ML20024H544

Amends 123 & 112 to Licenses DPR-39 & DPR-48,respectively, Revising Diesel Generator Testing Requirements & Allowable Outage Times by Incorporating Recommendations of Generic Ltr 84-15

ML20024H544
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	05/17/1991
From:	Barrett R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20024H542	List: ML20024H541 ML20024H544 ML20024H545
References
GL-84-15, NUDOCS 9106040428
Download: ML20024H544 (30)

Text

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g NUCLEAR REGULATORY COMMISSION L

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4 COMMONWEALTH EDISON COMPANY 00CKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 APENDMENT TO FACILIT) OPERATING LICENSE Amendment No.

123 License No. OPR-39 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated March 27, 1991, as supplemented by letter dated April 30, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations 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; There is reasonable assurance (i) that the activities authorized C.

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; The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.

51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the licer

'ded by changes to the Technical e attachment to this license Specifications as in(

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amendment, and paragre of facility Operating License No. DPR-39 is hereby a.....oed to read as follows:

9106040420 910517 PDR ADDCK 05000295 PDR P

i

_ _ _ _ - - -.... _. - - _ _ =

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.123

, are hereby incorporated in the license.

The licensee shall operate the f acility in accordance with the Technical Specifications.

3.

The license is further amended by removing item B 6 from Appendix A of the Order dated February 29, 1980.

4 This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMM15510N Richat J Barfett, Director project Directorate 111-2 Division of Reactor projects - lil/lV/V Office of fluclear Reactor Reguation

Attachment:

1.

Changes to the Technical Specifications 2.

Page 3 of Appendix A of the 6rder dated February 29, 1980 Date of Issuance:

May 17, 1991

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UNITED ST ATES g

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NUCLE AR REGULATORY COMMISSION 5

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C,0MMONWEALTH EDISON COMPANY DOCKET NO. 50-304 710N NUCLEAR POWER STATION, UNIT ?

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

112 License No. DPR 48 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated March 27, 1991, as supplemented by letter dated April 30, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Cormission's rules and regulations set forth in 10 CFR Chapter 1; 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; D.

The issuance of this anendment 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:

4 2

(2) Techniral Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.112, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license is further amended by removing item B.6 from Appendix A of the Order dated February 29, 1980.

4 This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Richard J. Barrett, Director Project Directorate 111-2 Division of Reactor Projects - Ill/lV/V Office of Nuclear Reactor Regulation

Attachment:

1.

Changes to the Technical Specif icatior,s 2.

Page 3 of Appendix A of the Order dated February 29, 1980 Date of Issuance:

May 17,1991 l

l

ATT ACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.123 TO F ACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO.112 TO FACILITY OPERATING LICENSE NO. DPR 48 DOCKET N05. 50-795 AND 50-304 revise the Appendix A Technical $pecifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Remove Pages insert Pages iv iv X

X 151 151 165 165 169 169 172 17?

176 176 179 179 194 194

?S5a 255b 256 256 257 257

?58 258 259

?59 259a 2ED 260 264 264 265 265 265a 266a

?66a 267 267 270a 272 272 273 272 274 274 324 324 9

i 4

Y SURVElllANCE

~

LIMITING CONDlH0fLEDR_0ECR&H09 REGIIEDfEMI EAGE i

3.13 Refueling Operations 4.17 243

}

3.13.1 Core Reactivity 4.13..'

243 I

3.13.2 Protection from Damaged Spett fuel 4.13.2 244 l

t 3.13.3 Containment Status 4.13.3 245 l

r 3.13.4 Radiation Monitoring 4.13.4 246 i

3.13.5 Refueling Equipment Checkout 4.13.5 246 3.13.6 Refueling Equipment Operablitty 4.13.6 246 I

3.13.7 Spent fuel Pit Cooling Systems 4.13.7 246

}

3.13.8 Fuel Inspection Pro 9 ram 4.13.8 247 i

3.13.9 Residual Heat Removal System Operation

(

247c 3.13.10 Hater Level - Reactor Vessel 247d 3.13.11 Water Level - Storage Pool 4.13.9 247a i

Bases 248 i

3.14 Plant Radiation Monitoring 4.14 250 Bases 254 3.15 Auxiliary Electrical Power System 4.15 255 i

i Bases 271 l

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3.16 Radiological Environmental Monttoring 4.16 275 j

Bases 279 f

3.17.1 Ventilation 4.17.1 281 i

3.17.2 (Section Deleted) 283 i

3.18 Steam Generator Activity 4.18 289

[

Bases 290 i

3.19 Failed fuel Monitoring 4.19 292

)

Bases 3.20 Radioactive Solids 293 i

4.20 295a l

Bases 3.21 Fire Protection i

Bases 4.21 2950-V f

i 3.22 Shock Suppressors (Snubbers) 4.22 295H Bases 295Z j

3.23 Special Test Exceptions 4.23 295AB

]

Bases

+

295AC I

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TABLE OF CONTENTS (Continued)

