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Vogtle Units 1 & 2 - Page Numbering Scheme Clarification for License Amendment Request for Adoption of TSTF-425-A, Rev. 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controll
	ML110070455
Person / Time
Site:	Vogtle
Issue date:	01/07/2011
From:	Ajluni M J; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-10-2375, TSTF-425-A, Rev 3
	Download: ML110070455 (37)
	v • d • e

Mark J. Ajluni, P.E. Southern Nuclear Nuclear Director Operating Company, Inc. 40 Inverness Center Parkway Post Offi ce Box 1295 Birmingham, Alabama 35201 Tel Fax January 7, 2011 SOUTHERN'\

COMPANY Docket 50-424 U. S. Nuclear Regulatory A TIN: Document Control Washington, D. C.

Vogtle Electric Generating Plant, Units 1 and Page Numbering Scheme Clarification for License Amendment Request Adoption of TSTF-425-A, Rev. 3, Risk-Informed Justification for the Relocation Specific Surveillance Frequency Requirements to a Licensee Controlled Ladies and Gentlemen:

By letter dated March 31,2006, the Nuclear Regulatory Commission issued Amendment No. 120 which revised Vogtle Electric Generating Plant, Unit 2 Technical Specification (TS) section 3.7.6, "Condensate Storage Tank (CST)," to require two CSTs to be OPERABLE and to increase the combined safety-related minimum volume. The amendment also revised Surveillance Requirement 3.7.6 to reflect the additional limit for CST volume. As a result of Amendment No. 120, VEGP TS section 3.7.6 currently includes two pages with identical page numbers; page 3.7.6-1 for Unit 1 and page 3.7.6-1 for Unit 2. On June 15, 2010, Southern Nuclear Operating Company (SNC) submitted a license amendment request to modify the VEGP TSs by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, Revision 1 "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." This amendment request included revisions to VEGP TS page 3.7.6-1 for Unit 1 and TS page 3.7.6-1 for Unit 2. To clarify the page numbering scheme described above, SNC is submitting revised TS marked-up and clean typed pages, attached in Enclosures 1 and 2, respectively, for VEGP Unit 1 (TS page 3.7.6-1) and Unit 2 (TS page 3.7.6-2).

By letter dated January 29, 1999, the Nuclear Regulatory Commission issued Amendment Nos. 105 and 83 for VEGP Units 1 and 2, respectively, which revised LCO 3.7.6 by deleting the words "Redundant CSTs" from the title and deleting LCO 3.7.6a. However, the Table of Contents page containing the reference to LCO page 3.7.6a-1 was not updated. SNC is submitting a marked-up and a clean typed page correcting the Table of Contents for the Technical Specifications for VEGP Units 1 and 2 (Enclosure 3).

U. S. Nuclear Regulatory Page Mr. M. J. Ajluni states he is Nuclear Licensing Director of Southern Operating Company, is authorized to execute this oath on behalf of Nuclear Operating Company and to the best of his knowledge and belief, facts set forth in this letter are This letter contains no NRC commitments.

If you have any questions, contact Jack Stringfellow at (205)

Respectfully submitted, M. J. Nuclear Licensing cribed before me this Z+t-day of , 2011. My commission expires: ) I-;;2 -<<U( '3 MJAlSY Alemm .

Enclosures:

Revised Marked-up Pages -VEGP TS page 3.7.6-1 for Unit 1 and TS page 3.7.6-2 for Unit 2 Revised Clean Typed Pages -VEGP TS page 3.7.6-1 for Unit 1 and TS page 3.7.6-2 for Unit 2 Marked-up and Clean Typed VEGP TS Table of Contents Page Containing a Reference to TS Page 3.7.6a-1 Southern Nuclear Operating Mr. J. T. Gasser, Executive Vice Mr. T. E. Tynan, Vice President

-Ms. P. M. Marino, Vice President

-

RType: U. S. Nuclear Regulatory Mr. L. A. Reyes, Regional Mr. R. E. Martin, NRR Project Manager -Mr. M. Cain, Senior Resident Inspector

-Mr. P.G. Boyle, NRR Project State of Mr. Allen Barnes-Environmental Director Protection VogtJe Electric Generating Plant, Units 1 and 2 Page Numbering Scheme Clarification for License Amendment Request Adoption of TSTF-425-A, Rev. 3, Risk-Informed Justification for the Relocation Specific Surveillance Frequency Requirements to a Licensee Controlled Enclosure Revised Marked-up Pages -VEGP TS page 3.7.6-1 for Unit 1 and TS page 3.7.6-2 for Unit 2 3.7.6 THIS PAGE APPLICABLE TO UNIT 1 ONLY 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST) LCO One CST shall be OPERABLE with a safety-related volume ;::: 340,000 gallons.

