ML20034A041

From kanterella
Jump to navigation Jump to search
Amend 37 to License NPF-42,allowing Operational Mode Changes While Certain Control Room Ventilation Tech Spec Action Statements in Effect
ML20034A041
Person / Time
Site: Wolf Creek 
Issue date: 03/28/1990
From: Hebdon F
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20034A042 List:
References
NUDOCS 9004190220
Download: ML20034A041 (7)


Text

]

- 4 ['ye asog'o UNITED STATES.

' ; }4

' NUCLEAR REGULATORY COMMISSION.

' ' 1 WASHINGTON, D. C. 20665 -

9

%,...**/

WOLF CREEK NUCLEAR OFERATING CORPORATION WOLF CREEK GENERAT,1,N,G,,ST,AT),0N_

DOCKETNO.(50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.37 License No. NPF-42 1.

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

A.

The application for amendment to the Wolf Creek Generating Station I

'(the facility) Facility Operating License No. NPF-42 filed by)the W j

d dated February 7.1990, complies wita 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, as amended, the provisions of the Act, and the rules-and regtilations -

of the Comission; C.

There is reasonable assurance: L (i)'that.the, activities' authorized by this amcreent can. be condta :

without endangering th_e health and safety oi the public, anc (i u that such activities will'be' conducted in compliance with the-Comission's. regulations;-

l D.

The issuance of this license anendment will nct be inimical to'the comon defense and security a 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.

.1 kn j

j.8S"$88$0 $So$hg2 1

o P

j

- 2_-

2.

Accordingly, the licor.se is amended by changos to the Technical Specifi-cations 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:

2.

Te,chnical Specif,1 cations-The Technical' Specifications-contained in Appendix A,_as revised through Amendment No. 37. and the Environmental Protection Plan.

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

3.

The license anendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY C0ttfilSSION

)*AbMk fdddh Frederick J. Hebdon,- Director Project Directorate IV Divisica of Reactor Projects - III..

IV, V and Special Projects Office of Nuclear Reactor Pegulation-

Attachment:

Charges to the Technical

-Specifications Date of Issuance: March 28. 1990 i

i i

i i

i

ATTACWE N,T,,TO,,L,1,C,EN,S,E,, ape NDF,Ep,T,,Np, y, _

FACILITY OPERATING LICENSE NO. NPF-42'-

DOCKET,j(0,, 5,0,,4,8,2 Revise Appendix. A Technical Specifications by removing.the pages identified below and inserting'the enclosed pages.

The revised pages.are identified b aniendoent number and contain margit-- ' lines indicating the area of' change. y The corresponding overleaf pages ari trovided to maintain-docunient conipleieness.

REMOVE PAGE,5

-' PA,GES 3/4 3-21 3/4 4

3/4 7-14 3/4 7 14 1

- I 1

l 1

.D*

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued) b.

The Minimum Channels OPERABLE requirement is met; however, the~ inoperable channel may be bypassed for up to_2 hours for surveillance testing of other channels per Specification

4. 3. 2.1..

ACTION 20 - With less than the Minimum Channels 0PERABLE, within 1 hour-determine by observation of the associated permissive annunciator window (s) that the interlock is in ' ts. required state: for the1 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 HOT. STANDBY-within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed 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 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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 /> and in at least HOT SHUTDOWN within the -following 6' hours.

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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.thantthe Minimum Channels OPERABLE' requirement, declare the affected auxiliary feedwater pump inoperable and take the ACTION' required by-Specification 3.7.1.2.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum i

Channels OPERABLE-requirement, declare the affected: diesel-generator and off-site power source inoperable and take the ACTION required by Specification-3.8.1.1; ACTION 26 - With the number of 0PERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel i

to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or initiate-and maintain operation of the Control Room Emergency' Ventilation System.

l During operation in MODE 5 and 6, the provisions of Specification 3.0.4 are not applicable.