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IV' Amendmont Nos.123 and 112 1,

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EAnt Table 185 4.8-1 Centrifugal Charging Pump System 186 4.8-2 Safety Injection Pump System 187 4.8-3 Residual Heat Removal Pump System 188 4.8-4 Accumulator Tanks 189 4.8-5 Component Cooling Pump System 190 4.8-6 Service Water Pump System 192 4.8-7 Hydrogen Control System 192b Accident Monitoring Instrumentation Surveillance Requirements 4.8.9-1 203 4.9-1 Isolation Seal Hater System 204 4.9-2 Penetration Pressurization System 227 Radioactive Liquid Effluent Sampilng and Analysis 4.11-1 Survelliance 228b Radioactive Liquid Effluent Monitoring Instrumentation 4.11-2 Surveillance 238 Radioactive Gaseous Effluent Sampilng and Analysis Program 4.12-1 240 Radioactive Gaseous Effluent Monitor Instrumentation 4.12-2 Survelliance 253 Plant Radiation Monitoring Instrumentation Surveillance 4.14-1 270 4160 Volt Engineered Safeguard Bus Main Reserve, and 4.15-1 l

Standby Feeds 270a 4.15-2 Diesel Generator Test Schedule 280 Mastmum Values for the lower Limits of Detection (LLD) 4.16-1 LIST OF TABLES (Continued)

X Amendment Mos. 123 and 112

.- r LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT i

3.6.1 4.6.1.A 2.

The containment spray power operated valves shall be stroned manually from the control room each month.

Performance will be acceptable if I

valve motion is indicated upon l

actuation.

3.

The spray nozzles shall be checked for proper functioning at least every five years.

B.

The three containment spray systems B.

Not Applicable.

l shall be operable for pressure i

reduction and two of three systems for todine removal whenever the reactor is in hot standby or operating except as specified in 1.6.lC.

C.

From and after the time that one of C.

When it is determined that one the three containment spray systems containment spray system 15 inoperable, for pressure reduction or two of the the remaining system shall be three systems for lodine removal are demonstrated to be operable immediately.

made or found to be Inoperable for j

any reason, reactor operation including recovery from an inadvertent trip is permissible only i

during the succeeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> i

I provided that during those 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

1) for pressure reduction the

-emaining containment spray systems i

shall be operable and four fan coolers are operable, or 2) for icdtne removal the remaining containment spray systems are l

operable.

I D.

If these conditions cannot be met.

D.

Not Appilcable.

the reactor shall be brought to the 151 Amendment Nos.123 and 112 1

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I SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION i

i 4.8.1.A 1.

and the discharge pressure is within

[

i 3.8.1 1 01 of a point on the pump heat curve.

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2.

The centrifugal charging pump system 4

power operated valves shall be stroked manually from the control room each l

month. Performance will be acceptable if valve motion is indicated upon actuation.

B.

Not Applicable.

i B.

The two centrifugal charging pump systems shall be operable whenever the l

reactor is in hot standby or operating except as specified in 3.8.1.C.

C.

From and after the date that one of the C.

When It is determined that one of the two centrifugal charging pump systems is

[

two centrifugal charging pump systems inoperable, the remaining centrifugal 1s nade or found to be Inoperable for any reason, reactor operation including charging pump system, both residual heat l

removal pump systems, and both safety recovery from an inadvertent trip is injection pump systems shall be permissible only during the succeeding demonstrated to be operable lamediately and 7 days provided that during those 7 days the remaining centrifugal charging dally thereafter.

pump system 1s operable and both l

residual heat removal pump systems and l

both safety injection purp systems are operable.

i D.

Not Applir.able.

[

D.

If these conditions cannot be met the i

reactor shall be brought to the hot

[

shutdown condition within four hours.

f Affer a max 1 mum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the hot shutdown condition, if the system 15 i

not operable the reactor shall be br:ught to the cold shutdown condition l

wtthin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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Amendment Nos-123 and 1!2

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT i

3.8.2 4.8.2.A 3.

The normally open valve (MOV-SIS 806) In j

the suction line of the safety injection pumps shall be stroked manually from the control room to check l

l the position Indicators and j

annunc14 tors every refueling outage.

I' B.

The two safety injection pump systems 8.

Not Appilcable

i shall be operable whenever the reactor i

is in hot standby or operating except i-as spec 1 fled in 3.8.2.C.

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l C.

From and after the date that one of the C.

When it is determined that one of the two j

j two safety injection pumps is made or safety injection pump systems Is inoperable j

i found to be Inoperable for any reason, the remaining safety injection pump system.

l j

reactor operation including recovery both centrifugal charging pump systems, and

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l from an inadvertent trip is permissible both residual heat removal pump systems l'

only durlag the succeeding 7 days shall be demonstrated to be operable i

provided that during those 7 days the immediately and daily thereafter.

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remaining safety injection pump system 1

and both centrifugal charging pump

[

systems and both residual heat removal j

j pump systems are operable.

