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| number = ML14252A556
| number = ML14252A556
| issue date = 09/08/2014
| issue date = 09/08/2014
| title = Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank, and Surveillance Requirement SR 4.6.2.1a
| title = NRR E-mail Capture - Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank, and Surveillance Requirement SR 4.6.2.1a
| author name = Thadani M
| author name = Thadani M
| author affiliation = NRC/NRR/DORL/LPLI-1
| author affiliation = NRC/NRR/DORL/LPLI-1
| addressee name = Craft W D
| addressee name = Craft W
| addressee affiliation = Dominion Energy Co
| addressee affiliation = Dominion Energy Co
| docket = 05000423
| docket = 05000423
Line 12: Line 12:
| document type = E-Mail
| document type = E-Mail
| page count = 4
| page count = 4
| project =
| stage = RAI
}}
}}


=Text=
=Text=
{{#Wiki_filter:1 NRR-PMDAPEm Resource From: Thadani, Mohan Sent: Monday, September 08, 2014 2:10 PM To: Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)
{{#Wiki_filter:NRR-PMDAPEm Resource From:                       Thadani, Mohan Sent:                       Monday, September 08, 2014 2:10 PM To:                         Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)
Cc: Dennig, Robert; Sallman, Ahsan
Cc:                         Dennig, Robert; Sallman, Ahsan


==Subject:==
==Subject:==
Millstone 3-Request for Additional Informati on: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a.
Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a.
Wanda: The NRC staff has reviewed the Dominion Nuclear Connecticut Inc. (the licensee's) request in support of establishing additional margin for controlling the Refueling Water Storage TANK temperature. The NRC staff has determined that additional information is needed to facilitate timely completion of NRC's review of the licensee's request.  
Wanda:
The NRC staff has reviewed the Dominion Nuclear Connecticut Inc. (the licensees) request in support of establishing additional margin for controlling the Refueling Water Storage TANK temperature. The NRC staff has determined that additional information is needed to facilitate timely completion of NRCs review of the licensees request.
Please provide your response to the request for additional information, pasted below, within 30 days from the date of this request for additional information, so that the NRC staff can respond to the licensees request.
Best regards, Mohan C Thadani Senior Project Manager Millstone, Ginna, and Constellation Fleet Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov REQUEST FOR ADDITIONAL INFORMATION By CONTAINMENT AND VENTILATION BRANCH TECHNICAL SPECIFICATION CHANGES FOR THE REFUELING WATER STORAGE TANK TEMPERATURE MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423 By letter dated November 6, 2013 (Reference 1), pursuant to Section 50.90 of the Title 10 of the Code of Federal Regulations, Dominion Nuclear Connecticut, Inc. requested an amendment to Operating License Numbers NPF-49 in the form of changes to the Technical Specifications (TSs) for Millstone Power Station Unit 3 (MPS3).
The proposed change would revise TS 3.5.4, "Refueling Water Storage Tank," and Surveillance Requirement (SR) 4.6.2.1a).2 for providing additional operational margin for controlling the Refueling Water Storage Tank (RWST) temperature.
The Containment and Ventilation Branch (SCVB) staff has reviewed licensees information supporting the proposed amendment and is requesting responses to the following items to complete its review:
1


Please provide your response to the request for additional information, pasted below, within 30 days from the date of this request for additional information, so that the NRC staff can respond to the licensee's request.
SCVB-RAI-1 Reference 1, Section 3.2, last sentence of last paragraph:
 
While not using 100oF, subsequent analyses have been performed which continue to bound the RWST maximum temperature of 73oF proposed herein.
Best regards,' 
Please provide responses to the following:
 
: a. Does the subsequent analyses replace the licensing basis containment analysis for the Stretch Power Uprate (SPU) in Reference 3? Is the subsequent analysis the current Analysis of Record (AOR) in the current Final Safety Analysis Report (FSAR)? Provide reasons for performing this analysis.
Mohan C Thadani Senior Project Manager Millstone, Ginna, and Constellation Fleet Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476      Mohan.Thadani@nrc.gov
_______________________________________________________________________________________
___________________________________________________________
REQUEST FOR ADDITIONAL INFORMATION By CONTAINMENT AND VENTILATION BRANCH TECHNICAL SPECIFICATION CHANGES FOR THE REFUELING WATER STORAGE TANK TEMPERATURE MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423 By letter dated November 6, 2013 (Reference 1), pursuant to Section 50.90 of the Title 10 of the Code of Federal Regulations, Dominion Nuclear Connecticut, Inc. requested an amendment to Operating License Numbers NPF-49 in the form of changes to the Technical Specifications (TSs) for Millstone Power Station Unit 3 (MPS3).
The proposed change would revise TS 3.5.4, "Refueling Water Storage Tank," and Surveillance Requirement (SR) 4.6.2.1a).2 for providing additional operational margin for controlling the Refueling Water Storage Tank (RWST) temperature.
 
