Text

Amends 100 & 78 to Licenses NPF-68 & NPF-81,respectively, Changing VEGP TS to Allow Extended Allowed Outage Time for Emergency Diesel Generator of 14 Days
	ML20247M751
Person / Time
Site:	Vogtle
Issue date:	05/20/1998
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	; Southern Nuclear Operating Co, Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20247M757	List: ML20247M751; ML20247M770;
References
	NPF-68-A-100, NPF-81-A-078 FACA, NUDOCS 9805260369
	Download: ML20247M751 (38)
	v • d • e

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i UNITED STATES 3

NUCLEAR REGULATORY COMMISSION

=

e WASHINGTON, D.C. -t **1

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SOUTHERN NUCLEAR OPERATING COMPANY. INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA VOGTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 License No. NPF-68 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated January 22,1998, as supplemented by letters dated March 18,1998, April 21,1998, and May 15, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

~

9805260369 980520 PDR ADOCK 05000424 P

PDR 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to read as follows:

Tedc. c=! St+c;fM: ens and Environmental Protection Plan The. Technical Specifications contained in Appendix A, as revised through Amendment No.100, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.-

In addition, the license is amended to add paragraph 2.C.(10) to Facility Operating License No. NPF-68 as follows:

(10) AdditionalConditions The Additional Conditions contained in Appendix D, as revised through Amendment No.100, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Additional Conditions.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 40%

for Herbert N. Berkow, Director Project Directorate ll-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachments:

1. Operating License Changes

2. Technical Specification Changes Date oflasuance:

May 20, 1998 l

u-__-_-_--_----------____--_---

L ATTACHMENT TO LICENSE AMENDMENT NO.100 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 Replace the following pages of the Operating License with the enclosed pages. The revised pages are identified by Amendment number and contain vertial lines indicating the areas of j

change.

l Remove Inmed Pages 6 and 8 Pages 6 and 8 Appendix D Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines indicating the areas of change.

Remove inand l-3.8-2 3.8-2 l

3.8-3 3.8-3 3.8-3a 3.8-3b 3.8-4 3.8-4 3.8-5 3.8-5 5.0-27 5.0-27 B 3.8-5 B 3.8-5 B 3.8-6 B 3.8-6 B 3.8-7 B 3.8-7 B 3.8-8 B 3.8-8 B 3.8-8a B 3.8-8b B 3.8-g B 3.8-g B 3.8-10 B 3.8-10 B 3.8-10s B 3.8-10b l

l B 3.8-11 B 3.8-11 B 3.8-11a B 3.8-11b B 3.8-12 B 3.8-12 B 3.8-13 B 3.8-13 B 3.8-14 B 3.8-14 8 3.8-15 B 3.8-15

c

) 4.

documentation showing tradeoff analyses and other information used

(

in resolving HEDs 5.

the methodology by which control room changes were to be factored into the operators' training program 6.

procedures that incorporate human factors review into the design process for future control room modifications (8)

Zine Coatina of Diesel Fuel Oil Storaae Tanks (Section 9.5.4.2, SSER 4)

Prior to restart following the first refueling, GPC shall (1) replace the zine coating in the diesel generator fuel oil storage tanks with a coating which does not contain zine or (2) by March 1,1988 provide an acceptable justification to the staff that the present fuel oil storage tank zinc-based coating will not affect the operability and reliability of the diesel generators over the life of the plant as specified in IE Circular 77-15.

If option (1)is chosen, GPC shall provide the NRC with a modification status report 30 days before the expiration of the license condition.

i (9)

Attemate Radwaste Faciru (Section 11.4, SSERs 3 and 4)

Prior to restart following the first refueling, the ventilation exhaust of the attemate radwaste facility shall be modified to exhaust through HEPA filters already installed in the auxiliary building HVAC system.

GPC shall provide the NRC with a modification status report 30 days before the expiration of the license condition.

(10) Additional Conditions The Additional Conditions contained in AppencW D, as revised through Amendment No.100, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Additional Conditions.

D.

The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include (a) an exemption from the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area, (b) an exemption from l

the requirements of Paragraph lli.D.2(b)(ii) of Appendix J of 10 CFR 50, the testing of containment air locks at times when containment integrity is not required, and (c) a i

schedular exemption from 10 CFR 50.34(b)(2)(i) as it pertains to GDC 2,61, and 62 l

of Appendix A to 10 CFR 50 for the spent fuel pool racks for the time period before the racks contain irradiated fuel. The special circumstances regarding exemptions b and c are identified in Sections 6.2.6 and 9.1.2 of SSER 5, respectively.

Amendment No. 100

l l

\\

8.-

H.

Reporting to the Commission Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Southem Nuclear shall report any violations of the requirements contained in Section 2.C of th;s license in the following manner; initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).

l 1.

The Owners shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

J.

This license is effective as of the date of issuance and shall expire at midnight on January 16,2027.