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j 169 Amendment Nas 123 and itz i

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2 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT i

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3.8.3 4.8.3.A 6.

The containment 'Rectrculation Sump to RHR Pump Suction Valves' shall be i

stroked at a containment pressure of 20 j

psig following each containment leakage i

rate test to insure operability (MOV-SI8811A, MOV-SI88118).

j I

B.

The two residual heat removal pump 8.

Not Appilcable.

l systems shall be operable whenever the l

J reactor is in hot standby or operating except as specified in 3.8.3.C.

1

)

C.

From and after the date that one of the C.

When it is determined that one of the two j

j tuo residual heat removal pump systems residual heat removal pump systems is i

is made or found to be Inoperable for inoperable the remaining residual heat any reason, reactor operation including removal system, both centrifugal charging l

recovery from an inadvertent trip 15 pump systems,.nd both safety injection pump f

i permissible only during the succeeding 7 systems shall be demonstrated to be operabia days provided that during those 7 days immediately and dally thereafter.

the remaining residual heat removal pump l

i system is operable and both centrifugal charging pump systems and both safety 2

injection pump systems are operable.

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172 Amendment Nos. 123 and 112

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q LIMITING CONDITION FOR OPERATION SURVEllt.ANCE REQUIREMENT L

L 3.8.6 B.

Except as specified in Sections 3.8.6C 4.8.6 B.

Not Applicable.

i and 3.8.60 the following numbers of i

components cooling water pumps and heat exchangers shall be operable when the i

reactors are in hot standby or operating:

t 1.

One untt:

3 pumps and 2 heat exchangers

{

l 2.

Two units:

I 4 pumps and 3 heat exchangers l

C.

From and after the date that two of the C.

lehen it is determined that two of the l

component cooling water pumps are found f1ve component cocling pumps are or made 1t. operable during 2 unit inoperabic, the remaining pugs shall be

[

operation, reactor operation on one un.

demonstrated to be operable lamediately I

may proceed Indefinitely.

Reactor and daily thereafter.

The status of the operation is limited to 7 days on the heat exchangers shall be checked other unit provided that, dur1pg those 7 1mmediately and daily thereafter.

days, the remaining three pumps and the y

three heat exchangers are operable.

D.

From and after the date that two of the D.

14 hen it is determined that two of the component cooling uater pumps and.wi-five component cooling water pumps and f

l the heat exchangers are found or a l.

one of the component Cooling heat i

j inoperable during 2 untt operation, enchangers are Inoperable the standby reactor operation on one unit may heat exchanger shall be made operable y

proceed indefinttely. Reactor operation lamediately and the remaining pump i

is Ilmited t 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on the other unit vertfled operable tsumediately as l

provided that, during those 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, spectfled in section 4.8.6.C above.

the s'emaining three pumps and the p

reaming 2 heat exchangers are operable.

)

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176 Amendment Nos. 123 and 112 f

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT B.

Three service water pumps

• per unit shall be 4.8.7 B.

Not Applicable.

operable whenever the reactor is in hot standby or operating except as specified in 3.8.7.C C.

Frc 7nd after the date that one of the C.

When it is determined that one of the three

<lce water pumps

• per unit is made three service water pumps ** per unit is or fout.- to be inoperable for any reason.

Inoperable, the remaining systems shall i

reactor operation is permissible only during be demonstrated to be operable the succeeding 7 days provided that the two Immediately and dally thereafter.

remaining service water pumps are operable.

D.

If these conditions cannot be met the D.

Not Applicable.

reactor shall be brought to the hot shutdown condition within four hours. After a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the hot shutdown condition, if the system is not operable the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• With the 48-inch service water discharge headers There are no surveillance requirements for l

In the cross-tied mode, one operable service one service water pump on a unit inoperable, water pump from the other unit with independent provided that the 48 inch service water standby AC and DC power supplies may be used to discharge headers are in the cross-tied fulfill the operating requirements of 3.8.7.A.

mode, and one operable service water pump 3.8.7.B. and 3.8.7.C. for both Units 1 and 2.

from the other unit with Independent standby Only one of the six service water pumps may be AC and DC power supplies is being used to used to fulfill the operability requirements for fulfill the operability requirements of I

both Units I and 2.

3.8.7.C.

In this case, if an additional service water pump becomes Inoperable, the l

surveillance requirements of 4.8.7.C apply.

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l 179 Amendment Nos.

12,

,,a 5,9

Bales 3.8 and 4.8 (Continued)

The availability of the systems is demonstrated by The pressure and

,N l t' fr 1.ie accumulators water is injected t - r immediately demonstrating the OPERABILITY of the assure that the regt

.a components redundant to the failed one, as well as with the required bot std cc9 centration following the OPERABILITY of the Inter-related systems.

The a loss-of-coolant acc)Je.it.

The limits are based on continued availability of these components during the the values used for the accident analyses. (4) repair period is demonstrated by repeating these tests dally.

