Text

Amend 16 Licenses NPF-37 & NPF-66 & Amend 7 to Licenses NPF-72 & NPF-75,changing Tech Specs to Eliminate Setpoint Verification in Trip Actuating Device Operational Test for Relays
	ML20148S388
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	04/08/1988
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20148S391	List: ML20148S388; ML20148S398;
References
	NPF-37-A-016, NPF-66-A-016, NPF-72-A-007, NPF-75-A-007 NUDOCS 8804180387
	Download: ML20148S388 (16)
	v • d • e

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'4r UNITED STATES 6.

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NUCLEAR REGULATORY COMMISSION 3 ( W). ;i WASWNGTON D. C. 20555

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,g; v COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. NPF-37 1.

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

A.

The application for amendment by Comonwealth Edison Company (the licensee) dated May 20, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.

There is reasonable assurance (1) 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tion 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:

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2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.16 and the Environtnental 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.

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Huller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 8,1988

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UNITED STATES es j. f., Gaj) t NUCLEAR REGULATORY COMMISSION 1

WASHINGTON, D. C. 20555

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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. NPF-66 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee)datedMay 20, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No NPF-66 is hereby amended to read as follows:

l l

2 (2) Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.16 and revised by Attachment 2 to NPF-60, and the Environmental Protection Plan contained in Appendix 8, both of which are 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.

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 8,1988

ATTACHMENT TO LICENSE AMENDMENT NOS.16 AND 16 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN-50-454 AND STN 50-455 l

Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-10 3/4 3-10 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 l

l l

l i

4 TABLE 4.3-1 (Continued)

E5 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS z

TRIP EE El

.'NALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLhMCE

"' FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED e

- 12.

Reactor Coolant Flow-Low S

R Q

N.A.

1 13.

Steam Generator Water Level-S R

Q**

N.A.

1, 2 Low-Low l

14.

Undervoltage-Reactor Coolant N.A.

R N.A.

Q**(10)

N.A.

1 Pumps (Above P-7) t' 15.

Underfrequency-Reactor N.A.

R N.A.

Q(10)

N.A.

1 Coolant Pumps (Above P-7) l T

$$ 16.

Turbine Trip (Above P-7) a.

Emergency Trip Header N.A.

R N.A.

S/U(1, 10)

M.A.

1 Pressure b.

Turbine Throttle Valve N.A.

R N.A.

S/U(1,10)

N.A.

1 Closure 17.

Safety Injection Input from N.A.

N.A.

R N.A.

1, 2 ESF l

18.

Reactor Coolant Pump Breaker N.A.

N.A.

R N.A.

1 3E Position Trip (Above P-7) a n,

!E 19. Reactor Trip System Interlocks a

i E

a.

Intermediate Range Neutron Flux, P-6 N.A.

R(4),

Q N.A.

N.A.

2##

-d z

P b.

Low Power Reactor Trips Block, P-7 N.A.

R(4)#

Q (8)

N.A.

1 c.

Power Range Neutron Flux, P-8 N.A.

R(4),

Q (8)

N.A.

1

- --=-

u

-v---

v, m u m.--

,,y,---y.,

-p:.,--y1 um s4y..

,,y

TABLE 4.3-2 (Continued) oo Yg ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENIS E

TRIP g

ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH g

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

, FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED g

5. Turbine Trip and Feedwater (Continued) b.

Steam Generator Water S

R M

N.A.

1, 2 Level-High-High (P-14) c.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

6. Auxiliary Feedwater w

A Manual Initiation N.A.

N.A.

R N.A.

N.A.

1,2,3 a.

{

b.

Automatic Actuation N.A.

N.A N.A.

N.A.

N(1)

M(1)

Q 1,2,3 Logic and Actuation Relay w

c.

Steam Generator Water S

R M

N.A.

1, 2, 3 Level-Low-Low d.

Undervoltage-RCP Bus N.A.

R N.A.

M(3)

N.A.

1, 2 l

e.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

f.

Division 11 fo Unit 1 N.A.

R N.A.

M(2, 3)

N.A.

