Text

Proposed TS Section 2.7(2) Re Mod of Min Requirements for Electrical Sys & Section 5.9.3 Re Types of Special Repts to Be Submitted to Regional Administrator of Appropriate NRC Regional Ofc
	ML20101P537
Person / Time
Site:	Fort Calhoun
Issue date:	06/25/1992
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20101P527	List: ML20101P524; ML20101P531; ML20101P537;
References
	NUDOCS 9207130112
	Download: ML20101P537 (12)
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b l 2.0 1,lMITING CONDITIONS l'OR OPERATIOA' 2.7 lilectrical Systems (Continued)

(2) Modi 0 cation of Minimum Requirements The minimum requirements may be modified to the extent that one of the following conditions will be allowed after the reactor coolant has been heated above 300 F made eritical, lig. wever. the reaticuhall not br made criticalunless all minimunurquirements ate met, if any of the provisions of these exceptions are violated, the reactor shall be placed in a hot shutdown condition within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , if the violation is not corrected within an additional 12 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be placed in a cold shutdown condition within an additiona' 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a. 110th unit auxiliary power transformers TilA-1 and -2 (4.16 kV) may be inoperable for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided the operability of both diesel generators is demonstrated immediately. ;

b. House service-transformers T4A+or-T4A-4-(4r16kV)-may4>e-inoperable for-up-toene-week-House-service-t r ansfor mers-T4 A-4-and+(4rl 6-kV) may-be-inoperable-for-up-k>-24-hours-provided-the-operability-of-both diesel-generators-is-demonst rated-immediatelyrand-t he-N RG-is-wified im mediately-and-a-report-inubmitted-to4he-N RC-at+pecified4n4eet um h6-with-mamtline-of-the-plans-for-prompt-restoratiomef-off-site-power and-tiendditional-precautimao4>e-taken-while-t he-t rans formers-are-cut of+ervicer Either house service transformer Tl A 3 or Tl A-4 (4.16kV) may be inoperable for up to 7 days provided the operability of the diesel generator usociated with the inongrable transformer is immediately veri 0cd. The .

NRC Operations Center shall be notified by telephone within 4_he.uriafici transformer inoperability. Continued operation beyond 7 days is perm _issible. provided a special report is submitted to the NRC within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after tthasformer inoperability pursuant to Section 5.9.3 of the Icchnical Speci0 cations. The special report will outline the plans for restoration of transformer operability and the additional precautions to bg laken while the transformer is out of service.

c. Iloth house service transformers Tl A-3 and Tl A-4 (4.16kV) may bg inonerable for un to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the operability of both diesel l generators is immediately veri 0ed. The loss of'the 16112V incoming line renders both transformers inonerable. The_ NRC Operations Center shall be notificil by telephone within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after transformer inoperability.

.Co.ntinued operation beyond 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is permissible. provided a special report is submitted to the NRC within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months af ter both transformers' inonerability pursuant to Section 5.9.3 of the Technical Speci0 cations.

The_sprejal report _will outline the plans for restoration of tile transformers' operability and the additional precautions to be taken while the transformers are out of service.

2-33 Amendment No. 25 9207130112 920625 PDR ADOCK 05000285 p PDR i

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$.0 LIMITING CONDITIONS FOR OPERATION 2 '. 7 ' Electrical S 31tems (Continued) h nh Either one of the 125V d-e PG distribution panels Al-41 A et and Al 41B may be inoperable for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

rm In Either one_of the 120V_a-c AG instrument panels Al-42A or AI-42B may be inoperable for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , n: The461 kV4 ransmission4ine4ney+e+ut+f+ervice-andsnit eperation-m ay con tinue+r-the4eactor-mny-befestarted4tonte-hot +hutdow ereendition4 f (i)-operability-of-the-femaining-sourceds-ifnmediately-Veri 6ed-and-(ii) immediatenotificatkm4sanade4y-telephone-or-telegraph 4o4he-Director of4he-NRG-Regionai-Of6ce4n-Arlingtordexas-of4he40ss-and+f-the plat &tosestore 4heelect rie-power-syst en Ho4ts-full-eepebilityr Da5ls Le electrical system equipment is arranged so that no single failure can inactivate enough engineered safeguards to jeopardize the plant safety. The 480 V safeguards are arranged on nine bus sections. The 4.16 kV safeguards are supplied from two buses.

