ML18143B513

Proposed Tech Spec Changes,Revising Limiting Conditions for Operation & Surveillance Requirements for Reactor Trip & Bypass Breakers,Undervoltage Trip Logic & Shunt Trip Logic

ML18143B513
Person / Time
Site:	Surry
Issue date:	09/09/1985
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18143B511	List: ML18143B510 ML18143B513
References
NUDOCS 8509160363
Download: ML18143B513 (9)

Text

• ( I i e ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE 8509160363 B50909 *

• PDR

• ADOCK 05000280 P PDR SURRY POWER STATION \ !

• FUNCTIONAL UNIT 17. Low Steam Generator Water Level With Steam/Feedwater*

Mismatch Flow 18. A. Reactor Trip Breakers B. Reactor Trip Bypass Breaker TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS COLUMN 1 MINIMUM OPERABLE CHANNELS !/non-isolated loop !/non-isolated loop 2 1 COLUMN 2 DEGREE OF REDUNDANCY 1 0 COLUMN 3 PERMISSIBLE BYPASS CONDITIONS COLUMN 4 OPERATOR ACTION IF CONDITIONS OF COLUMN 1 OR 2, EXCEPT AS CONDITIONED BY COLUMN 3, CANNOT BE M~ Maintain hot shutdown Maintain hot shutdown; if one diverse trip feature (undervoltage or shunt trip attachment) is inoperable, restore it to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and maintai, hot shutdown.

• • • t-3 C/) i I I I I FUNCTIONAL UNIT 19. Auto Trip Logic A. Undervoltage Trip Logic B. Shunt Trip Logic TABLE 3. 7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS COLUMN 1 MINIMUM OPERABLE CHANNELS 2 2 COLUMN 2 DEGREE OF REDUNDANCY 1 1 COLUMN 3 PERMISSIBLE BYPASS CONDITIONS

• COLUMN 4 OPERATOR ACTION IF CONDITIONS OF COLUMN 1 OR 2, EXCEPT AS CONDITIONED BY COLUMN 3, CANNOT BE MET Maintain hot shutdown; if one diverse trip feature (undervoltage or shunt trip attachment) is inoperable, restore it to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and maintain hot shutdown.

Maintain hot shutdown; if one diverse trip feature (undervoltage or shunt trip attachment) is inoperable, restore it to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and maintain hot shutdown.

• • If both misalignment monitors (a and b) inoperable

• for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or more, the nuclear overpower trip shall be reset to 93 percent of rated power in addition to the increased surveillance noted. *** Terminate testing of Reactor Trip Breakers and open the Reactor Trip Bypass Breakers.

Channel Description

26. Environmental Radiation Monitors 27. Logic Channel Testing 28. Turbine Overspeed Protection Trip Channel (Electrical)

29. Turbine Trip Setpoint 30. Seismic Instrumentation

31. Reactor Trip Breaker a. Undervoltage Trip Logic b. Shunt Trip Logic 32. Reactor Coolant Pressure 33. Auxiliary Feedwater

a. b. c. d. e. Steam Generator Water Level Low-Low RCP Undervoltage

s. I. Station Blackout Main Feedwater Pump Trip Check *M N.A. N.A. N.A. M N.A N.A. . N.A. N.A. s s (All N.A. N.A. TABL~i-1 (Continued)

Calibrate N.A. N.A. R R R N.A N.A. N.A. R. R R Test N.A. M R R M M M M N.A. M M

• Remarks TLD Dosimeters Stop valve closure or low EH fluid pressure The test shall independently verify operability of the voltage and shunt trip attachments Safety Injection surveillance requirements)

R N.A. N.A. R -I-' I 00

• * * --Page 4.1-8a is deleted. Item 34, Loss of Power, also appears on page 4.1-9. The legend at the bottom of page 4.1-8a has also been moved to page 4.1-9

• TABLE 4.1-1 (Continued)

Channel Description Check Calibrate.

