Text

Amend 121 to License NPF-42,revising TS Tables 3.3-3,3.3-4 & 4.3-2 Requirements by Establishing Separate Requirements for Analog & Digital Portions of Associated Circuit
	ML20205B767
Person / Time
Site:	Wolf Creek
Issue date:	03/23/1999
From:	Thomas K; NRC (Affiliation Not Assigned)
To:	;
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ML20205B772	List: ML20205B767; ML20205B778;
References
	NUDOCS 9903310358
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UNITED STATES j

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 0001 4

o 9.....g l

l WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION. UNIT 1 DOCKET NO. 50-482 AMENDMEN1,O FACILITY OPERATING LICENSE Amendment No.121 License No. NPF-42 1.

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

A.

The application for amendment by Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) dated February 4,1998, as supplemented by letter dated October 20,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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 puh*:e, 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-42 is hereby amended to read as follows:

i 9903310358 990323 PDR ADOCK 05000482 P

PDR

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(...

(2)

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 121 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of its date of issuance to be implemented within 30 days from the date of issuana.

FOR THE NUCLEAR REGULATORY COMMISSION hMM Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

March 23, 1999

l ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.121 TO FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 3-17 3/4 3-17 3/4 3-21a 3/4 3-21a 3/4 3-26 3/4 3-26 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 i

i

.]

I h

TABLE 3.3-3 (Continued) k gi ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

'1 o

2 MINIMUM l

lE.-

TOTAL NO.

CHANNELS CHANNELS APPLICABLE i

?

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I

Cz 6.

Auxiliary Feedwater

-4 a.

Manual Initiation 3(1/ pump) 1/ pump 1/ pump

1. 2. 3 24 b.

Automatic Actuation Logic 2

1 2

1, 2. 3 29

,o and Actuation Relays (SSPS) c.

Automatic Actuation Logic 2

1 2

1. 2. 3 21 i

and Actuation Relays (BOP ESFAS) d.

Stm. Gen. Water Level-y

.i Low-Low Y

4

1) Start Motor-Driven Pumps 4/stm. gen.

2/stm. gen.

3/stm. gen.

1. 2. 3 28*

I in any opera-in each ting stm.

operating gen.

stm. gen.

i.

2) Start-Turbine-Driven Pump 4/stm. gen.

2/stm. gen.

3/stm. gen.

1. 2. 3 28*

in any 2 in each operating operating

+

stm. gen.

j e.

Safety Injection - Start i

y Motor-Driven Pumps See Item 1. above for all Safety Injection initiating functions g

and requirements.

o.

t 8

f.

Loss-of-Offsite Power -

a Start Turbine-Driven Pump i

z

1) 4kV Bus Undervoltage -

4/ Bus 2/ Bus 3/ Bus

1. 2. 3 19*

Loss of Voltage j

5

2) Automatic Actuation 2

1 2

1. 2. 3 31 Logic and Actuation Relays (LSELS and B0P ESFAS)

i 2

t TABLE 3.3-3 (Cor,tinued) t, 5

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUENTATION i

G c,

MINIPtM i5?

TOTAL NO.

CHANNELS CHANNELS APPLICABLE R

FUNCTIONAL UlGI 0F CHANNELS TO TRIP OPERABLE MODES ACTION.

I h

6.

Auxiliary Feedwater (Continued)

U g.

Trip of All Main Feedwater

~

Pumps - Start Motor-Driven Pumps 4-(2/ pump)**

2-(1/ pump 3

1 19***

in same separation) l

h. Auxiliary Feedwater Pump i

i Suction Pressure-Low i

(Transfer to ESW) 3 2

2

1. 2. 3 15*

7.

Automatic Switd c.a to ca R

Containment Sump 5

a.

Automatic Actuation Logic 2

1 2

1.-2. 3. 4 14 and Actuation Relays (SSPS) b.

RWST Level - Low-low 4

2 3

1.2.3.4 30 Coincident With Safety Injection See Item 1. above for Safety Injection initiating functions and requirements.

1I g

8.

Loss of Power l

'l.

o a.

4 kV Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus l' 2.3.4 19*

l

-Loss of Voltage i

5 l

b.

4 kV Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus 1.2.3.4 19*

l li'

! s

-Grid Degraded Voltage h

l' b

u l

?

4 TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Cont *nued) i b.

The Minimum Channels OPERABLE requirement is met; however, the 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 other channels per Specification 4.3.2.1.

ACTION 20 - With less than the Minimum Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least H0T STANDBY within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and in at least HOT SNUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however one 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 per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least NOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT $NUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE channels one less than the. Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the action required by Specification 3.7.1.5.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected auxiliary feedwater pump inoperable and take the ACTION required by Specification 3.7.1.2.

ACT10N 25 - With the number of OPERABLE channels one less than the Minimum Channels 0PERABLE requirement, declare the affected diesel generator and off-site power source inoperable and take the j

ACTION required by Specification 3.8.1.1.

f i

ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel j

to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or initiate and maintain i

operation ~of the Control Room Emergency Vent'lation Systen.