ACTION 27 - With the number of OPERABLE channels-one less than the Minimum Channels OPERABLE requirement, 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 />; however, one channel may be bypassed 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 per Specification 4.3.2.1 provided the other channel is OPERABLE.

WOLF CREEK - UNIT 1 3/4 3-21 Amendment No.37 a

,.,.u.-

TABLE 3.3-4 i

r ENGINEERED SAFETY FEATURES' ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

~@n

-2 TOTAL SENSOR

-TRIP ALLOWABLE G

FUNCTIONAL UNIT ALLOWANCE (TA)

ERROR (S)

SETPOINT VALUE Z

n

1. Safety Injection (Reactor E

Trip, Phase "A" Isolation, O

Feedwater Isolation, Component Cooling Water, Turbine Trip, Auxiliary Feedwater-Motor-Driven Pump, Emergency Diesel Generator Operation, Containment Cooling, and.

Essential Service Water Operation)

, {

a.

Manual Initiation N.A.

N.A.

N.A.

N.A.

N. A.

T

b. -Automatic Actuation M

Logic and Actuation Relays (SSPS)

N. A.

N.A.

N.A.

'N.A.

N.A.

c.

Containment Pressure High-1

- 3. 6 0.71.

1.98' 5 3.5 psig 5 4.5 psig d.

Pressuri2er Pressure -

Low-16;2 10.71

~2.49

.t 1830 psig 3.1815 psig e.

Steam Line Pressure -'

Low

-19.6 14.81-

'1.93

> 615 psig

> 571 psig*

t w

n o

y

.. ~ ~..

.,.._...n.

- + - -.,, -,... ~.,.

..--..-._-L-L.

.A-

PLANT SYSTEMS' 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION

'3.7.5 TheLultimate heat sink (VHS) shall be OPERABLE =with:

-The crest of the UHS dam below the rip rap cover and corresponding-a.

water level at or above elevation,1070 Mean Sea Level, USGS datum, and b.

The plant inlet water temperature of less than or equal to 90*F.-

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

i With the requirements of the above specification.not satisfied, be in.at least' HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within-the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

i 1

SURVEILLANCE REQUIREMENTS 4.7,5 The UHS shall be determined OPERABLE:

k At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the above required water i

a.

temperature and water level to be within their limits, and

)

b.

At least once per 12 months by verifying that the crest of-the UHS dam below the rip rap cover is at or above elevation 1070 Mean-i Sea Level, USGS datum.

[

i r

WOLF CREEK - UNIT 1 3/4 7-13 f

I

PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6 Two independent Control Room Emergency Ventilation Systems shall be OPERABLE.

APPLICABILITY: All MODES.

s ACTION:

MODES 1, 2, 3 and 4:

1 With one Control Room Emergency Ventilation System inoperable, restore the i

inoperable system to_ OPERABLE status within 7 days or be in at least HOT-i STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in. COLD SHUTDOWN within the following.

j 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, i

MODES S and 6:

n With one Control. Room Emergency Ventilation System' inoperable, a.

restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the:. remaining.0PERABLE Control Room Emergency Ventilation System in the recirculation mode.

The-provisions.of Specification 3.0.4 are not applicable.

b.

With both Control-Room Emergency Ventilation Systems inoperable, or 1

with the OPERABLE Control Room Emergency Ventilation System, required to be in the recirculation mode by ACTION a.

not capable of being powered by an OPERABLE emergency power. source,, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

l SURVEILLANCE REQUIREMENTS i

4.7.6 'Each Control Room Emergency Ventilation System shall.be demonstrated i

OPERABLE:

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room a.

air temperature k less than or equal to 84*F; b.

At least once p r 11 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers of both the Filtration and Pressurization Systems and verifying that the Pressurization System operates-for at least 10 continuous hours with.the heaters operating; L

' WOLF CREEK - UNIT 1 3/4 7-14 Amendment.No. 37