ML20199C165

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Amends 96 & 96 to Licenses NPF-37 & NPF-66,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement at Plant
ML20199C165
Person / Time
Site: Byron  Constellation icon.png
Issue date: 01/15/1998
From: Dick G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20199C170 List:
References
NPF-37-A-096, NPF-66-A-096 NUDOCS 9801290150
Download: ML20199C165 (12)
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t UNITED STATES g

j NUCLEAR REGULATORY COMMISSION g,

t WASHINGTON. D.C. 30W. 0001 COMMONWEALTH ED! SON COME6NY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. %

Ucense No. NPF-37 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licenso) dated February 18,1997, as supplemented by letter dated September 22,1997, 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, t

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 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 satisfici 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:

9001290150 900115 PDR ADOCK 05000454 p

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2-(2) Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. % 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 24 4 4C L

Geo F. Dick, Seni r Project Manager Project Directorate lil 2 Division of Reactor Projects til/lV Office of Nuclear Reactor Regula'!on

Attachment:

Changes to the Technical Specifications Date of Issuance: January 15, 1998 l

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION g

WASHINGTON, D.C. 30066 0001

'49.....,d COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50 455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. NPF 66 1.

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

A.

The application for amendment by Commonwealth Edison Coinpany (the licensee) dated February 18,1997, as supplemented by letter dated September 22,1997, 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 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 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-66 is hereby amended to read as follows:

9 2

(2)

Technical Soecifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. % 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 shah operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Geo$

rge F. Dick, Sen or Project Manager Project Directorate 1112 Division of Reactor Projects - lil/lV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 15, 1998

ATTACHMENT TO LICENSE AMENDMENT NOS. % AND EAQlLITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginallines indicating the area of change. Pages indicated by an asterisk (*) are provided for convenience only.

Remove Paoes insed Panes 2-5 25 3/4 3-25 3/4 3-25 3/4326 3/4326

  • 3/4 4-1
  • 3/4 4 1 3/4 4 2 3/4 4 2
  • 3/4 4 3

'3/4 4-3 3/4 4-4 3/4 4-4 3/4 4-5 3/4 4 5

  • 3/4 4-6
  • 3/4 4-6 l

T w

  • 2.2-1 (Continuedl REACTtMt TRIP SYSTEM IWomunn.alaTION TRIP SETPolmia EMPCTIONAL UNIT TRIP.SETPOINTS ALLOIRELE VALUE
12. Reactor Coolant Flow-Low-290% of loop mini-289.3% of loop mipi-num measured flow num measured flow
13. Steam Generator Nater Level Low-Low a.

Unit 1.

233.0% (prior to 231.04 (prior to cycle 9) cycle 9) 218.04 (cycle 9 and 216.11 (cycle 9 and 1

after) of narrow after) of narrow range instrument range instrument span span 6

b.

Unit 2 236.3% of narrow 234.8% of narrow range instrument range instrument span span

14. Undervoltage - Reactor 25268 volts -

24920 volts -

Coolant Pumpe each bus each bus

15. Underfrequency - Reactor 257.0 Hz 256.08 Hz Coolant Pumps 16.. Turbine Trip a.

Emergency Trip Header 21000 peig 1815 peig Pressure b.

Turbine Throttle Valve 21% open 21% open closure

17. Safety Injection Input N.A.

N.A.

from ESF

18. Reactor Coolant Pump N.A.

N.A.

Breaker Position Trip

  • Ninimum measured flow = 92,850 gym t

BYRON - UNITS 1 & 2 2-5 AMENDMENT NO. E

~

TABLE 3.3-4 fcontinued) i ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLONABLE VALUE 4.

Steam Line Isolation a.

Manual Initiation N.A.

N.A.

1 b.

Automatice Actuation Logic N.A.

N.A.

and Actuation Relays c.

Containment Pressure-High-2 58.2 peig s9.4 peig d.

Steam Line Pressure-2640 peig*

2614 peig*

Low (Above P-11) e.

Steam Line Preseure s100 psi +*

s165.3 pel*

Negative Rate-High (Below P-11) 5.

Turbine Trip and Feedwater Isolation a.

Automatic Actuation Logic and Actuation Relays N.A.

N.A.

t b.

Steam Generator Nater Level-High-High (P-14)

1) Unit I sal.4% (prior s83.4% (prior to cycle 9) to cycle 9) 588.04 (cycle 9 589.9% (cycle 9 and after) of and after) of narrow range narrow range instrument span instrument span
2) Unit 2 s80.8% of 582.8% of narrow range narrow range instrument instrument span span I

BYRON - UNITS 1 & 2 3/4 3-25 AMENDMENT NO. N

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP ALLOWABLE FUNCTIONAL UNIT _

SETPOINT VALUE 5.

Turbine Trip a'd Feedwater Iso.. ion (continued) c._

Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

6..

Auxiliary Feedwater a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation Logic and Actuation Relays N.A.

M.A.

c.

Steam Generator Water Level-Low-Low-Start Motor-Driven Pump and Diesel-Driven Pump

1) Unit 1 233.0% (prior to 231.0% (prior to cycle 9) cycle 9) 218.0% (cycle 9 216.1% (cycle 9 and after) of and after) of narrow range narrow range instrument span instrument span
2) Unit 2 136.3% of 234.8% of narrow range narrow range instrument instrument span span d.

Undervoltage-RCP Bus-25268 volts 24920 volts Start Motor Driven Pump and Diesel-Driven Pump i

e.

