ML20217N363

Amends 111,111,104 & 104 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Requirements Related to cross- Tie DC Power Buses Between Units & Removing Refs to At&T Batteries Which Have Been Replaced at Braidwood Station

ML20217N363
Person / Time
Site:	Byron, Braidwood
Issue date:	10/13/1999
From:	Anthony Mendiola Office of Nuclear Reactor Regulation
To:	Commonwealth Edison Co
Shared Package
ML20217N369	List: ML20217N363 ML20217N371
References
NPF-37-A-111, NPF-66-A-111, NPF-72-A-104, NPF-77-A-104 NUDOCS 9910280197
Download: ML20217N363 (20)

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UNITED STATES a-NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066dHXO1 COMMONWEALTH EDISON COMPANY DOCKL:T NO. STN 50-454

SYRON STATION UNIT NO 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.111 e

License No. NPF-37 1.

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

A.

'.The application for amendment t.y Commonwealth Edison Company (the

, licensee) dated June 30; 1999, comu'ies 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; C.

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

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. NPF-37 is hereby amended to read as follows:

9910280197 991013 PDR AD0cn 05000454 p

PDR i

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a-Q.(2)

Technical Specifications

' The Technical Specifications contained in Appendix A as revised through Amendmerit No.111 and the Environmental Protection Plan contained in

. Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

. 3.

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

FOR THE NUC, LEAR REGULATORY COMMISSION

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' Adthony J. Mendiola, Chief, Section 2 foject Directorate til Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

. Specifications Date of issuance: October 13, 1999

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION t

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WASHINGTON, D.C. 205584M1

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u COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NOJ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.111 License No. NPF-66 j

1.

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

i A.

The application for amendment by Commonwealth Edison Company (the licensee) dated June 30,1999, complies with the standards and requirements of 1

the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the 1

I 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 j

Commission's regulations;

]

' D.

The issuance of this amendment will not be inimical to the common defense and security or to the health ana 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 Facdity

' Operating License No. NPF-66 is hereby amended to read as follows:

I

..t.

, (2); ' Technical Specification _g.

' The Technical Specifications contained in Appendix A (NUREG-1113), as

' revised through Amendment No.111 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix 'B, both of which were attached to License No NPF-37, dated February 14,1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the

' facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance an:.1 shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

, _j[

thony J. Mendiola, Chief, Section 2 -

Project Directorate Ill Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

.. Changes to the Technical Specifications Date of Issuance:' October 13, 1999 1

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ATTACHMENT TO LICENSE AMENDMENT NOS.111 AND 111

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. FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454'AND STN 50-455

(

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Revise the Appendix A Technical Specifications by removing the page identified below and

- inserting the attached page. The revised page is identified by the captioned amendment number and contains marginal lines indicating the areas of change'.

h:rve Paae -

Insert Paae 3.8.5-1 3.8.5-1 i

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w, DC Sources-Shutdown 3.8.5 i

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g J3l8GELECTRICAL; POWER. SYSTEMS 3'8151DC S6urces-Shutdown m

_ l LC0 C3.8 51<

}Theifol.lowingshallbe!0PERABLE-

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q One.DC electrical power subsystem ca)able of supplying

a;

.one division of.the.onsiteLC1. ass 1E )C: electrical power distritiution subsystem (s) required by. LC0 3.8.10.

_ " Distribution. System--Shutdown. ".with at. least one unit:

crosstie breaker,open: and b.

One' source of DC electrical power other than that.

M 1

yr.equired by LCO 3.8:5.a. capable of supplying the o

ed

? remaining onsite Class 1E DC electrical aower

- " ~

. distribution subsystem (s)"when required ay LC0 ~3.8.10.

~

.N0TE 10ne' division may be crosstied to the opposite unit, when the~

-opposite unit is in MODE l'..2. 3. or 4 with an inoperable a..

battery. charger.

l LAPPLICABILITY:'

MODES 5 and'6.

m During movement of-irradiated fuel ' assemblies.

2 e

ACTIONSj.

-NOTE LCO '3,0:3Jis not ' applicable'.

1 i.

s i

. W CONDITION.

