ML20237A298

Proposed Tech Specs Reducing Steam Generator Low Level Trip Setpoint to 16.4 Inches

ML20237A298
Person / Time
Site:	Davis Besse
Issue date:	12/07/1987
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20237A250	List: ML20237A248 ML20237A260 ML20237A298
References
TAC-66007, NUDOCS 8712140389
Download: ML20237A298 (3)

Text

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THIS PAGE PROVIDED FORINFORMATION DNLY INSTRUMENTATION STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.2 The Steam and Feedwater Rupture Control System (SFRCS) instrumr+tation channels shown in Table 3.3-11 shall be OPERABLE with their trrp setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-12 and with RESPONSE TIMES as shown in Table 3.3-13.

APPLICABILITY: MODES 1, 2 and 3.  !

ACTION:

a. With a SFRCS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Valuae column of Table 3.3-12, declare the channel inoperable and apply the opplicable ACTION requirement of Table 3.3-11, until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trfp Setpoint value.

b. With a SFRCS instrumentation channel inoperable, take the action shown in Table 3.3-11.

SURVEILLANCE REQUIREMENTS  !

4.3.2.2.1 Each GFRCS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNQ, CALIBR) TION and CHANNEL FUNCTIONAL TEST during the' MODES and at the frequeueles shown in l Table 4.3-11. '

4.3.2.2.2 The logic for the bypasses shall be demonstrated OPERAELE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bynass operation. The total bypass function shall be demonstrated ,

OPERABLE at leaat once per 18 months during CHANNEL CALIBRATION testing f of each rhannel affected by bypara operation, j 4.3.2.2,3 The STEAM AND FEEDWATER RUPTURE COUTROL SYSTEM RESPONSE TIME of coch SFRCS function shall be demonstrated to be within the limit at i l 1 east once per 18 months. Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific SFRCS function as shown in the " Total No. of Channela" Column of Table 3.3-11.

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EASES 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND SAFETY SYSTEM INSTRUMENTATION The OPERABILITY of the RPS, SFAS and SFRCS instrinnentation systems ensure that 1) the associated action and/or trip will be initiated when the parameter monitored by each channel or combination thereof exceeds iu.

setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for

testing or maintenance, and 4) sufficient system functional capability is available for RPS, SFAS and SFRCS purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient con-l ditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall. system functional capability is maintained comparable to the originsi design' standards. The periodic surveillance tests performed at the minimum frequencies arc sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the RPS, SFAS, and SFRCS action function associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlap-ping or total channel tent measurements provided that such test demon-strate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sencoes with certified response times.

An SFRCS channel consists of 1) the sensing device (s), 2) associated logic and output relays (including Isolation of Main Feedwater Non Essential Valves and Turbine Trip), and 3) power sources.

Safety-grade anticipatory reactor trip is initiated by a turbine trip (above 25 percent of RATED THERMANL F0WER) or trip of both main feedwater pump turbines. This anticipatory trfp will operate in advance of the reactor coolant systen high pressure reactor trip to reduce the peak reactor coolant system pressure ed thus reduce challenges to the power operated relief valve. This anticipatory reactor trip system was installed to satisfy Item II.K.2.10 of NUREG-0737.

DAVIS-BESSE, UNIT 1 B 3/4 3-1 Amendment No. 73 L _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ - l