ML20246P028

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Amend 35 to License NPF-43,revising Tech Specs to Reflect Mods Made to Automatic Depressurization Sys
ML20246P028
Person / Time
Site: Fermi 
Issue date: 08/30/1989
From: Thoma J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246P031 List:
References
NUDOCS 8909110025
Download: ML20246P028 (11)
v • d • e


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DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

License No. NP -43 1.

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

A.

The application for amendment by the Detroit Edison Company (the licensee) dated April 3, 1989, 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 Comission; C.

There is reasonable assurance (1) 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the cosmon 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 Specifica-tions as indicated.in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:

Technie.a1 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 35, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the ifcense. Deco shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8909110025 890830 PDR ADOCK 05000341 P

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This license amendment is effective as of its date of its issuance with full implementation within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

o. L J n 0. Thoma, Acting Director Project Directorate 111-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the_ Technical Specifications Date of Issuance: August 30, 1989

' ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341:

Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain a. vertical line indicating the area of change. The corresponding overleaf pages are also provided to maintain' document completeness.

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L TABLE 3.3.3-1 (Contir,ued) iL EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS I

ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum GPERABLE Channels per Trip System requirement:

a.

For one t rip system, place that trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

I b.

For both trip tystems, declare the associated ECCS inoperable.

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare the associated ADS Trip Sysum inoperable.

l ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 33 -

Restore the manual initiation and/or manual inhibit function to l

OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ECCS or ADS Trip System inoperable.

1 ACTION 34 -

With the number of OPEPABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within I hour *, align the HPCI system to take suction from the suppres-sion pool, or declare the HPCI system inoperable.

ACTION 35 -

With the number of OPERABLE channels:

a.

One less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

b.

tas than the Minimum Channels OPERABLE requirement, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

  • The provisions of Specification 3.0.4 are not applicable.

FERMI - UNIT 2 3/4 3-26 Amendment No. 35

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TABLE 3.3.3-3 EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES TRIP FUNCTION RESPONSE TIME (Seconds) 1.

CORE SPRAY SYSTEM a.

Reactor Vessel Low Water Level - Level 1.

(30 b.

Drywell Pressure-High 730 c.

Reactor Steam Dome Pressure-Low RA*

d.

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LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.

Reactor Vessel Low Water Level - Level 1

< 43 b.

Drywell Pressure - High 7 43 c.

Reactor Steam Dome Pressure - Low RA*

d.

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HIGH PRESSURE COOLANT INJECTION SYSTEM a.

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< 30 b.

Drywell Pressure - High 530 c.

Cor.densate Storage Tank Level-Low NA d.

Reactor Vessel Water Level-High, Level B NA e.

Suppression Pool Water Level-High NA f

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AUTOMATIC DEPRESSURIZATION SYSTEM a.

Reactor Vessel Low Water Level

- level 1 NA b.

Drywell Pressure-High NA c.

ADS Timer NA d.

Core Spray Pump Discharge Pressure-High NA e.

RHR LPCI Mode Pump Discharge Pressure-High NA f,.

F.eactor Vessel low Water i.evel - Level 3 NA g.

Manual Initiation NA h.

Drywell Pressure - High Bypass Tiner NA i.

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  • These are permissive signals only.

They do not activate ECCS initiation.

l FERMI - UNIT 2 3/4 3-29 Amendment NO. 35 h_-____._______

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INSTRUMENTATION 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3.3.4-1 shall be OPERABLE with their trip setpoints set consistent with the values shcwn in the Trip Setpoint column of Table 3.3.4-2.

APPLICABILITY:

OPERATIONAL CONDITION 1.

ACTION:

a.

With an ATWS-RPT system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Tr'9 Setpoint value.

b.

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per trip system requirement for one trip function in one trip system, restore the inoperable channel to OPERABLE status within 14 days or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.3.4.1 Each ATWS-RPT system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4-1.

4. 3.-L 2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channele, shall be performed at least en e per 18 montns.

i i

FERMI - UNIT 2 3/4 3-32 Amendment No. 35

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