MODES 1, 2, and 3, ACTIONS REQUIRED ACTION COMPLETION TIME CST volume not within A.1 Align Auxiliary Feedwater 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pumps to Required Action and B.1 Be in MODE 3. 6 associated Time not met. B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS FREQUENCY 3.7.6.1 Verify the CST volume is within limit. 112

..........--

In accordance with Surveillance Control Vogtle 1 3.7.6-1 Amendment No. (Unit 1) V\,mendment No. (Unit 3.7.6 THIS PAGE APPLICABLE TO UNIT 2 ONLY PLANT 3.7.6 Condensate Storage Tank LCO 3.7.6 Two CSTs shall be OPERABLE A combined safety-related volume of 378,000 gallons; and The CST aligned to supply the auxiliary feedwater pumps shall have a safety-related volume 340,000 gallons. APPLICABILITY:

MODES 1, 2, and 3, ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME CST volume(s) not A.1 Restore volume( s) to 2 within limit(s).

within Required Action and B.1 Be in MODE 3. 6 associated Time not met. B.2 Be in MODE4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify CST volumes within ,.112 houFSj In accordance with Surveillance Control Vogtle UnitlS 1 and 3.7.6-@ Amendment No. (Unit 2)

Vogtle Electric Generating Plant, Units 1 and Page Numbering Scheme Clarification for License Amendment Request Adoption of TSTF-42S-A, Rev. 3, Risk-Informed Justification for the Relocation Specific Surveillance Frequency Requirements to a Licensee Controlled Enclosure Revised Clean Typed Pages -VEGP TS page 3.7.6-1 for Unit 1 TS page 3.7.6-2 for Unit CST 3.7.6 THIS PAGE APPLICABLE TO UNIT 1 ONLY 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST) LCO One CST shall be OPERABLE with a safety-related volume ;::: 340,000 gallons.

MODES 1, 2, and 3, ACTIONS REQUIRED ACTION COMPLETION TIME CST volume not within A.1 Align Auxiliary Feedwater 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pumps to Required Action and B.1 Be in MODE 3. 6 associated Time not met. B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS FREQUENCY SR 3.7.6.1 Verify the CST volume is within I n accordance the Frequency Vogtle Unit 3.7.6-1 Amendment No. (Unit 1)

CST 3.7.6 THIS PAGE APPLICABLE TO UNIT 2 ONLY 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank LCO 3.7.6 Two CSTs shall be OPERABLE A combined safety-related volume of;;:: 378,000 gallons; and The CST aligned to supply the auxiliary feedwater pumps shall have a safety-related volume;;::

340,000 gallons. APPLICABILITY:

MODES 1, 2, and 3, ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME CST volume(s) not A.1 Restore volume( s) to 2 within limit(s).

within Required Action and B.1 Be in MODE 3. 6 associated Time not met. B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS FREQUENCY SR 3.7.6.1 Verify CST volumes within In accordance the Frequency Vogtle Unit 3.7.6-2 Amendment No. (Unit 2)

Vogtle Electric Generating Plant, Units 1 and 2 Page Numbering Scheme Clarification for License Amendment Request Adoption of Rev. 3, Risk-Informed Justification for the Relocation Specific Surveillance Frequency Requirements to a Licensee Controlled Enclosure Marked-up and Clean Typed VEGP TS Table of Contents Page Containing Reference to TS Page TABLE OF 3.6.1 3.6.2 3.6.3 3.6.4 3.6.5 3.6.6 3.6.7 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 Delete 3.7.6 3.7.7 3.7.8 3.7.9 3.7.10 3.7.11 3.7.12 3.7.13 3.7.14 3.7.15 3.7.16 3.7.17 3.7.18 CONTAINMENT SySTEMS................................................................... Containment....

........ ...... ...... ...... ...... ...... ............

...... ........ .... ...... .... .... ..... Containment Air Locks ........................................................................... Containment Isolation Valves ................................................................. Containment Pressure............................................................................ Containment Air Temperature

................................................................ Containment Spray and Cooling Systems.............................................. Hydrogen Recombiners...................

