ML20196D124

From kanterella
Jump to navigation Jump to search
Amend 31 to License NPF-30,deleting Item 1.a from Table 4.3-3 & Revising Section 4.11.2.5 to Correct Administrative Oversight Ref Wrong Spec for Table 3.1-13
ML20196D124
Person / Time
Site: Callaway 
Issue date: 01/27/1988
From: Perkins K
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20196D130 List:
References
NUDOCS 8802170024
Download: ML20196D124 (7)


Text

'

'f

,\\,

UNITED STATES y

c g

NUCLEAR REGULATORY COMMISSION t

WASHING TON, D, c. 20656

%,...../

UNION ELECTRIC COMPANY CALLAWAY, PLANT, UNIT 1 DOCKET NO. STN 50-483 AMENDMENT TO FACILITY OPER,ATING LICENSE

/cendment No. 31 License No. NPF-30 1.

The huclear Regulatory Comission (the Ccmmission) has found that:

A.

The application for amendment filed by Union Electric Company (the licensee) dated September 10, 1987 complies with the standards and requirerents 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 roesonable 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 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 attachinent to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:

$$g2Qggy $$

g3 P

2

~

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 31, and the Environmental Protection Plan contained in Appendix B, both of which are attachea hereto, are hereby incorporated into the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION n-_

Kenneth E.

erkins, Director Project Directorate III-3 Division of Reactor Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: January 27, 1988 j

i

i ATTACHMENT TO LICENSE AMENDMENT NO. 31 OPERATING LICENSE NO. NPF-30

)

DOCKET NO. 50-483 i

Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Corresponding overleaf pages are provided to raintain document completeness, j

REMOVE INSERT 3/4 3-41 3/4 3-41 l

3/4 11-15 3/4 11-15 1

1 l

J

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT Q

OPERATIONS SURVEILLANCE REQUIREMENTS F

E ANAL.0G CHANNEL CHANNEL CHANNEL OPERATIONAL MODES FOR WHICH FUNCTIONAL UNIT CHECK CALIBRATION TEST SURVEILLANCE IS REQUIRED c5 1.

Containment a.

Gaseous Radioactivity-RCS Leakage Detection S

R M

1, 2, 3, 4 (GT-RE-31 & 32) b.

Particulate l

Radioactivity -

w2 RCS Leakage Detection S

R M

1,2,3,4 wg 2.

Fuel Building a.

Fuel Building Exhaust -

Gaseous Radioactivity-l High (GG-RE-27 & 28)

S R

M b.

Criticality-High Radiation Level S

R M

k

1) Spent Fuel Pool (SD-RE-37 & 38)
2) New Fuel Pool S

R M

(SD-RE-35 & 36)

O

{

3.

Control Room

~

Air Intake-Gaseous Radioactivity-High S

R M

All (GK-RE-04 & 05)

  • With fuel in the respective fuel storage pool.

4

    • With irradiated fuel in the fuel storage areas or fuel building.

I

INSTRUMENTATION MOVA3LE INCORE' OETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

a.

At least 75% of the detector thimbles, b.

A minimum of two detector thimbles per core quadrant, and c.

Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the Movable Incore Detection System is used for:

a.

Recalibration of the Excore Neutron Flux Detection System, or b.

Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofFh,F(Z)andF,y.

c.

9 ACTION:

a.

With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE 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 normalizing each detector output when required for:

a.

Recalibration of that Excore Neutron Flux Detection System, or b.

Monitoring the QUADRANT POWER TILT RATIO, or c.

Measuremen". of F H. F (Z), and F,.

9 l

CALLAWAY - UNIT 1 3/4 3-42 1

i RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to 3% by volume whenever the hydrogen concentration exceeds 4% by volume, j

APPLICABILITY:

At all times, ACTION:

a.

With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM greater than 3% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

h.

With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a. above.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

1 SURVE!LLANCE REQUIREMENTS t

I 4.11.2.5 The concentrations of hydrogen and oNygen in the WASTE GAS HOLDUP SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLOUP SYSTEM witn the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

l 1

i 1

1 i

i j

CALLAWAY - UNIT 1 3/4 11-15 Amendment No. 31 4

r-

RAD 10ACilVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 2.5 x 105 Curies of noble gases (considered as Xe-133 equivalent).

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVE!LLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days when radioactive materials are being added and within 7 days following any addition of radioactive material to the tank, i

l

\\

i CAI L AWAY - IINii 1 3/4 11-16 9

.