FOR THE NUCLEAR REGULATORY COMMISSION let Harold R. Denton, Director Office of Nuclear Reactor Regulation l

Enclosures:

1. Attachment 1 - DELETED 2.: Appendix A-Technical Specifications

3. Appendix B - Environmental

Protection Plan

4. Appendix C - Antitrust Conditions

5. Appendix D - Additional Conditions l

Date of Issuance: March 16,1987 Amendment No. 100

4 APPENDIX D ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-68 l

Amendment Implementation Number Additional Condition Date 100 The licensee shall implement a procedure that Prior to implementation will prohibit entry into an extended Emergency Diesel of Amendment No.100.

Generator Allowed Outage Time (14 days), for I

scheduled maintenance purposes, if severe weather conditions are expected, as described in the licensee's application dated January 22,1998, as supplemented by letter dated March 18,1998, and evaluated in the staff's Safety Evaluation dated May 20, 1998.

l l

i l

l Amendment No.100 l

[

L

L*?oqk UNITED STATES g

g NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. 30006 4001 SOUTHERN NUCLEAR OPERATING COMPANY. INC.

GEORGIA POWER COMPANY i

OGLETHORPE POWER CORPORATION MUNICIPAL Ft FCTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA VOGTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. NPF-81 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No. NPF-81 filed by the Southern Nuclear Operating Company, Inc. (Southem Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Delton, Georgia (the licensees), dated January 22,1998, as supplemented by letters dated March 18,1998, April 21,1998, and May 15, 1998, cwplies with the standards and requirements of the Atomic Energy Act of 1954, as Amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

l

- 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 78, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

In addition, the license is amended to add paragraph 2.C.(3) to Facility Operating License No. NPF-81 as follows:

(3) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 78

, are hereby incorporated into this license.

Southern Nuclear shall operate the facility in accordance with the Additional Conditions.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FO NUCLEAR REGULATORY COMMISSION V/h if Herbert N. Berkow, Director Project Directorate Il-2 Division of Reactor Projects - t/ll Office of Nuclear Reactor Regulation

Attachment:

1

1. Operating License Changes

2. Technical Specification l

. Changes Date oflasuance: May 20, 1998 l

i I

1

ATTACHMENT TO LICENSE AMENDMENT NO. 78__

FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Operating License with the enclosed pages. The revised pages are identified by Amendment number and contain vertial lines indicating the areas of change.

Remove Insert Pages 4,5, and 6 Pages 4,5, and 6 Appendix D Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment nurr.ber and contain vertica! Vnes indicating the areas of change.

Remove Insert 3.8-2 3.8-2 3.8-3 3.8-3 3.8-3a 3.8-3b 3.8-4 3.8-4 3.8-5 3.8-5 5.0-27 5.0-27 B 3.8-5 B 3.8-5 B 3.8-6 B 3.8-6 B 3.8-7 8 3.8-7 B 3.8-8 8 3.8-8 B 3.8-8a B 3.8-8b B 3.8-9 B 3.8-9 i

B 3.8-10 B 3.8-10 l

B 3.8-10a B 3.8-10b B 3.8-11 B 3.8-11 1

B 3.8-11a B 3.8-11b B 3.8-12 B 3.8-12 8 3.8-13 B 3.8-13 8 3.8-14 B 3.8-14 8 3.8-15 B 3.8-15

-a

4_

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all l

applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.

l (1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100 percerd power) in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 78, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance Requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment No. 74. The SRs listed below shall be successfully demonstrated prior to the time and condition specified below for each:

a)

SRs 3.8.1.8,3.8.1.11 and 3.8.1.13 shall be successfully demonstrated prior to the first entry into MODE 4 following the fifth refueling outage.

b)

SR 3.8.1.g shall be successfully demonstrated prior to the first entry into MODE 4 following the sixth refueling outage.

c)

SR 3.8.1.20 shall be successfully demonstrated at the first regularly scheduled performance after implementation of this i', ense amendment.

(3)

Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 78, are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Additional Conditions.

Amendment No. 78 l

D.

The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include (a) an exemption from the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area, (b) an exemption from the requirements of Paragraph Ill.D.2(b)(ii) of Appendix J of 10 CFR 50, the testing of containment air locks at times when containment integrity is not required, and (c) an exemption from the schedule requirements of 10 CFR 50.33(k)(1) related to l

ava!! ability of funds for decommissioning the facility. The special circumstances regarding exemptions b and c are identified in Sections 6.2.6 and 22.5 of SSER 8, respectively.

An exemption was previously granted pursuant to 10 CFR 70 24. The exemption was granted with NRC materials license No. SNM-1981, issued July 13,1988, and relieved GPC from the requirement of having a criticality alarm system. GPC and Southern Nuclear are hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items b and c above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in

. conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the. Commission.

E.

Southem Nuclear shall fully implement and maintain in effect all provisions of the Ccmmission-approved physical security, guard training and qua'ification, and f

safeguards contingency plans including amendments made pursuant to provisions of I

the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The plans are entitled: "Vogtle Electric Generating Plant Unit 1 and Unit 2 Physin Security and Contingency Plan" (which contains Safeguards Information protecteo under 10 CFR 73.21) with revisions submitted through September 12,1996, and "Vogtle Electric Generating Plant Guard Training and Qualification Plan," with revisions submitted through March 13,1996. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F.