The five component cooling system pumps and three heat exchangers are located in the Auxillary Butiding Assuming a reactor has been OPERATING at full rated and are a shared system between Units I and 2.

The i

power for at least 100 days, the magnitude of the components are accessible for repair after a decay heat decreases after inttlating MODE 3.

Thus, loss-of-coolant accident. During the rectrculation the requirement for core cooling in case of a 3hase following a loss-of-coolant accident on a unit, j

postulated loss-of-coolant accident while in the MODE only one component cooling pump and heat exchanger is 3 condition is significantly reduced below the required for minimum safeguards of that unit.

requirements for a postulated loss-of-coolant Therefore, a alnimum requirement of four component accident during POWER OPERATION. Putting a reactor cooling pumps and three heat exchangers for two In the M00E 3 condition significantly reduces the OPERATING units provides sufficient redundancy. (5) potential consequences of a loss-of-coolant accident, and also allows more free access to some of the A total of six service water pumps are Installed; i

engineered safeguards components in order to effect only one service water pump 1s required immediately repairs.

following a postulated loss-of-coolant accident. (6)

(See p. 195)

Failure to complete repairs within the allowable time after going to the MODE 3 condit!on is considered indicative of a requirement for major maintenance and therefore in such a case, the reactor'in general 15 to be put into the MODE 5 condition.

The limits for the accumulators and refueling water storage tank Insure the required amount of water with the required boron concentration is available for i

injection into the primary coolant system following a l

loss-of-coelint accident and are based on the values used for the accident analysts (4).

1 194 Amendment Nos. 123 and 112

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SURVEILLANCE REQUIREMENT LlHITING CONDITION FOR OPERATION 3.lS.I.A.2 supplying power to the Unit 4.15.1 2.4160-volt safeguards buses 247, 248 and 249.

B.

Diesel Generators (IA, 18 and 0, 2A and B.

Standby AC on-site power 28)

The unit diesel generators (IA and 18 for Unit 1 - 2A and 2B fcr Unit 2) and 1.

Not appilcable.

the common diesel-generator (0) shall be operable.

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256 Amendment Nos.123 and 112

5 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.1.8 4.15.1.8.1 2.

Each diesel generator shall be demonstrated operable when tested in accordance with Regulatory Guide 1.108, Revision 1. August 1977, ut111 zing the frequency specified in Table 4.15-2, and:

a.

The diesel generators shall be started and loaded to 4000 KH.

This load shall be maintained until diesel-generator operating temperatures have stabilized.

b.

Duringthedieselgeneratortestl specified in 4.15.1.B.2.a. the diesel starting air compressors shall be checked for operation and their ability to recharge the air receivers.

During the diesel generator test l c.

specified in 4.15.1.B.2.a., the diesel oil transfer pumps shall be checked for operation and their ability to transfer oil to the day tank.

Ps7 Amendment Nos. 171 ami 11^

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS

(

3.15.1.8 4.15.1.B 3.

Refueling outage testing shall be i

4 I

4 performed in accordance with Regulatory

, Guide 1.108, Revision 1. August 1977 and:

a.

During each refueling outage the j

diesel generators shall be started

't and loaded under simulated LOCA and-I Loss-of-Offsite power conditions.

[

and run for a minimum of 5 minutes j

in each case, wlth emergency loads.

The proper diesel-generator starting and loading time, required bus load sheriding, and sequential starting i

and operation of emergency equipment shall be vertfled.

b.

During each refueling outage, the diesel generator shall be loaded to 4000 KW and held at this load for

[

one hour after the diesel generator l

operating temperatures have stabilized.

This test need not be I

performed on the common diesel (0)

'(

if it was performed in conjunction with the previous refueling outage of the other' unit.

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c.

During each refueling outage, the capabillty of the diesel generator i

to reject a load of 4000 KW shall be demonstrated.

This test need not be

[

performed on the common diesel (0) if it was performed in conjunction with the previous refueling outage i

of the other unit.

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?58 Amendment Mos. 173 and 1 r-f

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.-l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.1.B 4.15.1.B.3 d.

During each refueling outage.

[

the capability of each-starting j

air compressor to charge the air i

receiver to 250 pstg within 60 k

minutes shall be.ver1fted.

e.

During each refueling outage.

the capacity of each diesel oli transfer pump shall be vertfled to be at least 6 gpe.

4.

Inspection i

i Each diesel generator shall be given j

an Inspection, at least every l

refueling outage following procedures prepared in conjunction.

l with the manufacturer's recommendation. This need not be t

performed on the common diesel (0) i if it was performed in conjunction with the previous refueling outage l

of the other unit.

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259 Amendment Nos. 123 and 112 l

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i LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.1.8 4.15.1.B.5 Repotis - All diesel generator fattures, l

valid or non-valid, shall be reported within 30 days to the Commission.

Reports of diesel generator failures l

shall include the information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

If the number of failures in the last 20!'.00 valid tests (on a per diesel generator basis) is greater than or equal to 7, the report shall be supplemented to include the additional Information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1 August 1977.