..............

......................................... 3.6.7-1 PLANT SYSTEMS ................................................................................. Main Steam Safety Valves (MSSVs)......................................................

3.7.1-1 Main Steam Isolation Valves (MSIVs) ....................................................

3.7.2-1 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves ................................................................................

3.7.3-1 Atmospheric Relief Valves (ARVs).........................................................

3.7.4-1 Auxiliary Feedwater (AFW) System........................................................

3.7.5-1 Condensate Stora e Tank CST -Redundant CSTs ..........................

3.7.6-1 Component Cooling Water (CCW) System ............................................

3.7.7-1 Nuclear Service Cooling Water (NSCW) System ...................................

3.7.8-1 Ultimate Heat Sink (UHS).......................................................................

3.7.9-1 Control Room Emergency Filtration System (CREFS) -Both Units Operating...............................................................................

3.7.10-1 Control Room Emergency Filtration System (CREFS) -One Unit Operating

................................................................................

3.7.11-1 Control Room Emergency Filtration System (CREFS) -Both Units Shutdown ..............................................................................

3.7.12-1 Piping Penetration Area Filtration and Exhaust System (PPAFES) ..........................................................................

3.7.13-1 Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System........................................................

3.7.14-1 Fuel Storage Pool Water Level...............................................................

3.7.15-1 Secondary Specific Activity ....................................................................

3.7.16-1 Fuel Storage Pool Boron Concentration

.................................................

3.7.17-1 Fuel Assembly Storage in the Fuel Storage Pool...................................

3.7.18-1 (continued)

Vogtle Units 1 and 2 iii Amendment No. (Unit 1) Amendment No. (Unit 2)

TABLE OF CONTAINMENT SySTEMS...................................................................

3.6.1-1 3.6.1 Containment

....................................

..................................

..............

....... 3.6.1-1 3.6.2 Containment Air Locks ...........................................................................

3.6.2-1 3.6.3 Containment Isolation Valves ..........

.... ..........

........ ...... ........ ...... .............

3.6.3-1 3.6.4 Containment Pressure............................................................................

3.6.4-1 3.6.5 Containment Air Temperature

................................................................

3.6.5-1 3.6.6 Containment Spray and Cooling Systems..............................................

3.6.6-1 3.6.7 Deleted ..................................................................................................

3.6.7-1 3.7 PLANT SYSTEMS .................................................................................

3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) ......................................................

3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ....................................................

3.7.2-1 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves ................................................................................

3.7.3-1 3.7.4 Atmospheric Relief Valves (ARVs) .........................................................

3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System........................................................

3.7.5-1 3.7.6 Condensate Storage Tank (CST) -(Redundant CSTs)..........................

3.7.6-1 3.7.7 Component Cooling Water (CCW) System ............................................

3.7.7-1 3.7.8 Nuclear Service Cooling Water (NSCW) System...................................

3.7.8-1 3.7.9 Ultimate Heat Sink (UHS).......................................................................

3.7.9-1 3.7.10 Control Room Emergency Filtration System (CREFS) -Both Units Operating...............................................................................

3.7.10-1 3.7.11 Control Room Emergency Filtration System (CREFS) -One Unit Operating

................................................................................

3.7.11-1 3.7.12 Control Room Emergency Filtration System (CREFS) -Both Units Shutdown ..............................................................................

3.7.12-1 3.7.13 Piping Penetration Area Filtration and Exhaust System (PPAFES) ..........................................................................

3.7.13-1 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System.. .........

.... ........ ...... .... ....

...... .... ....

..... 3.7.14-1 3.7.15 Fuel Storage Pool Water Level...............................................................

3.7.15-1 3.7.16 Secondary Specific Activity ....................................................................

3.7.16-1 3.7.17 Fuel Storage Pool Boron Concentration.................................................

3.7.17-1 3.7.18 Fuel Assembly Storage in the Fuel Storage Pool...................................

