ML20248A115

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Amend 123 to License DPR-20,revising Tech Specs to Provide Clarifications & Editorial Corrections to Radiological Effluent Tech Specs
ML20248A115
Person / Time
Site: Palisades 
Issue date: 05/30/1989
From: Yandell L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248A120 List:
References
NUDOCS 8906080059
Download: ML20248A115 (8)


Text

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NUCLEAR REGULATORY COMMISSION 7,

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CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE l

4 4

Amendment No.123 License No. DPR-20

1. - The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Consumers Power Company (the licensee) dated March 10, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended

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(the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, l

the provisions of the Act, and the rules and regulations of the l

Commission; i

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 i

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 j

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 3.B. of Provisional Operating License No. DPR-20 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B,.

as revised through Amendinent No.123, are hereby incorporated

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in the license.

The licensee shall operate the facility 1

in accordance with the Technical Specifications.

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3.

This license amendment is effective as of the date of it's issuance

and shall be implemented not later than Julyh14.1989.'

I FOR THE NUCLEAR REGULATORY COMMISSION

'g-g ig bl Lawrence A. Yandell, Acting Director-Project Directorate 111-1 Division of Reactor Projects - III IV, V

& Special. Projects Office of Nuclear Reactor Regulation A' ttachmen' t:

Changes to,the. Technical Specifications Date of Issuance: May 30. 1989 I

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_ _ _ _ _, _ - - _ _ - _ _ - - - - - - - = - - - - - - - -

ATTACHMENT TO LICENSE AMENDMENT NO.123 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise 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 marginal lines indicating the area of change.

_ REMOVE INSERT 3-115 3-115 4-14a 4-14a 4-92 4-92 4-94 4-94

1' TABLE 3.24-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTR WENT OPERABLE ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AND AUTOMATIC TERMINATION OF RELEASE Liquid Radwaste Effluent Line (RIA 2049)

(1) 28 a.

b.

Steam Generator Blowdown Effluent Line (RIA 0707)

(1) 29

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE Service Water System Effluent Line (RIA 0833)

(1) 30 a.

b.

Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211)

(1) 30

3. FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line (FIC 1051 or 1050)

(1) 31

4. CONTINUOUS COMPOSITE SAMPLERS (Alarm / Trip Setpoints

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are not applicable)

I a.

Turbine Building Sumps Effluent Line (1) 30 b.

Service Water System Effluent (1) 30

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3-115 Amendment No. M,123

= = - _ _- _-____ _-. - -_- -_-_ ___ _ -- - -_-_________-___ -_-_-

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Table 4.2.1 Minimum Frequencies for Sampling Tests FSAR Section Test Frequency Reference I)

6. Spent Fuel

' Boron Concentration Monthly 9.4 Pool Bulk Water Temperature Continuously when None bundles are stored in tilt pit racks with less than(6)

,=

one year decay 7 Secondary Coolant ~

Coolant Gross Radio-3 times /7 days with None activity a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples Isotopic Analysis for a) I per 31 days,

. Dose Equivalent 1-131 whenever the Concentration gross activity determination indicates iodine concentrations greater than 10%

of the allowable limit b) I per 6 months, whenever the gross activity determination indicates iodine concentrations below 10%.of the allowable limit (I) A daily sample shall be obtained and analyzed if fission product monitor is out of service.

I2) After.3t least 2 EFPD and at least 20 days since the last shutdown of longer than 48 heurs.

(3, 4, 5) Deleted.

l (6) Reference Specification 3.8.5 for maximum hulk water temperature and monitoring requirements.

( } Reference Bases section of Spor:ification 3.8 and Sectien 5.4.2f of the Design Features for minimum boron concentration (U720 ppe).

4-14a Amendment No. 27, UD,123

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4-14b Amendraent No. 29, 70,123

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