C.

Reserve AC off-site power C.

The status of reserve AC off-site power shall be checked dally.

1.

Un i t._1 One 345-KV line (in addition to that described in Section 3.15.1.A.1 above),

345-)V bus Section 3, the Unit 2 system Amendment Nos. 773 anq tt-psoa

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.l.C.1 auxillary transformer (TR #242) and Unit 4.15.1.C.

2 4160-volt bus 241 shall be energized.

The switchgear necessary to supply this power to Unit 1 4160-volt buses 147, 148 and 149 shall be operable.

2.

Unll_2 One 345-KV line (in addition to that described in Section 3.15.1.A.2 above).

345-XV bus section 7, the Unit I system auxillary transformer (TR #142), and Unit 1 4160-volt bus 141 shall be energized.

The switchgear necessary to supply this power to Unit 2 4160-volt buses 247, 248 and 249 shall be operable.

D.

Engineeied Safeguards Buses 0.

1.

The unit 4160-volt engineered safeguards 1.

During each refueling outage the buta; (147, 148 and 149 for Unit 1 -

following interlocks associated with the 247 248 and 249 for Unit 2) are unit 4160-volt engineered safeguards enei;ized.

buses (147, 148 and 149 for Unit I -

247, 248 and 249 for Unit 2) shall be functionally tested (see Table 4.15-1):

a.

Auto-transfer from main or reserve feed to standby feed.

b.

Parallel-feed prevention between reserve feed and main or standby feed.

2.

The unit 480-volt engineered safeguards 2.

Not Applicable.

based t137, 138 and 139 for Unit 1 -

237, 238 and 239 for Unit 2) and their respective Motor Control Centers are energized.

260 Amendrent Nos. 123 and 112

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15 2.

For power operation, including recovery from 4.15 2.

Power Operation inadvertant trip, the availability of I

electric power shall be as specified In 3.15.1 except as specified in 3.15.2. A.

3.15.2.B. 3.15.2.C. 3.15.2.D. 3.15.2.E.

3.15.2.F. and 3.15.2.G.

A.

From and after the date that off-site A.

When incoming power is available power to a unit is available from only from only one source to a unit, one source (Normal or Reserve as demonstrate the operability of the described in 3.15.1.A and 3.15.1.C),

remaining off-site power source by reactor operation is permissible only performing Surveillance Requirement l

during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided 4.15.1.A within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least the three emergency diesel-generators for once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

In that unit referred to in 3.15.1.8 are addition, the operability of that operable.

The three diesel-generators unit's diesel-generators (IA, 18 and shall be demonstrated to be operable O for Unit 1 - 2A, 28 and 0 for Unit l

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2) shall be confirmed by conducting l

the testing specified in Section 4.15.1.B.2.

This shall be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B.

From and after the time lat'which no B.

When no off-site power is available off-site power is available to a unit to a unit the three diesel the reactor for that unit shall be generators of the unit shall be placed in the hot shutdown condition and started and loaded to their j

maintained in this conditlnn.

While at respective buses.

hot shutdown, the three above mentioned diesel generators of the unit shall be in operation.

l 264 Amendment Nos. 123 and 112 4

J LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT-3.15.2.8 4.15.2.B.

If off-site power cannot be. restored within 48. hours after reaching the hot shutdown condition, the reactor of that unit shall be placed in the cold

-shutdown condition.

C.

From.and after the date that one of the C.

When one diesel generator is diesel generators for a unit (IA, 18 or inoperable, the other two diesel 0 for Unit 1.- 2A, 28 or 0 for Unit 2) generators shall be demonstrated to l

1s made or found inoperable reactor be operable by conducting the operation on that unit.ls permissible-testing specified in Section I

only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• 4.15.1.B.2 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The provided that the two remaining diesel availability of the two sources of l

generators are operable and the two off-site power shall be demonstrated sources of off-site power in Sections by performing Surveillance 3.15.1.A and 3.15.1.C are available.

Requirement 4.15.1.A within i hour The availability of two sources of and.at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> off-site power shall be demonstrated thereafter.

j within ! hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

The operability of the two remaining diesels shall be demonstrated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(

0.

From and after the date that one of the D.

When an Engineered Safeguards Engineered Safeguards 4160-volt buses of 4160-volt bus of a unit (147, 148 or a unit (147, 148 or 149 for Unit 1 -

149 for Unit 1 - 247, 248 or 249 for 247, 248, or 249 for Unit 2) is made or Unit 2) is inoperable the equipment found to be Inoperable for any reason, listed in Table 3.15-1 for that~ unit the reactor of that unit will be placed will be demonstrated to be operable-in the hot shutdown condition within 4 immediately and daily thereafter hours until the bus is made operable or the reactor of that unit placed in The reactor may be maintained in this the cold shutdown condition.

condition for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided the major components listed in Table 3.15-1

.t are operable.

