ML20247D400

Amend 37 to License NPF-43,changing Tech Specs to Incorporate Revised Changes for Reactor Protection Sys & Eliminate Backup Manual Scram Function

ML20247D400
Person / Time
Site:	Fermi
Issue date:	09/01/1989
From:	Thoma J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247D405	List: ML20247D400 ML20247D408 ML20247D413
References
NUDOCS 8909140243
Download: ML20247D400 (12)

Text

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UNITED STATES

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WASHINGTON, D. C. 20555 DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.^37 License No. NPF-43 1.

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

A.

The application for amendment by the Detroit Edison Company (the licensee) dated May 10, 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 Commission; 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 common defense and security or to the health and safety of the public; and l

E.

The issuance of this amendment is in &ccordance with 10 CFR Part 51 of l

the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-

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tions as indicated in the attachment to this license amendment and paragraph L

2.C.(2) of Facility Operating Licens= No. NPF-43 is hereby amended to

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read as follows:

Technical Specifications and Environmental Protection Plan l

l The Technical Specifications contained in Appendix A, as revised through Amendment No. 37, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. Deco shall operate the facflity in accordance with the Technical Specifications and the Environmental Protection Plan.

8909140243 890901 PDR ADOCK 05000341

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

FOR THE NUCLEAR REGULATORY COMMISSION i -

John Thoma, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special. Projects-Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: ' September 1, 1989

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ATTACHMENT TO LICENSE AMENDMENT NO.27 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341

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Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and t.

L contain a vertical line indicating'the area of change. The corresponding l

overleaf pages are also provided to maintain document completeness.

REMOVE INSERT

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SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The reactor protection system instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2.1-1.

APPLICABILITY:

As shown in Table 3.3.1-1.

ACTION:

With a reactor protection system instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2.1-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.

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, LIMITING SAFETY SYSTEM SETTINGS BASES REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS( Continued) 8.

Scram Discharge Volume Water Level-High The scram discharge volume receives the water displaced by the motion of the control rod drive pistons during a reactor scram.

Should this volume fill up to a point where there is insufficient volume to accept the displaced water at pressures below 65 psig, control rod insertion would be hindered.

The reac-tor is therefore tripped when the water level has reached a point high enough to indicate that it is indeed filling up, but the volume is still great enough to accommodate the water from the movement of the rods at pressures below 65 psig when they are tripped.

9.

Turbine Stop Valve-Closure The turbine stop valve closure trip anticipates the pressure, neutron flux, and heat flux increases that would result from closure of the stop valves. With a trip setting of 7% of valve closure from full open, the resultant increase in heat flux is such that adequate thermal margins are maintained during the worst case transient.

10.

Turbine Control Valve Fast Closure The turbine control valve fast closure trip anticipates the pressure, neutron flux, and heat flux increase that could result from fast closure of the turbine control valves due to load rejection with or without coincident failure of the turbine bypass valves.

The turbine control valve (TCV) fast closure signal is generated independently in each valve control logic and connected directly to the Reactor Protection System.

The signal to the Reactor Protection System is generated simultaneously with the deenergizing of the solenoid dump valves which produces control valve fast closure.

Therefore, when TCV fast closure occurs, a scram trip signal is initiated.

11.

Reactor Mode Switch Shutdown Position The reactor mode switch Shutdown position is a redundant channel to the automatic protective instrumentation channels and provides additional manual reactor trip capability.

12.

Manual Scram The Manual Scram is a redundant channel te the automatic protective instrumentation channels and provides manual reactor trip capability.

13.

Deleted Amendment No.37

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. REACTOR PROTECTION SYSTEM-INSTRUMENTATION:

ACTION STATEMENTS-Be in at.least HOT.. SHUTDOWN within.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

' ACTION l'.

Verify all insertable control rods to be inserted in' the core ACTION 2; and lock the-reactor mode. switch in the. Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />..

t Suspend all operations involving CORE ALTERATIONS and' insert

. ACTION 3 all insertable control rods within 1-hour.

Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION.4

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.Be in STARTUP with the main steam line isolation valves closed ACTION 5' within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in at least HOT; SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Initiate a reduction in. THERMAL POWER within 15 minutes and ACTION 6 reduce turbine first stage pressure to <~154 psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />..

Verify all insertable control rods.to be ~ inserted within.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

. ACTION 7 Lock.the~ reactor mode switch in the Shutdown position within ACTION 8 o

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTI'ON' 9' Suspend all operations involving CORE ALTERATIONS, and ' insert all insertable control rods and-lock the reactor mode switch in the Shutdown l position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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___________--_---19

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATICNS (a) A channel may be placed in an inoperable status 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 required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

(b) This function shall be automatically bypassed when the reactor mode switch is in the Run pcsition.

(c) Unless adequate shutdown margin has been demonstrated per Specifica-tion 3.1.1, the " shorting ~1 inks" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn.*

(d) When the " shorting links" are removed, the Minimum OPERABLE Channels Per Trip System is 4 APRMs, 6 IRMs and per Specification 3.9.2, 2 SRMs.

(e) An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.

(f) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(g) This function shall be automatically bypassed when the reactor mode switch is not in the Run position.

(h) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

(i) With any control, rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(j) This function shall be automatically bypassed when turbine first stage pressure is < 154 psig, equivalent to THERMAL POWER less than 30% of RATED THERMAE POWER.

"Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

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