ML20148F299

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Amend 1 to License NPF-62,ammending Tech Specs,App a & Environ Protection Plan in App B
ML20148F299
Person / Time
Site: Clinton Constellation icon.png
Issue date: 03/18/1988
From: Muller D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148F303 List:
References
NPF-62-A-001 NUDOCS 8803280120
Download: ML20148F299 (5)


Text

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[gf UNITED STATES

.b i)D NUCLEAR REGULATORY COMMISSION I (.

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WASHINGTON, O C. 20555 o

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ILLIN0IS POWER COMPANY, ET AL DOCKETNO.5046J CLINTON POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 License No. NPF-62 1.

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

A.

The application for amendrnent by the Illinois Power Company * (IP),

Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. (the licensees) dated December 10, 1987, and supplemented January 29, 1988, complies with 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, 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 (11) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this arnenament 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 arnendment 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 Specifications as indicated in the attachdent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through 8803280120 880318 DR ADOCK 050 1

' 1111nois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the

facility,

.. Amendrnent No.1, are hereby incorporated into this license.

IP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license arnendrnent is effective as of its date of issuance.

F R THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate 111-2 Division of Reactor Projects - III.

IV, V and Special Projects Attachnent:

Changes to the Technical Specifications Date of issuance: March 18, 1988 l

l l

i ATTACHMENT TO LICENSE AMENDMENT NO. 1 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by Amendment nurber and contain vertical lines indicating the area of change. Overleaf page(s) are provided to maintain document completeness.

Remove Insert 3/4 4-14 3/4 4-14 3/4 6-4 3/4 6-4

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,,_---a,---

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REACTOR COOLANT SYS_ TEM OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENTS __(Continued) 4.4.3.2.1 (Continued) d.

Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE hy leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a.

At least once per 18 months.*

l b.

Prior to returning the valve to service following maintenance, repair, or replacement work on the valve or its associated actuator, c.

As outlined in ASME Code,Section XI, paragraph IW-3427(b).

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

  • The requirements of this specification for valves 1E12F023,1E51F066, and 1E51F013 will not be completed until prior to startup following the first refueling outage.

CLINTON - UNIT 1 3/4 4-14 Amendment No.1

4 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE SURVEILLANCE REQUIREMENTS (Continued)

4. 6.1. 2 (Continued) 2.

Has duration sufficient to establish accurately the change in leakage-rate between the Type A test and the supplemental test.

3.

Requires the quantity of gas injected into the primary containment or bled from the primary containment during the supplemental test to be between 0.75 La and 1.25 La.

d.

Type B and C tests shall be conducted with gas at Pa, 9.0 psig*, at inter-vals no greater than 24 months except for tests involving:**

l 1.

Air locks, 2.

Main steam line isolation valves, 3.

Penetrations using continuous leakage monitoring systems, 4.

All containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment, and 5.

Purge supply and exhaust isolation valves with resilient material seals.

e.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1,3.

f.

Main steam line isolation valves shall be leak tested at least once per 18 months.

g.

Type B tests for penetrations employing a continuous leakage monitoring system shall be cunizeted at Pa, 9.^ psig, at every other reactor shutdown fer refueling, but in no ca=e at intervals no greater than once per 3 years, h.

All containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primsry containment shall be leak tested at least once per 18 months.

i.

Purge supply and exhaust isolation valves with rosilient material seals shall be tested and demonstrated OPERABLE per Survoillance Require-ment 4.6.1.8.3.

J.

The provisions of Specification 4.0.2 are not applicable to Specifica-tions 4.6.1.2.a, 4,6.1.2.b, 4.6cl.2.d, and 4.6.1.2.g.

"Unless a hydrostatic test is required per Table 3.6.4-1.

    • The requirements of ti.is specification for valves 1E12-F023,1E51-F034, 1E51-F035,1E51-F390, IE51-F391,1E12-F061,1E12-F062, and 1E51-F013 will not be completed until prior to startup following the first refueling outage.

CLINTON - UNIT 1 3/4 E.4 knendment No.1

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