The Containment and Ventilation Branch (SCVB) staff has reviewed licensee's information supporting the proposed amendment and is requesting responses to the following items to complete its review:
 
2 SCVB-RAI-1
 
Reference 1, Section 3.2, last sentence of last paragraph:
"While not using 100 oF, subsequent analyses have been performed which continue to bound the RWST maximum temperature of 73 oF proposed herein."
 
Please provide responses to the following: a. Does the "subsequent analyses" replace the licensing basis containment analysis for the Stretch Power Uprate (SPU) in Reference 3? Is the subsequent analysis the current Analysis of Record (AOR) in the current Final Safety Analysis Report (FSAR)? Provide reasons for performing this analysis.  
: b. Provide the values of other input parameters and assumptions that have been revised from the SPU Mass and Energy (M&E) release and containment response analyses to the AOR in the current FSAR which is the proposed basis for changes in the RWST temperatures. Justify the differences between the input parameters and assumptions.
: b. Provide the values of other input parameters and assumptions that have been revised from the SPU Mass and Energy (M&E) release and containment response analyses to the AOR in the current FSAR which is the proposed basis for changes in the RWST temperatures. Justify the differences between the input parameters and assumptions.
SCVB-RAI-2
SCVB-RAI-2 The LOCA containment M&E release analysis documented in the SPU application (References 2 and 3) was not based on the presently corrected versions of the computer codes in WCAP-10325-P-A (Reference 4) methodology. Westinghouse has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2 reporting errors in the WCAP-10325-P-A methodology and requires containment analyses should be corrected. These specific NSALs have been addressed by other licensees in recent LARs. Describe changes in the following containment analyses results using the corrected Reference 4 methodology that incorporates corrections listed in the above NSALs, together with the revised RWST temperatures: (a) containment peak pressure, (b) containment peak gas temperature for Environment Equipment Qualification (EEQ), (c) containment peak wall temperature, (d) containment sump peak water temperature, (e) pump Net Positive Suction Head Available (NPSHA) for the pumps that draw water from the containment sump during recirculation mode of safety injection and containment cooling, and (f) containment minimum pressure analysis for Emergency Core Cooling System (ECCS) performance capability.
 
REFERENCES
The LOCA containment M&E release analysis documented in the SPU application (References 2 and 3) was not based on the presently corrected versions of the computer codes in WCAP-10325-P-A (Reference 4) methodology. Westinghouse has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2 reporting errors in the WCAP-10325-P-A methodology and requires containment analyses should be corrected. These specific NSAL s have been addressed by other licensees in recent LARs. Describe changes in the following containment analyses results using the corrected Reference 4 methodology that incorporates corrections listed in the above NSALs, together with the revised RWST temperatures: (a) containment peak pressure, (b) containment peak gas temperature for Environment Equipment Qualification (EEQ), (c) containment peak wall temperature, (d) containment sump peak water temperature, (e) pump Net Positive Suction Head Available (NPSHA) for the pumps that draw water from the containment sump during recirculation mode of safety injection and containment cooling, and (f) containment minimum pressure analysis for Emergency Core Cooling System (ECCS) performance capability. REFERENCES
: 1.       Letter from Dominion to NRC dated November 6, 2013, Dominion Nuclear Connecticut, Inc. Millstone Power Station Unit 3, Licensee Amendment Request, Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures, (ADAMS Accession Number ML13322A415)
: 1. Letter from Dominion to NRC dated November 6, 2013, "Dominion Nuclear Connecticut, Inc. Millstone Power Station Unit 3, Licensee Amendment Request, Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures", (ADAMS Accession Number ML13322A415)  
: 2.       Letter from Dominion to NRC, "Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate," dated July 13, 2007, (ADAMS Accession Number ML072000386)
: 2. Letter from Dominion to NRC, "Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate," dated July 13, 2007, (ADAMS Accession Number ML072000386)
: 3.       NRC letter to Dominion dated August 12, 2008, "Millstone Power Station, Unit No. 3, Issuance of Amendment RE: Stretch Power Uprate (TAC No. MD6070), (ADAMS Accession Number ML081610585)
: 3. NRC letter to Dominion dated August 12, 2008, "Millstone Power Station, Unit No. 3, Issuance of Amendment RE: Stretch Power Uprate (TAC No. MD6070)," (ADAMS Accession Number  
: 4.       WCAP-10325-P-A, May 1983 (Proprietary) and WCAP-10326-A (Nonproprietary), Westinghouse LOCA Mass and Energy Release Model for Containment Design, March 1979.
 