If 1

265 Amendment Nos. 123 and 112

~

p The common diesel generator (0) may be' inoperable for up to 7 days for maintenance and testing provided one unit is' in MODE 5 or 6 and three remaining diesel generators are OPERABLE-(two OPERABLE on the operating unit and one OPERABLE on the unit in MODE 5 or 6).

The three remaining OPERABLE diesel generators shall be demonstrated OPERABLE by performance of Surveillance Requirement 4.t5.1.B.2 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to removal of the common diesel (0) from service.

In addition.. prior to taking the coremon diesel generator (0) out of service, verify (#) that at least three service water pumps and three component coollr.g water pumps are OPERABLE with their associated emergency power supplies. During the 7 day period, the three remaining OPERABLE diesel generatorsishall be vertfled (#) OPERABLE daily, in addition to any testing required by Surveillance Requirement 4.15.1.B.2.

During the 7 day period, for the unit in MODE 5 or 6 no mid-loop or reduced RC5 Inventory operations, as defined in MRC Generic Letter 88-17, will be performed while fuel is in the vessel.

In the event one or more diesel generators (other than the common diesel generator (0)) for the operating unit becomes Inoperable, the operating unit will be brought to MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 5 within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

In the event two diesel generators (other than the connon diesel generator (0)) on the un t in Mode 5 or i

6 become Inoperable, the operating. unit will enter Actions 3.15.2.C and 3.0.5.

(#) The term " verify" as used in this context means to administratively check by examining logs or other-Information to determine if certain components are out of service for maintenance or other reasons.

It does not mean to perform the Survelliance Requirements needed to demonstrate the OPERABILITY of the components.

265a Amendment Mos. 123 and 117

. ~

=..

LIMITING COM0! TION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.2 (Continued) 4.15.2. (Continued)

F.

From and after the date that a 125-volt F.

During the period when a battery l

battery charger is made or found inoperable, charger is inoperable and the reactor operation on that unit is battery charge is being maintained permissible only during the succeeding 14 by a battery charger of the other days.

During this period the tie breakers unit, the output voltage and current from the battery charger's bus to the of the cross-tied charger shall be e

corresponding battery bus of the other unit checked and recorded inanedtately and shall be closed and the battery charger of dally thereafter.

In addition the that battery shall be OPERABLE.

testing specified in section-4.15.1.E.1 shall be performed 1sumediately and dally thereafter on the two batteries that are cross-tied.

l t

i 266a Amendment Nos. 123 and 112 i

r l

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT-3.15.2.

G.

From and after the date that one 4.15.2.

G.

During the period when one of the instrument inver ter of a unit (111,112, instrument inverters of a unit is 113 or 114 for Unit 1 -'211, 212, 213 inoperable, the remaining inverters and 214 for Unit 2) is not operable, of that unit shall be vertfled to be i

reactor operation of that unit 1s operable dally by checking the permissible only during the succeeding output voltage and current of the 14 days.

If the inverter is not Inverters.

l restored to service within the 14 days, or if a second inverter becomes inoperable, the reactor of the unit shall be brought to the cold shutdown condition.

H.

If more than one of the conditions specified in 3.15.2.A. 3.15.2.8, 3.15.2.C. 3.15.2.0, 3.15.2.E. 3.lS.2.F and 3.15.2.G occur concurrently, the reactor of the affected unit shall be brought to the hot shutdown condition immediately.

If a specified limiting condition for operation has not been restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor of that unit shall be placed in the cold shutdown condition.

3.

Diesel Fuel 3.

Diesel fuel l

A.

There shall be a minimum of 40,000 A.

The quantity of diesel fuel available in the storage and day gallons of diesel fuel in the storage tanks shall be checked once a month tants and 350 gallons in the day tanks or on a daily basis when the diesel for each diesel.

generators are used.

267 Amendment Nos. 123 and 112

n l

-t h

NUMBER OF FAILURES'IN LAST 20 VALID TESTS

• TEST FREQUENCY t

i i1 at least once per 31 days 12 at least once per 7 days **

i 1

f Criteria for determining number of failures'and number of valid tests shall be in accordance with Regulatory l

Position C.2.e of Regulatory Guide 1.108 Revision 1 August 1977.

The number of failures and valid tests are to be determined on a per diesel generator basis.

Failure to satisfactorily complete 4.15.1.B.2.b.

i 4.15.1.B.2.c., 4.15.1.8.3.d 4.15.1.B.3.e, or 4.15.1.B.4 does not constitute failure of a valid test and does not require an increased frequency of testing.

l i

This test riequency shall be maintained untti seven consecutive failure free demands have been performed And I

the number of failures in the last 20 valid demands has been reduced to one.

i i

i i

l i

\\

Olesel Generator Test Schedule i

i r

TABLE 4.15-2

.i l

i 270a Amendment Nos. 123 and 1' 2 4

i

In the normal mode of operation for a unit, the 345-KV system is operating and three diesel generators are operational for that unit.