GPC shall comply with the antitrust conditions delineated in Appendix C to this license.

G.

Southem Nuclear shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as approved in the SER (NUREG-1137) through Supplement 9 subject to the following provision:

Southem Nuclear may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fir'e.-

Amendment No.78

)

l H.

Reporting to the Commission Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Southern Nuclear shall report any violations of the requirements contained in Section 2.C of this license in the following manner; initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).

I.

The Owners shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the l~

Atomic Energy Act of 1954, as amended, to cover public liability claims.

J.

This license is effective as of the date of issuance and shall expire at midnight on February 9,2029.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Thomas E. Murley, Director Office of Nuclear Reactor Regulation i

Enclosures:

1. Appendix A-TechnicalSpecifications

2. Appendix B - Environmental Protection Plan l

3. Appendix C - Antitrust Conditions

4. Appendix D - Additional Conditions l

l Date of issuance: March 31,1989 i-l l

Amendment No. 78

)

I I

l APPENDIX D l

ADDITIONAL CONDITIONS 1

FACILITY OPERATING LICENSE NO. NPF-81 l

l Amendment implementation i

Number Additional Condition Date 78 The licensee shall implement a procedure that Prior to l

will prohibit entry into an extended Emergency implementation l

Diesel Generator Allowed Outage Time (14 days),

of Amendment No.78.

for scheduled maintenance purposes, if severe weather conditions are expected, as described in the licensee's application dated January 22,1998, as supplemented March 18,1998, and evaluated i

in the staff's Safety Evaluation dated May 20, 1998.

I l

Amendment No. 78 l

i l

i NOTE ONE SET OF COMBINED TECHNICAL SPECIFICATION PAGES PROVIDED FOR BOTH UNITS 1 AND 2.

l

AC Sources - Operating 3.8.1 ACTIONS l

CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from feature (s) with no discovery of no offsite power offsite power to available inoperable one train when its redundant concurrent with required feature (s) inoperability of is inoperable.

redundant required feature (s)

ANJ A.3 Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months offsite circuit to OPERABLE status.

MQ 14 days from l

discovery of failure to meet LCO (continued)

Vogtle Units 1 and 2 3.8-2 Amendment No. 100 (Unit 1)

Amendment No.

78 (Unit 2)

AC Sources -- Operating 3.8.1 CONDITION REQUIRED ACTION COMPLETION TIME B.

One DG inoperable.

8.1 Perform ER 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for the required offsite circuit (s).

M Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter M

B.2 Verify SAT 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months available.

M Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.3 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from l

feature (s) supported discovery of by the inoperable DG Condition B inoperable when its concurrent with required redundant inoperability of feature (s) is redundant inoperable, required feature (s)

M B.4.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

DG is not inoperable due to common cause failure.

DB B.4.2 Perform SR 3.8.1.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

for OPERABLE DG.

M (continued)

Vogtle Units 1 and 2 3.8-3 Amendment No. 100 (Unit 1)

Amendment No.

78 (Unit 2)

AC Sources -- Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

NOTE Required Action B.5.1 is only applicable if the combined reliability of the enhanced black-start combustion turbine generators (CTG) and the black-start diesel generator is 2 95%.

Otherwise, Required Action B.5.2 applies.

B.5.1 Verify an enhanced 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months black-start CTG is functional by QB verifying the CTG and the black-start Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months diesel generator prior to' entry starts and achieves into Condition B steady state voltage and frequency.

QB B.5.2 Start and run at 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months least one CTG while in Conditon B.

QB Prior to entry into Conditon B for preplanned maintenance SEQ (continued)

Vogtle Units 1 and 2 3.8-3a Amendment No.100 (Unit 1)

Amendment No.

78 (Unit 2)

AC Sources - Operating 3.8.1 ACTIONS (continued)

This Page Intentionally left Blank i

I Vogtle Units 1 and 2 3.8-3b Amendment No.100 (Unit 1)

Amendment No. 78 (Unit 2) i

l AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.6 Restore DG to 14 days from l

OPERABLE status.

discovery of failure to meet LCO l

C.

Required Actions B.2, C.1 Restore DG 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.5.1, or B.5.2 and to OPERABLE

{

associated Completion status.

Times not met.

D.

Two required offsite D.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from l

circuits inoperable.

feature (s) discovery of inoperable when its Condition D l

redundant feature (s) concurrent with is inoperable.

inoperability of redundant required features A!iD l

D.2 Restore one required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

offsite circuit to OPERABLE status.

l E.

One required offsite

NOTE-------------

circuit inoperable.

Enter applicable Conditions and Required Actions of A!iQ LC0 3.8.9, " Distribution Systems - Operating," when l

One DG inoperable.

Condition E is entered with no AC power source to one or more trains.

(continued)

Vogtle Units 1 and 2 3.8-4 Amendment No.100 (Unit 1)

Amendment No. 78 (Unit 2)

l l

AC Sources - Operating 3.8.1 ACTIONS (continued)-

CONDITION REQUIRED ACTION COMPLETION TIME E..(continued)

E.1 Restore required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

l offsite circuit to OPERABLE status.

98 E.2 Restore DG to OPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

status.