N.A 1, 2, 3, 4 l

(Division 21 for Unit 2)

ESF Bus Undervoltage g

g.

Auxiliary Feedwater S

R M

N.A.

1, 2, 3 g

Pump Suction Pressure-g Low m

l

57. Automatic Opening of g

Containment Sump Suction Isolation Valves 4

I s

TABLE 4.3-2 (Continued)

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION h

SURVEILLANCE REQUIREMENTS TRIP E

ANALOG ACTUATING MODES U

CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

[FUNCTIONALUNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED D. Automatic Opening (Continued) a.

Automatic Actuation Logic and Actuation Relays N.A.

N.A.

M(1)

Q 1,2,3,4 b.

RWST Level-Low-Low S

R M

N.A.

1, 2, 3, 4 Coincident With Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements w

M. Loss of Power

{

a.

ESF Bus Undervoltage N.A.

R N.A.

M(2, 3)

N.A.

1,2,3,4 l

b.

Grid Degraded Voltage N.A.

R N.A.

M(3)

N.A.

1,2,3,4 9.

Engineered Safety Feature Actuation System Interlocks a.

Pressurizer Pressure, N.A.

R M

N.A.

1,2,3

~

P-11 b.

Reactor Trip, P-4 N.A.

N,A.

N.A.

R N.A.

N.A.

1, 2, 3 c.

Low-Low T,yg, P-12 N.A.

R N

N.A.

1,2,3 5

d.

Steam Generator Water S

R M

N.A.

M(1)

Q 1, 2 Level, P-14

'i (High-High)

TABLE NOTATION g

g'(1)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2)

Undervoltage relay operability is to be verified independently. An inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the OPERABLE channel per Specification 4.3.2.1.

(3)

Setpoint verification is not applicable.

l The specified 18 month interval may be extended to 32 months for Cycle 1 only.

8

/[s.%f ['t UNITED STATES NUCLEAR REGULATORY COMMISSION j.I 1

WASHING TON, D. C. 20555 t],;, ',f s,..v C06HONWEALTH EDISON COMPANY DOCKET h0. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendroent No. 7 License No. NPF-72 1.

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

A.

The application for amendment by Comonwealth Edison Company (the licensee) dated May 20, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter It B.

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

There is reasonable assurance (1) that the activities authorized by this arnendment 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 amendment will not be inimical to the consnon 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 4

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

2.

Accordingly, the license is amended by changes to the Technical Specifica-tion 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 reed as follows:

2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 7 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.

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate 111-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 8,1988 l

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1

8, UNITED $TATES

%. ' > m ',g NUCLEAR REGULATORY COMMISSION y4 E

W ASHING T O N, 0. C. 20555

...../

COM)NWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. NPF-75 1.

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

A.

The application for amendment by Comonwealth Edison Company (the licensee)datedMay 20, 1987, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct) and the Comission'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 Comission; C.

Thereisreasonableassurance(1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-75 is hereby amended to read as follows:

I 2

i (2) Technical Specifications The Technical Specifications contained in Anpendix A as revised through Anendment No. 7 and the Environmental Protection Plan contained in Appendix B. both of which were attached to License No.

NPF-72, dated July 2,1987, are hereby incorporated into this license. Attachment 2 contains revisions to Appendix A which are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environrental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Huller, Director i

Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects i

Attachment:

Changes to the Technical Specifications Date of Issuance: April 8. 1988 I

T

O ATTACHMENT TO LICENSE AMENDMENT NOS. 7 AND 7 AND FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-75 DOCKET NOS. STN-50-456 AND STN 50-457 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-10 3/4 3-10 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 E

f P

f l

i

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o

E5 TRIP ES ANALOG ACTUATING MODES FOR CHANNEL.

DEVICE WHICH gg CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED w

- 12.

Reactor Coolant Flow-Low 5

R#

Q

- N. A.

N.A.

1 e-63 13.

Steam Generator Water Level-S R#

Q**

N.A.

1, 2 Low-Low 14.

Undervoltage-Reactor Coolant N.A.

R N.A.