One diesel-generator may be allowed out of service based ao the availabtllt, >f power to the 345-KV switchyard, with normal supply from that unit's system aux 111ary transformer, a reserve supply from the other unit's system aux 111ary transformer, and the fact that any two diesels are capable of supplying all engineered safeguards equipment necessary to cover all possible postulated accident conditions.

The footnote for Limiting Condition 3.15.2.C requires that when two diesel generators (other than the common diesel (0)) on the unit in Mode 5 or 6 become' Inoperable, the operating unit will enter Actions 3.15.2.C (to require reactor shut down within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) and will enter 3.0.5 (to ensure that components depending on the common (0) diesel generator for emergency power are OPERABLE and powered from their corresponding normal power supplies, and to ensure that all required redundant components are OPEEABLE).

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Allowed Outage Time entered in 3.15.2.C will cosamence upon discovery of the second inoperable diesel generator on the unit in Mode 5 or 6.

The resoirement to ensure that at least three total diesel generators are OPERABLE for an operating unit, stherwise 3.15.2.C is entered, is entered, is due to Technical Specification requirements tP4t require that at least 3 service water pumps be OPERABLE for an operating unit'(Specificattor. 3.8.7.8), and that at least 3 component cooling water pumps be OPERABLE for an operating unit (Specifications 3.8.6.A.1 and 3.8.6.B.1).

The Action Statements of the proposed footnote are therefore consistent with ensuring that the operating unit will be safely shut down without delay.

t 272 Amendment Mos. 123 and 112

An inoperable engineered Safeguards 4160-volt bus results in the Inoperability of the safeguards components supplied by this bus (See Table 3.15.2).

If the equipment supplied by the other two Safeguards 4160-volt buses remains operable (See Table 3.15.1), sufficient components are available for safe shutdown and decay heat removal following a loss of coolant accident and/or loss of off-site power, but redundancy has been The required available equipment stated in the Specification are consistant with those of the remaining lost.

operable Engineered Safeguard components.

In addition, a crosstle is j

The battery charger can carry the DC load of its bus Independently of the battery.

available from a corresponding bus on the other untt; this tie can be ut1112ed to maintain bus voltage and allow safe unit shutdown if the charger and battery are unavailable.

Since the battery charger can carry the bus, and since a backup source of power is available for shutdown I

should the charger be lost, the battery may be Inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without loss of control power for the engineered safeguards features.

If a battery charger were to fall, the proper state of charge can be maintained on the fatted charger's battery by closing the cross-tie breakers to the other unit's battery bus and utilizing that battery charger to maintain the proper state of charge on both batteries.

Operation with a Unit 1 and Unit 2 battery crosstled is permissible because a single failure will, at most, cause loss of control power to one of the three safeguards system on each unit; the two remaining systems are designed for safe shutdown and decay heat removal.

Because the independence of redundant systems is thus maintained, the requirements of Section 9 of IEEE 308-1971 are satisfied for this inter-unit tie.

Under these conditions, a battery charger may be inoperable without unduly compromising the reliability of the safeguards systems.

Operating conditions or equipment maintenance may require one inverter to be inoperable for brief periods.

480/120 AC transformer. Reference (1)

During these perlods, the instrument bus will be supplied by adiscusses the ramifications if, during this The probability of simultaneous loss of off-site power to both units is, however, estimated to 10-5 fo, one occurrence over a forty year period; with this low a probability, one inverter can be l

are affected l

be 5 x Inoperable for i 14 day period without unduly compromising reliability.

The minimum of storage tank for each diesel generator has a capacity of 50,000 gallons.

The diesel fuel 40,000 gallons aach will supply each diesel a minimum of one week of operation at rated power.

f (1) L. DI Butterfield letter of Dec. 1, 1972

~

to 8 H Grter in response to Regulatory f

Operations Bulletin 72-2.

273 Amendment Nos. 123 and 112 j

f

Haiti:

e 4.15 Q1eieLGeneratori The qualification testing of the diesel generator is designed to establish a 0.99 reliability with a confidence level of 951.

This testing is described in response to Question 8.22 of the FSAR and hus been accepted by the Directorate of Licensing.

(1)

The periodic testing of the diesel generators is conducted to meet the intent of Section 6.4.1 of IEEE Trial-Use Standard 387-1972 and conducted in accordance with Regulatory Guide 1.108. Revision 1. August, 1977, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Pover Systems at Nuclear Power Plants," which demonstrates the continued availability of the diesel generators.

The diesel generator will be manually started and loaded to 4000 KH as recommended by the manufacturer; this load will be maintained until operating temperatures are normaltzed.

In conjunction with this testing, the diesel starting air compressors and the diesel oil transfer pumps are also tested to demonstrate their continued availability.

The surveillance frequency requirements are consistent with the intent of NRC Generic Letter 84-15, " Proposed Staff Actions to Improve and Maintain Diesel Generator Rellability," issued July 2, 1984.