Mohan C Thadani 2
ML081610585)  
: 4. WCAP-10325-P-A, May 1983 (Proprietary) and WCAP-10326-A (Nonproprietary), "Westinghouse LOCA Mass and Energy Release Model for Containment Design, March 1979."


Mohan C Thadani 3Senior Project Manager Millstone, Ginna, and Constellation Fleet Plants Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476     Mohan.Thadani@nrc.gov
Senior Project Manager Millstone, Ginna, and Constellation Fleet Plants Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov 3


Hearing Identifier: NRR_PMDA Email Number: 1554   Mail Envelope Properties   (Mohan.Thadani@nrc.gov20140908140900)
Hearing Identifier:   NRR_PMDA Email Number:         1554 Mail Envelope Properties     (Mohan.Thadani@nrc.gov20140908140900)


==Subject:==
==Subject:==
Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a. Sent Date:   9/8/2014 2:09:55 PM Received Date: 9/8/2014 2:09:00 PM From:   Thadani, Mohan Created By:   Mohan.Thadani@nrc.gov Recipients:     "Dennig, Robert" <Robert.Dennig@nrc.gov> Tracking Status: None "Sallman, Ahsan" <Ahsan.Sallman@nrc.gov> Tracking Status: None "Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)" <wanda.d.craft@dom.com> Tracking Status: None Post Office:     Files     Size     Date & Time MESSAGE   5437     9/8/2014 2:09:00 PM
Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4
 
,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a.
Options Priority:     Standard   Return Notification:   No   Reply Requested:   No   Sensitivity:     Normal Expiration Date:     Recipients Received:}}
Sent Date:             9/8/2014 2:09:55 PM Received Date:         9/8/2014 2:09:00 PM From:                 Thadani, Mohan Created By:           Mohan.Thadani@nrc.gov Recipients:
"Dennig, Robert" <Robert.Dennig@nrc.gov>
Tracking Status: None "Sallman, Ahsan" <Ahsan.Sallman@nrc.gov>
Tracking Status: None "Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)" <wanda.d.craft@dom.com>
Tracking Status: None Post Office:
Files                         Size                       Date & Time MESSAGE                       5437                       9/8/2014 2:09:00 PM Options Priority:                     Standard Return Notification:           No Reply Requested:               No Sensitivity:                   Normal Expiration Date:
Recipients Received:}}

Latest revision as of 17:46, 5 February 2020

NRR E-mail Capture - Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank, and Surveillance Requirement SR 4.6.2.1a
ML14252A556
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/08/2014
From: Thadani M
Plant Licensing Branch 1
To: Craft W
Dominion Energy Co
References
Download: ML14252A556 (4)
v • d • e


Text

NRR-PMDAPEm Resource From: Thadani, Mohan Sent: Monday, September 08, 2014 2:10 PM To: Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)

Cc: Dennig, Robert; Sallman, Ahsan

Subject:

Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a.

Wanda:

The NRC staff has reviewed the Dominion Nuclear Connecticut Inc. (the licensees) request in support of establishing additional margin for controlling the Refueling Water Storage TANK temperature. The NRC staff has determined that additional information is needed to facilitate timely completion of NRCs review of the licensees request.

Please provide your response to the request for additional information, pasted below, within 30 days from the date of this request for additional information, so that the NRC staff can respond to the licensees request.