JREQUIRED ACTION

~ COMPLETION TIME 1A? 'Onelor,more required.

A.1L Declare affected Immediately

" 'DC electrical power; required feature (s) r.subsystemsninops able; inoperable.

tfor reasonsLoahrithan o

m

. Condition'Bi er

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,i LBYRON?. UNITS T & 2,

, Amendment 111 & 111 w

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3.8 ; 5 - 1:

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UNITED STATES j

,j NOCLEAR REGULATORY COMMISSION WASHINGTON, o.C. 2055&4001

'+9....,o COMMONWEALTH EDISON COMPANY D_Off 4O_.,5TN 50-456 O

BRAIDWOOD STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF-72 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated June 30,1999, 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; C.

There is reasonable assurance (i) that the activities authorized by this i

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 1

Commission's regulations; 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 i

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. NPF-72 is hereby amended to read as.'ellows:

l 3

.a 2-

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,-(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through

- Amendment No.104 and the Environmental Protection Plan contained in

' Appendix B both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. '

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

FOR THE NUCLEAR REGULATORY COMMISSION g _' -

[

2' pony J. Mendiola, Chief, Section 2

/ Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

- Changes to the Technical Specifications Date of issuance: October 13, 1999-L k

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UNITED STATES

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NUCLEAR REGULATCRY COMMISSION

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WASHINGTON, D.C. 20555-4001 y.....,e COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 -

BRAlpWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF-77

- 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated June 30,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules -d 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; 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

' Coramission's regulations:

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 amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating L! cense No. NPF-77 is hereby amended to read as follows:

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- Technical Soecifications q

The Technical Specifications contained in Appendix A as revised through

{

s Amendment No.104 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, j

1987, are hereby incorporated into this license. The licensee shall operate the I

facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

]

FOR THE NUCLEAR REGULATORY COMMISSION J'a. -

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hony J. Mendiola, Chief, Section 2 roject Directorate 111 DMslon of Licensing Project Management Office of Nuclear Reactor Regulation j

.'Attachmen't:

Changes to the Technical

Specifications-Date of issuance: - October 13, 1999-l

e

- ATTACHMENT TO LICENSE AMENDMENT NOS. 104 AND 104 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77

• DOCKET NOS. STN 50-456 AND STN 50 457 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines L

indicating the areas of change.

Remove Paaes Insert Paaes 3.8.4 3.8.4-2 3.8.4 3.8.4-3

'3.8.4-4 3.8.4-4

.3.8.4-5 3.8.4-5

' 3.8.4-6 3.8.5-1 3.8.5-1 3.8.5-3 3.8.5-3 3.8.6 3.8.6-4 i

3.8.9-2 3.8.9-2 3.8.9-3 3.8.9-3 I

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DC Sources-Operating la 3.8.4 ACTIONS' (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One DC electrical C.1 NOTE power-division Only required when crosstied to opposite unit has an opposite-unit DC inoperable battery.

electrical power subsystem with an i

inoperable source.

Verify opposite-unit Once per while opposite unit is DC bus load 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l

in MODE 5. 6. or s 200 amps.

defueled.

.A.M C.2 Open at least one 7 days crosstie breaker between the crosstied divisions.

l D.

One DC electrical D.1 Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> power subsystem power subsystem to inoperable for reasons OPERABLE status.

Other than Condition A. B. or C.

I

~l E.

Required Action and E.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated-Completion Time not met.

AND l

E.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> l

I i

l BRAIDWOOD - UNITS 1 & 2

3. 8.4 - 2 Amendment 104 & 104 l

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' DC Sources -Operating 3.8.4' j

1 SURVEILLANCE REQUIREMENTS iSURVEILLANCE FREQUENCY

]

L iSR1 3'8.4,1'

. Verify! battery terminal voltage is 7 days

-ll a 127.6 V on float l charge.

L

SR -3.8,4 2-Verify no visible corrosion at battery 92 days sterminals and connectors.

1 o

. Verify battery connection ~ resistance.is s 1.5E-4' ohm for inter-cell connections.

s 1.5E-4 ohm for inter-rack connections,

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s

.s 1.5E-4 ohm.for: inter-tier connections, and s 1.5E-4 ohm:for terminal connections.