The normal source of auxiliary power with the plant at power for the safeguards buses is from the house service power transformers being fed from the 161 kV !acoming line with on site emergency power from either one of two diesel generators and off-site standby power via the unit auxiliary transformers.m The loss of the 161kV incoming line Icaders the house service transformers (Tl A-3 and TI A-4) inoperable in that the transformers cannot supply power to the 4.16kV safeguards buses l A3 and 1 A4.

Inonerability of the house service transformer (s) or loss of the 161kV incomine line is DDLicoortable pursuant to 10 CFR 50.72 criteriathowever. the NRC will be prorr.ptly notified of these events via the NRC Oncrations Center.

The two emergency diesel generators on site do not require outside power for start up or operation.

Upon loss of normal and standby power sources, the 4.16 kV buses lA3 and 1 A4 are energized from the diesel generators. Bus load shedding, transfer to the diesel generator -

and pickup of criticalloads are carried out -atomatically.*

When the turbine generator is out of service for an extended period, the generator can be isolated by openinr, motor operated disconnect switch DS-Tl in the bus between the generator and the main transformer, allowing the main transformer and the unit auxiliary power transformers (Tl A-1 and TI A 2) to be retumed to service.* Ihe auxiliary power transformers are not considered inonerable during these normal plant startup/ shutdown realignments.

2-35 Amendment No. 76 l

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. I 5.9.3 Soecial Reoorts 1

Special reports shall be submitted to the Regional Administrator of the appropriate NRC !

Regional Office within the time period specified for each report. 'Itese reports shall be submitted covering the activities identined below pursuant to the requirements of the applicable reference specification where appropriate: -

a. In service inspection report, reference 3.3.

b. Tendon surveillance, reference 3.5.

c. Containment structural tests, reference 3.5.

d. Special maintenance reports.

c. Containment leak rate tests, reference 3.5.

f. Radioactive efnuent releases, reference 2.9.

g. Materials radiation surveillance specimens reports, reference 3.3.

h. Fire protection equipment outrge, reference 2.19.

1. Post accident monitoring instrumentation, reference 2.21.

L Electrical svtems. reference 2.7(2L 5.9.4 Unique Reoorting Recuirements

a. Radioactive Efnuent Release Reoort A report covering the operation of the Fort Calhoun Station during the previous six months shall be submitted within 60 days after January 1 and July 1 of each year per the requirements of 10 CFR 50.36a.

The radioactive efnuent release report shall include a summary of the quantities of radioactive liquid and gaseous efnuents and solid waste released from the plant as outlined in Regulatory Guide 1.21, Revision 1.

The radioactive effluent release report shall include a summary of the meteorological conditions concurrent with the release of gaseous efnuents daring each quarter as outlined in Regulatog Guide 1.21, Revision 1.

The radioactive effluent release report shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 1.

In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The meteorologica1 conditions concurrent with the '

5-15 Amendment No. 9,24,38,46,86,+10,43,G3

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2. 0 IJAllTING COND111 DES 101LDERAllON 2.7 Electrical Syllems (Continued)

(2) hiMincation of Minimum RequiIcmen1s The minimum requitements may be modified to the extent that one of the following conditions will be allowed after the rea.;tw coolant has been heated above 300*F.

Ilowever, the reactor shall not be made crai<al unless all minimum requiremcots are met. If any of the provisions of these exceptions are violated, the reactor shall be placed in a hot r,hutdown condition within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . If the violation is not corrected within an additional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the reactor shall be placed in a cold shutdown condition within an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a. Both unit auxiliary power transformers Tl A 1 and -2 (4.16 kV) may be inoperable for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided the operability of both diesel generators is demonstrated immediately.

b. liither house service transformer TI A 3 or TI A 4 (4.16kV) may be inoptrable for up to 7 days provided the operability of the diesel generator associated with the inoperable transformer is immediately verified The NRC Operations Center shall be notined by telephone within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months eiter '

transformer inoperability. Continued operation beyond 7 days is j permissible, provided a special report is submitted to the NRC within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after transformer inoperability pursuant to Section 5.9.3 of the Technical Specifications. The special report will outline the plans for restoration of transformer operability and the additional precautions to be taken while the transformer is out of service.

c. Iloth house service transformers TI A 3 and TI A-4 (4.16kV) may be inoperable for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the operability of both diesel generators is immediately verified. The loss of the 161kV incoming line renders both transformers inoperable. The NRC Operations Center shall be notined by telephone within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after transformer inoperability.

Continued operation beyond 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is permissible, provided a special report is submitted to the NRC within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after both transformers' ,

inoperability pursuant to Section 5.9.3 of the Technical Specifications.

l The special report will outline the plans for restoration of the f

transformers' operability and the additional precautions to be taken while the transformers are out of senice.