Safety Injection-Start Motor-l Driven Pump and See Item 1. above for all Safety Injection Trip Setpoints and Diesel-Driven Pump Allowable Values.

l l

BYRON - UNITS 1 & 2 3/4 3-26 AMEN 0 MENT NO. 96 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION-STARTUP AND POWER OPERATION

-LIMITING CONDITION FOR OPERATIONS 3.4.1.1 All reactor coolant loops shall be in operation.

APPLICABILITY:

MODES I and 2.*

ACTION:

With less than the above required reactor coolant loops in operation, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

"See Special Test Exceptions Specification 3.10.4.

BYRON - UNITS 1 & 2 3/4 4-1

REACTOP COOLANT SYSTEM HOT.3TANDBY LIMITING COMDITION FOR OPERATION 3.4.1.2 At least two of the reactor coolant loops listed below shall be OPERABLE with two reactor coolant loops in operation when the Reactor Trip system breakers are closed and one reactor coolant loop in operation when the Reactor Trip system breakers are opent*

Reactor Coolant Loop A and its associated steam generator and a.

reactor coolant pump, b.

Reactor Coolant Loop B and its associated steam generator and reactor coolant pump, c.

Reactor Coolant Loop C and its associated steam generator and reactor coolant pump, and d.

Reactor Coolant Loop D and its associated steam generator and reactor coolant pump.

APPLICABILITY: MODE 3.**

ACTION:

With less than the above required reactor coolant loops OPERABLE, a.

restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.

With only one reactor coolant loop in operation and the Reactor Trip system breakers in the closed position, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> open the Reactor Trip System breakers.

c.

With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant system and immediately initiate corrective action to return the required reactor coolant loop to operation.

SURVEILLANCE REOUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 The required steam generators shall be determined OPERABLE by verifying secondary side narrow range water level to be greater than or equal to 18% (41% for Unit 1 prior to cycle 9) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.2.3 The required coolant loops shall be verified in operation and circu-lating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(1) no operations-are permitted that would cause dilution of the Reactor Coolant system boron concentration, and (2) core outlet temperature is maintained at least 10*F below esturation temperature.

    • see special Test Exceptions specification 3.10.4.

BYROM - UNITS 1 & 2 3/4 4-2 AMENDMENT NO. %

REACTOR COOLANT SYSTEM-HOT SHUTDOWN.

j-LIMITING-CONDITION FOR OPERATION 3.4.1.3-At least two of the loops listed below shall be OPERABLE and at least one of-these loops shall be in operation:*

a.

Reactor Coolant Loop A and its associated steam generator and reactor 4

coolant pump,**

b.

Reactor Coolant Loop B and its associated steam generator and reactor coolant pump,**

c.

Reactor Coolant Loop C and its associated steam generator and reactor coolant pump,"*

d.

Reactor Coolant Loop D and its associated steam generator and reactor coolant pump,**

e.

RHR Loop A, and f.

RHR Loop B.

APPLICABILITY:

MODE 4.

ACTION:.

a.

With less than the above required reactor coolant and/or RHR loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; if the remaining OPERABLE loop is an RHR loop, be in COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With no reactor coolant or RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

(1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet. temperature is maintained at least 10*F below saturation temperature.

BYRON - UNITS 1 & 2 3/4 4-3

REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS 4.4.1.3.1 The required reactor coolant pump (s) and/or RHR pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.2 The required steam generttor(s) shall be determined OPERABLE by verifying secondary side narrow range water level to be greater than or equal to 18% (41% for Unit 1 prior to cycle 9) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.3 At least one reactor coolant or AHR loop shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i.

4 G

l

)

BYRON - UNITS 1 & 2 3/4 4-4 AMENDMENT NO. %

4 EEACTOR COOLhMT SYSTEM COLD REUTDOWN - LOOPS FILLED l

L1MTTIMO N ITION FOR OPERATION 3.4.1.4.1-At least one residual heat removal 3 DR) loop shall be OPERABLE and in operation *, and either a.

One additional RNA loop shall be OPERABLE #, or b.

The secondary side narrow range water level of at least two steam generators shall be greater than 184 (41% for Unit 1 prior to cycle 9).

APPLICARILITY: MODE 5 with reactor coolant loops filled ##.

&EZlM8 With one of the RHR loops inoperable and with less than the required

-a.

steam generator level, inunediately initiate corrective action to return the inoperable RHR loop to OPERABLE status or restore the required steam generator level as soca as possible, b.

With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and inanediately initiate corrective action to return the required RHR loop to operation.

EURVEf f TAMCE REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.4.1.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

  • The RHR pump may_ be doenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:

(1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

  1. 0ne RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other RHR loop is OPERABLE and in operation.
    1. A reactor coolant pump shall not be started with one or more of the Reactor coolant System cold leg temperatures less than or equal to 350*F unless the secondery water temperature of each steam generator is less than 50*F ibove

.each of the Reactor' Coolant System cold leg temperatures.

BYRON - UNITS 1 & 2 3/4 4-5 AHENDHENT NO. %

k l

l REACTOR COOLANT SYSTEM h

COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION-3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE

  • and at least one RHR loop shall be in operation.**

APPLICABILITY:

MODE 5 with recctor coolant loops not filled.

ACTION:

a.

With less than the above required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.

b.

With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.

-SURVEILLANCE REQUIREMENTS 4.4.1.4.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

  • 0ne RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other RHR loop is OPERABLE and in operation.
    • The RHR pump may be deenergized for up to I hour provided: (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below saturation temperature.

BYRON - UNITS 1 & 2 3/4 4-6

_ - _ _ - - _ _ - _ - _ - _ _ - _ - _ _ - - _ _ _ _.

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