-6 L

SR ' 3. 8.'4,3 -

-Verify battery cells,: cell plates, and 18 month.s racks show no visual indication of physical L

damage or abnormal deterioration that could

degrade battery performance.

/

SR 3.8;4.4-Remove visible' terminal corrosion $erify.

18 months t

battery cell to cell and terminal connections are clean and tight, and are

.. coated with anti-corrosion material.

l Sfi 3.8 W.5

' Verify battery connection resistance is 18' months

's 1-5E-4.ohmLfor inter-cell connections.

L s l.5E-4 ohm for' inter-rack connections.

Es'1.5E-4 ohm for: inter-tier connections, and s.1.5E-4 ohm for terminal connections.

(continued) 1

.BRAIDWOOD - UNITS 1.& 2-3.8.4 - 3?

Amendment 104 & 104 L

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DC Sources-Operating a

3.8.4 SURVEILLANCE REQUIREMENTS l(continued)

SURVEILLANCE FREQUENCY SR '3.8 4.6 Verify each battery charger supplies a load 18 months 1

equal;to the~ manufacturer's rating for 1

. = 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

j 1

- SR - '3.8:4L. 7.

. NOTES---.

1.

The modified performance discharge test in SR 3.8.4-8 may be performed in

' lieu of the service test.in ESR.3.8.4.7.

- 2.

'This Surveillance shall not be

~

l;.

performed in MODE 1.'2. 3. or 4.

1

' Verify battery capacity is adequate-to 18 months supply, and maintain OPERABl.E status, the required ' emergency loads for the design r

-. duty cycle when subjected to a battery service test.

(continued) i u

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c.

4-DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE.

FREQUENCY

~

SR 3.8.4.8-

-NOTE This Surveillance shall not be performed in

~

4 MODE 1.;2,3.or.-4.

i l

' Verify battery capacity is a 80% of:the.

60 months manufacturer.'s. rating when subjected to'a performance discharge' test or a modified AND-performance' discharge test.

12 months when battery shows degradation or has reached 85%

of the expected-life with capacity'< 100%

of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity = 100%

of.

manufacturer's rating i

i

.BRAIDWOOD'- UNITS 1.& 2:.

- 3. 8.4 - 5 '

' Amendment 104 & 104 i

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ge; DC Sources-Shutdown w

3.8.5 L3.8 ELECTRICAL-POWER' SYSTEMS -

3.8.5^ DC Sources--Shutdown l 'LCOL: 3.8.5 (Thefollowingshall:beOPERABLE:

Ja.

One DC': electrical power subsystem'ca3able of supplying

~

one division.of the onsite Class 1E JC electrical power

distribution subsystem (s) required by LCO 3.8.10.

" Distribution System-Shutdown." with at. least :one unit crosstie. breaker open; and

.b.

One source of DC electrical power; other than that

required by LCO 3.8,5.a. capable of supplying the

remaining onsite Class'1E DC-electrical Jower

distribution' subsystem (s) when required )y LC0 3.8.10.

' NOTE =

One division may be crosstied.to'.the opposite unit. when the

= opposite unit is in M00E 1( 2.-3. or 4 with an inoperable battery. charger..

APPLICABILITY:

MODES 5 and:6.

i During movement of irradiated ~ fuel-assemblies.

-l ACTIONS-1

~-

LLCO'3.0.3 is not applicable,

~ NOTE l

j i

CONDITION.

LREQUIREDACTION

' COMPLETION TIME 7

A; 10ne or more required.

'A.1-Declare affected Immediately i

DC' electrical power.

required: feature (s)~

subsystems /ino3erable.-

inoperable.

'for reasons otler.than L

Condition;B.

2-

-1 1

L

'(continued) i

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h 1BRAIDWOOD - UNITS 1 &'2~

<3. 8. 5 ' Amendment 104 &-104

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DC Sources-Shutdown 3.8.5 ACTIONS -(continued)

CONDITION-REQUIRED ACTION COMPLETION TIME B..One DC electrical 8.1 NOTE

. power division

_Only required when crosstied to opposite unit has an

opposite-unit-DC:

inoperable battery.

electrical power subsystem with an inoperable source..