2-33 Amendment No. 25 i

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2.0 , LIMITING CONDITIONS FOR OITR6110E 2.7 Ek:Arkal Systems (Continued)

m. liither one of the 125V d-e distribution panels Al-41 A or Al-41B may be inoperable for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

n, liither one of the 120V a-c instrument panels Al 42A or Al-42B may be inoperable for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Unb The electrical systern equipment is arranged so that no single failure can inactivate enough engineered safeguards to jeopardire the plant safety. The 480 V safeguards are arranged on nine bus sections. The 4.16 kV safeguards are supplied from two buses.

The normal source of auxiliary power with the plant at power for the safeguards buses is from the house service power transformers being fed from the 161 kV incoming line ,

with on-site emergency power from either one of two diesel generators and off site standby power via the unit auxiliary transformers.* The loss of the 161kV incoming line renders the house service transformers (TI A 3 and TI A-4) inoperable in that the transformers cannot supply pcwcr to the 4.16kV safeguards buses l A3 and 1 A4.

Inoperability of the house service transformer (s) or loss of the 161kV incoming line is not reportable pursuant to 10 CFR 50.72 criteria; however, the NRC will be promptly notifirx! of these events via the NRC Operations Center.

The two emergency diesel generators on site do not require outside power for start up or operation.

Upon loss of normal and standby power sources, the 4.16 kV buses l A3 and 1 A4 are energized from the diesel generators. Iki load shedding, transfer to the diesel generator and pickup of critical loads are carried out automatically.*

. When the turbine generator is out of serdee for an extended period, the generator can be isolated by opening motor operated disconnect switch DS-Tl in the bus between the generator and the main transformer, allowing the main transformer and the unit auxiliary power transformers (TI A-1 and Tl A-2) to be returned to service.* The auxiliary power transformers are not considered inoperable during these normal plant startup/ shutdown l realignments.

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2-35 Amendment No. 76

. 4 5,.9.3 Soccial Reggls Special reports shall be submitted to the Regional Administrator of the appropriate NRC Regional Office within the time periou specified for each report. These reports shall be submitted covering the activities identined below pursuant to the requirements of the applicable reference specification where appropriate:

a. In service inspection report, reference 3.3. l

b. Tendon surveillance, reference 3.5. l

c. Containment structural tests, reference 3.5.

d. Special maintenance reports,

c. Containment leak rate tests, reference 3.5.

f. Radioactive efDuent releases, reference 2.9.

g. Materials radiation surveillarice specimens reports, reference 3.3.

h. Fire protection equipment outage, reference 2.19.

i. Post-accident monitoring instrumentation, reference 2.21

j. Electrical systems, reference 2.7(2). l 5.9.4 Unique Reporting Requirements

a. Radioactive Effluent Relpase Reoort A report covering the operation of the Fort Calhoun Station during the previous six months shall be submitted within 60 days after January I and July 1 of each year per the requirements of 10 CFR 50.36a.

The radioactive efnuent release report shall include a summary of the quantities of radioactive liquid and gaseous ef0uents and solid waste rcicased from the plant as outUncd in Regulatory Guide 1.21, Revision 1.

The radioactive efnuent release report shall include a summary of the meteorological conditions concurrent with the release of gaseous efnuents during each quarter as outlined in Regulatory Guide 1.21, Revision 1.

The radioactive effluent release report shall ina.ude an assessment of radiation doses from the radioactive liquid and gaseous ef0uents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 1.

In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The meteorological conditions concurrent with the-5 15 Amendment No. 9,34,38,46,86, 440,444,433

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DISCUSSION, JUSTIFICATION, AND NO SIGNIFICANT HAZARDS CONSIDERATION Omaha Public Power District (OPPD) is proposing to change Specification 2.7,

" Electrical Systems," to correct inconsistencies and to provide further guidance on equipment necessary for the 161kV powr supply. Addie. tonally, administrative changes are proposed for Specification 2.7. following is the discussion and justification for the proposed changes.

Specification 2.7 Electrical Systems Specification 2.7 1)

Minimum Requiremen(ts As currently written this specification applies when the reactor coolant is above 300 degrees Fi however, the modification to minimum requirements only applies after the reactor is critical. If the reactor coolant is above 300 degrees but not yet critical, and a listed system is declared inoperable Specification 2.0.1 is invoked which requires the unit to be placed in liot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . If the same system is declared inoperable at full power the modification to minimum requirements apply which contain an allowed outage time for the specific system and additionally allow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to place the unit in hot shutdown if the system outage time cannot be met.