During operation in MODE 5 and 6. the provisions of 4

Specification 3.0.4 are not applicable.

i i

l l

WOLF CREEK UNIT 1 3/4 3-21 Amendment No. 77, 43 i

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 27 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement. be in at least HOT STANDBY within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 28 - With the number of OPERABLE channels one less than the Total Number of Channels. STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

I

a. 'The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

The minimum channels OPERABLE requirement is met: however.

the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification-4.3.2.1.

ACTION 29 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s: however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is operable.

ACTION 30 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following

. conditions are satisfied:

a.

The inoperable channel is placed in the bypass condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

The minimum channels OPERABLE requirement is met: however, one additional channel may be tripped for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

ACTION 31 - Wits the number of OPERABLE channels less than the Total Number of d annels, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

WOLF CREEK - UNIT 1 J/4 3-21a Amendment No. 49-t11.121

TABLE 3.3-4 (Continued)

[

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TkIP SETPOINTS E

TOTAL SENSOR TRIP ALLOWABLE-ng FUNCTIONAL UNIT ALLOWANCE (TA)

Z ERROR (S)

SETPOINT VALUE E

5. Turbine Trip and Feedwater Isolation i

E i

y a.

Automatic Actuation Logic and Actuation y

Relays (SSPS)

N.A.

M.A N.A.

M.A.

N.A.

b.

Steam Generator Water Level-High-High 5.0 2.18 2.51

< 78% of

< 79.7% of narrow range Warrow range instrument instrument span span

,t c.

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

f g

y

6. Auxiliary Feedwater U.

\\

a.

Manual Initiation N.A.

N.A.

f i

b.

Automatic Actuation t

Logic and Actuation

[

Relays (SSPS)

N.A.

I c.

Automatic Actuation l

Logic and Actuation

?

Relays (BOP ESFAS)

N.A.

M.A.

N.A.

j d.

Steam Generator Water Level-Low-Low

[

1) Start Notor-Driven Pumps 23.5 21.18 2.51 1 23.5% of 1 22.3% of narrow range narrow range j

l instrument instrument span span

i

. ENGINEERED SAFETY FEATURES ACTUATION SYSTEM _ INSTRUMENTATION TRIP SETPOINTS TABLE 3.3-4 (Continued) t

E i

O i!

5 ALLOWANCE (TA) Z ERROR (S)

SETPOINT VALUE TOTAL SENSOR TRIP ALLOWABLE ij Q

FUNCTIONAL UNIT 6.

Auxiliary Feedwater (Continued)

A

2) Start Turbine-E Driven Pumps 23.5' 21.18 2.51 2 23. A of 2 22.3% of 3;

narrow range narrow range j

j instrument span instrument span

.I Lt e.

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

~

f.

Loss of Offsite Power -

Start Turbine-Driven Pump

1) 4 kV Bus See Item 8.a below for Trip Setpoints and Allowable Values.

i Undervolage - Loss of Voltage I

2) Automatic Actuation N.A.

N.A.

Y logic and Actuation i

W Relays (LSELS and BOP ESFAS)

I g.

Trip of All Main i

Feedwater Pumps -

1 Start Motor-Driven Pumps N.A.

N.A.

h.

Auxiliary Feedwater i

i Pump Suction Pressure-j Low (Transfer to ESW)

N.A.

221.60 psia 220.53 psia l

t I

7.

Automatic Switchover to l

l Containment Sump a.

i 3

a.

Automatic Actuation a

logic and Actuation Relays (SSPS)

N.A.

t i

G b.

RWST Level-Low-Low 3.4 1.21 1.86 2 36% of 2 35.1% of i

instrument instrument

~

span span 1

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

t

3 l

TABLE 4.3-2 (Continued)

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION O

SURVEILLANCE REQUIREMENTS i

O TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE g

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED q

..j 6.

Auxiliary Feedwater (Continued) a

t c.

Automatic Actuation N.A.

N.A.

M(1)(2)

N.A.

1.2.3 Logic and Actuation Relays (B0P ESFAS) d.

Steam Generator Water S R

0 N.A.

N.A.

1.2.3 Level-Low-Low e.

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

f.

Loss of Offsite Power -

Start Turbine Driven Pump

1) 4 kV Bus Under-N.A.

R N.A.

M N.A.

N.A.

1.2.3 W

voltage - Loss of Voltage j

2) Automatic N.A.

N.A.

R N.A.

N.A.

1.2.3 I

Actuation Logic and Actuation Relays (LSELS and B0P ESFAS) g.

Trip of All Main N.A.

N.A.

R.

N.A.

1 Feedwater Pumps h.

Auxiliary feedwater S

R M

N.A.

1.2.3 Pump Suction Pressure-Low 7.

Automatic Switchover to a

Containment Sump 8

a.

Automatic Actuation N.A.

N.A.

M(i)

M(1) 0(3) 1.2.3.4 l

a Logic and Actuation i

z Relays (SSPS}

i b.

RWST Level - Low-Low S

R 0

N.A.

1.2.3.4 Coincident With l

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

D 8.

Loss of Power a.

4 kV Undervoltage-N.A.

R(4)

N.A.

M(4)

N.A.

1.2.3.4 l

'-~

Loss of Voltage b.

4 kV Undervoltage-N.A.

R(4)

N.A.

M(4)

N.A.

1.2.3.4 l

Grid Degraded Voltage

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