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Amends 74 & 55 to Licenses NPF-9 & NPF-17,respectively, Adding Requirements for Testing of Undervoltage & Shunt Trip Attachments of Reactor Trip Breakers & Testing of Reactor Trip Bypass Breakers
	ML20237L733
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/02/1987
From:	Crocker L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20237L737	List: ML20237L733; ML20237L758;
References
	NUDOCS 8709090054
	Download: ML20237L733 (12)
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UNITED STATES NUCLEAR REGULATORY COMMISSION n

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DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-9 1.

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

A.

The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated December 7, 1985, and supplements filed March 16 and April 1,1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, 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 Comission's regulations set forth in 10 CFR Chapter I; 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 accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied, j

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Accordingly, the lkense is hereby amende ' by:page changes.t', the Technical Specifications as indicated in the attachments to this license amendment,.

and Paragraph 2.C.(2) of Facility Operating. License No. NPF-9 is hereby I

wended to read as fcilows:

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(2) Technical Specifigti,ons The fechnical Specifications contained in Appendix A, as revised through Amendment No. 74, are hereby incorporated into the license.

I The licensee shall operate the facility in accordance with the Technical Specifications and the EnvWonmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Lawrence P. Crokcer, Acting Director Project Directorate II-?

Division of Reactor Projects-I/II

Attachment:

Technical Specification Changes Date of Issuance:

september 2, 1987 psp PD#11-3'DRP PD#11-3/DKP-I/i!

a PD#11-3/DRP-I/II Mduri8ah'mac-l/IIDHood LCrocker, Acting Director 08/,1b/87 08/j;/87 0

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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-17 1.

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

A.

The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated December 7, 1985, and supplements filed March 16 and April 1,1997, complies with as amended (the Act)quirements of the Atomic Energy Act of 1954, the stanchrds and re and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, 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 set forth in 10 CFR Chapter I; 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.

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(' 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, nd Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby

.wnded to read as follows:

(2)TechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 55, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Ew/ironmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Lawrence P. Crocker, Acting Director Project Directorate II-3 Division of Reactor Projects-l/II

Attachment:

Technical Specification Changes Date of Issuance: September 2, 1987 1

l p.Hr PD#p-DRP-I/II PD#II-3/DRP-I/II OG>Ba,fth sda PD#II-3/DRP-I/II Mbuhth mac DHood y}4 LCrocker, Acting Director j

08/jb/87 08/ g /87

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ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND I

, TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE N0. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with

_the enclosed pages. The revised pages are identified by Amendaent number and

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contain vertical lines indicating the areas of change. The corresponding over-leaf page is also provided to maintain document completeness.

Amended Overleaf Page Page 3/4~3-5 3/4 3-8 3/4 3-11 3/4 3-12 3/4 3-13 3/4 3-14 3/43-14a(new)

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ACTION STATEMENTS (Continued)

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;-however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 12 - With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 9.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

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McGUIRE - UNITS 1 and 2 3/4 3-8 Amendment No.74(Unit 1)

I Amendment No.55(Unit 2) l

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TABLE 4.3-1 (Continued)

TABLE NOTATION With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.

Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)

If not performed in previous 7 days.

(2)

Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than'2%.

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provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

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Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.

Recalibrates if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

Detector plateau curves shall be obtained, evaluated, and compared to manufacturer's data.

For the Intermediate Range and Power Range Neutron Flux chan~nels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7)

Each train shall be tested at least e,ery 62 days on a STAGGERED TEST BASIS.

(8)

With power greater than or equal to the interlock Setpoint the i

required operational test shall consist of verifying that the interlock is in the required state by observing the permissive i

annunciator window.

(9)

Monthly surveillance in MODES 3*, 4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

Monthly surveillance shall include verification

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of the Boron Dilution Alarm Setpoint of less than or equal to five

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times background.

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f (10) -

Setpoint verification is not required.

McGUIRE - UNITS 1 and 2 3/4 3-14 Amendment No.74 (Unit 1)

Amendment No.55 (Unit 2) l l

E_----_---------

TABLE 4.3-1 (Continued)

TABLE NOTATION (11) -

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual. Reactor Trip Function.

(12) -

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(13) -

Prior to placing breaker in service, a local manual shunt trip shall be performed.

(14) -

The-automatic undervoltage trip capability shall be verified-operable.

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l McGUIRE - UNITS 1 and 2 3/4 3-14a Amendment No74 (Unit 1) l Amendment No35 (Unit 2) lw_-__--___-_'_________

INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident:

(1) Safety Injection pumps start and automatic valves position, (2) Reactor trip, (3) feedwater isolation, (4) startup of the emergency diesel generators, (5) containment spray pumps start and automatic valves position, (6) containment isolation, (7) stean; line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start and automatic valves position, and (10) nuclear service water pumps start and automatic valves position.

. Technical Specifications for the Reactor Trip Breakers and the Reactor Trip Bypass Breakers are based upon NRC Generic Letter 85-09 " Technical Specifica-tions for Generic Letter 83-28, Item 4.3," dated May 23, 1985.

l McGUIRE - UNITS 1 and 2 B 3/4 3-la Amendment No74(Unit 1)

Amendment No)S(Unit 2) u__

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ML20237L733

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