The proposed revision to Specification 2.7 2) as it applies to 2.7(1),

would allow the same modifications to min (imum requiremer.ts above 300 degrees F as allowed after criticality. However, it would not allow the reactor to be made critical unless all of the listed systems are operable.

The statement concerning minimum requirements is being ruvised to add the word " coolant" and delete the word *up" to be more consistent with Specification 2.5.

Administrative Changes Specifications 2.7(1)a.,2.7(1)b., and 2.7(1)d. contain typographical

errors. The equipment designation for transformers is identified as "Tl" l

and is being corrected to read "T1."

Specification 2.7(1)i,j, and k are being revised to include the specific equipment designations.

Specification 2.7(1)h. contains tynographical errors. The equipment designation for electrici.1 panels is identified as "Al" and is being corrected to read "Al."

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Specification 2.7f25 Modification of Min' mum Requirements The proposed revision would allow the modification of minimum requirements to apply af ter the reactor is above 300 degrees f or af ter the reactor has been made critical. This revision will not allnd the reactor to be made critic 01 unless all systems listed in 2.7(1) are operable. Additional clarification is also proposed for the time limits contained in the action statement. This proposed change is consistent with the present specif; cation and does not change the allowed outage time. The action statement allows a total of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to reach the cold shutdown condition.

Specification 2.0.1, which would be invoked if syAtems in excess of the modification to mininium requirements are inoperable, allows a total of 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months to reach the cold shutdown condition.

Proposed Specifications Concerning inoperability of Housu Service Transformers OPPD has reviewed Technical Specification 2.7(2)b house service transformers TIA-3 and TIA 4 and 2.7(2)n 161kV off-site power supply Limiting Conditions for Operation for that equipment using the guideline provided by the NRC in a Safety Evaluation Report dated January 30, 1990. (ACN No. 9002070242) The proposed Technical Specification will delete the present specification 2.7(2)n in its entirety and modify 2.7(2)b to provide direction on the 161kV supply. The proposed specification will define time limits and reporting requirements.

Proposed Specification 2.7(2)b One House Service Transformer (TIA-3 or TIA-4) Inoperable This specification would allow operation for seven (7) days with one house service transformer out of service and is consistent with the present specifications. Verbal notification of the transformer inoperability will be made within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Added to this portion of the specification is a clause which permits operation beyond the seven days provided OPPD submits a special report to the NRC within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months detailing restoration plans and measures taken to prevent a plant trip and diesel generator inoperability while the transformer is out of service.

Continued operation is considered desirable in that a unit shutdown would result in the loss of one of the 4.16kV safeguards buses resulting in challenges to the diesel safety system and primary system transients. The proposed specification also directs the operability verification of the diesel generator associated with the inoperable House Service Transformer to be completed. This provides additional assurance that the plant can be safely shutdown, if required. Verification is defined as a reverification of the last monthly surveillance test. Demonstrating operability of the diesel generator by conducting the surveillance test is not desirable.

Conducting the surveillance test requires that the diesel be taken out of the automatic modo. This would create a situation whereby one division of safeguards equipment would be without any emergency power for the duration of the test.

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Pro)osed Specification 2.7 2 Sot 1 House Service Transfor(me)c. rs (T1A-3 and TIA-4) Inoperable The proposed specification would allow operation for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .vith both house service transformers out of service. The specification has been clarified to indic. ate that the loss of the 161kV off-site power is considered to render both House Service Transformers inoperable.

Demonstrating operability of the diesel generators by conducting the surveillance test is not desirable. Consistent with the present specification, the operability of both diesel generators is to be verified, which is defined as a reverification of the last monthly surveillance test. Conducting the surveillance test requires that the diesel be taken out of the automatic mode. This would create a situation whereby one division of safeguards equipment would be without any emergency power for the duration of the test.

The reporting requirement specifies that a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months verbal notification be made to the NRC. If operation is to be continued beyond 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months a i

special report must be sent to the NRC within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months detailing restoration plans and additional measures to be taken while the transformers are out of service.

Continued operation is a preferred course of action rather than shutdown because a turbine generator trip would result in a loss of off-site power.

This loss of off-site power would cause the following:

1. Diesel generator start and energizing of the safety busses.

2. Natural circulation cooling of fuel to remove decay heat, j

3. Decay heat removal from the steam generators via the main steam safety valves due to loss of the condenser.

4. A challenge to the automatic auxiliary feedwater system.

The plant cannot establish the normal hot shutdown configuration until 345kV backfeed has been established after the turbine generator trip.

