Vice President - Nuclear Engineering STATE OF CONNECTICUT                                   )
                                                        )                                       P COUNTY OF NEW LONDON                                   )
The foregoing document was acknowledged before me, in and for the County and State aforesaid, today by J. Alan Price, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 2Z                 day of       "     2012.
My Commission Expires:             .*    . ,                   .
WM. E. BROWN                                 Nota Notalr ublic NOTARYPPUBUC MY COMMISION EXPIRES MAR. 31,2016
 
Serial No. 12-485A Docket No. 50-423 Correction to TSTF-51 0 Submittal Page 2 of 2


==Attachment:==
==Attachment:==
: 1. Marked-Up Technical Specification Page 6-21 Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 J. S. Kim NRC Project Manager, Mail Stop 08 C2A U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No. 12-485A Docket No. 50-423 ATTACHMENT 1 MARKED-UP TECHNICAL SPECIFICATION PAGE 6-21 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 OctlubA7,21 ADMINISTRATIVE CONTROLS 6.9.1.6.c The core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.6.9.1.6.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
: 1. Marked-Up Technical Specification Page 6-21 Commitments made in this letter: None cc:   U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 J. S. Kim NRC Project Manager, Mail Stop 08 C2A U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
STEAM GENERATOR TUBE INSPECTION REPORT 6.9.1.7 A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with TS 6.8.4.g, Steam Generator (SG)Program. The report shall include: a. The scope of inspections performed on each SQ b. Aet,*&Agradation mechanisms found, c. Nondestructive examination techniques utilized for each degradation mechanism, d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, e. Number of tubes plugged during the inspection outage for each a.,i.edegradation mechanism, f. Te nsulbts gd ditomontag,0___
 
including te, g. e results of condition monitoring, including the results of tube pulls and in-situ\te ing, Sýý, During efueling Outage 14 and the subsequent operating cycle, the primary to seconda LEAKAGE rate observed in each SG (if it is not practical to assign the LEAKAG to an individual SG, the entire primary to secondary LEAKAGE should be c nservatively assumed to be from one SG) during the cycle preceding the inspectio which is the subject of the report, STONE -UNIT 3 6-21 Amendment No. -24, 40, -9, 69, 1-04, 4... --24 -24 , 29,- 2 9 24 ,249.---MILL The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator}}
Serial No. 12-485A Docket No. 50-423 ATTACHMENT 1 MARKED-UP TECHNICAL SPECIFICATION PAGE 6-21 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
 
OctlubA7,21 ADMINISTRATIVE CONTROLS 6.9.1.6.c The core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.
6.9.1.6.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
STEAM GENERATOR TUBE INSPECTION REPORT 6.9.1.7 A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with TS 6.8.4.g, Steam Generator (SG)
Program. The report shall include:
: a. The scope of inspections performed on each SQ
: b. Aet,*&Agradation mechanisms found,
: c. Nondestructive examination techniques utilized for each degradation mechanism,
: d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
: e. Number of tubes plugged during the inspection outage for each a.,i.edegradation mechanism,
: f. Te nsulbts     gd ditomontag,0___     including   te,
: g.       e results of condition monitoring, including the results of tube pulls and in-situ
                      \te ing, Sýý,   During efueling Outage 14 and the subsequent operating cycle, the primary to seconda LEAKAGE rate observed in each SG (if it is not practical to assign the LEAKAG to an individual SG, the entire primary to secondary LEAKAGE should be c nservatively assumed to be from one SG) during the cycle preceding the inspectio which is the subject of the report, MILL STONE - UNIT 3                         6-21               Amendment No. -24,40, -9, 69, 1-04, 4...
                                                                    -     24 , 29,-2 9 24 ,249.---
The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator}}

Latest revision as of 22:57, 11 November 2019

Correction to Proposed Technical Specifications to Adopt TSTF-510
ML12250A664
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/28/2012
From: Price J
Dominion, Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
12-485A
Download: ML12250A664 (4)
v • d • e


Text

Dominion Nuclear Connecticut, Inc. AUG cO eDominion 2821 Millstone Power Station A Rope Ferry Road Waterford, CT 06385 U.S. Nuclear Regulatory Commission Serial No. 12-485A Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 CORRECTION TO PROPOSED TECHNICAL SPECIFICATIONS TO ADOPT TSTF-510 In a letter dated July 31, 2012 (Serial No.12-485), Dominion Nuclear Connecticut, Inc.

(DNC) submitted a license amendment request for Facility Operating License NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed amendment would modify technical specification (TS) requirements regarding steam generator tube inspections and reporting as described in Technical Specifications Task Force (TSTF) Traveler TSTF-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."

After submittal, an error in Attachment 2, "Marked-up Technical Specification Changes,"

was identified. Specifically, the error involves omission of the word "percentage" in the newly proposed text for TS 6.9.1.7f. which appears on Page 6-21. To correct this error, a new marked-up TS Page 6-21 is being resubmitted as Attachment 1 to this letter.

If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687.

Sincerely, Vice President - Nuclear Engineering STATE OF CONNECTICUT )

) P COUNTY OF NEW LONDON )

The foregoing document was acknowledged before me, in and for the County and State aforesaid, today by J. Alan Price, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this 2Z day of " 2012.

My Commission Expires: .* . , .

WM. E. BROWN Nota Notalr ublic NOTARYPPUBUC MY COMMISION EXPIRES MAR. 31,2016

Serial No. 12-485A Docket No. 50-423 Correction to TSTF-51 0 Submittal Page 2 of 2

Attachment:

1. Marked-Up Technical Specification Page 6-21 Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 J. S. Kim NRC Project Manager, Mail Stop 08 C2A U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127

Serial No. 12-485A Docket No. 50-423 ATTACHMENT 1 MARKED-UP TECHNICAL SPECIFICATION PAGE 6-21 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

OctlubA7,21 ADMINISTRATIVE CONTROLS 6.9.1.6.c The core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.6.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

STEAM GENERATOR TUBE INSPECTION REPORT 6.9.1.7 A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with TS 6.8.4.g, Steam Generator (SG)

Program. The report shall include:

a. The scope of inspections performed on each SQ
b. Aet,*&Agradation mechanisms found,
c. Nondestructive examination techniques utilized for each degradation mechanism,
d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
e. Number of tubes plugged during the inspection outage for each a.,i.edegradation mechanism,
f. Te nsulbts gd ditomontag,0___ including te,
g. e results of condition monitoring, including the results of tube pulls and in-situ

\te ing, Sýý, During efueling Outage 14 and the subsequent operating cycle, the primary to seconda LEAKAGE rate observed in each SG (if it is not practical to assign the LEAKAG to an individual SG, the entire primary to secondary LEAKAGE should be c nservatively assumed to be from one SG) during the cycle preceding the inspectio which is the subject of the report, MILL STONE - UNIT 3 6-21 Amendment No. -24,40, -9, 69, 1-04, 4...

- 24 , 29,-2 9 24 ,249.---

The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator

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