Test Remarks 34. Loss of Power a. 4.16 KV Emergency Bus Under-N.A. R M voltage (Loss of Voltage) b. 4.16 KV Emergency Bus Under-N.A. R M voltage .(Degraded Voltage) 3.5. Control Room Chlorine Detectors s R M 36. Manual Reactor Trip N.A. N.A. R The test shall independently verify the operability of the undervoltage and shunt trip attachments for the manual reactor trip function.

The test shall also verify the operability of the bypass breaker trip circuit. 37. Reactor Trip Bypass Breaker a. Undervoltage attachment N.A. N.A. M Test prior to placing in service b. Shunt trip attachment N.A. N.A. R S -Each shift D -Daily W Weekly N.A. -Not applicable SA -Semiannually Q -Every 90 effective

• See Specification 4.lD M -Monthly P Prior to each startup if not done previous week R Each Refueling Shutdown BW -Every two weeks AP -After each startup if not. done previous week full power days I ~I I- I '°

• . ' *" .

• ATTACHMENT 2

• DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGES *

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--~ . .. "I, . .,..' ,*'), * *

• e SAFETY EVALUATION FOR SUPPLEMENTAL PROPOSED CHANGE This supplemental proposed change to the Technical Specification provides clarification for the required testing of the reactor trip breakers, reactor trip bypass breakers and the manual scram switches; and provides further definition of operability for the reactor trip breakers.

To meet the guidance of the Generic Letter 85-09, "Technical Specifications for Generic Letter 83-28, item 4 .3," a supplemental proposed change is submitted to provide a Limiting Condition for Operation for the reactor trip breakers; and trative notes to clarify the surveillance testing requirements for the reactor trip breakers, reactor trip bypass breakers, and the manual scram switches.

50.59 Safety Review Pursuant to lOCFRS0.59, we have reviewed the supplemental proposed change and have concluded that no unreviewed safety question exists: In that, (i) The probability of occurrence or the consequences of an accident or malfunction of equipment importantant to safety is not increased by these supplemental changes. One change redefines the operability of the reactor trip breaker with one of the diverse trip features (undervoltage or shunt trip attachments) inoperable.

Since either trip feature being operable would initiate a reactor trip the probability of occurrence or consequence of an accident or malfunction of equipment important to safety is not increased from that previously evaluated in the UFSAR, (ii) The possibility of a different type of accident other than discussed in the UFSAR has not been created by this supplemental proposed change. The proposed changes are bounded by the previous submittal and no new or different type of accidents are created by this additional change. (iii) The margin of safety as defined in the basis for any Technical Specification is not reduced by this change. The proposed changes provide further definition of reactor trip breaker operability and clarification of surveillance test requirements for the reactor trip and reactor trip bypass breakers, and the manual scram switches.

These supplemental changes are bounded by the previous submittal and do not*reduce the margin of safety *

• * *

• e* Page 2 50.92 Significant Hazards Review The supplemental proposed changes do not pose a significant hazards tion as definec:I in 10CFR50. 92. The Commission has provided examples of changes that constitute no significant safety hazards consideration in Federal Regiiter, Volume 48, page 14870. Example (ii) consist of additional tion, restrictions or controls beyond those presently specified in the Technical Specifications.

Example (vii) consists of a change to make the licensee conform to changes in Commission guidances.

The supplemental proposed change is similar to example (ii) in that it clarifies the intent of the su.rveill~nce testing requirements for reactor trip and reactor trip bypass breakers, and the manual scram switches.

Specifically, the Technical Specification requires independent testing of the undervoltage and shunt trip attachments in the reactor trip and reactor trip bypass breakers.

In addition the p*roposed change is similar to example (vii) in that it clarifies operability of the reactor trip breakers in the action statement.

Specifically the Commission's guidance, in Generic Letter 85-09, permits power operation of the reactor with one (1) of the diverse trip features of a reactor-trip breaker (undervoltage or shunt trip attachment) inoperable for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to shuting down. Based on the above we concluded that this proposed Technical Specification supplemental change does not involve an unreviewed safety question as defined in 10CFR50.59 nor a significant hazards consideration as defined in 10CFR50.92.

ETS/acm/m045