Verify opposite-unit Once per l'f while' opposite unit-is.

DC' bus load is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in MODE 5. 6.-ori s 200 amps.

defueled.

AND B.2 Open at least one 7 days crosstie breaker between the crosstied divisions.

SURVEILLANCE REQUIREMENTS SURVEILLANCE' FREQUENCY SR.3.8.5.1.

-NOTE

~The following SRs are not required to be performed: SR 3.8.4.6, SR 3.8.4.7. and SR 3.8.4.8.

For DC. sources required to be OPERABLE. the In accordance

-following SRs are. applicable:

with applicable SRs SR 3.8.4.1 SR 3 8.4.5 SR 3.8.4.2 SR 3.8.4.6 SR 3.8.4.3 SR 3.8.4.7

.SR 3.8.4.4 SR 3.8.4.8.

P BRAIDWOOD - UNITS 1 & 2-3.8. 5 - 3 Amendment 104 & 104 g...

-. _.., ____i...

o C-Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameters Requirements

-CATEGORY A:

CATEGORY 8:

' CATEGORY C:

LIMITS FOR EACH LIMITS FOR EACH CONNECTED ALLOWABLE LIMITS FOR EACH PARAMETER DESIGNATED PILOT CELL CELL CONNECTED CELL Electrolyte Level

> Minimum level

> Minimum level Above top of plates, and k

indication mark, and s k indication mark, and s V not overflowing i

inchabovemaxif Indication mark g level inchabovemaxiy indication mark g level l

F.loat Voltage a 2.13 V

= 2.13 V(b) l

> 2.07 V l ' Specific Gravity (C)(d)

= 1.200 m'1.195 Not more than 0.020 below 1

dVerage of all Connected g

cells

.l Average of all connected AND cells > 1.205

-.l Average of all connected tells = 1.195 (a)

'It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing.

(b)

Corrected for average electrolyte temperature.

(c)

Corrected for. electrolyte temperature.

(d)

A battery charging current of < 3 amps when on float charge is acceptable for meeting specific gravity 11mits following a battery recharge, for a maximum of 7 days. When CharginQ Current is used to satisfy specific gravity reQu1rementf..

of the 7 day allowance.

Specific gravity of each connected ceil shall be measured prior to expiration L

Bb,0 WOOD-- UNITS 1 & 2

3. 8. 6 - 4 Amendment 104 & 104

o' Distribution Systems-Operating

• L 3.8.9

-ACTIONS-J CONDITION REQUIRED ACTION COMPLETION TIME I

1 A.. One AC electrical A.1 Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

power. distribution..

power distribution subsystem inoperable.

subsystem to OPERABLE AND status.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LC0

' B.- One AC instrument bus B.1 Restore AC instrument 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> electrical power bus electrical power distribution subsystem distribution AND

. inoperable.

subsystem to OPERABLE status.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LCO C.

One DC electrical C.1 Restore DC electrical-2 hours power distribution power distribution subsystem inoperable.

subsystem to OPERABLE AND status.

16. hours from discovery of failure to meet l

LCO D.

Required Action and D.1 Be'in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion

. Time of. Condition A.

AND B. - or C not met.

D.2 Be in MODE 5.

36 nours (continued)

L

'BRAIDWOOD - UNITS 1 & 2 3.B.9 - 2 Amendment 104 & 104

)fI i

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- Distribution Systems -Operating 3.8.9 ACTIONS - (continued'r CONDITION REQUIRED ACTION COMPLETION TIME E.. Two electrical power ;

E. L Enter LC0 3.0.3.

Immediately l

' distribution subsystems: inoperable

.that. result'in a loss of safety function.

I SURVEILLANCEREQUIR$MENTS-SURVEILLANCE FREQUENCY SR--3.8.9.1.

Verify correct breaker alignments and 7 days

. voltage to AC, DC, and AC instrument bus electrical power distribution subsystems, l

l l

l b

.'BRAIDWOOD UNITS 1 & 2i

3. 8. 9'- 3 Amendment 104 & 104

,