3.7.18-1 (continued)

Vogtle Units 1 and 2 iii Amendment No. (Unit 1) Amendment No. (Unit 2)

Southern Nuclear Operating Company Nuclear NL-006-F03 SOUTHERN A Licensing Licensing Action and Concurrence Version 1.0 COMPANY e1U1'f.]t1JS,rrw Yp*r Page 1 of 6 NL Letter Due Date (if applicable):

Hya1l29H}..-thf;;L (5 U Y1r:, -,II

Subject:

Vogtle Elecmc Generating Plant, Units 1 and 2Page Numbering Scheme Clarification for l License Amendment Request for Adoption of TSTF-425-A, Rev. 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program RLE I Extension:

Stephanie Agee x7556 SEC"nON I -CORRESPONDENCE SCREENING (to be completed by YES NO i 1.1. Does this letter affect the FSAR or any other License Basis Documents?

If YES, r;;complete 1.1.a. If unsure, obtain peer review from 10 CFR 50.59 qualified individual.

1.1.a HasSection III been completed to update each document?

rl YES rl NO r;;1.2. Does this letter require posting per 10 CFR 19? If YES, ensure posting after submittal.

1.3. Does this letter contain Safeguards Information?

If YES, do NOT scan to SNC r;;Intranet.

Enter Special Handling Instructions below and review with the AA. i Does this letter contain information to be withheld from public disclosure (e.g., Proprietary or Non-Safeguards Security-Related Information)?

If YES, do NOT scan r.;to SNC Intranet.

If Proprietary, include appropriate affidavit.

Enter Special Handling Instructions below and review with the AA. 1.5. Does this letter contain sensitive, limited access or distribution items? If YES, enter r.;Special Handling Instructions below and review with the AA. Special Handling Instructions Ciick hBre to mter tuX!j ". ",A' l, 1.6. Oath or Affirmation Required?

If YES, verify proper letter template is used. r;; r I 1.7. Verification Required?

If YES, use the guidance of NL-006-GL04.

r r;; i 1.8. Office of External Affairs and General Counsel Consultation Required?

concurrence signature in Section II. If YES, obtain r;; I 1.9. Engineering Independent Technical Review (ITR) Required?

concurrence signature in Section II. If YES, obtain rv 1.10. Challenge Board Required?

If YES, complete 1.1 O.a. rv 1.10.a HasSection III c5!npleteg to :;Jocument results? rI YES rl NO *1.11 RLE Signature:

I Date: 1.2-/./"/4) Jto. 1.12 Licensing Peer Revie"-' Date: Click fJi:Ji(! 0 i' l:>

Southern Nuclear Operating Company Nuclear Nl-006-F03 SOUTHERN A Licensing licensing Action and Concurrence Version 1.0 COMPANY Form Page 2 of 6 EMYDro,lnw Y#I"I'Wuritf 1.13 Signature:

,1..,...

Date: Office of External Affairs and General Counsel 1.14 """"Signature:

______________

........Date: __________ Independent Technical Reviewer Southern Nuclear Operating Company Nuclear NL-006-F03 SOUTHERN A. Licensing Licensing Action and Concurrence Version 1.0 COMPANY Page 3 of 6 SECTION 11-DEPARTMENTAL REVIEW NOTE: Letter concurrence and AGREEMENT to perform action{s) required to meet Commitments is performed in Section IV. The purpose of Section II is to document departmental concurrence regarding the accuracy and completeness of information provided for SNC submittals to the NRC. A concurrence signature in Section II means that the signatory has assured that the submittal is appropriate and consistent with SNC policy, applicable Commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.

Reviewer Name Statements Reference Attached (Print) Verified (list Documents Documents Reviewer numbers) (Signature)

I Date 11 I,'" \ \-/ J I V\ \ Section III -ACTION ITEMS (Obtain agreement of AI recipient before assignment)

REQUIRED RESPONSIBLE ACTION ITEM DUE DATE PRIORITY*

DEPARTMENT/MANAGER NUMBER INITIALS / / / / /

Actions to meet commitments with firm dates are Priority 4. Note in the AI that the date cannot be extended without NL Manager approval.

Actions to meet commitments with non-firm dates are Priority 5.

Southern Nuclear Operating Company Nuclear NL-006-F03 SOUTHERN A Licensing Licensing Action and Concurrence Version 1.0 COMPANY E,,"'D Y"llr Page 4 of 6 SECTION IV -FINAL REVIEW AND APPROVAL (Mark "NA" for signatures that are not required, includin / '7 I hll individual signing letter) I ? I\IL Manager or Supervisor:

Date: NL Director:

____________________

_ Date: _____ FNP Vice President:

_________________

_ Date: _____ HNP Vice President:

_________________

_ Date: _____ VEGP Vice President:

_________________

_ Date: _____ Vice President:

___________________

_ Date: ____

Vice President:

___________________

_ Date: ____Fleet Executive Vice President:

________________

_ Date: ____IV.1. Does this letter contain Commitments?