F.

Two DGs inoperable.

F.1 Restore one DG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months l

OPERABLE status.

G.

One automatic load G.1 Restore automatic load 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

sequencer inoperable.

sequencer to OPERABLE status.

H.

Required Action and H.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

associated Completion Time of Condition A, AtiD C, D, E, F, or G not l

met.

H.2 -Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months QB Required Action B.1, B.3, B.4.1, B.4.2, or B.6 and associated Completion Time not met.

I.

Three or more I.1 Enter LC0 3.0.3.

Immediately l

required AC sources inoperable.

Vogtle Units I and 2 3.8-5 Amendment No.100 (Unit 1)

Amendment No. 78 (Unit 2)

1 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Containment Laakaae Rate Testina Proaram (continued)

The provisions of SR 3.0.2 do not apply to the test frequencies l

specified in the Containment Leakage Rate Testing Program.

The provisions of. SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

5.5.18 Configuration Risk Manaaement Proaram The Configuration Risk Management Program (CRMP) provides a

)

proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed allowed outage time has been granted. The program shall include the following elements:

a.

Provisions for the control and implementation of a Level 1 at power internal events PRA-informed methodology.

The assessment shall be capable of evaluating the applicable plant configuration.

b.

Provisions for performing an assessment prior to entering the LCO Condition for preplanned activities.

c.

Provisions for performing an assessment after entering the LCO Condition for unplanned entry into the LCO Condition.

d.

Provisions for assessing the need for additional actions after the discovery.of additional equipment out of service conditions while in the LCO Condition.

e.

Provisions for considering other applicable risk'significant contributors such as Level 2 issues and external events, qualitatively or quantitatively.

Vogtle Units 1.and 2 5.0-27 Amendment No.100 (Unit 1)

Amendment No. 78 (Unit 2) l

AC Sources - Operating I

B 3.8.1 1

BASES f

LCO train.

For the DGs, separation and independence are (continued) complete.

For the offsite AC sources, separation and independence are to the extent practical. A circuit may be connected to more than one ESF bus while the bus is being transferred to the other circuit.

APPLICABILITY The AC sources and sequencers are required to be OPERABLE in MODES 1, 2, 3, and 4 to ensure that:

a.

Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of A00s or abnormal transients; and b.

Adequate core cooling is provided and containment OPERABILITY and other vital functions are maintained in the event of a postulated DBA.

The AC power requirements for MODES 5 and 6 are covered in LCO 3.8.2, "AC Sources - Shutdown."

ACTIONS M

To ensure a highly reliable power source remains with one offsite circuit inoperable, it is necessary to verify the OPERABILITY of the remaining required offsite circuit on a more frequent basis.

Since the Required Action only specifies " perform," a failure of SR 3.8.1.1 acceptance criteria does not result in a Required Action not met.

However, if a second required circuit fails SR 3.8.1.1, the second offsite circuit is inoperable, and Condition D, l

for two offsite circuits inoperable, is entered.

U Required Action A.2, which only applies if the train cannot be powered from an offsite source, is intended to provide assurance that an event coincident with a single failure of the associated DG will not result in a complete loss of safety function of critical redundant required features.

(continued)

Vogtle Units 1 and 2 B 3.8-5 i

Ag g g.1g g g

AC Sources - Operating B 3.8.1 BASES ACTIONS L1 (continued)

These features are powered from the redundant AC electrical power train. This includes motor driven auxiliary feedwater pumps. Single train systems, such as turbine driven auxiliary feedwater pumps, may not be included.

The Completion Time for Required Action A.2 is intended to allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal " time zero" for beginning the allowed outage time " clock."

In this Required Action, the Completion Time only begins on discovery that both:

a.

The train has no offsite power supplying its loads; l

and b.

A required feature on the other train is inoperable.

If at any time during the existence of Condition A (one offsite circuit inoperable) a redundant required feature subsequently becomes inoperable, this Completion Time begins to be tracked.

Discovering no offsite power to one train of the onsite Class IE Electrical Power Distribution System coincident with one or more inoperable required support or supported features, or both, that are associated with the other train that has offsite power, results in starting the Completion Times for the Required Action. Twenty-four hours is acceptable because it minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown.

The remaining OPERABLE offsite circuit and DGs are adequate to supply electrical power to Train A and Train B of the onsite Class IE Distribution System. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time takes into account the component OPERABILITY of the redundant counterpart to the inoperable required feature.

Additionally, the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period.

l l

l (continued)

Agmg g.1g g Q Vogtle Units 1 and 2 B 3.8-6

AC Sources - Operating B 3.8.1 BASES UTIONS AJ.

icontinued)

According to Regulatory Guide 1.93 (Ref. 6), operation may continue in Condition A for a period that should not exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . With one required offsite circuit inoperable, the reliability of the offsite system is degraded, and the potential for a loss of offsite power is increased, with attendant potential for a challenge to the unit safety systems.

In this Condition, however, the remaining OPERABLE offsite circuit and DGs are adequate to supply electrical power to the onsite Class IE Distribution System.

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period.

