Text

Amends 63 & 57 to Licenses NPF-35 & NPF-52,respectively, Modifying Tech Spec to Add Changes Required by Generic Ltr 85-09, Tech Specs for Generic Ltr 83-28,Item 4.3, Re Automatic Actuation of Shunt Trip Attachment
	ML20246L970
Person / Time
Site:	Catawba
Issue date:	05/09/1989
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20246L976	List: ML20246L970; ML20246L979;
References
	GL-83-28, GL-85-09, GL-85-9, NUDOCS 8905190005
	Download: ML20246L970 (15)
	v • d • e

- _ - _ _ _ _ _ _

UNITED STATES 8"

NUCLEAR REGULATORY COMMISSION o

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WASHINGTON, D. C. 20666 j

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l NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION q

l SALUDA RIVER ELECTRIC COOPERATIVE, INC.

i DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE q

i Amendment No. 63 License No. NPF-35 1

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

A.

The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Du ke Power Company acting for itself, North Carolina Electric Membership) Corporation and Saluda River Electric Cooperative, Inc.,

(licensees dated June 19, 1987, as supplemented March 10, 1989, l

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules ard regulations as 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; t

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 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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P h____________.__________

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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 anendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby -

amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 63, are hereby incorporated into the license.

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

3.

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

FOR THE IlUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Atta chnent:

Technical Specification Changes Data of Issuance: May 9, 1989

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 63, are hereby incorpora'ed into the license.

The licensee shall operate the facility in accordarm. with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

,h l

David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes l

Date of Issuance: May 9, 1989 l

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UNITED STATES Il

't NUCLEAR REGULATORY COMMISSION 5

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0 UKE POWER COMPANY l-l NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDM0NT MUNICIPAL POWER AGENCY l

DOCKET N0.-50-414 l

CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING-LICENSE i

Amendment No. 57 License No. NPF-52 1.

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

i A.

The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency, (licensees) dated slune 19,1987, as supplemented March 10, 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 as 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 (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 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.

L l

' 2.

Accordingly, the license is hereby amended by page changes to the Technical 1

Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:

(2) Technical Specifications l.

'The Technical Specifications contained in Appendix A, as revised through Amendment No. 57, are hereby incorporated into the license.

The licensee shall operate the. facility in accordance with the Technical Specifications and the Environmental Protection' Plan.

3.

This -license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation

Attachment:

Technical-Specification Changes Date of Issuance:

May 9, 1989 I

. 2.

Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

57, are hereby incorporated into the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION l

[*

David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Attachnent:

Technical Specification Changes Date of Issuance: May 9, 1989 i

0FFICIAL RECORD COPY LA jl-3 PM: DII-3 PDII-3 MR KJabbour:

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ATTACHMENT-TO LICENSE AMENDMENT NO.' 63 FACILITY OPERATING LICENSE NO. NPF-35 l'

DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 57 -

FACILITY OPERATING LICENSE N0. NPF-52 1

DOCKET NO. 50-414 E1 Replace the.following pages of the Appendix "A" Technical Specifications with:

l the enclosed pages.

The revised pages are identified by Amendment number and ;

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

Amended Page Overleaf Page' 3/4 3-4 3/4 3-6 3/4 3-9 3/4 3-11 3/4 3-12 B 3/4 3 B 3/4 3-4 3/4 3-12a (new page)

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TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirenient, suspend all operations involving positive reactivity changes.

ACTION 5 - Delete

. ACTION 6 - With the number of OPEaABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - Delete ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 9 - With the number of OPERABLE channels one less than the Minimun 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 l

t"if attachment) inoperable, restore it to OPERABLE status within 4b tours 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 perform-ing maintenance to restore the breaker to OPERABLE status.

With the breaker bypassed, apply ACTION 9.

ACTION 13-With any reactor trip bypass breaker inoperable, restore the bypass breaker to OPERABLE status prior to placing it in service.

CATAWBA - UNITS 1 & 2 3/4 3-6 Amendment No.63(Unit 1)

Amendment No.57 (Unit 2)

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l TABLE 4.3-1 (Continued)

TABLE NOTATIONS Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.

I Above P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.

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

1. 1. 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%.

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 l

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 channels the provisions of Specification 4.0.4 are not applicable for entry 9 to 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 I

BASIS.

(8) With power greater than or equal to the interlock setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive status light.

(9) Monthly surveillance in MODES 3*, 4*, and 5* shall also include verifi-cation that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive status light.

(10) Setpoint verification is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verifi-cation of the operability of the Undervoltage and Shunt trips.

(12) Deleted I

(13) For Unit 1, CHANNEL CALIBRATION shall ensure that the filter time constant associated with Steam Generator Water Level Low-Low is adjusted to a value less than or equal to 1.5 seconds.

(14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the l

OPERABILITY of the undervoltage and shunt trip circuits for the flanual Reactor Trip Fur.; tion.

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

CATAWBA - UNITS 1 & 2 3/4 3-12 Amendment No. 63 (Unit 1)

Amendment No. 57 (Unit 2)

=.- - -

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TABLE 4.3-1 (Continued)

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TABLE NOTATIONS (15) A local manual shunt trip on'the bypass breakers shall be performed prior to placing breaker in service.

(16) The automatic undervoltage trip capability shall be verified OPERABLE.

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CATAWBA - UNITS 1 & 2 3/4 3-12a Amendment No. 63 (Unit 1)

Amendment No. 57 (Unit 2)

H

J INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATUP.ES ACTUATION SYSTEM INSTRUMENTATION (Continued) spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start and automatic valves position,-(10) nuclear service water pumps start and automatic valves position, and (11) component cooling pumps start and automatic valves position.

The-Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T below Setpoint, prevents the opening of the main avg feedwater valves which were closed by a Safety Injection or High Steam Generator Water Level signal, allows safety injection block so that components can be reset or tripped.

Reactor not tripped prevents manual block of Safety Injection.

P-11 Defeats the manual block of Safety Injection actuation on low pres-surizer pressure and low steam line pressure and defeats steam line isolation on negative steam line. pressure rate.

Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level.

P-12 On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump block for the cooldown valves only.

On increasing reactor coolant loop temper-ature, P-12 automatically defeats the manual bypass of the steam dump block.

P-14 On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, purgs and turbine and inhibits feedwater control valve modulation.

Surveillance for the Reactor Ti.p Bypass Breakers are included in response to the NRC's Generic Letter 85-09, dated May 23, 1985.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:

(1) the u sociated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance.

The radiation monitors for plant operations senses radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions.

Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.

CATAWBA - UNITS 1 & 2 B 3/4 3-3 Amendment No.63 (Unit 1)

Amendment No.57 (Unit 2)

INSTRUMENTATION BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core.

The OPERABILITY of this system is demonstrated by irradiating each detector used ed determining the acceptability of 'ts voltage curve.

For the purpose of measuring F (Z) or F a full incore flux map is used.

q H

Quarter-core flux maps, as defined in WCAF-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when.one Power Range channel is inoperable.

3/4.3.3.3 SEISMIC INSTRUMENTATION I

The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly cetermine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capa-bility is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100.

The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-quakes," April 1974.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SHUTDOWN SYSTEM The OPERABILITY of the Remote Shutdown System ensures that sufficient capability is available to permit safe shutdown of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.

The OPERABILITY of the Remote Shutdown System ensures that a fire will not preclude achieving safe shutdown.

The Remote Shutdown System instrumentation, CATAWBA - UNITS 1 & 2 B 3/4 3-4

_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _.

ML20246L970

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