The refueling outage testing is conducted in accordance with Regulatory Guide 1.108, Revision 1, August 1977, and to meet the intent of Section 6.4.2 of IEEE Trial-Use Standard 387-1972 which demonstrates the continued capability of the diesel generators to perform their functions.

In conjunction with this testing, tests are also performed on the diesel starting air compressors and the diesel oil transfer pumps to demonstrate their l continaed capability to perform their functions.

The performance criteria for the air compressors is based on the acceptance standards for the system; the criteria for the diesel oil transfer pumps is based upon supplying fuel at a rate greater than the maximum rate of consumption of the diesel.

Batteries Station batteries can be expected to deteriorate with time but precipitous failure is extremely unlikely.

The type of weekly and quarterly surveillance specified has demonstrated over the years the ability to detect Indications of a cell becoming irregular or unserviceable long before it fatis.

The periodic equalizing charge will ensure that the ampere-hour capacity of the batteries is maintained.

Each refueling outage the batteries are visually inspected and subjected to a discharge performance test or service teit as recommended by IEEE Std. 450-1980, "IEEE Recommended Practice for Halntenance, Testing, and Replacement of Large Lead Storage Battertes for Generating Stations and Substations," to ensure that the battery ha ; maintained its required capacity.

Following this discharge test the battery is restored to the fully chatged condition.

In addition, a performance test is conducted on the battery charger to verify its ability ta supply sufficient amperage to recharge a battery and also supply normal loads.

(2)

The tests described above are proven power plant practice and will ensure the continued availability of the battery as well as its continued capability to carry design load.

(1) Section 8.3.1 of Safety Evaluation by the Directorate of Licensing U.S.A.E.C., in the Matter of Commonwealth Edison Company Zion Nuclear Power Station Units I and 2 Docket Nos 50-295 and 50-304, dated October 6, 1972 (2) FSAR Section 8.4.1.4 274 Amendment Nos. 123 and 112

l 6.6.3.8 Sacclai Reoorts (Continued)

IDElC SUBMITTAL DATE l

1.

Pressurizer PORV or Safety Valve Document the event in the Annual Report l

challenges l

j.

(future) k.

Steam generator tube inspection and/or Per surveillance requirements 4.3.1.8.5 plugging.

l.

Emergency Core Cooling System (ECCS)

W1 thin 30 days as LER - include nozzle usage actuation and injection when RCS temp 2 fi.ctor per T.S. 3.3.2.F.3 350*F m.

Fire detector inoperability Within 30 days per T.S. 3.21.1.C n.

Fire pump system inoperability Within 30 days per T.S. 3.21.2.8 o.

Fire-suppression system inoperability Within 30 days per T.S. 3.21.2.C cr 3.21.2.0 p.

Sprinkler system looperability Within 30 days per T.S. 3.21.3.C i

q.

Low prassure CO2 syn em inoperability Within 30 days per T.S. 3.21.4.C Diesel generator failures Per survelliance requirement 4.15.1.B.5 r.

SPECIAL REPORTS Table 6.6-1 (Continued) 324 Amendment Nos. 123 and 112

1 2.

To ensure control room habitability under accident conditions, the licensee shall reexamine ventilat,on intakes, location of potential plant leakage (ingress and egress), and control room filter capabilities, and submit the results of this revitet to the NRC.

3.

Emergency action levcis shall be revised to require notification of the NRC for all events in the emer9ency classes described in NUREG-0610, September 1979.

4.

The licensee shall comply with the NRC's "!NTERIM POSITION FOR CON-TAINMENT PURGE AND VENT VALVE OPERATION PENDING RESOLUTION OF ISOLATION VALVE OPERABILITV", as contained in the October 1979 letter to the licensee. The licensee comitted to this position in its December 14, 1979 letter to the NRC.

5.

Plant personnel shall be trained or retrained in the following areas within thirty days, or prior to startup if required by the Lessons Learned implementation schedule. Plant personnel shall also be re-trained in the following areas within thirty days of the time that there are significant changes to the procedures or requirements applicable to these areas:

Containment and Degraded Core Sampling Degraded Core - Training Emergency Power for Pressurizer Heaters and Decay Heat Removal Containnent Isolation Containment Purge / Purge Valve Operation Subcooling Meter Operation Technical Support Center Onsite Operational Support Center Near-Site Emergency Operations Center Emergency Preparedness Plan in-Plant Area Airborne Radioiodine Monitors y;

6. Alicensee shall perform diesel generator testing in accordance with Reguhqry Guide 1.108 with a corresponding change in the allowable c

outage tt stipulated in the Limiting Conditions of Operation as follows:

m Numbers of OG Failu h Test Interval (Days)

Allowable In Prior 100 Tests

( R. G. 1.108)

Outage Time 8

C 0 or 1 As is 8

2 14 As is 12 x

3 7

As Is E

4 3

32 hr.

5 3

8 h r.

b" 6 or more 3

ene*

• Plant must achieve hot shutdown with 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown he following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l

_