Best regards, Mohan C Thadani Senior Project Manager Millstone, Ginna, and Constellation Fleet Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov REQUEST FOR ADDITIONAL INFORMATION By CONTAINMENT AND VENTILATION BRANCH TECHNICAL SPECIFICATION CHANGES FOR THE REFUELING WATER STORAGE TANK TEMPERATURE MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423 By letter dated November 6, 2013 (Reference 1), pursuant to Section 50.90 of the Title 10 of the Code of Federal Regulations, Dominion Nuclear Connecticut, Inc. requested an amendment to Operating License Numbers NPF-49 in the form of changes to the Technical Specifications (TSs) for Millstone Power Station Unit 3 (MPS3).

The proposed change would revise TS 3.5.4, "Refueling Water Storage Tank," and Surveillance Requirement (SR) 4.6.2.1a).2 for providing additional operational margin for controlling the Refueling Water Storage Tank (RWST) temperature.

The Containment and Ventilation Branch (SCVB) staff has reviewed licensees information supporting the proposed amendment and is requesting responses to the following items to complete its review:

1

SCVB-RAI-1 Reference 1, Section 3.2, last sentence of last paragraph:

While not using 100oF, subsequent analyses have been performed which continue to bound the RWST maximum temperature of 73oF proposed herein.

Please provide responses to the following:

a. Does the subsequent analyses replace the licensing basis containment analysis for the Stretch Power Uprate (SPU) in Reference 3? Is the subsequent analysis the current Analysis of Record (AOR) in the current Final Safety Analysis Report (FSAR)? Provide reasons for performing this analysis.
b. Provide the values of other input parameters and assumptions that have been revised from the SPU Mass and Energy (M&E) release and containment response analyses to the AOR in the current FSAR which is the proposed basis for changes in the RWST temperatures. Justify the differences between the input parameters and assumptions.

SCVB-RAI-2 The LOCA containment M&E release analysis documented in the SPU application (References 2 and 3) was not based on the presently corrected versions of the computer codes in WCAP-10325-P-A (Reference 4) methodology. Westinghouse has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2 reporting errors in the WCAP-10325-P-A methodology and requires containment analyses should be corrected. These specific NSALs have been addressed by other licensees in recent LARs. Describe changes in the following containment analyses results using the corrected Reference 4 methodology that incorporates corrections listed in the above NSALs, together with the revised RWST temperatures: (a) containment peak pressure, (b) containment peak gas temperature for Environment Equipment Qualification (EEQ), (c) containment peak wall temperature, (d) containment sump peak water temperature, (e) pump Net Positive Suction Head Available (NPSHA) for the pumps that draw water from the containment sump during recirculation mode of safety injection and containment cooling, and (f) containment minimum pressure analysis for Emergency Core Cooling System (ECCS) performance capability.

REFERENCES

1. Letter from Dominion to NRC dated November 6, 2013, Dominion Nuclear Connecticut, Inc. Millstone Power Station Unit 3, Licensee Amendment Request, Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures, (ADAMS Accession Number ML13322A415)
2. Letter from Dominion to NRC, "Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate," dated July 13, 2007, (ADAMS Accession Number ML072000386)
3. NRC letter to Dominion dated August 12, 2008, "Millstone Power Station, Unit No. 3, Issuance of Amendment RE: Stretch Power Uprate (TAC No. MD6070), (ADAMS Accession Number ML081610585)
4. WCAP-10325-P-A, May 1983 (Proprietary) and WCAP-10326-A (Nonproprietary), Westinghouse LOCA Mass and Energy Release Model for Containment Design, March 1979.

Mohan C Thadani 2

Senior Project Manager Millstone, Ginna, and Constellation Fleet Plants Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov 3

Hearing Identifier: NRR_PMDA Email Number: 1554 Mail Envelope Properties (Mohan.Thadani@nrc.gov20140908140900)

Subject:

Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4

,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a.

Sent Date: 9/8/2014 2:09:55 PM Received Date: 9/8/2014 2:09:00 PM From: Thadani, Mohan Created By: Mohan.Thadani@nrc.gov Recipients:

"Dennig, Robert" <Robert.Dennig@nrc.gov>

Tracking Status: None "Sallman, Ahsan" <Ahsan.Sallman@nrc.gov>

Tracking Status: None "Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)" <wanda.d.craft@dom.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 5437 9/8/2014 2:09:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

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