ML17261A788

Proposed Tech Spec Changes Re Reactor Trip Breakers

ML17261A788
Person / Time
Site:	Ginna
Issue date:	01/26/1988
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17261A787	List: ML17261A785 ML17261A788
References
GL-83-28, NUDOCS 8802030538
Download: ML17261A788 (9)

Text

ATTACHMENT A Revise Appendix A Technical Specifications by removing the pages identified. below and inserting the enclosed pages.

INSERT 3.5-8 3.5-8 3.5-15 3.5-15 4.1-7 4.1-7 4.1-7a so>a6 SS020305SB, 8>000a44 PDR gDOCK 0>0 PgR P

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TABLE 3 '-1 Continued PROTECTION SYSTEM INSTRUMENTATION

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Z 0 5 OPERATOR ACTION TOTAL NO. of MIN. PERMISSIBLE IF CONDITIONS OF (3DNNEL NO. of CHiQQ&LS OPERABLE BYPASS COLUMN 1 OR 3 OPERABLE NO. FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS CANNOT BE MET ABOVE

19. Degraded Voltage 2/bus 2/bus 1/bus TT*a~ = 350 F 480V Safeguards Bus

20. Automatic Trip Logic Note 4 When RCCA Including Reactor Trip is withdrawn Breakers GD Ql I

CO NOTE 1: When block condition exists, maintain normal operation.

NOTE 2: Channels should be operable at all modes below the bypass condition with the reactor trip system breakers in the closed position and control rod drive system capable of rod withdrawal.

NOTE 3: Channels shall be operable at all modes below the bypass condition except during refueling defined to be when fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

NOTE 4: One reactor trip breaker may be bypassed for surveillance testing t provided the other reactor trip breaker is operable.

F.P. Full Power 0

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12. With the number of operable channels less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Should the next Channel Functional Test require the bypass of an inoperable channel to avoid the generation of an actuation signal, operation may proceed until this Channel Functional Test. At the time of this Channel Functional Test, or if at any time the number of operable channels is less than the Minimum Operable Channels required, be at hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and at an RCS temperature less than 350 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

13. With the number of operable channels less than the Minimum Operable Channels required, operation may continue provided the containment purge and exhaust valves are maintained closed.

14. Should one reactor trip breaker or channel of trip logic be inoperable the plant must not be in the operating mode following a six hour time period.

If one of the diverse reactor trip breaker trip features (undervoltage or shunt trip attachment) on one breaker 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 breaker inoperable.

If at the end of the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period one trip feature is inoperable it must be repaired or the plant must not be in the operating mode, and the reactor trip breaker must be open, following an additional six hour time period.

Amendment No. 3.5-15 proposed

g TABLE 4 1-1 (CONTINUED) 0

'U o Channel Descri tion Check Calibrate Test Remarks O.

25. Containment Pressure Narrow range containment pressure

(-3.0, +3 psig) excluded

26. Steam Generator Pressure S

27. Turbine First Stage Pressure S

28. Emergency Plan Radiation Instruments

29. Environmental Monitors P

NA NA

30. Loss of Voltage/Degraded NA Voltage 480 Volt Safeguards Bus

31. Trip of Main Feedwater Pumps NA NA

32. Steam Flow S Lvo S

34. Chlorine Detector, Control Room NA Air Intake

35. 'mmonia Detector, Control Room NA Air Intake

36. Radiation Detectors, Control Room NA Air Intake 37a. Trip Breaker NA NA Notes 1, 2 and 3 Logic Channel Testing 37b. Trip Breaker NA NA Note 1 Logic Channel Testing 3

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TABLE 4. 1-1 (CONTINUED)

Channel Check Calibrate Test Remarks

38. Reactor Trip Breakers NA NA M Function test Includes independent testing of both undervoltage and shunt trip attachment of reactor trip breakers. Each of the two reactor trip breakers will be tested. on alternate months.

Note 2

39. Manual Reactor Trip NA NA Includes independent testing of both undervoltage and shunt trip circuits. The test shall also verify the operability of the bypass breaker.

40a. Reactor Trip Bypass Breaker NA NA Using test switches in the reactor protection rack manually trip the reactor trip bypass breaker using the shunt trip coil.

40b. Reactor Trip Bypass Breaker NA NA Automatically trip the under-voltage trip attachment.

NOTE 1: Logic trains will be tested on alternate months corresponding to the reactor trip breaker testing.

Monthly logic testing will verify the operability of all sets of reactor trip logic actuating contacts on that train (See Note 3). Refueling shutdown testing will verify the operability of all sets of reactor trip actuating contacts on both trains. In testing, operation of one set of contacts will result in a reactor trip breaker trip; the operation of all other sets of contacts will be verified by the use of indication circuitry.

NOTE 2: Testing shall be performed monthly, unless the reactor trip breakers are open, or shall be performed prior to startup if testing has not been performed within the last 30 days.

NOTE 3: The source range trip logic may be excluded from monthly testing provided it is tested within 30 days prior to startup.

ATTACHMENT B This proposed Technical Specification change reflects the request made in the January 9, 1987 NRC letter from Dominic C. DiIanni to Roger N. Kober concerning the "Review of Design for Automatic Shunt Trip for Reactor Trip Breakers (Generic Letter 83-28 Item 4.3)". The proposed. changes incorporate on-line reactor trip breaker testing into the Technical Specifications. A detailed description of all the changes is presented. on Table 1.

This change in Technical Specifications clearly is not a request for a change in the authorized power level as it is related only to operational and testing requirements of the reactor trip break-ers within the plant. Further, the major possible consequence of this change that can be foreseen at this time is that over a period of time additional plant trips may occur through actions taken during monthly testing of the reactor trip breakers.

However, occasional trips are considered within the normal operating conditions at a power plant.

A significant hazards analysis has been accomplished against the criteria. in 10CFR50.92.'ecause the'proposed. changes constitute

." addition'al limitations 'and control'on both operation and testing

'i'hey do 'not:

(1) involve a significant increase in the probability or consequences'of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

Therefore, Rochester Gas and Electric submits that the issues associated with this amendment request warrant a no significant hazards finding.

TABLE 1 Detailed Technical S ecification Chan es Location Descri tion of Chan e Reason for Chan e

p. 3.5-8, Add Item 20 - Automatic Trip This change reflects new operating Table 3.5-1 Logic including Reactor Trip condition requirements for the Page 3 of 3 Breakers. Reactor Trip Breakers and reactor trip logic.

Change Note 3 the fifth Correct typographical error.

word of sentence should be changed from "of" to "at".

Add Note 4 to the bottom of This Note is needed to explain the this page. bypass condition in the new Item 20.

p. 3.5-15 Add Number 14 to the bottom This note is required to explain Action Statement of this page. fully the operator actions required if the requirement of column 3 for

'-1 line 20 of Table 3 cannot be met.

p. 4.1-7 Add Items 37a and 37b con- This addition reflects new testing Table 4.1-1 cerning logic testing on a requirements in response to NRC monthly and refueling outage letter 83-28.

basis.

p. 4.1-7a Add Item 38 concerning the This addition reflects new testing Table F 1-1 testing of Reactor Trip requirements in response to NRC Breakers. letter 83-28.

Add Item 39 concerning the This addition reflects new testing testing of the manual requirements in response to NRC tripping of the Reactor letter 83-28.

Trip Breakers.

Add Items 40a and 40b con- This addition reflects new testing cerning the testing of the requirements in response to NRC Reactor Trip Bypass Breaker. letter 83-28.

Add Notes 1, 2, 3 These notes are required to explain the testing requirements of the logic associated with the React'.or Trip Breakers.

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