Text

Amend 78 to License NPF-12,implementing Recommendations of Generic Ltr 85-09, Tech Specs for Generic Ltr 83-28,Item 4.3, Re Reactor Trip Breaker Testing
	ML20244D705
Person / Time
Site:	Summer
Issue date:	06/06/1989
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20244D707	List: ML20244D705; ML20244D715;
References
	GL-83-28, GL-85-09, GL-85-9, NUDOCS 8906190223
	Download: ML20244D705 (8)
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UNITED STATES 8

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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUPf4ER NUCLEAR STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. NPF-12 1.

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

A.

The application for amendment by South Carolina Electric & Gas Company (the licensee), dated January 20, 1989, as supplemented on March 20, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will o)erate in conformity with the application, the provisions of t1e 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 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.

2.

Accordir. gly, the license is amended by changes to the Technical Specifications, as indicated in the attachm ot to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as foilows:

l 8906190223 890606 PDR ADOCK 05000395 P

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(2) Technical' Specifications and Environmental Protection Plan

.The Technical Specifications contained in Appendix A, as revised through Amendment No. 78

. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental' Protection Plan.

1 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:

Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 6,1989 i

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l ITACHMENT TO LICENSE AMENDMENT NO. 78 TO FACILITY OPERATING LICENSE N0. NPF-12 l

DOCKET NO. 50-395 l

Replace the following pages of the Appendix Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.

Remove Pages Insert Pages 3/4 3-5 3/4 3-5 3/4 3-7 3/4 3-7 (overleaf) 3/4 3-8 3/4 3-8 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 (overleaf) 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-14a 1

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ACTION STATEMENTS (Continued)

ACTION 8 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 9 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 10 - 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 11 - 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 8.

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 OPERABLE status.

I SUMMER - UNIT i 3/4 3-8 Amendment No. 78

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TABLE NOTATION 1

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With the reactor trip system breakers closed and the control rod i

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.

1 (2)

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

Adjust excora channel gains consistent with calorimetric power if absolute difference is greater than 2 percent.

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

(3)

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 percent. 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 Power Range Neutron Flux Channels 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 every 62 days on a STAGGERED TEST BASIS.

(8)

With power greater than or equal to the interlock setpoint the required OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive 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.

(10) -

Setpoint verification is not required.

(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.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(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) -

Automatic undervoltage trip.

SUMMER - UNIT 1 3/4 3-14 Amendment No. /3, 78 ~

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ML20244D705

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