The second Completion Time for Required Action A.3 establishes a limit on the maximum time allowed for any combination of required AC power sources to be inoperable during any single contiguous occurrence of failing to meet the LCO.

If Condition A is entered while, for instance, a DG is inoperable and that DG is subsequently returned OPERABLE, the LCO may already have been not met for up to 11 days.

This could lead to a total of 14 days, since initial failure to meet the LCO, to restore the offsite circuit. At this time, a DG could again become inoperable, the circuit restored OPERABLE, and an additional 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or 14 days depending on SAT availability, allowed prior to complete restoration of the LCO. The 14 day Completion Time provides a limit on the time allowed in a specified condition after discovery of failure to meet the LCO. This limit is considered reasonable for situations in which conditions A and B are entered concurrently. The "ANQ" connector between the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and 14 day Completion Times means that both l

Completion Times apply simultaneously, and the more restrictive Completion Time must be met.

1 Tracking the 14 day Completion Time is a requirement for l

beginning the Completion Time " clock" that is in addition to the normal Completion Time requirements. With respect to the 14 day Completion Time, the " time zero" is specified as l

l j

(continued)

%QQQ{ g,1g gt {;

Vogtle Units 1 and 2 B 3.8-7

AC Sources - Operating B 3.8.1 BASES ACTIONS M (continued) commencing at the time LCO 3.4.1 was initially not met, instead of at the time Condition A was entered. This results in the requirement when in this Condition to track the time elapsed from both the Condition A " time zero" and the " time zero" when LCO 3.8.1 was initially not met.

u l

To ensure a highly reliable power source remains with an inoperable DG, it is necessary to verify the availability of the offsite circuits on a more frequent basis. Since the Required Action only specifies " perform," a failure of SR 3.8.1.1 acceptance criteria does not result in a Required Action being not met. However, if a circuit fails to pass SR 3.8.1.1, it is inoperable. Upon offsite circuit inoperability, additional Conditions and Required Actions must tten be entered.

M The 13.8/(.16 kV Standby Auxiliary Transformer (SAT) is a qualified offsite circuit that may be connected to the onsite Class IE distribution system independently of the RATS and may be utilized to meet the LCO 3.8.1 requirements for an offsite circuit.

Its availability permits an extension of the allowable out-of-service time for a DG to 14 days from the discovery of failure to meet LCO 3.8.1.

The SAT is available when it is:

Operable in accordance with plant procedures; Not already being applied to any of the four 4.16 kV ESF buses for Units 1 and 2 in accordance with l

Specification 3.8.1 as either an offsite source or to meet the requirements of an LCO 3.8.1 Condition; and, Not providing power to the other unit when that unit is in MODE 5 or 6 or defueled, l

(continued) gg g.1% g []

Vogtle Units 1 and 2 B 3.8-8

f i

AC Sources - Operating B 3.8.1 l

BASES l

ACTIONS M (continued)

Furthermore, the SAT can be applied to only one of the four 4.16 kV ESF buses at any given time for Units 1 and 2 to meet the requirements of an LCO 3.8.1 Condition.

When one or more of these criteria are not satisfied, the SAT is not available. These criteria are structured to ensure that the SAT is available as an alternate offsite source to support the extended DG Completion Time of 14 days. Therefore, when a DG is inoperable, it is necessary to verify the availability of the SAT within one hour and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

If Required Action B.2 is not met or the status of the SAT changes after Required Action B.2 is initially met, Condition C must be entered concurrently.

M Required Action B.3 is intended to provide assurance that a loss of offsite power, during the period that a DG is inoperable, does not result in a complete loss of safety function of critical systems. These features are designed with redundant safety related trains.

This includes motor driven auxiliary feedwater pumps. Single train systems, such as turbine driven auxiliary feedwater pumps, are not included. Redundant required feature failures consist of inoperable features associated with a train, redundant to I

the train that has an inoperable DG.

I TheComp]etionTimeforRequiredActionB.3isintendedto l

allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal " time zero" for beginning the allowed outage time " clock." In this Required Action, the Completion Time only begins on discovery that both:

a.

An inoperable DG exists; and b.

A required feature on the other train (Train A or Train B) is inoperable.

l l

l (continued) i Vogtle Units 1 and 2 B 3.8-8a Amendment No.100 (Unit 1)

{

Amendment No.

78 (Unit 2) l l

l i

AC Sources - Operating B 3.8.1 BASES This Page Intentionally left Blank i

i l

(continued)

Vogtle Units 1 and 2 8 3.8-8b A$*e0NESkNo'.

2

AC Sources - Oparating B 3.8.1 BASES-ACTIONS LJ (continued) l If at any time during the existence of this Condition (one DG inoperable) a required feature subsequently becomes inoperable, this Completion Time would begin t, be tracked.

Discovering one required DG inoperable coincident with one or more inoperable required support or supported features, or both, that are associated with the OPERABLE DC, results in starting the Completion Time for the Required Action.

Four hours from the discovery of these events existing concurrently is acceptable because it minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown.-

In this Condition, the remaining OPERABLE DG and offsite circuits are adequate to supply electrical power to the onsite Class 1E Distribution System. Thus, on a component i

basis, single failure ~ protection for the required feature's function may have been lost; however, function has not been lost. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time takes into account the OPERABILITY of the redundant counterpart to the inoperable required feature. Additionally, the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period.