If YES, complete 1.a and 1.b. IV.1.a Has the NL Principal Licensing Engineer been notified?

rI YES rl ompleted for each Commitment?

n YES rI RLE Final Date:

Date: (-7-) f Admin (date and distribution):

Southern Nuclear Operating Company Nuclear NL-006-F03 SOUTHERN A Licensing Licensing Action and Concurrence Version 1.0 COMPANY ennvwSnwYD9rWw1J' Form Page 5 of 6 EXPLANATION OF SIGNATURES ASSOCIATED WITH NL-006-F03 PREPARER or Responsible Licensing Engineer (RLE): The individual within Licensing responsible for preparing the letter package. This individual is responsible for ensuring that necessary letter package elements are present and included and all items are properly addressed on the concurrence form. OATH & AFFIRMATION (O&A) is required for submittals that involve License Applications or Amendments per 10 CFR 50.30(b), FSAR Amendments per 10 CFR 50.71 (e)(2), or any response to NRC that the staff invokes 10 CFR 50.54(f).

Methods for O&A are discussed in Appendix C of this procedure.

VERIFICATION:

The RLE is responsible for determining whether a response requires verification in accordance with NL-006-GL04,"Guidelines for Verification of Submittals." This guideline provides details on how to assemble an appropriate Verification Package. The department that has been designated as the technical lead for developing input for the response is responsible for providing the supporting documents (objective evidence) for the verifiable statements contained in the response.

COMMITMENTS are identified, assigned as appropriate, and processed in accordance with existing individual site procedures.

If no commitments are made, the RLE should state in the cover letter that this letter made no new regulatory commitments.

POSTING REQUIREMENT for incoming and outgoing correspondence must be met in accordance with 10 CFR 19, (Le., Notices of Violation, proposed imposition of Civil Penalties, and Orders, any of which relate to radiological working conditions).

FSAR IMPACT: The RLE is responsible for determining whether the submittal involves or requires a change to the plant licensing basis and ensuring that an amendment request, if appropriate, is generated in accordance with NMP-AD-009 "Licensing Document Change Requests." OFFICE OF EXTERNAL AFFAIRS AND GENERAL COUNSEL: The RLE is required to consult with General Counsel on correspondence regarding escalated enforcement, denials of notices of violation, exemptions or exceptions to regulatory requirements or guidelines, comments on proposed legislation or rules, programmatic issues of major significance, and other items as designated by licensing management.

INDEPENDENT TECHNICAL REVIEW (ITR): The RLE is responsible for determining if Engineering ITR is required for a License Amendment or Technical Specification (TS) change (Refer to Section 6.4.9 of NL-006-003, "Outgoing NRC Correspondence," for specific process information).

If the change is covered by a design change or other qualified input, then listing the engineering document number in lieu of the ITR review is acceptable.

PEER REVIEW is a review of the correspondence package prior to issuance of the letter to NRC. Peer Reviewers use their licensing institutional knowledge and the guidance in NL-006-GL03, "Guidelines for Preparing Submittals" to ensure appropriate submittal quality. A Peer Checker's signature also means that the signatory has confirmed that all licensing aspects of the concurrence sheet are complete and accurate.

CONCURRENCE signatures are obtained from managers of affected departments providing input to the submittal and from departments that may be impacted by the results of the submittal.

Signatures Southern Nuclear Operating Company Nuclear NL-006-F03 SOUTHERN A Licensing Licensing Action and Concurrence Version 1.0 COMPANY Form Page 60t 6 EfmV Ytlu; \VtrrlJ> indicate that the intent ot the submittal is appropriate as it concerns that department and is consistent with SI\JC policy, applicable commitments are approved for implementation, and documentation to support submittal completeness and accuracy is present and reasonable.

Concurrence signatures should include signatures of management reviewers responsible tor ensuring technical accuracy of the submittal, subject to confidentiality constraints (e.g., drug test reports, employee allegations, personal information such as name and social security number, EP scenarios, etc.). In lieu of an actual signature, concurrence may be obtained electronically via an e-mail from the management reviewers.

The e-mail must clearly indicate management's approval of the submittal.

A printed version of the mail shall be maintained in the letter package as an attachment to the concurrence sheet.