Condenser operations can then be reestabl.shed and the reactor coolant pumps restarted.

Specification 2.7(2)n This specification is to be deleted. The loss of the 161kV off-site supply will be specified in Te:nnical Specifict. tion 2.7(2)c. The specification which permits reactor startup with the 161kV out of service p will be deleted. The present Technical Specification is incorrect in that i although the reactor could be taken to hot standby (critical), the rid or even suppl house

! To:merator ads. could not be synchronized This is because the disconnect switch to the power hS-T1, is a manuaf/ motor switch with no synchronization capability. The 345kV bus must be de-energized before - closing DS-T1. Removal of the 345kV bus would de-energize all four - Reactor Coolant Pumps and this would scram the reactor.

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Basis of Specification 2.7 Changes to Discussions Concerning the 161kV Power Supply Contained in the Basis Clarification concerning the loss of the 161kV line has been added tu the basis of Specification 2.7. This clarification indicates that the loss of the incoming 161kV line renders the house transformers inoperable due to their inability to supply the 4.16kV safeguards buses lA3 and 1A4. In order to restore off-site power to i the safeguards buses upon loss of the 161kV line 345kV backfeed must be manually established. Therefore, upon the Ioss of the 161kV line, the house servi e transformers are considered inoperable.

A statement is being added clarifying that the loss of 161kV will not be reported pursuant to 10 CfR 50.72 criteria.

Additional clarification has also been added concerning the operability of the auxiliary transformers. Normal plant startup and shutdown requires manually transferring the 4.16kV buses IAl, lA?, '

1A3 and 1A4 between the 345/22kV and the 161kV power supply.

During thu actual realignment manipulations, off-site power, although available, cannot power the transformers until completion of the manipulations. This clarification states that the transformers are not considered inoperable during these startup and shutdown realignments. During normal power operations should the 161kV incoming line be lost, the auxiliary power transformers supply the 4.16kV buses lAl, IA2, IA3, and 1A4 from the 345/22kV system after automatic fast transfer occurs.

5.0.3 Special P,eports Specification 5.9.3 is being revised to add a reference to Technical pecification 2.7(2).

Administrative Changes to the Basis A correction has been made to the example contained in the basis which discusses the results of losing bus lA3. In the normal electrical lir.eup bus IA3 (4.16kV) powers bus IB3A (480 V)f two and island bus IB3A aA (480 V . This lineu would cause the loss o pumps and one containment high spray CS p(ressure safety pump and leave one HPSinj)ection HPSI (I anavailable upon two CS pumps loss of b)us IA3. This correction does not affect the number of pumps assumed to be available in a Design Basis Accident.

The rating of tha battery chargers is being revised from "200" to

- "400" amperes to reflect an increase in rating as a result of modification MR FC-84-119.

The word "avilible" is misspelled and is being corrected to read "available."

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9 Basis for No Significant Hazards consideration The proposed changes do not involve significant hazards consideration Lacause operation of fort Calhoun Station in accordance with this change would not:

1. Involve ti significant increase in the probability or consequence of an accident previously evaluated.

Changes to the Minimum Requirements and Modification to the Minimum Requirements The proposed changes to the minimum requirements and modification to minimum requirements do not increase the arobability or consequences of an accident previously evaluated. "his propcsed change would allow the modification to minimum requirements that apply when the reactor is at full power to also apply when the reactor is above 300 degrees F but not critical. The consequences of an accident at full power are significantly greater than when the reactor is not critical. By not allowing the unit to be made critical unless all of the systems listed in the minimum requirements are operable ensures that the consequences would not be increased.

Changes Concerning the Operation of the 161kV Line and Associated Equipment The proposed changes concerning the operation of the 16)kV off-site power line and associated equipment does not adversely affect the consequences or probability of an accident or event previously evaluated. This change clarifies the operability requirements of the remaining power sources during times when the House Service

Transformers are out-of service, requires reporting of actions to l restore the transformer (s) and other precautions to be taken while the t'ansformer is out-of service, and removes the permissive to restart with the 161kV linr! eut of-service. The present Specifications allow the 161kV line, and therefore the transformers, to be out-of-service for an indefinite time period. This change defines a consistent allowed cutage time for both the 161kV line and the associated transformers.

Changes to Table 2-10

! The proposed changes to Table 2-10 are administrative only. These changes consist of correcting typographical errors and providing clarification which is consistent with an interpretation from the l Office of Nuclear Reactor Paquiation. Therefore, the changes to

, Table 2-10 does not invoke a significant increase in the probability or consequences of an accident previously evaluated.

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ML20101P537

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