B.4.1 and B.4.2 l

Required Action B.4.1 provides an allowance to avoid unnecessary testing of the OPERABLE DG.

If it can be determined that the cause of the inoperable DG does not exist on the OPERABLE DG, SR 3.8.1.2 does not have to be performed.

If the cause of inoperability exists on the other DG, the other DG would be declared inoperable upon discovery and Condition F of LCO 3.8.1 would be entered.

Once the failure is repaired, the common cause failure no longer exists, and Required Action B.4.1 is satisfied.

If l

the cause of the initial inoperable DG cannot be confirmed not to exist on the remaining DG, performance of SR 3.8.1.2 suffices to provide assurance of continued OPERABILITY of that DG, I

{

(continued)

Vogtle Units 1 and 2 B 3.8-9 Amendment No.100 Unit 1 Amendment No. 78 Unit 2 i

i AC Sources - Operating B 3.8.1 BASES ACTIONS B.4.1 and B.4.2 (continued)

In the event the inoperable DG is restored to OPERABLE status prior to completing either B.4.1 or B.4.2, the

[

applicable plant procedures will continue to require the evaluation of the common cause possibility. This continued evaluation, however, is no longer under the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months constraint imposed while in Condition B.

According to Generic Letter 84-15 (Ref. 7), 24. hours is.

reasonable to confirm that the OPERABLE DG is not affected by the same problem as the inoperable DG.

B.5.1 and B.S.2 Required Action B.5.1 provides assurance that an enhanced black-start combustion turbine generator (CTG) is functional when a DG is out of service for greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Required Action B.5.1 is modified by s Nnte that states that it is only applicable provided that f.he two enhanced black-start CTGs and black-start diesel generator have a combined reliability of 1 95% based on a minimum of 20 tests per enhanced black-start CTG and quarterly testing thereafter.

This quarterly testing will subject each enhanced black-start CTG to a start and load-run test. The black-start diesel generator will also be tested quarterly, but separately from the enhanced black-start CTGs.

Required Action B.5.1 may be met by starting either of the enhanced black-start CTGs and the black-start diesel generator and verifying that they achieve steady state voltage and frequency. The black-start diesel generator may be started separately.

If a DG is to be removed from service voluntarily for greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , it may be advantageous to test an enhanced black-start CTG prior to taking the DG out of service.

In such cases where advanced notice of removing a DG from service is available, Requireo Action B.5.1 may be performed up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to entry into Condition B.

In other cases, Required Action B.5.1 must be performed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after entry into Condition B.

(continued)

Vogtle Units 1 and 2 B 3.8-10 Amendment No. 100 Unit 1 Amendment No.

78 Unit 2

AC Ssurces - Operating B 3.8.1 BASES ACTIONS JLj.1 and B.L2 (continued)

If the combined reliability of the enhanced black-start CTGs has not been demonstrated or maintained 1 95%, the option of starting and running any one of the six CTGs while in Condition B is available in the form of Required Action B.5.2.

In the event of preplanned maintenance that would exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , any one of the six CTGs must be started prior to entry into Condition B and allowed to run for the duration of Condition B.

Otherwise, any one of the six CTGs must be started within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (and allowed to run) after entry into Condition B if the DG is to be out of service for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Note that Required Action B.5.1 requires that one of the two enhanced black-start CTGs be started, but any one of the six CTGs could be started to satisfy Required Action B.5.2.

Since a CTG is started and running while the DG is inoperable, it is not necessary that the CTG have enhanced black-start capability.

B.&

The availability of the SAT provides an additional AC source which permits operation to continue for a period not to exceed 14 days from discovery of failure to meet the LCO.

In Condition B, the remaining OPERABLE DG and offsite circuits are adequate to supply electrical power to the onsite Class IE Distribution System.

The 14 day Completion l

Time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period.

In addition, the Configuration Risk Management Program (CRMP) is used to assess changes in core damage frequency resulting from applicable plant configurations. The CRMP uses the equipment out of service risk monitor, a computer based tool that may be used to aid in the risk assessment of on-line maintenance and to evaluate the change in risk from a component failure. The equipment out of service risk monitor uses the plant probabilistic risk assessment model to evaluate the risk of removing equipment from service I

(continued)

$$[( % h{ h Vogtle Units I and 2 B 3.8-10a l

l i

AC Sources - Operating B 3.8.1 BASES ACTIONS B.5.1 and B.5.2 (continued) based on current plant configuration and equipment condition.- The CRMP is used when a DG is intentionally taken out of service for a planned activity excluding short duration activities (e.g., performing an air roll on the EDG prior to a routine surveillance).

In addition, the CRMP is used for unplanned maintenance or repairs of a DG.

Planned activities involving an extended DG A0T will be synchronized with other maintenance activities as much as possible in order to maximize equipment reliability while

)

4 minimizing the time equipment is unavailable.