Q**(10)

N.A.

1 Pumps (Above P-7)

R: 15. Underfrequency-Reactor N.A.

R N.A.

Q(10)

N.A.

1 Coolant Pumps (Above P-7) w

[g 16.

Turbine Trip (Above P-7) a.

Emergency Trip Header N.A.

'R N.A.

S/U(1, 10)

N.A.

1 Pressure b.

Turbine Throttle Valve N.A.

R N.A.

S/U(1,10)

N.A.

1 l

Closure l

l 17.

Safety Injection Input from N.A.

N.A.

R N.A.

1, 2 ESF 18.

Reactor Coolant Pump Breaker N.A.

N.A.

R N.A.

1 Position Trip (Above P-7) '

ll

19. Reactor Trip System Interlocks me a.

Intermediate Range ll Neutron Flux, P-6 N.A.

R(4)#

Q N.A.

N.A.

2##

E b.

Low Power Reactor gg Trips Block, P-7 N.A.

R(4)#

Q (8)

N.A.

I c.

Power Range Neutron flux, P-8 N.A.

R(4)#

Q (8)

N.A.

1

'd

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

SURVEILLANCE REQUIREMENTS 68 TRIP ANALOG ACTUATING MODES c

CHANNEL DEVICE MASTER SLAVE FOR WHICH l

35 CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE UFUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

~

e.S. Turbine Trip and Fcedwater (Continued) b.

Steam Generator Water S

R#

M N.A.

N.A.

1, 2 Level-high-High (P-14) c.

Safety Injection See Item 1. abeve for all Safety Injection Surveillance Requirements.

6. Auxiliary Feedwater l

{

a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3 w

b.

Automatic Actuation N.A.

N.A N.A.

N.A.

M(1)

Q 1,2,3 O

Logic and Actuation Relay w

i.

c.

Steam Generator Water S

R#

M N.A.

N.A.

1, 2, 3 Level-Low-Low d.

Underv01tage-RCP Bus N.A.

R N.A.

M(3)

N.A.

M.A.

N.A.

1, 2 l

e.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

f.

Division 11 for Unit 1 N.A.

R N.A.

M(2,3)

N.A.

N.A 1, 2, 3, 4 l

(Division 21 for Unit 2)

ESF Bus Undervoltage g.

Auxiliary Feedwater 5

R M

N.A.

1 A.

N.A.

1,2,3 Pump Suction Pressure-Low E

97. Automatic Opening of E

Containment Sump Suction 9

Isolation Valves

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS co sf TRIP E5 ANALOG ACTUATING MODES E5 CHANNEL DEVICE MASTER SLAVE FOR WHICH E$

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED e

7. Automatic Opening (Continued) a.

Automatic Actuation Logic and Actuation

[,*

Relays N.A.

N.A.

M(1)

Q 1, 2, 3, 4 b.

RWST Level-Low-Low 5

R#

M N.A.

N.A.

1, 2, 3, 4 Coincident With Safety Injection See Item 1 above for all Safety Injection Surveillance Requirements

8. Loss of Power to a.

ESF Bus Undervoltage N.A.

R N.A.

M(2,3)

N.A.

1, 2, 3, 4 l

[]

b.

Grid Degraded Voltage N.A.

R N.A.

M(3)

N.A.

1, 2, 3, 4 d>9. Engineered Safety Feature Actuation System Interlocks a.

Pressurizer Pressure, N.A.

R#

M N.A.

N.A.

1, 2, 3 P-11 b.

Reactor Trip, P-4 H.A.

N.A.

R N.A.

N.A.

1, 2, 3 Low-Low T,yg, P-12 N.A.

?,#

M N.A.

N.A.

1, 2, 3 c.

d.

Steam Generator Water S

R#

M N.A.

M(1)

Q 1, 2 Level, P-14 (High-High)

TABLE NOTATION Nni(1)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

Esd'(2)

Undervoltage relay operability is to be verified independently. An inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the OPERABLE channel per Specification 4.3.2.1.

25(3)

Setpoint verification is not applicable.

g 5

i

ML20148S388

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