In addition, 1

Required Action B.3 requires that features supported by the inoperable DG be declared inoperable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of discovery when redundant features are discovered to be inoperable. The combination of planned maintenance centered around the extended DG A0T, Required Action B.3, and use of the CRMP provides an appropriate level of assurance that risk significant activities with an unacceptable risk achievement worth will be minimized during an extended DG A0T.

The Completion Time for Required Action B.6 also establishes l

a limit on the maximum time allowed for any combination of required AC power sources to be inoperable during any single contiguous occurrence of failing to meet the LCO.

If Condition B is entered while, for instance, an offsite circuit is inoperable, the LCO may already have been not met for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

If the offsite circuit is restored within the required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , this could lead to a total of 17 days, since initial failure to meet the LCO, to restore compliance with the LCO (i.e., restore the DG).

However, the 14 day Completion Time provides a (continued)

A*e" genmenko'.

njk Vogtle Units 1 and 2 B 3.8-10b

AC Sources - Operating B 3.8.1 BASES ACTIONS B.5.1 and B.5.2 (continued) limit on time allowed in a specified condition after discovery of failure to meet the LCO. This limit is considered reasonable for situations in which conditions A and B (and consequently Condition E) are entered l

concurrently.

Tracking the 14 day Completion Time is a requirement for l

beginning the Completion Time " clock" that is in addition to the normal Completion Time requirements. With respect to the Completion Time, the " time zero" is specified as commencing at the time LCO 3.8.1 was initially not met, instead of at the time Condition B was entered. This results in the requirement when in this Condition to track the time elapsed from both the Condition B " time zero" and the " time zero" when LCO 3.8.1 was initially not met, fu.1 If the availability of the SAT cannot be verified, or if no CTG meets the requirements of either Required Action B.5.1 or i

B.5.2, the DG must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time begins upon entry into Condition C.

However, the total time to restore an inoperable DG cannot exceed 14 days (per the Completion Time of Required Action B.6).

The Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (in the absence of the SAT) is consistent with Regulatory Guide 1.93 (Ref.6). The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time takes into account the capacity and capability of the remaining AC sources, a reasonable time 'or repairs, and low probability of a DBA occurring this period.

D.1 and D.2 Required Action D.1, which applies when two offsite circuits are inoperable, is intended to provide assurance that an event with a coincident single failure will not result in a l

complete loss of redundant required safety functions. The j

Completion Time for this failure of redundant required features is reduced to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from that allowed for one l

train without offsite power (Required Action A.2).

The rationale for the reduction to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is that Regulatory l

Guide 1.93 (Ref 6) allows a Completion Time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for (continued) l Vogtle Units 1 and 2 B 3.8-11 ge g eng g i g g g {

f AC Sources - Operating B 3.8.1 BASES ACTIONS D.1 and D.2 (continued) two required offsite circuits inoperable, based upon the assumption that two complete safety trains are OPERABLE.

When a concurrent redundant required feature failure exists, this assumption is not the case, and a shorter Completion Time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is appropriate. These features are powered from redundant AC safety trains. This includes motor driven auxiliary feedwater pumps. Single train features, such as turbine driven auxiliary pumps, are not included in the list.

The Completion Time for Required Action D.1 is intended to l

allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows for an exception to the normal "t.me zero" for l

l (continued)

Vogtle Units 1 and 2 B 3.8-lla Amendment No.100 Unit 1 Amendment No.

78 Unit 2

..m.._.J

AC Sources - Operating B 3.8.1 BASES This Page Intentionally Left Blank l

l

[

l l

(continued)

Vogtle Units 1 and 2 B 3.8-11b Am n en o.1g{gjt}]

n

AC Sources - Operating B 3.8.1 BASES ACTIONS D.1 and D.2 (continued) b3 ginning the allowed outage time " clock."

In this Required l

Action the Completion Time only begins on discovery that both:

a.

All required offsite circuits are inoperable; and b.

A required feature is inoperable.

l If at any time during the existence of Condition D (two l

offsite circuits inoperable) a required feature becomes inoperable, this Completion Time begins to be tracked.

According to Regulatory Guide 1.93 (Ref. 6), operation may continue in Condition D for a period that should not exceed l

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This level of degradation means that the offsite electrical power system does not have the capability to effect a safe shutdown and to mitigate the effects of an accident; however, the onsite AC sources have not been degraded. This level of degradation generally corresponds to a total loss of the immediately accessible offsite power sources.

Because of the normally high availability of the offsite sources, this level of degradation may appear to be more severe than other combinations of two AC sources inoperable that involve one or more DGs inoperable. However, two factors tend to decrease the severity of this level of degradation:

a.

The configuration of the redundant AC electrical power system that remains available is not susceptible to a single bus or switching failure; and b.

The time required to detect and restore an unavailable offsite power source is generally much less than that required to detect and restore an unavailable onsite AC source.

With both of the required offsite circuits inoperable, sufficient onsite AC sources are available to maintain the unit in a safe shutdown condition in the event of a DBA or transient.

In fact, a simultaneous loss of offsite AC sources, a LOCA, and a worst case single failure were I

(continued)

Amendment No.100 (Unit 1)

Vogtle Units I and 2 B 3.8-12 Amendment No. 78 (Unit 2)

l-AC Sourcss - Operating B 3.8.1 BASES' ACTIONS D.1 and D.2 (continued) postulated as a part of the design basis in the safety i

l analysis. Thus, the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time provides a period of time to effect restoration of one of the offsite circuits commensurate with the importance of maintaining an l

AC electrical power system capable of meeting its design criteria.

According to Reference 6, with the available offsite AC l-sources, two less than required by the LCO, operation may continue for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If two offsite sources are restored I

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , unrestricted operation may continue.

If only one offsite source is restored within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , power operation continues in accordance with Condition A.

E.1 and E.2 l

Pursuant to LCO 3.0.6, the Distribution System ACTIONS would not be entered even if all AC sources to it were inoperable, resulting in de-energization. Therefore, the Required Actions of Condition E are modified by a Note to indicate that when Condition E is entered with no AC source to one or more trains, the Conditions and Required Actions for LCO 3.8.9, " Distribution Systems - Operating," must be immediately entered. This allows Condition E to provide l

requirements for the loss of one offsite circuit and one DG, without regard to whether a train is de-energized.

LCO 3.8.9 provides the appropriate restrictions for a de-energized train.

According to Regulatory Guide 1.93 (Ref. 6), operation may continue in Condition E for a period that should not exceed l

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

In Condition E, individual redundancy is lost in both the l

offsite electrical power system and the onsite AC electrical power system.

Since power system redundancy is provided by two diverse sources of power, however, the reliability of the power systems in this Condition may appear higher than that in Condition D (loss of both required offsite circuits).

l This difference in reliability is offset by the susceptibility of this power system configuration to a (continued)

Amendment No. 100 (Unit 1)

Vogtle Units 1 and 2 B 3.8-13 Amendment No. 78 (Unit 2)

AC Sources - Operating B 3.8.1 BASES ACTIONS E.1 and E.2 (continued) single bus or switching failure. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Completion Time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period.

f.d With Train A and Train B DGs inoperable, there are no remaining standby AC sources. Thus, with an assumed loss of 1

offsite electrical power, insufficient standby AC sources are available to power the minimum required ESF functions.

Since the offsite electrical power system is the only source of AC power for this level of degradation, the risk associated with continued operation for a very short time could be less than that. associated with an immediate controlled shutdown (the immediate shutdown could cause grid instability, which could result in a total loss of AC power).

Since any inadvertent generator trip could also result in a total loss of offsite AC power, however, the time allowed for continued operation is severely restricted. The intent here is to avoid the risk associated with an immediate controlled shutdown and to minimize the risk associated with this level of degradation.

According to Reference 6, with both DGs inoperable, operation may continue for a period that should not exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

El The sequencer (s) is an essential support system to both the offsite circuit and the DG associated with a given ESF bus.

Furthermore, the sequencer is on the primary success path for most major AC electrically powered safety systems powered from the associated ESF bus. The sequencers are required to provide the' system response to both an SI signal and a loss of or degraded ESF bus voltage signal.

Therefore, loss of an ESF bus sequencer affects every m:.jor ESF system in the train. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Completion Time provides a period of time to correct the problem commensurate with the importance of maintaining sequencer (continued)

Vogtle Units 1 and 2 B 3.8-14 Amendment ho.100 (Unit 1)

Amendment No.

78 (Unit 2)

L-

i l

AC Sources - Operating B 3.8.1 l

l BASES l

ACTIONS M,;ontinued)

OPERABILITY. This time period also ensures that the probability of an accident (requiring sequencer OPERABILITY) occurring during periods when the sequencer is inoperable is minimal.

H.1 and H.2 l

If the inoperable AC electric power sources or an automatic load sequencer cannot be restored to OPERABLE status within the required Completion Time, or Required Actions B.1, B.3, B.4.1, B.4.2, or B.6 cannot be met within the required l

Completion Times, the unit must be brought to a MODE in which the LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging plant systems.

M l

Condition I corresponds to a level of degradation in which l

all redundancy in the AC electrical power supplies has been lost. At this severely degraded level, any further losses in the AC electrical power system will cause a loss of unction.

Therefore, no additional time is justified for continued operation. The unit is required by LCO 3.0.3 to commence a controlled shutdown.

SURVEILLANCE The AC sources are designed to permit inspection and testing REQUIREMENTS of all important areas and features, especially those that have a standby function, in accordance with 10 CFR 50, Appendix A, GDC 18 (Ref. 8).

Periodic component tests are supplemented by extensive functional tests during refueling outages (under simulated accident conditions). The SRs for demonstrating the OPERABILITY of the DGs are in accordance with the recommendations of Regulatory Guide 1.9 (Ref. 3),

Regulatory Guide 1.108 (Ref. 9), and Regulatory Guide 1.137 (Ref. 10), as addressed in the FSAR.

(continued)

Vogtle Units 1 and 2 B 3.8-15 Amendment No.100 (Unit 1)

Amendment No.

78 (Unit 2) u------ ------_--- - - - - - - - - - - - - - - - - - - -

- -

ML20247M751

Contents

Text

Enclosures:

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